National Library of Energy BETA

Sample records for waste association iswa

  1. International Solid Waste Association (ISWA) | Open Energy Information

    Open Energy Info (EERE)

    Solid Waste Association (ISWA) Jump to: navigation, search Name: International Solid Waste Association (ISWA) Address: ISWA - International Solid Waste Association General...

  2. US Integrated Waste Services Association | Open Energy Information

    Open Energy Info (EERE)

    Integrated Waste Services Association Jump to: navigation, search Name: US Integrated Waste Services Association Place: Washington, DC Product: Focussed on promoting integrated...

  3. Thermal impact of waste emplacement and surface cooling associated with geologic disposal of nuclear waste

    SciTech Connect (OSTI)

    Wang, J.S.Y.; Mangold, D.C.; Spencer, R.K.; Tsang, C.F.

    1982-08-01

    The thermal effects associated with the emplacement of aged radioactive wastes in a geologic repository were studied, with emphasis on the following subjects: the waste characteristics, repository structure, and rock properties controlling the thermally induced effects; the current knowledge of the thermal, thermomechanical, and thermohydrologic impacts, determined mainly on the basis of previous studies that assume 10-year-old wastes; the thermal criteria used to determine the repository waste loading densities; and the technical advantages and disadvantages of surface cooling of the wastes prior to disposal as a means of mitigating the thermal impacts. The waste loading densities determined by repository designs for 10-year-old wastes are extended to older wastes using the near-field thermomechanical criteria based on room stability considerations. Also discussed are the effects of long surface cooling periods determined on the basis of far-field thermomechanical and thermohydrologic considerations. The extension of the surface cooling period from 10 years to longer periods can lower the near-field thermal impact but have only modest long-term effects for spent fuel. More significant long-term effects can be achieved by surface cooling of reprocessed high-level waste.

  4. Organizations and associations serving the Waste-To-energy industry

    SciTech Connect (OSTI)

    Not Available

    1998-12-01

    Professional organizations can provide leadership in disseminating information and answering questions about, and in providing support for, the industry. Eleven such organizations and association that directly, or in part, promote or provide technical assistance in the waste-to-energy field are listed and described briefly. Some actively lobby on waste-to-energy issues. Some provide useful publications and newsletters for those interested in keeping up with changes in the field.

  5. Problems associated with solid wastes from energy systems

    SciTech Connect (OSTI)

    Chiu, S.Y.; Fradkin, L.; Barisas, S.; Surles, T.; Morris, S.; Crowther, A.; DeCarlo, V.

    1980-09-01

    Waste streams from many energy-related technologies including coal, oil shale, tar sands, geothermal, oil and gas extraction, and nuclear power generation are reviewed with an emphasis on waste streams from coal and oil shale technologies. This study has two objectives. The first objective is to outline the available information on energy-related solid wastes. Data on chemical composition and hazardous biological characteristics are included, supplemented by regulatory reviews and data on legally designated hazardous waste streams. The second objective is to provide disposal and utilization options. Solid waste disposal and recovery requirements specified under the RCRA are emphasized. Information presented herein should be useful for policy, environmental control, and research and development decision making regarding solid and hazardous wastes from energy production.

  6. 2013 Radiological Monitoring Results Associated with the Advanced Test Reactor Complex Cold Waste Pond

    SciTech Connect (OSTI)

    Mike Lewis

    2014-02-01

    This report summarizes radiological monitoring performed of the Idaho National Laboratory Site’s Advanced Test Reactor Complex Cold Waste wastewater prior to discharge into the Cold Waste Pond and of specific groundwater monitoring wells associated with the Industrial Wastewater Reuse Permit (#LA-000161-01, Modification B). All radiological monitoring is performed to fulfill Department of Energy requirements under the Atomic Energy Act.

  7. 2011 Radiological Monitoring Results Associated with the Advanced Test Reactor Complex Cold Waste Pond

    SciTech Connect (OSTI)

    Mike Lewis

    2012-02-01

    This report summarizes radiological monitoring performed of the Idaho National Laboratory Site's Advanced Test Reactor Complex Cold Waste wastewater prior to discharge into the Cold Waste Pond and of specific groundwater monitoring wells associated with the Industrial Wastewater Reuse Permit (LA-000161-01, Modification B). All radiological monitoring is performed to fulfill Department of Energy requirements under the Atomic Energy Act.

  8. 2010 Radiological Monitoring Results Associated with the Advance Test Reactor Complex Cold Waste Pond

    SciTech Connect (OSTI)

    mike lewis

    2011-02-01

    This report summarizes radiological monitoring performed of the Idaho National Laboratory Site’s Advanced Test Reactor Complex Cold Waste wastewater prior to discharge into the Cold Waste Pond and of specific groundwater monitoring wells associated with the Industrial Wastewater Reuse Permit (#LA-000161-01, Modification B). All radiological monitoring is performed to fulfill Department of Energy requirements under the Atomic Energy Act.

  9. 2012 Radiological Monitoring Results Associated with the Advanced Test Reactor Complex Cold Waste Pond

    SciTech Connect (OSTI)

    Mike Lewis

    2013-02-01

    This report summarizes radiological monitoring performed of the Idaho National Laboratory Site’s Advanced Test Reactor Complex Cold Waste wastewater prior to discharge into the Cold Waste Pond and of specific groundwater monitoring wells associated with the Industrial Wastewater Reuse Permit (#LA-000161-01, Modification B). All radiological monitoring is performed to fulfill Department of Energy requirements under the Atomic Energy Act.

  10. 2014 Radiological Monitoring Results Associated with the Advanced Test Reactor Complex Cold Waste Pond

    SciTech Connect (OSTI)

    Lewis, Mike

    2015-02-01

    This report summarizes radiological monitoring performed of the Idaho National Laboratory Site’s Advanced Test Reactor Complex Cold Waste wastewater prior to discharge into the Cold Waste Pond and of specific groundwater monitoring wells associated with the Industrial Wastewater Reuse Permit (#LA-000161-01, Modification B). All radiological monitoring is performed to fulfill Department of Energy requirements under the Atomic Energy Act.

  11. Waste Issues Associated with the Safe Movement of Hazardous Chemicals

    SciTech Connect (OSTI)

    Dare, J. H.; Cournoyer, M. E.

    2002-02-26

    Moving hazardous chemicals presents the risk of exposure for workers engaged in the activity and others that might be in the immediate area. Adverse affects are specific to the chemicals and can range from minor skin, eye, or mucous membrane irritation, to burns, respiratory distress, nervous system dysfunction, or even death. A case study is presented where in the interest of waste minimization; original shipping packaging was removed from a glass bottle of nitric acid, while moving corrosive liquid through a security protocol into a Radiological Control Area (RCA). During the transfer, the glass bottle broke. The resulting release of nitric acid possibly exposed 12 employees with one employee being admitted overnight at a hospital for observation. This is a clear example of administrative controls to reduce the generation of suspect radioactive waste being implemented at the expense of employee health. As a result of this event, material handling procedures that assure the safe movement of hazardous chemicals through a security protocol into a radiological control area were developed. Specifically, hazardous material must be transferred using original shipping containers and packaging. While this represents the potential to increase the generation of suspect radioactive waste in a radiological controlled area, arguments are presented that justify this change. Security protocols for accidental releases are also discussed. In summary, the 12th rule of ''Green Chemistry'' (Inherently Safer Chemistry for Accident Prevention) should be followed: the form of a substance used in a chemical process (Movement of Hazardous Chemicals) should be chosen to minimize the potential for chemical accidents, including releases.

  12. Draft HAB Advice on Delaying Decisions Associated with the Final Tank Closure and Waste

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

    Committee Draft Advice - TC&WM EIS Delayed Decisions v1 - Mattson, et.al. Page 1/1 Draft HAB Advice on Delaying Decisions Associated with the Final Tank Closure and Waste Management EIS Background: The Hanford Advisory Board (HAB or Board) spent a considerable amount of time developing advice on the Draft Tank Closure and Waste Management Environmental Impact Statement (TC&WM EIS, EIS). The U.S. Department of Energy (DOE) has spent over $80 million on the EIS, and thousands of people

  13. Elemental characterization of LL-MA radioactive waste packages with the associated particle technique

    SciTech Connect (OSTI)

    Perot, B.; Carasco, C.; Toure, M.; El Kanawati, W.; Eleon, C.

    2011-07-01

    The French Alternative Energies and Atomic Energy Commission (CEA) and National Radioactive Waste Management Agency (ANDRA) are conducting an R and D program to improve the characterization of long-lived and medium activity (LL-MA) radioactive waste packages with analytical methods and with non-destructive nuclear measurements. This paper concerns fast neutron interrogation with the associated particle technique (APT), which brings 3D information about the waste material composition. The characterization of volume elements filled with iron, water, aluminium, and PVC in bituminized and fibre concrete LL-MA waste packages has been investigated with MCNP [1] and MODAR data analysis software [2]. APT provides usable information about major elements presents in the volumes of interest. However, neutron scattering on hydrogen nuclei spreads the tagged neutron beam out of the targeted volume towards surrounding materials, reducing spatial selectivity. Simulation shows that small less than 1 L targets can be characterised up to the half-radius of a 225 L bituminized drum, the matrix of which is very rich in hydrogen. Deeper characterization in concrete is possible but limited by counting statistics due to photon attenuation in this dense matrix and, unless large inspection volumes are considered, by the lack of spatial selectivity of the tagged neutron beam due to neutron scattering. (authors)

  14. MANAGING UNCERTAINTIES ASSOCIATED WITH RADIOACTIVE WASTE DISPOSAL: TASK GROUP 4 OF THE IAEA PRISM PROJECT

    SciTech Connect (OSTI)

    Seitz, R.

    2011-03-02

    It is widely recognized that the results of safety assessment calculations provide an important contribution to the safety arguments for a disposal facility, but cannot in themselves adequately demonstrate the safety of the disposal system. The safety assessment and a broader range of arguments and activities need to be considered holistically to justify radioactive waste disposal at any particular site. Many programs are therefore moving towards the production of what has become known as a Safety Case, which includes all of the different activities that are conducted to demonstrate the safety of a disposal concept. Recognizing the growing interest in the concept of a Safety Case, the International Atomic Energy Agency (IAEA) is undertaking an intercomparison and harmonization project called PRISM (Practical Illustration and use of the Safety Case Concept in the Management of Near-surface Disposal). The PRISM project is organized into four Task Groups that address key aspects of the Safety Case concept: Task Group 1 - Understanding the Safety Case; Task Group 2 - Disposal facility design; Task Group 3 - Managing waste acceptance; and Task Group 4 - Managing uncertainty. This paper addresses the work of Task Group 4, which is investigating approaches for managing the uncertainties associated with near-surface disposal of radioactive waste and their consideration in the context of the Safety Case. Emphasis is placed on identifying a wide variety of approaches that can and have been used to manage different types of uncertainties, especially non-quantitative approaches that have not received as much attention in previous IAEA projects. This paper includes discussions of the current results of work on the task on managing uncertainty, including: the different circumstances being considered, the sources/types of uncertainties being addressed and some initial proposals for approaches that can be used to manage different types of uncertainties.

  15. Fabrication of a Sludge-Conditioning System for Processing Legacy Wastes from the Gunite and Associated Tanks

    SciTech Connect (OSTI)

    Randolph, J.D.; Lewis, B.E.; Farmer, J.R.; Johnson, M.A.

    2000-08-01

    The Sludge Conditioning System (SCS) for the Gunite and Associated Tanks (GAATs) is designed to receive, monitor, characterize and process legacy waste materials from the South Tank Farm tanks in preparation for final transfer of the wastes to the Melton Valley Storage Tanks (MVSTs), which are located at Oak Ridge National Laboratory. The SCS includes (1) a Primary Conditioning System (PCS) Enclosure for sampling and particle size classification, (2) a Solids Monitoring Test Loop (SMTL) for slurry characterization, (3) a Waste Transfer Pump to retrieve and transfer waste materials from GAAT consolidation tank W-9 to the MVSTs, (4) a PulsAir Mixing System to provide mixing of consolidated sludges for ease of retrieval, and (5) the interconnecting piping and valving. This report presents the design, fabrication, cost, and fabrication schedule information for the SCS.

  16. Cost savings associated with landfilling wastes containing very low levels of uranium

    SciTech Connect (OSTI)

    Boggs, C.J.; Shaddoan, W.T.

    1996-03-01

    The Paducah Gaseous Diffusion Plant (PGDP) has operated captive landfills (both residential and construction/demolition debris) in accordance with the Commonwealth of Kentucky regulations since the early 1980s. Typical waste streams allowed in these landfills include nonhazardous industrial and municipal solid waste (such as paper, plastic, cardboard, cafeteria waste, clothing, wood, asbestos, fly ash, metals, and construction debris). In July 1992, the U.S. Environmental Protection Agency issued new requirements for the disposal of sanitary wastes in a {open_quotes}contained landfill.{close_quotes} These requirements were promulgated in the 401 Kentucky Administrative Record Chapters 47 and 48 that became effective 30 June 1995. The requirements for a new contained landfill include a synthetic liner made of high-density polyethylene in addition to the traditional 1-meter (3-foot) clay liner and a leachate collection system. A new landfill at Paducah would accept waste streams similar to those that have been accepted in the past. The permit for the previously existing landfills did not include radioactivity limits; instead, these levels were administratively controlled. Typically, if radioactivity was detected above background levels, the waste was classified as low-level waste (LLW), which would be sent off-site for disposal.

  17. The Gunite and Associated Tanks Remediation Project Tank Waste Retrieval Performance and Lessons Learned, vol. 1 [of 2

    SciTech Connect (OSTI)

    Lewis, BE

    2003-10-07

    The Gunite and Associated Tanks (GAAT) Remediation Project was the first of its kind performed in the United States. Robotics and remotely operated equipment were used to successfully transfer almost 94,000 gal of remote-handled transuranic sludge containing over 81,000 Ci of radioactive contamination from nine large underground storage tanks at the Oak Ridge National Laboratory (ORNL). The sludge was transferred with over 439,000 gal of radioactive waste supernatant and {approx}420,500 gal of fresh water that was used in sluicing operations. The GAATs are located in a high-traffic area of ORNL near a main thoroughfare. A phased and integrated approach to waste retrieval operations was used for the GAAT Remediation Project. The project promoted safety by obtaining experience from low-risk operations in the North Tank Farm before moving to higher-risk operations in the South Tank Farm. This approach allowed project personnel to become familiar with the tanks and waste, as well as the equipment, processes, procedures, and operations required to perform successful waste retrieval. By using an integrated approach to tank waste retrieval and tank waste management, the project was completed years ahead of the original baseline schedule, which resulted in avoiding millions of dollars in associated costs. This report is organized in two volumes. Volume 1 provides information on the various phases of the GAAT Remediation Project. It also describes the different types of equipment and how they were used. The emphasis of Volume 1 is on the description of the tank waste retrieval performance and the lessons learned during the GAAT Remediation Project. Volume 2 provides the appendixes for the report, which include the following information: (A) Background Information for the Gunite and Associated Tanks Operable Unit; (B) Annotated Bibliography; (C) Comprehensive Listing of the Sample Analysis Data from the GAAT Remediation Project; (D) GAAT Equipment Matrix; and (E) Vendor List

  18. Directory of mine-waste characterization and drainage-quality contacts in Western Governors' Association member states

    SciTech Connect (OSTI)

    Not Available

    1991-09-01

    Contained within the directory are contacts with access to information on metal mine waste characterization, metal mine drainage quality, and drainage quality prediction for each of the twenty-one Western Governors' Association (WGA) member states. Each state was contacted and asked to provide names, addresses, phone numbers of people with access to information on ten topics relevant to mine waste characterization and drainage quality. The request, in the form of a questionnaire, was sent to WGA contacts as well as other people in associated departments and the information received was compiled. Ten questions listed for each state are followed by the contacts used to get the information requested. When necessary, an explanatory paragraph precedes the contact list. In some cases, supplemental information such as a mine or reference list is placed in appendices.

  19. Mechanical-biological waste treatment and the associated occupational hygiene in Finland

    SciTech Connect (OSTI)

    Tolvanen, Outi K. . E-mail: outolvan@bytl.jyu.fi; Haenninen, Kari I.

    2006-07-01

    A special feature of waste management in Finland has been the emphasis on the source separation of kitchen biowaste (catering waste); more than two-thirds of the Finnish population participates in this separation. Source-separated biowaste is usually treated by composting. The biowaste of about 5% of the population is handled by mechanical-biological treatment. A waste treatment plant at Mustasaari is the only plant in Finland using digestion for kitchen biowaste. For the protection of their employees, the plant owners commissioned a study on environmental factors and occupational hygiene in the plant area. During 1998-2000 the concentrations of dust, microbes and endotoxins and noise levels were investigated to identify possible problems at the plant. Three different work areas were investigated: the pre-processing and crushing hall, the bioreactor hall and the drying hall. Employees were asked about work-related health problems. Some problems with occupational hygiene were identified: concentrations of microbes and endotoxins may increase to levels harmful to health during waste crushing and in the bioreactor hall. Because employees complained of symptoms such as dry cough and rash or itching appearing once or twice a month, it is advisable to use respirator masks (class P3) during dusty working phases. The noise level in the drying hall exceeded the Finnish threshold value of 85 dBA. Qualitatively harmful factors for the health of employees are similar in all closed waste treatment plants in Finland. Quantitatively, however, the situation at the Mustasaari treatment plant is better than at some Finnish dry waste treatment plants. Therefore is reasonable to conclude that mechanical sorting, which produces a dry waste fraction for combustion and a biowaste fraction for anaerobic treatment, is in terms of occupational hygiene better for employees than combined aerobic treatment and dry waste treatment.

  20. Waste Form and Indrift Colloids-Associated Radionuclide Concentrations: Abstraction and Summary

    SciTech Connect (OSTI)

    R. Aguilar

    2003-06-24

    This Model Report describes the analysis and abstractions of the colloids process model for the waste form and engineered barrier system components of the total system performance assessment calculations to be performed with the Total System Performance Assessment-License Application model. Included in this report is a description of (1) the types and concentrations of colloids that could be generated in the waste package from degradation of waste forms and the corrosion of the waste package materials, (2) types and concentrations of colloids produced from the steel components of the repository and their potential role in radionuclide transport, and (3) types and concentrations of colloids present in natural waters in the vicinity of Yucca Mountain. Additionally, attachment/detachment characteristics and mechanisms of colloids anticipated in the repository are addressed and discussed. The abstraction of the process model is intended to capture the most important characteristics of radionuclide-colloid behavior for use in predicting the potential impact of colloid-facilitated radionuclide transport on repository performance.

  1. 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.

  2. A STRUCTURAL INTEGRITY ASSESSMENT OF UNDERGROUND PIPING ASSOCIATED WITH THE TRANSFER OF RADIOACTIVE WASTE

    SciTech Connect (OSTI)

    Wiersma, B

    2006-04-25

    Radioactive wastes are confined in 49 underground storage tanks at the Savannah River Site. The waste is transported between tanks via underground transfer piping. An assessment of the structural integrity of the transfer piping was performed to ensure that the present condition of the piping was sound and to provide life expectancy estimates for the piping based on anticipated service. The assessment reviewed the original design of the piping, the potential and observed degradation mechanisms, the results from past inspections of the piping, and a Fitness-For-Service evaluation for a section of piping that experienced pitting in a locally thinned area. The assessment concluded that the piping was structurally sound. Assuming that service conditions remain the same, the piping will remain functional for its intended service life.

  3. Panel report on coupled thermo-mechanical-hydro-chemical processes associated with a nuclear waste repository

    SciTech Connect (OSTI)

    Tsang, C.F.; Mangold, D.C.

    1984-07-01

    Four basic physical processes, thermal, hydrological, mechanical and chemical, are likely to occur in 11 different types of coupling during the service life of an underground nuclear waste repository. A great number of coupled processes with various degrees of importance for geological repositories were identified and arranged into these 11 types. A qualitative description of these processes and a tentative evaluation of their significance and the degree of uncertainty in prediction is given. Suggestions for methods of investigation generally include, besides theoretical work, laboratory and large scale field testing. Great efforts of a multidisciplinary nature are needed to elucidate details of several coupled processes under different temperature conditions in different geological formations. It was suggested that by limiting the maximum temperature to 100{sup 0}C in the backfill and in the host rock during the whole service life of the repository the uncertainties in prediction of long-term repository behavior might be considerably reduced.

  4. Report of the second meeting of the consultants on coupled processes associated with geological disposal of nuclear waste

    SciTech Connect (OSTI)

    Tsang, Chin-Fu; Mangold, D.C.

    1985-09-01

    The second meeting of the Consultants on Coupled Processes Associated with Geological Disposal of Nuclear Waste occurred on January 15-16, 1985 at Lawrence Berkeley Laboratory (LBL). All the consultants were present except Dr. K. Kovari, who presented comments in writing afterward. This report contains a brief summary of the presentations and discussions from the meeting. The main points of the speakers' topics are briefly summarized in the report. Some points that emerged during the discussions of the presentations are included in the text related to the respective talks. These comments are grouped under the headings: Comments on Coupled Processes in Unsaturated Fractured Porous Media, Comments on Overview of Coupled Processes, Presentations by Consultants on Selected Topics of Current Interest in Coupled Processes, and Recommendations for Underground Field Tests with Applications to Three Geologic Environments.

  5. The Gunite and Associated Tanks Remediation Project Tank Waste Retrieval Performance and Lessons Learned, vol. 2 [of 2

    SciTech Connect (OSTI)

    Lewis, BE

    2003-10-07

    The Gunite and Associated Tanks (GAAT) Remediation Project was the first of its kind performed in the United States. Robotics and remotely operated equipment were used to successfully transfer almost 94,000 gal of remote-handled transuranic sludge containing over 81,000 Ci of radioactive contamination from nine large underground storage tanks at the Oak Ridge National Laboratory (ORNL). The sludge was transferred with over 439,000 gal of radioactive waste supernatant and {approx}420,500 gal of fresh water that was used in sluicing operations. The GAATs are located in a high-traffic area of ORNL near a main thoroughfare. Volume 1 provides information on the various phases of the project and describes the types of equipment used. Volume 1 also discusses the tank waste retrieval performance and the lessons learned during the remediation effort. Volume 2 consists of the following appendixes, which are referenced in Vol. 1: A--Background Information for the Gunite and Associated Tanks Operable Unit; B--Annotated Bibliography; C--GAAT Equipment Matrix; D--Comprehensive Listing of the Sample Analysis Data from the GAAT Remediation Project; and E--Vendor List for the GAAT Remediation Project. The remediation of the GAATs was completed {approx}5.5 years ahead of schedule and {approx}$120,435K below the cost estimated in the Remedial Investigation/Feasibility Study for the project. These schedule and cost savings were a direct result of the selection and use of state-of-the-art technologies and the dedication and drive of the engineers, technicians, managers, craft workers, and support personnel that made up the GAAT Remediation Project Team.

  6. Technical considerations and problems associated with long-term storage of low-level waste

    SciTech Connect (OSTI)

    Siskind, B.

    1991-12-31

    If a state or regional compact does not have adequate disposal capacity for low-level radioactive waste (LLRW), then extended storage of certain LLRW may be necessary. The Nuclear Regulatory Commission (NRC) contracted with Brookhaven National Laboratory (BNL) several years ago (1984--86) to address the technical issues of extended storage. The dual objectives of this study were (1) to provide practical technical assessments for NRC to consider in evaluating specific proposals for extended storage and (2) to help ensure adequate consideration by NRC, Agreement States, and licensees of potential problems that may arise from existing or proposed extended storage practices. In this summary of that study, the circumstances under which extended storage of LLRW would most likely result in problems during or after the extended storage period are considered and possible mitigative measures to minimize these problems are discussed. These potential problem areas include: (1) the degradation of carbon steel and polyethylene containers during storage and the subsequent need for repackaging (resulting in increased occupational exposure), (2) the generation of hazardous gases during storage, and (3) biodegradative processes in LLRW.

  7. Technical considerations and problems associated with long-term storage of low-level waste

    SciTech Connect (OSTI)

    Siskind, B.

    1991-01-01

    If a state or regional compact does not have adequate disposal capacity for low-level radioactive waste (LLRW), then extended storage of certain LLRW may be necessary. The Nuclear Regulatory Commission (NRC) contracted with Brookhaven National Laboratory (BNL) several years ago (1984--86) to address the technical issues of extended storage. The dual objectives of this study were (1) to provide practical technical assessments for NRC to consider in evaluating specific proposals for extended storage and (2) to help ensure adequate consideration by NRC, Agreement States, and licensees of potential problems that may arise from existing or proposed extended storage practices. In this summary of that study, the circumstances under which extended storage of LLRW would most likely result in problems during or after the extended storage period are considered and possible mitigative measures to minimize these problems are discussed. These potential problem areas include: (1) the degradation of carbon steel and polyethylene containers during storage and the subsequent need for repackaging (resulting in increased occupational exposure), (2) the generation of hazardous gases during storage, and (3) biodegradative processes in LLRW.

  8. A field strategy to monitor radioactivity associated with investigation derived wastes returned from deep drilling sites

    SciTech Connect (OSTI)

    Rego, J.H.; Smith, D.K.; Friensehner, A.V.

    1995-05-26

    The U.S. Department of Energy, Nevada Operations Office, Underground Test Area Operable Unit (UGTA) is drilling deep (>1500m) monitoring wells that penetrate both unsaturated (vadose) and saturated zones potentially contaminated by sub-surface nuclear weapons testing at the Nevada Test Site, Nye County, Nevada. Drill site radiological monitoring returns data on drilling effluents to make informed management decisions concerning fluid management. Because of rapid turn-around required for on-site monitoring, a representative sample will be analyzed simultaneously for {alpha}, {beta} and {gamma} emitters by instrumentation deployed on-site. For the purposes of field survey, accurate and precise data is returned, in many cases, with minimal sample treatment. A 30% efficient high purity germanium detector and a discriminating liquid scintillation detector are being evaluated for {gamma} and {alpha}/{beta} monitoring respectively. Implementation of these detector systems complements a successful on-site tritium monitoring program. Residual radioactivity associated with underground nuclear tests include tritium, activation products, fission products and actinides. Pulse shape discrimination (PSD) is used in {alpha}/{beta} liquid scintillation counting and is a function of the time distribution of photon emission. In particular, we hope to measure {sup 241}Am produced from {sup 241}Pu by {beta} decay. Because {sup 241}Pu is depleted in fissile bomb fuels, maximum PSD resolution will be required. The high purity germanium detector employs a multichannel analyzer to count gamma emitting radionuclides; we will designate specific window configurations to selectively monitor diagnostic fission product radionuclides (i.e., {sup 137}Cs).

  9. Radioactive waste isolation in salt: Peer review of the Golder Associates draft test plan for in situ testing in an exploratory shaft in salt

    SciTech Connect (OSTI)

    Hambley, D.F.; Mraz, D.Z.; Unterberter, R.R.; Stormont, J.C.; Neuman, S.P.; Russell, J.E.; Jacoby, C.H.; Hull, A.B.; Brady, B.H.G.; Ditmars, J.D.

    1987-01-01

    This report documents the peer review conducted by Argonne National Laboratory of a document entitled ''Draft Test Plan for In Situ Testing in an Exploratory Shaft in Salt,'' prepared for Battelle Memorial Institute's Office of Nuclear Waste Isolation by Golder Associates, Inc. In general, the peer review panelists found the test plan to be technically sound, although some deficiencies were identified. Recommendations for improving the test plan are presented in this review report. A microfiche copy of the following unpublished report is attached to the inside back cover of this report: ''Draft Test Plan for In Situ Testing in an Exploratory Shaft in Salt,'' prepared by Golder Associates, Inc., for Office of Nuclear Waste Isolation, Battelle Memorial Institute, Columbus, Ohio (March 1985).

  10. Radiological Monitoring Results for Groundwater Samples Associated with the Industrial Wastewater Reuse Permit for the Materials and Fuels Complex Industrial Waste Ditch and Pond: November 1, 2012-October 31, 2013

    SciTech Connect (OSTI)

    Mike Lewis

    2014-02-01

    This report summarizes radiological monitoring performed on samples from specific groundwater monitoring wells associated with the Industrial Wastewater Reuse Permit for the Materials and Fuels Complex Industrial Waste Ditch and Industrial Waste Pond WRU-I-0160-01, Modification 1 (formerly LA-000160-01). The radiological monitoring was performed to fulfill Department of Energy requirements under the Atomic Energy Act.

  11. Radiological Monitoring Results for Groundwater Samples Associated with the Industrial Wastewater Reuse Permit for the Materials and Fuels Complex Industrial Waste Ditch and Pond: November 1, 2011-October 31, 2012

    SciTech Connect (OSTI)

    Mike lewis

    2013-02-01

    This report summarizes radiological monitoring performed on samples from specific groundwater monitoring wells associated with the Industrial Wastewater Reuse Permit for the Materials and Fuels Complex Industrial Waste Ditch and Industrial Waste Pond WRU-I-0160-01, Modification 1 (formerly LA-000160-01). The radiological monitoring was performed to fulfill Department of Energy requirements under the Atomic Energy Act.

  12. Radiological Monitoring Results For Groundwater Samples Associated with the Industrial Wastewater Reuse Permit for the Materials and Fuels Complex Industrial Waste Ditch and Pond: May 1, 2010-October 31, 2010

    SciTech Connect (OSTI)

    David B. Frederick

    2011-02-01

    This report summarizes radiological monitoring performed on samples from specific groundwater monitoring wells associated with the Industrial Wastewater Reuse Permit for the Materials and Fuels Complex Industrial Waste Ditch and Industrial Waste Pond (#LA-000160-01). The radiological monitoring was performed to fulfill Department of Energy requirements under the Atomic Energy Act.

  13. Radiological Monitoring Results For Groundwater Samples Associated with the Industrial Wastewater Reuse Permit for the Materials and Fuels Complex Industrial Waste Ditch and Pond: November 1, 2010-October 31, 2011

    SciTech Connect (OSTI)

    David Frederick

    2012-02-01

    This report summarizes radiological monitoring performed on samples from specific groundwater monitoring wells associated with the Industrial Wastewater Reuse Permit for the Materials and Fuels Complex Industrial Waste Ditch and Industrial Waste Pond (No.LA-000160-01). The radiological monitoring was performed to fulfill Department of Energy requirements under the Atomic Energy Act.

  14. Remaining Sites Verification Package for the 100-B-22:1 Pipelines and Associated Soils, Waste Site Reclassification Form 2005-042

    SciTech Connect (OSTI)

    L. M. Dittmer

    2006-09-12

    The 100-B-22:1 pipelines and associated soils were part of the 100-B Area water treatment facilities. The 100-B-22:1 waste site is limited to those pipelines that interconnected the 185-B Filter House, the 126-B-2 Clearwells, the 185-B Deaeration Plant, and the 190-B Process Pumphouse. None of the 100-B-22:1 pipelines carried environmentally significant contamination. In accordance with the historical information and field observations of this evaluation, the results support a reclassification of this site to No Action required to meet future rural-residential uses and be protective of groundwater and the Columbia River.

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

    SciTech Connect (OSTI)

    Randklev, E.H.

    1993-06-01

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

  16. Hanford Site Secondary Waste Roadmap

    SciTech Connect (OSTI)

    Westsik, Joseph H.

    2009-01-29

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

  17. 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

  18. 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 ...

  19. 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 ...

  20. Waste Disposition Update by Christine Gelles

    Office of Environmental Management (EM)

    Waste Disposition Update Christine Gelles Associate Deputy Assistant Secretary for Waste Management (EM-30) EM SSAB Chairs Meeting Washington, DC 2 October 2012 www.em.doe.gov 2 o ...

  1. 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.

  2. Surveillance study of health effects associated with cleanup of a hazardous waste site, Ralph Gray Trucking Company (a/k/a Westminster Tract Number 2633), Westminster, Orange County, California, Region 9: CERCLIS number CAD981995947

    SciTech Connect (OSTI)

    Hoshiko, S.; Underwood, M.C.; Smith, D.; DeLorenze, G.; Neuhaus, J.

    1999-04-01

    Excavation of a Superfund site, the Ralph Gray Truncking Company located in Westminster Orange County, California was anticipated to release sulfur dioxide and other chemicals. The California Department of Health Services, under cooperative agreement with the Agency for Toxic Substances and Disease Registry, conducted a surveillance study to assess whether illnesses were associated with cleanup activities. A panel primarily composed of more sensitive persons (n = 36) was selected to report daily respiratory symptoms and odors. Exposures included sulfur dioxide (SO{sub 2}) measurements and daily tonnage of waste removed. Analysis used Conditional Likelihood Regression and Generalized Estimating Equations (GEE) methods. Levels of SO{sub 2} were generally higher than usual ambient air, at times exceeding levels which can cause health effects among asthmatics in laboratory settings. Wheeze and cough were significantly associated with tonnage of waste removed, especially on days when the highest amounts of waste were removed. Upper respiratory symptoms were found to be associated with SO{sub 2}, and weak relationships were found with nausea and burning nose and SO{sub 2}.

  3. 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)

  4. 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 ...

  5. Remaining Sites Verification Package for the 100-F-26:15 Miscellaneous Pipelines Associated with the 132-F-6, 1608-F Waste Water Pumping Station, Waste Site Reclassification Form 2007-031

    SciTech Connect (OSTI)

    L. M. Dittmer

    2008-03-18

    The 100-F-26:15 waste site consisted of the remnant portions of underground process effluent and floor drain pipelines that originated at the 105-F Reactor. In accordance with this evaluation, the verification sampling results support a reclassification of this site to Interim Closed Out. The results of verification sampling show that residual contaminant concentrations do not preclude any future uses and allow for unrestricted use of shallow zone soils. The results also demonstrate that residual contaminant concentrations are protective of groundwater and the Columbia River.

  6. Transuranic Waste Characterization Quality Assurance Program Plan

    SciTech Connect (OSTI)

    NONE

    1995-04-30

    This quality assurance plan identifies the data necessary, and techniques designed to attain the required quality, to meet the specific data quality objectives associated with the DOE Waste Isolation Pilot Plant (WIPP). This report specifies sampling, waste testing, and analytical methods for transuranic wastes.

  7. Tank Waste Corporate Board Meeting 11/18/10

    Broader source: Energy.gov [DOE]

    The following documents are associated with the Tank Waste Corporate Board Meeting held on November 18th, 2010.

  8. Tank Waste Corporate Board Meeting 03/05/09

    Broader source: Energy.gov [DOE]

    The following documents are associated with the Tank Waste Corporate Board Meeting held on March 5th, 2009. 

  9. Tank Waste Corporate Board Meeting 07/29/09

    Broader source: Energy.gov [DOE]

    The following documents are associated with the Tank Waste Corporate Board Meeting held on July 29th, 2009.

  10. Tank Waste Corporate Board Meeting 07/24/08

    Broader source: Energy.gov [DOE]

    The following documents are associated with the Tank Waste Corporate Board Meeting held on July 24th, 2008.

  11. Tank Waste Corporate Board Meeting 08/01/12

    Broader source: Energy.gov [DOE]

    The following documents are associated with the Tank Waste Corporate Board Meeting held on August 1st, 2012.

  12. Fire hazards analysis of central waste complex

    SciTech Connect (OSTI)

    Irwin, R.M.

    1996-05-30

    This document analyzes the fire hazards associated with operational the Central Waste Complex. It provides the analysis and recommendations necessary to ensure compliance with applicable fire codes.

  13. Low temperature waste form process intensification

    SciTech Connect (OSTI)

    Fox, K. M.; Cozzi, A. D.; Hansen, E. K.; Hill, K. A.

    2015-09-30

    This study successfully demonstrated process intensification of low temperature waste form production. Modifications were made to the dry blend composition to enable a 50% increase in waste concentration, thus allowing for a significant reduction in disposal volume and associated costs. Properties measurements showed that the advanced waste form can be produced using existing equipment and processes. Performance of the waste form was equivalent or better than the current baseline, with approximately double the amount of waste incorporation. The results demonstrate the feasibility of significantly accelerating low level waste immobilization missions across the DOE complex and at environmental remediation sites worldwide.

  14. Acceptable knowledge document for INEEL stored transuranic waste -- Rocky Flats Plant waste. Revision 2

    SciTech Connect (OSTI)

    1998-01-23

    This document and supporting documentation provide a consistent, defensible, and auditable record of acceptable knowledge for waste generated at the Rocky Flats Plant which is currently in the accessible storage inventory at the Idaho National Engineering and Environmental Laboratory. The inventory consists of transuranic (TRU) waste generated from 1972 through 1989. Regulations authorize waste generators and treatment, storage, and disposal facilities to use acceptable knowledge in appropriate circumstances to make hazardous waste determinations. Acceptable knowledge includes information relating to plant history, process operations, and waste management, in addition to waste-specific data generated prior to the effective date of the RCRA regulations. This document is organized to provide the reader a comprehensive presentation of the TRU waste inventory ranging from descriptions of the historical plant operations that generated and managed the waste to specific information about the composition of each waste group. Section 2 lists the requirements that dictate and direct TRU waste characterization and authorize the use of the acceptable knowledge approach. In addition to defining the TRU waste inventory, Section 3 summarizes the historical operations, waste management, characterization, and certification activities associated with the inventory. Sections 5.0 through 26.0 describe the waste groups in the inventory including waste generation, waste packaging, and waste characterization. This document includes an expanded discussion for each waste group of potential radionuclide contaminants, in addition to other physical properties and interferences that could potentially impact radioassay systems.

  15. 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

  16. 1994 Solid waste forecast container volume summary

    SciTech Connect (OSTI)

    Templeton, K.J.; Clary, J.L.

    1994-09-01

    This report describes a 30-year forecast of the solid waste volumes by container type. The volumes described are low-level mixed waste (LLMW) and transuranic/transuranic mixed (TRU/TRUM) waste. These volumes and their associated container types will be generated or received at the US Department of Energy Hanford Site for storage, treatment, and disposal at Westinghouse Hanford Company`s Solid Waste Operations Complex (SWOC) during a 30-year period from FY 1994 through FY 2023. The forecast data for the 30-year period indicates that approximately 307,150 m{sup 3} of LLMW and TRU/TRUM waste will be managed by the SWOC. The main container type for this waste is 55-gallon drums, which will be used to ship 36% of the LLMW and TRU/TRUM waste. The main waste generator forecasting the use of 55-gallon drums is Past Practice Remediation. This waste will be generated by the Environmental Restoration Program during remediation of Hanford`s past practice sites. Although Past Practice Remediation is the primary generator of 55-gallon drums, most waste generators are planning to ship some percentage of their waste in 55-gallon drums. Long-length equipment containers (LECs) are forecasted to contain 32% of the LLMW and TRU/TRUM waste. The main waste generator forecasting the use of LECs is the Long-Length Equipment waste generator, which is responsible for retrieving contaminated long-length equipment from the tank farms. Boxes are forecasted to contain 21% of the waste. These containers are primarily forecasted for use by the Environmental Restoration Operations--D&D of Surplus Facilities waste generator. This waste generator is responsible for the solid waste generated during decontamination and decommissioning (D&D) of the facilities currently on the Surplus Facilities Program Plan. The remaining LLMW and TRU/TRUM waste volume is planned to be shipped in casks and other miscellaneous containers.

  17. Waste/By-Product Hydrogen

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

    WASTE/BY-PRODUCT HYDROGEN Ruth Cox DOE/DOD Workshop January 13, 2011 January 13, 2011 Fuel Cell and Hydrogen Energy Association The Fuel Cell and Hydrogen Energy Association FCHEA ƒ Trade Association for the industry ƒ Member driven - Market focused ƒ Developers, suppliers, customers, nonprofits, government Ad ƒ Advocacy ƒ Safety and standardization ƒ Education ƒ Strategic Alliances Fuel Cell and Hydrogen Energy Association O M b Our Members 5 W t /B d t H d Waste/By-product Hydrogen

  18. DRAFT EM SSAB Chairs Meeting Waste Disposition Strategies...

    Office of Environmental Management (EM)

    EM HQ Updates Waste Disposition Overview Christine Gelles Associate Deputy Assistant Secretary for Waste Management Office of Environmental Management EM SSAB Chairs Meeting 5 ...

  19. 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

  20. 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 ...

  1. 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.

  2. Reduced waste generation, FY 1986

    SciTech Connect (OSTI)

    Not Available

    1986-02-01

    The United States Department of Energy is committed to the principles of minimizing the quantity and transuranic content of its transuranium (TRU) waste being generated at its nuclear facilities. The reasons are to reduce costs associated with waste handling and disposal, and also to reduce radiation exposure to workers and risk for radionuclide release to man and the environment. The purpose of this document is to provide the USDOE with a plan of research and development tasks for waste minimization, and is prepared so as to provide the maximum impact on volumes based on cost/benefit factors. The document is to be updated annually or as needed to reflect current and future tasks. The Reduced Waste Generation (RWG) tasks encompass a wide range of activities with the principal goals of (1) preventing the generation of waste and (2) converting TRU waste into low-level wastes (LLW) by sorting or decontamination. Concepts for reducing the volume such as in incineration and compaction are considered within the discipline of Reduced Waste Generation, but are considered as somewhat developed technology with only a need for implementation. 33 refs.

  3. 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.

  4. Waste Hoist

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

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

  5. Waste Hoist

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

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

  6. Waste processing air cleaning

    SciTech Connect (OSTI)

    Kriskovich, J.R.

    1998-07-27

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

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

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

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

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

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

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

  9. Application of EPA regulations to low-level radioactive waste

    SciTech Connect (OSTI)

    Bowerman, B.S.; Piciulo, P.L.

    1985-01-01

    The survey reported here was conducted with the intent of identifying categories of low-level radioactive wastes which would be classified under EPA regulations 40 CFR Part 261 as hazardous due to the chemical properties of the waste. Three waste types are identified under these criteria as potential radioactive mixed wastes: wastes containing organic liquids; wastes containing lead metal; and wastes containing chromium. The survey also indicated that certain wastes, specific to particular generators, may also be radioactive mixed wastes. Ultimately, the responsibility for determining whether a facility's wastes are mixed wastes rest with the generator. However, the uncertainties as to which regulations are applicable, and the fact that no legal definition of mixed wastes exists, make such a determination difficult. In addition to identifying mixed wastes, appropriate methods for the management of mixed wastes must be defined. In an ongoing study, BNL is evaluating options for the management of mixed wastes. These options will include segregation, substitution, and treatments to reduce or eliminate chemical hazards associated with the wastes listed above. The impacts of the EPA regulations governing hazardous wastes on radioactive mixed waste cannot be assessed in detail until the applicability of these regulations is agreed upon. This issue is still being discussed by EPA and NRC and should be resolved in the near future. Areas of waste management which may affect generators of mixed wastes include: monitoring/tracking of wastes before shipment; chemical testing of wastes; permits for treatment of storage of wastes; and additional packaging requirements. 3 refs., 1 fig., 2 tabs.

  10. Epithermal interrogation of fissile waste

    SciTech Connect (OSTI)

    Coop, K.L.; Hollas, C.L.

    1996-09-01

    Self-shielding of interrogating thermal neutrons in lumps of fissile material can be a major source of error in transuranic waste assay using the widely employed differential dieaway technique. We are developing a new instrument, the combined thermal/epithermal neutron (CTEN) interrogation instrument to detect the occurrence of self- shielding and mitigate its effects. Neutrons are moderated in the graphite walls of the CTEN instrument to provide an interrogating flux of epithermal and thermal neutrons. The induced prompt fission neutrons are detected in proportional counters. We report the results of measurements made with the CTEN instrument, using minimal and highly self-shielding plutonium and uranium sources in 55 gallon drums containing a variety of mock waste matrices. Fissile isotopes and waste forms for which the method is most applicable, and limitations associated with the hydrogen content of the waste package/matrix are described.

  11. 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 ...

  12. 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 ...

  13. 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

  14. Waste Heat Recapture from Supermarket Refrigeration Systems

    SciTech Connect (OSTI)

    Fricke, Brian A

    2011-11-01

    The objective of this project was to determine the potential energy savings associated with improved utilization of waste heat from supermarket refrigeration systems. Existing and advanced strategies for waste heat recovery in supermarkets were analyzed, including options from advanced sources such as combined heat and power (CHP), micro-turbines and fuel cells.

  15. 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 ...

  16. 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 ...

  17. Electrochemical/Pyrometallurgical Waste Stream Processing and Waste Form Fabrication

    SciTech Connect (OSTI)

    Steven Frank; Hwan Seo Park; Yung Zun Cho; William Ebert; Brian Riley

    2015-07-01

    This report summarizes treatment and waste form options being evaluated for waste streams resulting from the electrochemical/pyrometallurgical (pyro ) processing of used oxide nuclear fuel. The technologies that are described are South Korean (Republic of Korea – ROK) and United States of America (US) ‘centric’ in the approach to treating pyroprocessing wastes and are based on the decade long collaborations between US and ROK researchers. Some of the general and advanced technologies described in this report will be demonstrated during the Integrated Recycle Test (IRT) to be conducted as a part of the Joint Fuel Cycle Study (JFCS) collaboration between US Department of Energy (DOE) and ROK national laboratories. The JFCS means to specifically address and evaluated the technological, economic, and safe guard issues associated with the treatment of used nuclear fuel by pyroprocessing. The IRT will involve the processing of commercial, used oxide fuel to recover uranium and transuranics. The recovered transuranics will then be fabricated into metallic fuel and irradiated to transmutate, or burn the transuranic elements to shorter lived radionuclides. In addition, the various process streams will be evaluated and tested for fission product removal, electrolytic salt recycle, minimization of actinide loss to waste streams and waste form fabrication and characterization. This report specifically addresses the production and testing of those waste forms to demonstrate their compatibility with treatment options and suitability for disposal.

  18. 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.

  19. Hazardous Waste Facility Permit Public Comments to Community...

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

    the Laboratory's corrective action and waste management activities and associated environmental issues. It is composed of citizens representing the communities and pueblos of...

  20. EM International Program Presentation for Waste Management 2015...

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

    EM Associate Principal Deputy Assistant Secretary Monica Regalbuto gave a presentation on EM's International Program at the Waste Management Conference in March 2015 in Phoenix. EM ...

  1. High Level Waste Management Division . H L W System Plan

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

    ... ANSIIANS standards, and National Fire Protection Association NFPA are utilized. ... et. aI., Annual Radioactive waste Tank Inspection report - 1992, WSRC-TR-93- 0166). ...

  2. Fire hazards analysis of transuranic waste storage and assay facility

    SciTech Connect (OSTI)

    Busching, K.R., Westinghouse Hanford

    1996-07-31

    This document analyzes the fire hazards associated with operations at the Central Waste Complex. It provides the analysis and recommendations necessary to ensure compliance with applicable fire codes.

  3. Salt Waste Processing Facility, Line Management Review Board Charter

    Broader source: Energy.gov [DOE]

    The Line Management Review Board (LMRB) serves an important oversight function to monitor the readiness processes and associated deliverables for the Salt Waste Processing Facility (SWPF). The...

  4. Tank Waste Corporate Board | Department of Energy

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

    The following documents are associated with the Tank Waste Corporate Board Meeting held on November 6th, 2008. Note: (Please contact Steven Ross at steven.ross@em.doe.gov for a HLW ...

  5. Solid Waste Assurance Program Implementation Plan

    SciTech Connect (OSTI)

    Irons, L.G.

    1995-06-19

    On June 6, 1995, a waiver to Hanford Site Solid Waste Acceptance Criteria, was approved by the US Department of Energy Richland Operations Office (RL) to replace the low-level, mixed, and transuranic (TRU) generator assessment programs with the Solid Waste Assurance Program (SWAP). This is associated with a waiver that was approved on March 16, 1995 to replace the Storage/Disposal Approval Record (SDAR) requirements with the Waste Specification System (WSS). This implementation plan and the SWAP applies to Solid Waste Disposal (SWD) functions, facilities, and personnel who perform waste acceptance, verification, receipt, and management functions of dangerous, radioactive, and mixed waste from on- and off-site generators who ship to or within the Hanford Site for treatment, storage, and/or disposal (TSD) at SWD TSD facilities.

  6. 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.

  7. 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.

  8. Tank Waste Strategy Update

    Office of Environmental Management (EM)

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

  9. Waste Heat Recovery

    Office of Environmental Management (EM)

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

  10. 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 ...

  11. 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 ...

  12. Waste/By-Product Hydrogen | Department of Energy

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

    Waste/By-Product Hydrogen Waste/By-Product Hydrogen Presentation by Ruth Cox, Fuel Cell and Hydrogen Energy Association, at the DOE-DOD Waste-to-Energy using Fuel Cells Workshop held Jan. 13, 2011 waste_cox.pdf (1.15 MB) More Documents & Publications Biogas Technologies and Integration with Fuel Cells Tri-Generation Success Story: World's First Tri-Gen Energy Station-Fountain Valley Biogas and Fuel Cells

  13. Recycling Of Cis Photovoltaic Waste

    DOE Patents [OSTI]

    Drinkard, Jr., William F.; Long, Mark O.; Goozner; Robert E.

    1998-07-14

    A method for extracting and reclaiming metals from scrap CIS photovoltaic cells and associated photovoltaic manufacturing waste by leaching the waste with dilute nitric acid, skimming any plastic material from the top of the leaching solution, separating glass substrate from the leachate, electrolyzing the leachate to plate a copper and selenium metal mixture onto a first cathode, replacing the cathode with a second cathode, re-electrolyzing the leachate to plate cadmium onto the second cathode, separating the copper from selenium, and evaporating the depleted leachate to yield a zinc and indium containing solid.

  14. 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 ...

  15. EA-1962: Analysis for Below Grade Suspect Transuranic (TRU) Waste at Technical Area (TA)-54

    Broader source: Energy.gov [DOE]

    DOE is preparing an EA to evaluate the legacy suspect transuranic (TRU) waste at Area G for the purposes of reclassification of waste type and determination of a final disposal path. Per DOE Order 435.1, Change 1, Radioactive Waste Management, and its associated guide, legacy waste at Los Alamos National Laboratory that contained TRU waste was stored and managed as TRU waste. The waste was given an interim classification for the purposes of applying the most restrictive standard until the waste could be adequately characterized and a final determination on the disposition classification was made.

  16. 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.

  17. 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.

  18. DWPF waste form compliance plan (Draft Revision)

    SciTech Connect (OSTI)

    Plodinec, M.J.; Marra, S.L.

    1991-01-01

    The Department of Energy currently has over 100 million liters of high-level radioactive waste in storage at the Savannah River Site (SRS). In the late 1970's, the Department of Energy recognized that there were significant safety and cost advantages associated with immobilizing the high-level waste in a stable solid form. Several alternative waste forms were evaluated in terms of product quality and reliability of fabrication. This evaluation led to a decision to build the Defense Waste Processing Facility (DWPF) at SRS to convert the easily dispersed liquid waste to borosilicate glass. In accordance with the NEPA (National Environmental Policy Act) process, an Environmental Impact Statement was prepared for the facility, as well as an Environmental Assessment of the alternative waste forms, and issuance of a Record of Decision (in December, 1982) on the waste form. The Department of Energy, recognizing that start-up of the DWPF would considerably precede licensing of a repository, instituted a Waste Acceptance Process to ensure that these canistered waste forms would be acceptable for eventual disposal at a federal repository. This report is a revision of the DWPF compliance plan.

  19. DWPF waste form compliance plan (Draft Revision)

    SciTech Connect (OSTI)

    Plodinec, M.J.; Marra, S.L.

    1991-12-31

    The Department of Energy currently has over 100 million liters of high-level radioactive waste in storage at the Savannah River Site (SRS). In the late 1970`s, the Department of Energy recognized that there were significant safety and cost advantages associated with immobilizing the high-level waste in a stable solid form. Several alternative waste forms were evaluated in terms of product quality and reliability of fabrication. This evaluation led to a decision to build the Defense Waste Processing Facility (DWPF) at SRS to convert the easily dispersed liquid waste to borosilicate glass. In accordance with the NEPA (National Environmental Policy Act) process, an Environmental Impact Statement was prepared for the facility, as well as an Environmental Assessment of the alternative waste forms, and issuance of a Record of Decision (in December, 1982) on the waste form. The Department of Energy, recognizing that start-up of the DWPF would considerably precede licensing of a repository, instituted a Waste Acceptance Process to ensure that these canistered waste forms would be acceptable for eventual disposal at a federal repository. This report is a revision of the DWPF compliance plan.

  20. Radiological, physical, and chemical characterization of transuranic wastes stored at the Idaho National Engineering Laboratory

    SciTech Connect (OSTI)

    Apel, M.L.; Becker, G.K.; Ragan, Z.K.; Frasure, J.; Raivo, B.D.; Gale, L.G.; Pace, D.P.

    1994-03-01

    This document provides radiological, physical and chemical characterization data for transuranic radioactive wastes and transuranic radioactive and hazardous (i.e., mixed) wastes stored at the Idaho National Engineering Laboratory and considered for treatment under the Private Sector Participation Initiative Program (PSPI). Waste characterization data are provided in the form of INEL Waste Profile Sheets. These documents provide, for each content code, information on waste identification, waste description, waste storage configuration, physical/chemical waste composition, radionuclide and associated alpha activity waste characterization data, and hazardous constituents present in the waste. Information is provided for 139 waste streams which represent an estimated total volume of 39,380{sup 3} corresponding to a total mass of approximately 19,000,000 kg. In addition, considerable information concerning alpha, beta, gamma, and neutron source term data specific to Rocky Flats Plant generated waste forms stored at the INEL are provided to assist in facility design specification.

  1. 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...

  2. 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.

  3. 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.

  4. Remote-handled transuranic waste study

    SciTech Connect (OSTI)

    1995-10-01

    The Waste Isolation Pilot Plant (WIPP) was developed by the US Department of Energy (DOE) as a research and development facility to demonstrate the safe disposal of transuranic (TRU) radioactive wastes generated from the Nation`s defense activities. The WIPP disposal inventory will include up to 250,000 cubic feet of TRU wastes classified as remote handled (RH). The remaining inventory will include contact-handled (CH) TRU wastes, which characteristically have less specific activity (radioactivity per unit volume) than the RH-TRU wastes. The WIPP Land Withdrawal Act (LWA), Public Law 102-579, requires a study of the effect of RH-TRU waste on long-term performance. This RH-TRU Waste Study has been conducted to satisfy the requirements defined by the LWA and is considered by the DOE to be a prudent exercise in the compliance certification process of the WIPP repository. The objectives of this study include: conducting an evaluation of the impacts of RH-TRU wastes on the performance assessment (PA) of the repository to determine the effects of Rh-TRU waste as a part of the total WIPP disposal inventory; and conducting a comparison of CH-TRU and RH-TRU wastes to assess the differences and similarities for such issues as gas generation, flammability and explosiveness, solubility, and brine and geochemical interactions. This study was conducted using the data, models, computer codes, and information generated in support of long-term compliance programs, including the WIPP PA. The study is limited in scope to post-closure repository performance and includes an analysis of the issues associated with RH-TRU wastes subsequent to emplacement of these wastes at WIPP in consideration of the current baseline design. 41 refs.

  5. Associate Directorate for Environmental Programs Update July...

    Office of Environmental Management (EM)

    July 30, 2014 Associate Directorate for Environmental Programs Update July 30, 2014 Topics: LANL Nitrate Salts Waste Chromium groundwater Remediation Storm Water Field Work PDF...

  6. 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.

  7. 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

  8. 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.

  9. 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.

  10. Progress of the High Level Waste Program at the Defense Waste Processing Facility - 13178

    SciTech Connect (OSTI)

    Bricker, Jonathan M.; Fellinger, Terri L.; Staub, Aaron V.; Ray, Jeff W.; Iaukea, John F. [Savannah River Remediation, Aiken, South Carolina, 29808 (United States)] [Savannah River Remediation, Aiken, South Carolina, 29808 (United States)

    2013-07-01

    The Defense Waste Processing Facility at the Savannah River Site treats and immobilizes High Level Waste into a durable borosilicate glass for safe, permanent storage. The High Level Waste program significantly reduces environmental risks associated with the storage of radioactive waste from legacy efforts to separate fissionable nuclear material from irradiated targets and fuels. In an effort to support the disposition of radioactive waste and accelerate tank closure at the Savannah River Site, the Defense Waste Processing Facility recently implemented facility and flowsheet modifications to improve production by 25%. These improvements, while low in cost, translated to record facility production in fiscal years 2011 and 2012. In addition, significant progress has been accomplished on longer term projects aimed at simplifying and expanding the flexibility of the existing flowsheet in order to accommodate future processing needs and goals. (authors)

  11. 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 ...

  12. 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

  13. 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

  14. 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

  15. Closed Fuel Cycle Waste Treatment Strategy

    SciTech Connect (OSTI)

    Vienna, J. D.; Collins, E. D.; Crum, J. V.; Ebert, W. L.; Frank, S. M.; Garn, T. G.; Gombert, D.; Jones, R.; Jubin, R. T.; Maio, V. C.; Marra, J. C.; Matyas, J.; Nenoff, T. M.; Riley, B. J.; Sevigny, G. J.; Soelberg, N. R.; Strachan, D. M.; Thallapally, P. K.; Westsik, J. H.

    2015-02-01

    This study is aimed at evaluating the existing waste management approaches for nuclear fuel cycle facilities in comparison to the objectives of implementing an advanced fuel cycle in the U.S. under current legal, regulatory, and logistical constructs. The study begins with the Global Nuclear Energy Partnership (GNEP) Integrated Waste Management Strategy (IWMS) (Gombert et al. 2008) as a general strategy and associated Waste Treatment Baseline Study (WTBS) (Gombert et al. 2007). The tenets of the IWMS are equally valid to the current waste management study. However, the flowsheet details have changed significantly from those considered under GNEP. In addition, significant additional waste management technology development has occurred since the GNEP waste management studies were performed. This study updates the information found in the WTBS, summarizes the results of more recent technology development efforts, and describes waste management approaches as they apply to a representative full recycle reprocessing flowsheet. Many of the waste management technologies discussed also apply to other potential flowsheets that involve reprocessing. These applications are occasionally discussed where the data are more readily available. The report summarizes the waste arising from aqueous reprocessing of a typical light-water reactor (LWR) fuel to separate actinides for use in fabricating metal sodium fast reactor (SFR) fuel and from electrochemical reprocessing of the metal SFR fuel to separate actinides for recycle back into the SFR in the form of metal fuel. The primary streams considered and the recommended waste forms include; Tritium in low-water cement in high integrity containers (HICs); Iodine-129: As a reference case, a glass composite material (GCM) formed by the encapsulation of the silver Mordenite (AgZ) getter material in a low-temperature glass is assumed. A number of alternatives with distinct advantages are also considered including a fused silica waste form

  16. Characterization of industrial process waste heat and input heat streams

    SciTech Connect (OSTI)

    Wilfert, G.L.; Huber, H.B.; Dodge, R.E.; Garrett-Price, B.A.; Fassbender, L.L.; Griffin, E.A.; Brown, D.R.; Moore, N.L.

    1984-05-01

    The nature and extent of industrial waste heat associated with the manufacturing sector of the US economy are identified. Industry energy information is reviewed and the energy content in waste heat streams emanating from 108 energy-intensive industrial processes is estimated. Generic types of process equipment are identified and the energy content in gaseous, liquid, and steam waste streams emanating from this equipment is evaluated. Matchups between the energy content of waste heat streams and candidate uses are identified. The resultant matrix identifies 256 source/sink (waste heat/candidate input heat) temperature combinations. (MHR)

  17. Encapsulation of hazardous wastes into agglomerates

    SciTech Connect (OSTI)

    Guloy, A.

    1992-01-28

    The objective of this study was to investigate the feasibility of using the cementitious properties and agglomeration characteristics of coal conversion byproducts to encapsulate and immobilize hazardous waste materials. The intention was to establish an economical way of co-utilization and co-disposal of wastes. In addition, it may aid in the eradication of air pollution problems associated with the fine-powdery nature of fly ash. Encapsulation into agglomerates is a novel approach of treating toxic waste. Although encapsulation itself is not a new concept, existing methods employ high-cost resins that render them economically unfeasible. In this investigation, the toxic waste was contained in a concrete-like matrix whereby fly ash and other cementitious waste materials were utilized. The method incorporates the principles of solidification, stabilization and agglomeration. Another aspect of the study is the evaluation of the agglomeration as possible lightweight aggregates. Since fly ash is commercially used as an aggregate, it would be interesting to study the effect of incorporating toxic wastes in the strength development of the granules. In the investigation, the fly ash self-cementation process was applied to electroplating sludges as the toxic waste. The process hoped to provide a basis for delisting of the waste as hazardous and, thereby greatly minimize the cost of its disposal. Owing to the stringent regulatory requirements for hauling and disposal of hazardous waste, the cost of disposal is significant. The current practice for disposal is solidifying the waste with portland cement and dumping the hardened material in the landfill where the cost varies between $700--950/ton. Partially replacing portland cement with fly ash in concrete has proven beneficial, therefore applying the same principles in the treatment of toxic waste looked very promising.

  18. 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,

  19. 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.

  20. 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.

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

    Office of Environmental Management (EM)

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

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

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

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

  3. 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

  4. Nuclear Waste Partnership, LLC

    Office of Environmental Management (EM)

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

  5. Hanford Tank Waste Residuals

    Office of Environmental Management (EM)

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

  6. Waste Specification Records - Hanford Site

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

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

  7. Solid waste handling

    SciTech Connect (OSTI)

    Parazin, R.J.

    1995-05-31

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

  8. Waste Heat Recovery

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

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

  9. Waste disposal package

    DOE Patents [OSTI]

    Smith, M.J.

    1985-06-19

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

  10. Model development for household waste prevention behaviour

    SciTech Connect (OSTI)

    Bortoleto, Ana Paula; Kurisu, Kiyo H.; Hanaki, Keisuke

    2012-12-15

    Highlights: Black-Right-Pointing-Pointer We model waste prevention behaviour using structure equation modelling. Black-Right-Pointing-Pointer We merge attitude-behaviour theories with wider models from environmental psychology. Black-Right-Pointing-Pointer Personal norms and perceived behaviour control are the main behaviour predictors. Black-Right-Pointing-Pointer Environmental concern, moral obligation and inconvenience are the main influence on the behaviour. Black-Right-Pointing-Pointer Waste prevention and recycling are different dimensions of waste management behaviour. - Abstract: Understanding waste prevention behaviour (WPB) could enable local governments and decision makers to design more-effective policies for reducing the amount of waste that is generated. By merging well-known attitude-behaviour theories with elements from wider models from environmental psychology, an extensive cognitive framework that provides new and valuable insights is developed for understanding the involvement of individuals in waste prevention. The results confirm the usefulness of the theory of planned behaviour and of Schwartz's altruistic behaviour model as bases for modelling participation in waste prevention. A more elaborate integrated model of prevention was shown to be necessary for the complete analysis of attitudinal aspects associated with waste prevention. A postal survey of 158 respondents provided empirical support for eight of 12 hypotheses. The proposed structural equation indicates that personal norms and perceived behaviour control are the main predictors and that, unlike the case of recycling, subjective norms have a weak influence on WPB. It also suggests that, since social norms have not presented a direct influence, WPB is likely to be influenced by a concern for the environment and the community as well by perceptions of moral obligation and inconvenience. Results also proved that recycling and waste prevention represent different dimensions of waste

  11. Indicators of waste management efficiency related to different territorial conditions

    SciTech Connect (OSTI)

    Passarini, Fabrizio, E-mail: fabrizio.passarini@unibo.it [University of Bologna, Dept. Industrial Chemistry and Materials, viale Risorgimento 4, I-40136 Bologna (Italy); Vassura, Ivano, E-mail: ivano.vassura@unibo.it [University of Bologna, Dept. Industrial Chemistry and Materials, viale Risorgimento 4, I-40136 Bologna (Italy); Monti, Francesco, E-mail: fmonti84@gmail.com [University of Bologna, Dept. Industrial Chemistry and Materials, viale Risorgimento 4, I-40136 Bologna (Italy); Morselli, Luciano, E-mail: luciano.morselli@unibo.it [University of Bologna, Dept. Industrial Chemistry and Materials, viale Risorgimento 4, I-40136 Bologna (Italy); Villani, Barbara, E-mail: bvillani@arpa.emr.it [Regional Environmental Protection Agency (Emilia-Romagna Region), Largo Caduti del Lavoro 6, I-40122 Bologna (Italy)

    2011-04-15

    The amount of waste produced and the control of separate collection are crucial issues for the planning of a territorial Integrated Waste Management System, enabling the allocation of each sorted waste fraction to the proper treatment and recycling processes. The present study focuses on assessing indicators of different waste management systems in areas characterized by different territorial conditions. The investigated case study concerns the municipalities of Emilia Romagna (northern Italy), which present a rather uniform socioeconomic situation, but a variety of geographic, urban and waste management characteristics. A survey of waste generation and collection rates was carried out, and correlated with the different territorial conditions, classifying the municipalities according to altitude and population density. The best environmental performances, in terms of high separate collection rate, were found on average in rural areas in the plain, while the lowest waste generation was associated with rural hill towns.

  12. Guidelines for developing certification programs for newly generated TRU waste

    SciTech Connect (OSTI)

    Whitty, W.J.; Ostenak, C.A.; Pillay, K.K.S.; Geoffrion, R.R.

    1983-05-01

    These guidelines were prepared with direction from the US Department of Energy (DOE) Transuranic (TRU) Waste Management Program in support of the DOE effort to certify that newly generated TRU wastes meet the Waste Isolation Pilot Plant (WIPP) Waste Acceptance Criteria. The guidelines provide instructions for generic Certification Program preparation for TRU-waste generators preparing site-specific Certification Programs in response to WIPP requirements. The guidelines address all major aspects of a Certification Program that are necessary to satisfy the WIPP Waste Acceptance Criteria and their associated Compliance Requirements and Certification Quality Assurance Requirements. The details of the major element of a Certification Program, namely, the Certification Plan, are described. The Certification Plan relies on supporting data and control documentation to provide a traceable, auditable account of certification activities. Examples of specific parts of the Certification Plan illustrate the recommended degree of detail. Also, a brief description of generic waste processes related to certification activities is included.

  13. An expert system framework for nondestructive waste assay

    SciTech Connect (OSTI)

    Becker, G.K.

    1996-10-01

    Management and disposition of transuranic (RU) waste forms necessitates determining entrained RU and associated radioactive material quantities as per National RU Waste Characterization Program requirements. Technical justification and demonstration of a given NDA method used to determine RU mass and uncertainty in accordance with program quality assurance is difficult for many waste forms. Difficulties are typically founded in waste NDA methods that employ standards compensation and/or employment of simplifying assumptions on waste form configurations. Capability to determine and justify RU mass and mass uncertainty can be enhanced through integration of waste container data/information using expert system and empirical data-driven techniques with conventional data acquisition and analysis. Presented is a preliminary expert system framework that integrates the waste form data base, alogrithmic techniques, statistical analyses, expert domain knowledge bases, and empirical artificial intelligence modules into a cohesive system. The framework design and bases in addition to module development activities are discussed.

  14. Requirements for shipment of DOE radioactive mixed waste

    SciTech Connect (OSTI)

    Gablin, K.; No, Hyo; Herman, J.

    1993-08-01

    There are several sources of radioactive mixed waste (RMW) at Argonne National Laboratory which, in the past, were collected at waste tanks and/or sludge tanks. They were eventually pumped out by special pumps and processed in an evaporator located in the waste operations area in Building No. 306. Some of this radioactive mixed waste represents pure elementary mercury. These cleaning tanks must be manually cleaned up because the RMW material was too dense to pump with the equipment in use. The four tanks being discussed in this report are located in Building No. 306. They are the Acid Waste Tank, IMOX/FLOC Tanks, Evaporation Feed Tanks, and Waste Storage Tanks. All of these tanks are characterized and handled separately. This paper discusses the process and the requirements for characterization and the associated paperwork for Argonne Waste to be shipped to Westinghouse Hanford Company for storage.

  15. Low-level waste inventory, characteristics, generation, and facility assessment for treatment, storage, and disposal alternatives considered in the US Department of Energy waste management programmatic environmental impact statement

    SciTech Connect (OSTI)

    Goyette, M.L.; Dolak, D.A.

    1996-12-01

    This report provides technical support information for use in analyzing environmental impacts associated with U.S. Department of Energy (DOE) low-level radioactive waste (LLW) management alternatives in the Waste-Management (WM) Programmatic Environmental Impact Statement (PEIS). Waste loads treated and disposed of for each of the LLW alternatives considered in the DOE WM PEIS are presented. Waste loads are presented for DOE Waste Management (WM) wastes, which are generated from routine operations. Radioactivity concentrations and waste quantities for treatment and disposal under the different LLW alternatives are described for WM waste. 76 refs., 14 figs., 42 tabs.

  16. Idaho National Engineering Laboratory code assessment of the Rocky Flats transuranic waste

    SciTech Connect (OSTI)

    1995-07-01

    This report is an assessment of the content codes associated with transuranic waste shipped from the Rocky Flats Plant in Golden, Colorado, to INEL. The primary objective of this document is to characterize and describe the transuranic wastes shipped to INEL from Rocky Flats by item description code (IDC). This information will aid INEL in determining if the waste meets the waste acceptance criteria (WAC) of the Waste Isolation Pilot Plant (WIPP). The waste covered by this content code assessment was shipped from Rocky Flats between 1985 and 1989. These years coincide with the dates for information available in the Rocky Flats Solid Waste Information Management System (SWIMS). The majority of waste shipped during this time was certified to the existing WIPP WAC. This waste is referred to as precertified waste. Reassessment of these precertified waste containers is necessary because of changes in the WIPP WAC. To accomplish this assessment, the analytical and process knowledge available on the various IDCs used at Rocky Flats were evaluated. Rocky Flats sources for this information include employee interviews, SWIMS, Transuranic Waste Certification Program, Transuranic Waste Inspection Procedure, Backlog Waste Baseline Books, WIPP Experimental Waste Characterization Program (headspace analysis), and other related documents, procedures, and programs. Summaries are provided of: (a) certification information, (b) waste description, (c) generation source, (d) recovery method, (e) waste packaging and handling information, (f) container preparation information, (g) assay information, (h) inspection information, (i) analytical data, and (j) RCRA characterization.

  17. Municipal waste processing apparatus

    DOE Patents [OSTI]

    Mayberry, J.L.

    1988-04-13

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

  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. Admin Chg 2, dated 6-8-11, supersedes DOE M 435.1-1 Chg 1.

  19. Central Facilities Area Facilities Radioactive Waste Management Basis and DOE Manual 435.1-1 Compliance Tables

    SciTech Connect (OSTI)

    Lisa Harvego; Brion Bennett

    2011-11-01

    Department of Energy Order 435.1, 'Radioactive Waste Management,' along with its associated manual and guidance, requires development and maintenance of a radioactive waste management basis for each radioactive waste management facility, operation, and activity. This document presents a radioactive waste management basis for Idaho National Laboratory's Central Facilities Area facilities that manage radioactive waste. The radioactive waste management basis for a facility comprises existing laboratory-wide and facilityspecific documents. Department of Energy Manual 435.1-1, 'Radioactive Waste Management Manual,' facility compliance tables also are presented for the facilities. The tables serve as a tool for developing the radioactive waste management basis.

  20. Research and Education Campus Facilities Radioactive Waste Management Basis and DOE Manual 435.1-1 Compliance Tables

    SciTech Connect (OSTI)

    L. Harvego; Brion Bennett

    2011-11-01

    U.S. Department of Energy Order 435.1, 'Radioactive Waste Management,' along with its associated manual and guidance, requires development and maintenance of a radioactive waste management basis for each radioactive waste management facility, operation, and activity. This document presents a radioactive waste management basis for Idaho National Laboratory Research and Education Campus facilities that manage radioactive waste. The radioactive waste management basis for a facility comprises existing laboratory-wide and facility-specific documents. Department of Energy Manual 435.1-1, 'Radioactive Waste Management Manual,' facility compliance tables also are presented for the facilities. The tables serve as a tool to develop the radioactive waste management basis.

  1. Materials and Security Consolidation Complex Facilities Radioactive Waste Management Basis and DOE Manual 435.1-1 Compliance Tables

    SciTech Connect (OSTI)

    Not Listed

    2011-09-01

    Department of Energy Order 435.1, 'Radioactive Waste Management,' along with its associated manual and guidance, requires development and maintenance of a radioactive waste management basis for each radioactive waste management facility, operation, and activity. This document presents a radioactive waste management basis for Idaho National Laboratory's Materials and Security Consolidation Center facilities that manage radioactive waste. The radioactive waste management basis for a facility comprises existing laboratory-wide and facility-specific documents. Department of Energy Manual 435.1-1, 'Radioactive Waste Management Manual,' facility compliance tables also are presented for the facilities. The tables serve as a tool for developing the radioactive waste management basis.

  2. Materials and Fuels Complex Facilities Radioactive Waste Management Basis and DOE Manual 435.1-1 Compliance Tables

    SciTech Connect (OSTI)

    Lisa Harvego; Brion Bennett

    2011-09-01

    Department of Energy Order 435.1, 'Radioactive Waste Management,' along with its associated manual and guidance, requires development and maintenance of a radioactive waste management basis for each radioactive waste management facility, operation, and activity. This document presents a radioactive waste management basis for Idaho National Laboratory's Materials and Fuels Complex facilities that manage radioactive waste. The radioactive waste management basis for a facility comprises existing laboratory-wide and facility-specific documents. Department of Energy Manual 435.1-1, 'Radioactive Waste Management Manual,' facility compliance tables also are presented for the facilities. The tables serve as a tool for developing the radioactive waste management basis.

  3. 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.

  4. Industrial Waste Landfill IV upgrade package

    SciTech Connect (OSTI)

    Not Available

    1994-03-29

    The Y-12 Plant, K-25 Site, and ORNL are managed by DOE`s Operating Contractor (OC), Martin Marietta Energy Systems, Inc. (Energy Systems) for DOE. Operation associated with the facilities by the Operating Contractor and subcontractors, DOE contractors and the DOE Federal Building result in the generation of industrial solid wastes as well as construction/demolition wastes. Due to the waste streams mentioned, the Y-12 Industrial Waste Landfill IV (IWLF-IV) was developed for the disposal of solid industrial waste in accordance to Rule 1200-1-7, Regulations Governing Solid Waste Processing and Disposal in Tennessee. This revised operating document is a part of a request for modification to the existing Y-12 IWLF-IV to comply with revised regulation (Rule Chapters 1200-1-7-.01 through 1200-1-7-.08) in order to provide future disposal space for the ORR, Subcontractors, and the DOE Federal Building. This revised operating manual also reflects approved modifications that have been made over the years since the original landfill permit approval. The drawings referred to in this manual are included in Drawings section of the package. IWLF-IV is a Tennessee Department of Environmental and Conservation/Division of Solid Waste Management (TDEC/DSWM) Class 11 disposal unit.

  5. DOE complex buried waste characterization assessment

    SciTech Connect (OSTI)

    Kaae, P.S.; Holter, G.M.; Garrett, S.M.K.

    1993-01-01

    The work described in this report was conducted by Pacific Northwest Laboratory to provide information to the Buried Waste Integrated Demonstration (BWID) program. The information in this report is intended to provide a complex-wide planning base for th.e BWID to ensure that BWID activities are appropriately focused to address the range of remediation problems existing across the US Department of Energy (DOE) complex. This report contains information characterizing the 2.1 million m[sup 3] of buried and stored wastes and their associated sites at six major DOE facilities. Approximately 85% of this waste is low-level waste, with about 12% TRU or TRU mixed waste; the remaining 3% is low-level mixed waste. In addition, the report describes soil contamination sites across the complex. Some of the details that would be useful in further characterizing the buried wastes and contaminated soil sites across the DOE complex are either unavailable or difficult to locate. Several options for accessing this information and/or improving the information that is available are identified in the report. This document is a companion to Technology Needs for Remediation: Hanford and Other DOE Sites, PNL-8328 (Stapp 1993).

  6. Safety analysis report for the Waste Storage Facility. Revision 2

    SciTech Connect (OSTI)

    Bengston, S.J.

    1994-05-01

    This safety analysis report outlines the safety concerns associated with the Waste Storage Facility located in the Radioactive Waste Management Complex at the Idaho National Engineering Laboratory. The three main objectives of the report are: define and document a safety basis for the Waste Storage Facility activities; demonstrate how the activities will be carried out to adequately protect the workers, public, and environment; and provide a basis for review and acceptance of the identified risk that the managers, operators, and owners will assume.

  7. Radioactive Waste Management Complex Wide Review | Department of Energy

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

    Radioactive Waste Management Complex Wide Review Radioactive Waste Management Complex Wide Review The main goal of this complex-wide review was to obtain feedback from DOE sites and Headquarters Program Offices on the effectiveness and workability of DOE Order 435.1 and its associated Manual and Guides as the Office of Environmental Management (EM) moves forward in updating the Order to ensure its continued protection of the public, workers, and the environment. Radioactive Waste Management

  8. 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

  9. DOE Issues RFP for Waste Treatment Services | Department of Energy

    Office of Environmental Management (EM)

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

  10. DOE model conference on waste management and environmental restoration

    SciTech Connect (OSTI)

    Not Available

    1990-01-01

    Reports dealing with current topics in waste management and environmental restoration were presented at this conference in six sessions. Session 1 covered the Hot Topics'' including regulations and risk assessment. Session 2 dealt with waste reduction and minimization; session 3 dealt with waste treatment and disposal. Session 4 covered site characterization and analysis. Environmental restoration and associated technologies wee discussed in session 5 and 6. Individual papers have been cataloged separately.

  11. Independent Oversight Review, Oak Ridge Transuranic Waste Processing

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

    Center, September 2013 | Department of Energy Oak Ridge Transuranic Waste Processing Center, September 2013 Independent Oversight Review, Oak Ridge Transuranic Waste Processing Center, September 2013 September 2013 Review of Management of Safety Systems at the Oak Ridge Transuranic Waste Processing Center and Associated Feedback and Improvement Processes. This report documents the results of an independent oversight review of the management of safety significant structures, systems, and

  12. Process to separate transuranic elements from nuclear waste

    DOE Patents [OSTI]

    Johnson, Terry R.; Ackerman, John P.; Tomczuk, Zygmunt; Fischer, Donald F.

    1989-01-01

    A process for removing transuranic elements from a waste chloride electrolytic salt containing transuranic elements in addition to rare earth and other fission product elements so the salt waste may be disposed of more easily and the valuable transuranic elements may be recovered for reuse. The salt is contacted with a cadmium-uranium alloy which selectively extracts the transuranic elements from the salt. The waste salt is generated during the reprocessing of nuclear fuel associated with the Integral Fast Reactor (IFR).

  13. Low Temperature Aluminum Dissolution Of Sludge Waste

    SciTech Connect (OSTI)

    Keefer, M.T.; Hamm, B.A.; Pike, J.A. [Washington Savannah River Company, Aiken, SC (United States)

    2008-07-01

    High Level Waste (HLW) at the Savannah River Site (SRS) is currently stored in aging underground storage tanks. This waste is a complex mixture of insoluble solids, referred to as sludge, and soluble salts. Continued long-term storage of these radioactive wastes poses an environmental risk. The sludge is currently being stabilized in the Defense Waste Processing Facility (DWPF) through a vitrification process immobilizing the waste in a borosilicate glass matrix for long-term storage in a federal repository. Without additional treatment, the existing volume of sludge would produce nearly 8000 canisters of vitrified waste. Aluminum compounds, along with other non-radioactive components, represent a significant portion of the sludge mass currently planned for vitrification processing in DWPF. Removing the aluminum from the waste stream reduces the volume of sludge requiring vitrification and improves production rates. Treating the sludge with a concentrated sodium hydroxide (caustic) solution at elevated temperatures (>90 deg. C) to remove aluminum is part of an overall sludge mass reduction effort to reduce the number of vitrified canisters, shorten the life cycle for the HLW system, and reduce the risk associated with the long term storage of radioactive wastes at SRS. A projected reduction of nearly 900 canisters will be achieved by performing aluminum dissolution on six targeted sludge batches; however, a project to develop and install equipment will not be ready for operation until 2013. The associated upgrades necessary to implement a high temperature process in existing facilities are costly and present many technical challenges. Efforts to better understand the characteristics of the sludge mass and dissolution kinetics are warranted to overcome these challenges. Opportunities to further reduce the amount of vitrified waste and increase production rates should also be pursued. Sludge staged in Tank 51 as the next sludge batch for feed to DWPF consisted

  14. Characteristics of potential repository wastes. Volume 1

    SciTech Connect (OSTI)

    Not Available

    1992-07-01

    This document, and its associated appendices and microcomputer (PC) data bases, constitutes the reference OCRWM data base of physical and radiological characteristics data of radioactive wastes. This Characteristics Data Base (CDB) system includes data on spent nuclear fuel and high-level waste (HLW), which clearly require geologic disposal, and other wastes which may require long-term isolation, such as sealed radioisotope sources. The data base system was developed for OCRWM by the CDB Project at Oak Ridge National Laboratory. Various principal or official sources of these data provided primary information to the CDB Project which then used the ORIGEN2 computer code to calculate radiological properties. The data have been qualified by an OCRWM-sponsored peer review as suitable for quality-affecting work meeting the requirements of OCRWM`s Quality Assurance Program. The wastes characterized in this report include: light-water reactor (LWR) spent fuel and immobilized HLW.

  15. Los Alamos Waste Management Cost Estimation Model; Final report: Documentation of waste management process, development of Cost Estimation Model, and model reference manual

    SciTech Connect (OSTI)

    Matysiak, L.M.; Burns, M.L.

    1994-03-01

    This final report completes the Los Alamos Waste Management Cost Estimation Project, and includes the documentation of the waste management processes at Los Alamos National Laboratory (LANL) for hazardous, mixed, low-level radioactive solid and transuranic waste, development of the cost estimation model and a user reference manual. The ultimate goal of this effort was to develop an estimate of the life cycle costs for the aforementioned waste types. The Cost Estimation Model is a tool that can be used to calculate the costs of waste management at LANL for the aforementioned waste types, under several different scenarios. Each waste category at LANL is managed in a separate fashion, according to Department of Energy requirements and state and federal regulations. The cost of the waste management process for each waste category has not previously been well documented. In particular, the costs associated with the handling, treatment and storage of the waste have not been well understood. It is anticipated that greater knowledge of these costs will encourage waste generators at the Laboratory to apply waste minimization techniques to current operations. Expected benefits of waste minimization are a reduction in waste volume, decrease in liability and lower waste management costs.

  16. Waste Stream Approval - Hanford Site

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

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

  17. 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

  18. Waste Isolation Pilot Plant Safety Analysis Report

    SciTech Connect (OSTI)

    1995-11-01

    The following provides a summary of the specific issues addressed in this FY-95 Annual Update as they relate to the CH TRU safety bases: Executive Summary; Site Characteristics; Principal Design and Safety Criteria; Facility Design and Operation; Hazards and Accident Analysis; Derivation of Technical Safety Requirements; Radiological and Hazardous Material Protection; Institutional Programs; Quality Assurance; and Decontamination and Decommissioning. The System Design Descriptions`` (SDDS) for the WIPP were reviewed and incorporated into Chapter 3, Principal Design and Safety Criteria and Chapter 4, Facility Design and Operation. This provides the most currently available final engineering design information on waste emplacement operations throughout the disposal phase up to the point of permanent closure. Also, the criteria which define the TRU waste to be accepted for disposal at the WIPP facility were summarized in Chapter 3 based on the WAC for the Waste Isolation Pilot Plant.`` This Safety Analysis Report (SAR) documents the safety analyses that develop and evaluate the adequacy of the Waste Isolation Pilot Plant Contact-Handled Transuranic Wastes (WIPP CH TRU) safety bases necessary to ensure the safety of workers, the public and the environment from the hazards posed by WIPP waste handling and emplacement operations during the disposal phase and hazards associated with the decommissioning and decontamination phase. The analyses of the hazards associated with the long-term (10,000 year) disposal of TRU and TRU mixed waste, and demonstration of compliance with the requirements of 40 CFR 191, Subpart B and 40 CFR 268.6 will be addressed in detail in the WIPP Final Certification Application scheduled for submittal in October 1996 (40 CFR 191) and the No-Migration Variance Petition (40 CFR 268.6) scheduled for submittal in June 1996. Section 5.4, Long-Term Waste Isolation Assessment summarizes the current status of the assessment.

  19. ANNUAL RADIOACTIVE WASTE TANK INSPECTION PROGRAM 2010

    SciTech Connect (OSTI)

    West, B.; Waltz, R.

    2011-06-23

    Aqueous radioactive wastes from Savannah River Site (SRS) separations and vitrification processes are contained in large underground carbon steel tanks. Inspections made during 2010 to evaluate these vessels and other waste handling facilities along with evaluations based on data from previous inspections are the subject of this report. The 2010 inspection program revealed that the structural integrity and waste confinement capability of the Savannah River Site waste tanks were maintained. All inspections scheduled per SRR-LWE-2009-00138, HLW Tank Farm Inspection Plan for 2010, were completed. Ultrasonic measurements (UT) performed in 2010 met the requirements of C-ESG-00006, In-Service Inspection Program for High Level Waste Tanks, Rev. 3, and WSRC-TR-2002-00061, Rev.6. UT inspections were performed on Tanks 30, 31 and 32 and the findings are documented in SRNL-STI-2010-00533, Tank Inspection NDE Results for Fiscal Year 2010, Waste Tanks 30, 31 and 32. A total of 5824 photographs were made and 1087 visual and video inspections were performed during 2010. Ten new leaksites at Tank 5 were identified in 2010. The locations of these leaksites are documented in C-ESR-G-00003, SRS High Level Waste Tank Leaksite Information, Rev.5. Ten leaksites at Tank 5 were documented during tank wall/annulus cleaning activities. None of these new leaksites resulted in a release to the environment. The leaksites were documented during wall cleaning activities and the waste nodules associated with the leaksites were washed away. Previously documented leaksites were reactivated at Tank 12 during waste removal activities.

  20. Transuranic (TRU) Waste | Department of Energy

    Office of Environmental Management (EM)

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

  1. Solid Waste Management Plan. Revision 4

    SciTech Connect (OSTI)

    1995-04-26

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

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

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

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

  3. Waste from grocery stores

    SciTech Connect (OSTI)

    Lieb, K.

    1993-11-01

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

  4. Underground waste barrier structure

    DOE Patents [OSTI]

    Saha, Anuj J.; Grant, David C.

    1988-01-01

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

  5. Hanford Dangerous Waste Permit

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

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

  6. THERMAL EVALUATION OF THE 2-MCO/2-DHLW WASTE PACKAGE

    SciTech Connect (OSTI)

    T. Schmitt

    2000-07-05

    The objective of this calculation was to determine the structural response of multi-canister overpacks (MCO) and the 2-MCO/2-Defense High-Level Waste (DHLW) Waste Package (WP) subjected to tip-over onto an unyielding surface (US). The scope of this calculation was limited to reporting the calculation results in terms of maximum stress intensities. This calculation is associated with the waste package design and was performed by the Waste Package Design Section in accordance with the DOE SNF Analysis Plan for FY 2000.

  7. Alpha low-level stored waste systems design study

    SciTech Connect (OSTI)

    Feizollahi, F.; Teheranian, B.; Quapp, W.J.

    1992-08-01

    The Stored Waste System Design Study (SWSDS), commissioned by the Waste Technology Development Department at the Idaho National Engineering Laboratory (INEL), examines relative life-cycle costs associated with three system concepts for processing the alpha low-level waste (alpha-LLW) stored at the Radioactive Waste Management Complex`s Transuranic Storage Area at the INEL. The three system concepts are incineration/melting; thermal treatment/solidification; and sort, treat, and repackage. The SWSDS identifies system functional and operational requirements and assesses implementability; effectiveness; cost; and demonstration, testing, and evaluation (DT&E) requirements for each of the three concepts.

  8. Alpha low-level stored waste systems design study

    SciTech Connect (OSTI)

    Feizollahi, F.; Teheranian, B. . Environmental Services Div.); Quapp, W.J. )

    1992-08-01

    The Stored Waste System Design Study (SWSDS), commissioned by the Waste Technology Development Department at the Idaho National Engineering Laboratory (INEL), examines relative life-cycle costs associated with three system concepts for processing the alpha low-level waste (alpha-LLW) stored at the Radioactive Waste Management Complex's Transuranic Storage Area at the INEL. The three system concepts are incineration/melting; thermal treatment/solidification; and sort, treat, and repackage. The SWSDS identifies system functional and operational requirements and assesses implementability; effectiveness; cost; and demonstration, testing, and evaluation (DT E) requirements for each of the three concepts.

  9. Waste minimization assessment procedure

    SciTech Connect (OSTI)

    Kellythorne, L.L. )

    1993-01-01

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

  10. Waste inspection tomography (WIT)

    SciTech Connect (OSTI)

    Bernardi, R.T.

    1995-10-01

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

  11. Waste to Energy

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

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

  12. Norcal Waste Systems, Inc.

    SciTech Connect (OSTI)

    Not Available

    2002-12-01

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

  13. 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''.

  14. Hanford Dangerous Waste Permit

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

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

  15. Pioneering Nuclear Waste Disposal

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

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

  16. Vitrification of waste

    DOE Patents [OSTI]

    Wicks, George G.

    1999-01-01

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

  17. Vitrification of waste

    DOE Patents [OSTI]

    Wicks, G.G.

    1999-04-06

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

  18. Decomposition of carbohydrate wastes

    DOE Patents [OSTI]

    Appell, Herbert R.; Pantages, Peter

    1976-11-02

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

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

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

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

  20. Performance Demonstration Program Plan for Nondestructive Assay of Drummed Wastes for the TRU Waste Characterization Program

    SciTech Connect (OSTI)

    Carlsbad Field Office

    2005-08-03

    Carlsbad Field Office (CBFO). The nuclear material type, mass and associated alpha activity of the NDA PDP radioactive standard sets have been specified and fabricated to allow assembly of PDP samples that simulate TRU alpha activity concentrations, radionuclidic/isotopic distributions and physical forms typical of the DOE TRU waste inventory. The PDP matrix drum waste matrix types were derived from an evaluation of information contained in the Transuranic Waste Baseline Inventory Report (TWBIR) to ensure representation of prevalent waste types and their associated matrix characteristics in NDA PDP testing. NDA drum analyses required by the Waste Isolation Pilot Plant (WIPP) may only be performed by measurement facilities that comply with the performance criteria as set forth in the NDA PDP Plan. In this document, these analyses are referred to as WIPP analyses, and the wastes on which they are performed are referred to as WIPP wastes.

  1. Scenarios for the Hanford Immobilized Low-Activity Waste (ILAW) performance assessment

    SciTech Connect (OSTI)

    MANN, F.M.

    1999-03-17

    Scenarios describing representative exposure cases associated with the disposal of low activity waste from the Hanford Waste Tanks have been defined. These scenarios are based on guidance from the Department of Energy, the U.S. Nuclear Regulatory Commission, and previous Hanford waste disposal performance assessments.

  2. Secondary Waste Cast Stone Waste Form Qualification Testing Plan

    SciTech Connect (OSTI)

    Westsik, Joseph H.; Serne, R. Jeffrey

    2012-09-26

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

  3. EIS-0303: Savannah River Site High-Level Waste Tank Closure

    Broader source: Energy.gov [DOE]

    This EIS evaluates alternatives for closing 49 high-level radioactive waste tanks and associated equipment such as evaporator systems, transfer pipelines, diversion boxes, and pump pits. DOE...

  4. EIS-0290: Idaho National Engineering and Environmental Laboratory Advanced Mixed Waste Treatment Project (AMWTP)

    Broader source: Energy.gov [DOE]

    The AMWTP Final EIS assesses the potential environmental impacts associated with alternatives related to the construction and operation of a proposed waste treatment facility at the Idaho National...

  5. 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...

  6. Using weeds to fight wastes

    SciTech Connect (OSTI)

    1992-10-01

    Researchers at Los Alamos National Laboratory and New Mexico State University have discovered that jimson weed and wild tomato plants can remove the toxic wastes in wastewater associated with the production of trinitrotoluene (TNT). According to Wolfgang F. Mueller of New Mexico State, tissue-cultured cells of jimson weed rapidly absorb and break down toxic and carcinogenic elements in {open_quotes}pink water,{close_quotes} a by-product of the manufacture of TNT. Mueller and his colleagues have found similar results with the wild tomato plant.

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

    Office of Environmental Management (EM)

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

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

    Office of Environmental Management (EM)

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

  9. Waste Isolation Pilot Plant Nitrate Salt Bearing Waste Container

    Office of Environmental Management (EM)

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

  10. WRPS MEETING THE CHALLENGE OF TANK WASTE

    SciTech Connect (OSTI)

    BRITTON JC

    2012-02-21

    -and-a-half years to modernize the infrastructure in Hanford's tank farms. WRPS issued 850 subcontracts totaling more than $152 million with nearly 76 percent of that total awarded to small businesses. WRPS used the funding to upgrade tank farm infrastructure, develop technologies to retrieve and consolidate tank waste and extend the life of two critical operating facilities needed to feed waste to the WTP. The 222-S Laboratory analyzes waste to support waste retrievals and transfers. The laboratory was upgraded to support future WTP operations with a new computer system, new analytical equipment, a new office building and a new climate-controlled warehouse. The 242-A Evaporator was upgraded with a control-room simulator for operator training and several upgrades to aging equipment. The facility is used to remove liquid from the tank waste, creating additional storage space, necessary for continued waste retrievals and WTP operation. The One System Integrated Project Team is ajoint effort ofWRPS and Bechtel National to identify and resolve common issues associated with commissioning, feeding and operating the Waste Treatment Plant. Two new facilities are being designed to support WTP hot commlsslomng. The Interim Hanford Storage project is planned to store canisters of immobilized high-level radioactive waste glass produced by the vitrification plant. The facility will use open racks to store the 15-foot long, two-foot diameter canisters of waste, which require remote handling. The Secondary Liquid Waste Treatment Project is a major upgrade to the existing Effluent Treatment Facility at Hanford so it can treat about 10 million gallons of liquid radioactive and hazardous effluent a year from the vitrification plant. The One System approach brings the staff of both companies together to identify and resolve WTP safety issues. A questioning attitude is encouraged and an open forum is maintained for employees to raise issues. WRPS is completing its mission safely with record

  11. SRNL CRP progress report [Development of Melt Processed Ceramics for Nuclear Waste Immobilization

    SciTech Connect (OSTI)

    Amoroso, J.; Marra, J.

    2014-10-02

    A multi-phase ceramic waste form is being developed at the Savannah River National Laboratory (SRNL) for treatment of secondary waste streams generated by reprocessing commercial spent nuclear. The envisioned waste stream contains a mixture of transition, alkali, alkaline earth, and lanthanide metals. Ceramic waste forms are tailored (engineered) to incorporate waste components as part of their crystal structure based on knowledge from naturally found minerals containing radioactive and non-radioactive species similar to the radionuclides of concern in wastes from fuel reprocessing. The ability to tailor ceramics to mimic naturally occurring crystals substantiates the long term stability of such crystals (ceramics) over geologic timescales of interest for nuclear waste immobilization [1]. A durable multiphase ceramic waste form tailored to incorporate all the waste components has the potential to broaden the available disposal options and thus minimize the storage and disposal costs associated with aqueous reprocessing.

  12. Nuclear waste solutions

    DOE Patents [OSTI]

    Walker, Darrel D.; Ebra, Martha A.

    1987-01-01

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

  13. Heterogeneous waste processing

    DOE Patents [OSTI]

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

    2000-01-01

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

  14. Improving medical waste disposal

    SciTech Connect (OSTI)

    O'Connor, L.

    1994-05-01

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

  15. Radioactive waste storage issues

    SciTech Connect (OSTI)

    Kunz, D.E.

    1994-08-15

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

  16. Radioactive waste disposal package

    DOE Patents [OSTI]

    Lampe, Robert F. (Bethel Park, PA)

    1986-01-01

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

  17. Radioactive waste disposal package

    DOE Patents [OSTI]

    Lampe, Robert F.

    1986-11-04

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

  18. Los Alamos National Laboratory names Jeffrey Mousseau Associate...

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

    new associate director for Environmental Programs. Mousseau currently works as a senior project manager for the Laboratory's transuranic waste disposal program. In his new...

  19. Waste Determination Equivalency - 12172

    SciTech Connect (OSTI)

    Freeman, Rebecca D.

    2012-07-01

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

  20. DOE complex buried waste characterization assessment. Buried Waste Integrated Demonstration Program

    SciTech Connect (OSTI)

    Kaae, P.S.; Holter, G.M.; Garrett, S.M.K.

    1993-01-01

    The work described in this report was conducted by Pacific Northwest Laboratory to provide information to the Buried Waste Integrated Demonstration (BWID) program. The information in this report is intended to provide a complex-wide planning base for th.e BWID to ensure that BWID activities are appropriately focused to address the range of remediation problems existing across the US Department of Energy (DOE) complex. This report contains information characterizing the 2.1 million m{sup 3} of buried and stored wastes and their associated sites at six major DOE facilities. Approximately 85% of this waste is low-level waste, with about 12% TRU or TRU mixed waste; the remaining 3% is low-level mixed waste. In addition, the report describes soil contamination sites across the complex. Some of the details that would be useful in further characterizing the buried wastes and contaminated soil sites across the DOE complex are either unavailable or difficult to locate. Several options for accessing this information and/or improving the information that is available are identified in the report. This document is a companion to Technology Needs for Remediation: Hanford and Other DOE Sites, PNL-8328 (Stapp 1993).

  1. Overview of mixed waste issues

    SciTech Connect (OSTI)

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

    1986-01-01

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

  2. Environmental waste disposal contracts awarded

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

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

  3. Waste Specification Records - Hanford Site

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

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

  4. High-Level Waste Inventory

    Office of Environmental Management (EM)

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

  5. Enhanced Tank Waste Strategy Update

    Office of Environmental Management (EM)

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

  6. Vitrification of NORM wastes

    SciTech Connect (OSTI)

    Chapman, C.

    1994-05-01

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

  7. DRAFT EM SSAB Chairs Meeting Waste Disposition Strategies Update

    Office of Environmental Management (EM)

    EM HQ Updates Waste Disposition Overview Christine Gelles Associate Deputy Assistant Secretary for Waste Management Office of Environmental Management EM SSAB Chairs Meeting 5 November 2013 www.energy.gov/EM 2 * Waste Management Accomplishments and Priorities * National TRU Program Update * LLW/MLLW Disposal Update * Other Programmatic Updates * Disposition Maps - Current Tools Discussion Outline www.energy.gov/EM 3 FY13 Waste Management Accomplishments * WIPP: Emplaced 5,065 cubic meters of

  8. 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.

  9. Hanford Waste Vitrification Plant Quality Assurance Program description for high-level waste form development and qualification. Revision 3, Part 2

    SciTech Connect (OSTI)

    Not Available

    1993-08-01

    The Hanford Waste Vitrification Plant Project has been established to convert the high-level radioactive waste associated with nuclear defense production at the Hanford Site into a waste form suitable for disposal in a deep geologic repository. The Hanford Waste Vitrification Plant will mix processed radioactive waste with borosilicate material, then heat the mixture to its melting point (vitrification) to forin a glass-like substance that traps the radionuclides in the glass matrix upon cooling. The Hanford Waste Vitrification Plant Quality Assurance Program has been established to support the mission of the Hanford Waste Vitrification Plant. This Quality Assurance Program Description has been written to document the Hanford Waste Vitrification Plant Quality Assurance Program.

  10. Permitting plan for the immobilized low-activity waste project

    SciTech Connect (OSTI)

    Deffenbaugh, M.L.

    1997-09-04

    This document addresses the environmental permitting requirements for the transportation and interim storage of the Immobilized Low-Activity Waste (ILAW) produced during Phase 1 of the Hanford Site privatization effort. Tri-Party Agreement (TPA) Milestone M-90 establishes a new major milestone, and associated interim milestones and target dates, governing acquisition and/or modification of facilities necessary for: (1) interim storage and disposal of Tank Waste Remediation Systems (TWRS) immobilized low-activity tank waste (ILAW) and (2) interim storage of TWRS immobilized HLW (IHLW) and other canistered high-level waste forms. Low-activity waste (LAW), low-level waste (LLW), and high-level waste (HLW) are defined by the TWRS, Hanford Site, Richland, Washington, Final Environmental Impact Statement (EIS) DOE/EIS-0189, August 1996 (TWRS, Final EIS). By definition, HLW requires permanent isolation in a deep geologic repository. Also by definition, LAW is ``the waste that remains after separating from high-level waste as much of the radioactivity as is practicable that when solidified may be disposed of as LLW in a near-surface facility according to the NRC regulations.`` It is planned to store/dispose of (ILAW) inside four empty vaults of the five that were originally constructed for the Group Program. Additional disposal facilities will be constructed to accommodate immobilized LLW packages produced after the Grout Vaults are filled. The specifications for performance of the low-activity vitrified waste form have been established with strong consideration of risk to the public. The specifications for glass waste form performance are being closely coordinated with analysis of risk. RL has pursued discussions with the NRC for a determination of the classification of the Hanford Site`s low-activity tank waste fraction. There is no known RL action to change law with respect to onsite disposal of waste.

  11. AVLIS production plant waste management plan

    SciTech Connect (OSTI)

    Not Available

    1984-11-15

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

  12. Key regulatory drivers affecting shipments of mixed transuranic waste from Los Alamos National Laboratory to the Waste Isolation Pilot Plant

    SciTech Connect (OSTI)

    Schumann, P.B.; Bacigalupa, G.A.; Kosiewicz, S.T.; Sinkule, B.J.

    1997-02-01

    A number of key regulatory drivers affect the nature, scope, and timing of Los Alamos National Laboratory`s (LANL`s) plans for mixed transuranic (MTRU) waste shipments to the Waste Isolation Pilot Plant (WIPP), which are planned to commence as soon as possible following WIPP`s currently anticipated November, 1997 opening date. This paper provides an overview of some of the key drivers at LANL, particularly emphasizing those associated with the hazardous waste component of LANL`s MTRU waste (MTRU, like any mixed waste, contains both a radioactive and a hazardous waste component). The key drivers discussed here derive from the federal Resource Conservation and Recovery Act (RCRA) and its amendments, including the Federal Facility Compliance Act (FFCAU), and from the New Mexico Hazardous Waste Act (NMHWA). These statutory provisions are enforced through three major mechanisms: facility RCRA permits; the New Mexico Hazardous Waste Management Regulations, set forth in the New Mexico Administrative Code, Title 20, Chapter 4, Part 1: and compliance orders issued to enforce these requirements. General requirements in all three categories will apply to MTRU waste management and characterization activities at both WIPP and LANL. In addition, LANL is subject to facility-specific requirements in its RCRA hazardous waste facility permit, permit conditions as currently proposed in RCRA Part B permit applications presently being reviewed by the New Mexico Environment Department (NNED), and facility-specific compliance orders related to MTRU waste management. Likewise, permitting and compliance-related requirements specific to WIPP indirectly affect LANL`s characterization, packaging, record-keeping, and transportation requirements for MTRU waste. LANL must comply with this evolving set of regulatory requirements to begin shipments of MTRU waste to WIPP in a timely fashion.

  13. Hanford Dangerous Waste Permit

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

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

  14. Hanford Dangerous Waste Permit

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

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

  15. Radioactive waste material disposal

    DOE Patents [OSTI]

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

    1995-01-01

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

  16. Radioactive waste material disposal

    DOE Patents [OSTI]

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

    1995-10-24

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

  17. Quality assurance plan for Final Waste Forms project in support of the development, demonstration, testing and evaluation efforts associated with the Oak Ridge reservation`s LDR/FFCA compliance

    SciTech Connect (OSTI)

    Gilliam, T.M.; Mattus, C.H.

    1994-07-01

    This quality assurance project plan specifies the data quality objectives for Phase I of the Final Waste Forms Project and defines specific measurements and processes required to achieve those objectives. Although the project is funded by the U.S. Department of Energy (DOE), the ultimate recipient of the results is the U.S. Environmental Protection Agency (EPA). Consequently, relevant quality assurance requirements from both organizations must be met. DOE emphasizes administrative structure to ensure quality; EPA`s primary focus is the reproducibility of the generated data. The ten criteria of DOE Order 5700.6C are addressed in sections of this report, while the format used is that prescribed by EPA for quality assurance project plans.

  18. Proposed Use of a Constructed Wetland for the Treatment of Metals in the S-04 Outfall of the Defense Waste Processing Facility at the Savannah River Site

    SciTech Connect (OSTI)

    Glover, T.

    1999-11-23

    The DWPF is part of an integrated waste treatment system at the SRS to treat wastes containing radioactive contaminants. In the early 1980s the DOE recognized that there would be significant safety and cost advantages associated with immobilizing the radioactive waste in a stable solid form. The Defense Waste Processing Facility was designed and constructed to accomplish this task.

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

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

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

  20. Waste Isolation Pilot Plant Nitrate Salt Bearing Waste Container

    Office of Environmental Management (EM)

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

  1. Social and economic aspects of radioactive waste disposal: considerations for institutional management

    SciTech Connect (OSTI)

    Not Available

    1984-01-01

    Issues addressed in this book include: magnitude, characteristics, and trends of public concerns over radioactive waste; the issue of public trust and confidence in the institutions responsible for radioactive waste management; effects of the number and location of waste repositories on socioeconomic and institutional burdens associated with nuclear waste management; effects associated with interim storage facilities located at reactors or away from reactors; kinds and relative magnitudes of effects associated with the use of alternative forms of transportation (rail, truck, barge); participation by local citizens in identifying, assessing, and proposing ways to ameliorate social and economic siting effects; and potential options for resolving conflict at federal, state, and local levels over repository siting.

  2. Generating power with waste wood

    SciTech Connect (OSTI)

    Atkins, R.S.

    1995-02-01

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

  3. Method for calcining radioactive wastes

    DOE Patents [OSTI]

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

    1979-01-01

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

  4. Methane generation from waste materials

    SciTech Connect (OSTI)

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

    2010-03-23

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

  5. Contained recovery of oily waste

    DOE Patents [OSTI]

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

    1989-01-01

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

  6. Melt processed crystalline ceramic waste forms for advanced nuclear fuel cycles: CRP T21027 1813: Processing technologies for high level waste, formulation of matrices and characterization of waste forms, Task 17208: Final report

    SciTech Connect (OSTI)

    Amoroso, J. W.; Marra, J. C.

    2015-08-26

    A multi-phase ceramic waste form is being developed at the Savannah River National Laboratory (SRNL) for treatment of secondary waste streams generated by reprocessing commercial spent nuclear. The envisioned waste stream contains a mixture of transition, alkali, alkaline earth, and lanthanide metals. Ceramic waste forms are tailored (engineered) to incorporate waste components as part of their crystal structure based on knowledge from naturally found minerals containing radioactive and non-radioactive species similar to the radionuclides of concern in wastes from fuel reprocessing. The ability to tailor ceramics to mimic naturally occurring crystals substantiates the long term stability of such crystals (ceramics) over geologic timescales of interest for nuclear waste immobilization [1]. A durable multi-phase ceramic waste form tailored to incorporate all the waste components has the potential to broaden the available disposal options and thus minimize the storage and disposal costs associated with aqueous reprocessing. This report summarizes results from three years of work on the IAEA Coordinated Research Project on “Processing technologies for high level waste, formulation of matrices and characterization of waste forms” (T21027), and specific task “Melt Processed Crystalline Ceramic Waste Forms for Advanced Nuclear Fuel Cycles” (17208).

  7. Melt processed crystalline ceramic waste forms for advanced nuclear fuel cycles: CRP T21027 1813: Processing technologies for high level waste, formulation of matrices and characterization of waste forms, task 17208: Final report

    SciTech Connect (OSTI)

    Amoroso, J. W.; Marra, J. C.

    2015-08-26

    A multi-phase ceramic waste form is being developed at the Savannah River National Laboratory (SRNL) for treatment of secondary waste streams generated by reprocessing commercial spent nuclear. The envisioned waste stream contains a mixture of transition, alkali, alkaline earth, and lanthanide metals. Ceramic waste forms are tailored (engineered) to incorporate waste components as part of their crystal structure based on knowledge from naturally found minerals containing radioactive and non-radioactive species similar to the radionuclides of concern in wastes from fuel reprocessing. The ability to tailor ceramics to mimic naturally occurring crystals substantiates the long term stability of such crystals (ceramics) over geologic timescales of interest for nuclear waste immobilization [1]. A durable multi-phase ceramic waste form tailored to incorporate all the waste components has the potential to broaden the available disposal options and thus minimize the storage and disposal costs associated with aqueous reprocessing. This report summarizes results from three years of work on the IAEA Coordinated Research Project on “Processing technologies for high level waste, formulation of matrices and characterization of waste forms” (T21027), and specific task “Melt Processed Crystalline Ceramic Waste Forms for Advanced Nuclear Fuel Cycles” (17208).

  8. Eliminating Medical Waste Liabilities Through Mobile Maceration and Disinfection

    SciTech Connect (OSTI)

    R. A. Rankin; N. R. Soelberg; K. M. Klingler; C. W. Lagle; L. L. Byers

    2006-02-01

    Commercial medical waste treatment technologies include incineration, melting, autoclaving, and chemical disinfection. Incineration disinfects, destroys the original nature of medical waste, and reduces the waste volume by converting organic waste content to carbon dioxide and water, leaving only residual inorganic ash. However, medical waste incinerator numbers have plummeted from almost 2,400 in 1995 to 115 in 2003 and to about 62 in 2005, due to negative public perception and escalating compliance costs associated with increasingly strict regulations. High-temperature electric melters have been designed and marketed as incinerator alternatives, but they are also costly and generally must comply with the same incinerator emissions regulations and permitting requirements. Autoclave processes disinfect medical waste at much lower operating temperatures than incinerators operate at, but are sometimes subject to limitations such as waste segregration requirements to be effective. Med-Shred, Inc. has developed a patented mobile shredding and chemical disinfecting process for on-site medical waste treatment. Medical waste is treated on-site at customer facilities by shredding and disinfecting the waste. The treated waste can then be transported in compliance with Health Insurance Portability and Accountability Act of 1996 (HIPAA) requirements to a landfill for disposal as solid municipal waste. A team of Idaho National Laboratory engineers evaluated the treatment process design. The process effectiveness has been demonstrated in mycobacterium tests performed by Analytical Services Incorporated. A process description and the technical and performance evaluation results are presented in the paper. A treatment demonstration and microbiological disinfecting tests show that the processor functions as it was intended.

  9. Solid waste management challenges for cities in developing countries

    SciTech Connect (OSTI)

    Abarca Guerrero, Lilliana; Maas, Ger; Hogland, William

    2013-01-15

    Highlights: Black-Right-Pointing-Pointer Stakeholders. Black-Right-Pointing-Pointer Factors affecting performance waste management systems. Black-Right-Pointing-Pointer Questionnaire as Annex for waste management baseline assessment. - Abstract: Solid waste management is a challenge for the cities' authorities in developing countries mainly due to the increasing generation of waste, the burden posed on the municipal budget as a result of the high costs associated to its management, the lack of understanding over a diversity of factors that affect the different stages of waste management and linkages necessary to enable the entire handling system functioning. An analysis of literature on the work done and reported mainly in publications from 2005 to 2011, related to waste management in developing countries, showed that few articles give quantitative information. The analysis was conducted in two of the major scientific journals, Waste Management Journal and Waste Management and Research. The objective of this research was to determine the stakeholders' action/behavior that have a role in the waste management process and to analyze influential factors on the system, in more than thirty urban areas in 22 developing countries in 4 continents. A combination of methods was used in this study in order to assess the stakeholders and the factors influencing the performance of waste management in the cities. Data was collected from scientific literature, existing data bases, observations made during visits to urban areas, structured interviews with relevant professionals, exercises provided to participants in workshops and a questionnaire applied to stakeholders. Descriptive and inferential statistic methods were used to draw conclusions. The outcomes of the research are a comprehensive list of stakeholders that are relevant in the waste management systems and a set of factors that reveal the most important causes for the systems' failure. The information provided is very

  10. Pioneering Nuclear Waste Disposal

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

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

  11. UMC Construction Waste (4493)

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

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

  12. Waste and Recycling

    ScienceCinema (OSTI)

    McCarthy, Kathy

    2013-05-28

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

  13. Pioneering Nuclear Waste Disposal

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

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

  14. Treatment of organic waste

    DOE Patents [OSTI]

    Grantham, LeRoy F.

    1979-01-01

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

  15. Women of Waste Management

    Broader source: Energy.gov [DOE]

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

  16. Household-level dynamics of food waste production and related beliefs, attitudes, and behaviours in Guelph, Ontario

    SciTech Connect (OSTI)

    Parizeau, Kate; Massow, Mike von; Martin, Ralph

    2015-01-15

    Highlights: • We combined household waste stream weights with survey data. • We examine relationships between waste and food-related practices and beliefs. • Families and large households produced more total waste, but less waste per capita. • Food awareness and waste awareness were related to reduced food waste. • Convenience lifestyles were differentially associated with food waste. - Abstract: It has been estimated that Canadians waste $27 billion of food annually, and that half of that waste occurs at the household level (Gooch et al., 2010). There are social, environmental, and economic implications for this scale of food waste, and source separation of organic waste is an increasingly common municipal intervention. There is relatively little research that assesses the dynamics of household food waste (particularly in Canada). The purpose of this study is to combine observations of organic, recyclable, and garbage waste production rates to survey results of food waste-related beliefs, attitudes, and behaviours at the household level in the mid-sized municipality of Guelph, Ontario. Waste weights and surveys were obtained from 68 households in the summer of 2013. The results of this study indicate multiple relationships between food waste production and household shopping practices, food preparation behaviours, household waste management practices, and food-related attitudes, beliefs, and lifestyles. Notably, we observed that food awareness, waste awareness, family lifestyles, and convenience lifestyles were related to food waste production. We conclude that it is important to understand the diversity of factors that can influence food wasting behaviours at the household level in order to design waste management systems and policies to reduce food waste.

  17. Rethinking the Hanford Tank Waste Program

    SciTech Connect (OSTI)

    Parker, F. L.; Clark, D. E.; Morcos, N.

    2002-02-26

    The program to treat and dispose of the highly radioactive wastes stored in underground tanks at the U.S. Department of Energy's Hanford site has been studied. A strategy/management approach to achieve an acceptable (technically sound) end state for these wastes has been developed in this study. This approach is based on assessment of the actual risks and costs to the public, workers, and the environment associated with the wastes and storage tanks. Close attention should be given to the technical merits of available waste treatment and stabilization methodologies, and application of realistic risk reduction goals and methodologies to establish appropriate tank farm cleanup milestones. Increased research and development to reduce the mass of non-radioactive materials in the tanks requiring sophisticated treatment is highly desirable. The actual cleanup activities and milestones, while maintaining acceptable safety standards, could be more focused on a risk-to-benefit cost effectiveness, as agreed to by the involved stakeholders and in accordance with existing regulatory requirements. If existing safety standards can be maintained at significant cost savings under alternative plans but with a change in the Tri-Party Agreement (a regulatory requirement), those plans should be carried out. The proposed strategy would also take advantage of the lessons learned from the activities and efforts in the first phase of the two-phased cleanup of the Hanford waste tank farms.

  18. The Integrated Waste Tracking Systems (IWTS) - A Comprehensive Waste Management Tool

    SciTech Connect (OSTI)

    Robert S. Anderson

    2005-09-01

    the changes were made. As regulations and permits change, and as the proliferation of personal computers flourish, procedures and data files begin to be stored in electronic databases. With many different organizations, contractors, and unique procedures, several dozen databases are used to track and maintain aspects of waste management. As one can see, the logistics of collecting and certifying data from all organizations to provide comprehensive information would not only take weeks to perform, but usually presents a variety of answers that require an immediate unified resolution. A lot of personnel time is spent scrubbing the data in order to determine the correct information. The issue of disparate data is a concern in itself, and is coupled with the costs associated with maintaining several separate databases. In order to gain waste management efficiencies across an entire facility or site, several waste management databases located among several organizations would need to be consolidated. The IWTS is a system to do just that, namely store and track containerized waste information for an entire site. The IWTS has proven itself at the INL since 1995 as an efficient, successful, time saving management tool to help meet the needs of both operations and management for hazardous and radiological containerized waste. Other sites have also benefited from IWTS as it has been deployed at West Valley Nuclear Services Company DOE site as well as Ontario Power Ge

  19. Contact-Handled Transuranic Waste Acceptance Criteria for the Waste Isolation Pilot Plant

    SciTech Connect (OSTI)

    Washington TRU Solutions LLC

    2005-12-29

    The purpose of this document is to summarize the waste acceptance criteria applicable to the transportation, storage, and disposal of contact-handled transuranic (CH-TRU) waste at the Waste Isolation Pilot Plant (WIPP). These criteria serve as the U.S. Department of Energy's (DOE) primary directive for ensuring that CH-TRU waste is managed and disposed of in a manner that protects human health and safety and the environment.The authorization basis of WIPP for the disposal of CH-TRU waste includes the U.S.Department of Energy National Security and Military Applications of Nuclear EnergyAuthorization Act of 1980 (reference 1) and the WIPP Land Withdrawal Act (LWA;reference 2). Included in this document are the requirements and associated criteriaimposed by these acts and the Resource Conservation and Recovery Act (RCRA,reference 3), as amended, on the CH-TRU waste destined for disposal at WIPP.|The DOE TRU waste sites must certify CH-TRU waste payload containers to thecontact-handled waste acceptance criteria (CH-WAC) identified in this document. Asshown in figure 1.0, the flow-down of applicable requirements to the CH-WAC istraceable to several higher-tier documents, including the WIPP operational safetyrequirements derived from the WIPP CH Documented Safety Analysis (CH-DSA;reference 4), the transportation requirements for CH-TRU wastes derived from theTransuranic Package Transporter-Model II (TRUPACT-II) and HalfPACT Certificates ofCompliance (references 5 and 5a), the WIPP LWA (reference 2), the WIPP HazardousWaste Facility Permit (reference 6), and the U.S. Environmental Protection Agency(EPA) Compliance Certification Decision and approval for PCB disposal (references 7,34, 35, 36, and 37). The solid arrows shown in figure 1.0 represent the flow-down of allapplicable payload container-based requirements. The two dotted arrows shown infigure 1.0 represent the flow-down of summary level requirements only; i.e., the sitesmust reference the regulatory source

  20. Waste Isolation Pilot Plant

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

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

  1. Waste Isolation Pilot Plant

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

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

  2. Defense Waste Management Programs

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

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

  3. Citrus Waste Biomass Program

    SciTech Connect (OSTI)

    Karel Grohman; Scott Stevenson

    2007-01-30

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

  4. 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

  5. WIPP WASTE MINIMIZATION PROGRAM DESCRIPTION

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

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

  6. WIPP WASTE MINIMIZATION PROGRAM DESCRIPTION

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

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

  7. 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

  8. Waste Management | Department of Energy

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

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

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

    SciTech Connect (OSTI)

    Not Available

    1993-12-31

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

  10. Characterization and process technology capabilities for Hanford tank waste disposal

    SciTech Connect (OSTI)

    Buelt, J.L.; Weimer, W.C.; Schrempf, R.E.

    1996-03-01

    The purpose of this document is to describe the Paciflc Northwest National Laboratory`s (the Laboratory) capabilities in characterization and unit process and system testing that are available to support Hanford tank waste processing. This document is organized into two parts. The first section discusses the Laboratory`s extensive experience in solving the difficult problems associated with the characterization of Hanford tank wastes, vitrified radioactive wastes, and other very highly radioactive and/or heterogeneous materials. The second section of this document discusses the Laboratory`s radioactive capabilities and facilities for separations and waste form preparation/testing that can be used to Support Hanford tank waste processing design and operations.