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Sample records for rwmc buried wastes

  1. Thermal processing system concepts and considerations for RWMC buried waste

    Energy Technology Data Exchange (ETDEWEB)

    Eddy, T.L.; Kong, P.C.; Raivo, B.D.; Anderson, G.L.

    1992-02-01

    This report presents a preliminary determination of ex situ thermal processing system concepts and related processing considerations for application to remediation of transuranic (TRU)-contaminated buried wastes (TRUW) at the Radioactive Waste Management Complex (RWMC) of the Idaho National Engineering Laboratory (INEL). Beginning with top-level thermal treatment concepts and requirements identified in a previous Preliminary Systems Design Study (SDS), a more detailed consideration of the waste materials thermal processing problem is provided. Anticipated waste stream elements and problem characteristics are identified and considered. Final waste form performance criteria, requirements, and options are examined within the context of providing a high-integrity, low-leachability glass/ceramic, final waste form material. Thermal processing conditions required and capability of key systems components (equipment) to provide these material process conditions are considered. Information from closely related companion study reports on melter technology development needs assessment and INEL Iron-Enriched Basalt (IEB) research are considered. Five potentially practicable thermal process system design configuration concepts are defined and compared. A scenario for thermal processing of a mixed waste and soils stream with essentially no complex presorting and using a series process of incineration and high temperature melting is recommended. Recommendations for applied research and development necessary to further detail and demonstrate the final waste form, required thermal processes, and melter process equipment are provided.

  2. Thermal processing system concepts and considerations for RWMC buried waste

    International Nuclear Information System (INIS)

    Eddy, T.L.; Kong, P.C.; Raivo, B.D.; Anderson, G.L.

    1992-02-01

    This report presents a preliminary determination of ex situ thermal processing system concepts and related processing considerations for application to remediation of transuranic (TRU)-contaminated buried wastes (TRUW) at the Radioactive Waste Management Complex (RWMC) of the Idaho National Engineering Laboratory (INEL). Beginning with top-level thermal treatment concepts and requirements identified in a previous Preliminary Systems Design Study (SDS), a more detailed consideration of the waste materials thermal processing problem is provided. Anticipated waste stream elements and problem characteristics are identified and considered. Final waste form performance criteria, requirements, and options are examined within the context of providing a high-integrity, low-leachability glass/ceramic, final waste form material. Thermal processing conditions required and capability of key systems components (equipment) to provide these material process conditions are considered. Information from closely related companion study reports on melter technology development needs assessment and INEL Iron-Enriched Basalt (IEB) research are considered. Five potentially practicable thermal process system design configuration concepts are defined and compared. A scenario for thermal processing of a mixed waste and soils stream with essentially no complex presorting and using a series process of incineration and high temperature melting is recommended. Recommendations for applied research and development necessary to further detail and demonstrate the final waste form, required thermal processes, and melter process equipment are provided

  3. Melter development needs assessment for RWMC buried wastes

    International Nuclear Information System (INIS)

    Donaldson, A.D.; Carpenedo, R.J.; Anderson, G.L.

    1992-02-01

    This report presents a survey and initial assessment of the existing state-of-the-art melter technology necessary to thermally treat (stabilize) buried TRU waste, by producing a highly leach resistant glass/ceramic waste form suitable for final disposal. Buried mixed transuranic (TRU) waste at the Idaho National Engineering Laboratory (INEL) represents an environmental hazard requiring remediation. The Environmental Protection Agency (EPA) placed the INEL on the National Priorities List in 1989. Remediation of the buried TRU-contaminated waste via the CERCLA decision process is required to remove INEL from the National Priorities List. A Waste Technology Development (WTD) Preliminary Systems Design and Thermal Technologies Screening Study identified joule-heated and plasma-heated melters as the most probable thermal systems technologies capable of melting the INEL soil and waste to produce the desired final waste form [Iron-Enriched Basalt (IEB) glass/ceramic]. The work reported herein then surveys the state of existing melter technology and assesses it within the context of processing INEL buried TRU wastes and contaminated soils. Necessary technology development work is recommended

  4. Assessment of selected furnace technologies for RWMC waste

    International Nuclear Information System (INIS)

    Batdorf, J.; Gillins, R.; Anderson, G.L.

    1992-03-01

    This report provides a description and initial evaluation of five selected thermal treatment (furnace) technologies, in support of earlier thermal technologies scoping work for application to the Idaho National Engineering Laboratory Radioactive Waste Management Complex (RWMC) buried wastes. The cyclone furnace, molten salt processor, microwave melter, ausmelt (fuel fired lance) furnace, and molten metal processor technologies are evaluated. A system description and brief development history are provided. The state of development of each technology is assessed, relative to treatment of RWMC buried waste

  5. A comprehensive inventory of radiological and nonradiological contaminants in waste buried or projected to be buried in the subsurface disposal area of the INEL RWMC during the years 1984-2003, Volume 1

    International Nuclear Information System (INIS)

    1995-05-01

    This report presents a comprehensive inventory of the radiological and nonradiological contaminants in waste buried or projected to be buried from 1984 through 2003 in the Subsurface Disposal Area (SDA) at the Radioactive Waste Management Complex (RWMC) of the Idaho National Engineering Laboratory. The project to compile the inventory is referred to as the recent and projected data task. The inventory was compiled primarily for use in a baseline risk assessment under the Comprehensive Environmental Response, Compensation, and Liability Act. The compiled information may also be useful for environmental remediation activities that might be necessary at the RWMC. The information that was compiled has been entered into a database termed CIDRA-the Contaminant Inventory Database for Risk Assessment. The inventory information was organized according to waste generator and divided into waste streams for each generator. The inventory is based on waste information that was available in facility operating records, technical and programmatic reports, shipping records, and waste generator forecasts. Additional information was obtained by reviewing the plant operations that originally generated the waste, by interviewing personnel formerly employed as operators, and by performing nuclear physics and engineering calculations. In addition to contaminant inventories, information was compiled on the physical and chemical characteristics and the packaging of the 99 waste streams. The inventory information for waste projected to be buried at the SDA in the future was obtained from waste generator forecasts. The completeness of the contaminant inventories was confirmed by comparing them against inventories in previous reports and in other databases, and against the list of contaminants detected in environmental monitoring performed at the RWMC

  6. Thermal processes evaluation for RWMC wastes

    International Nuclear Information System (INIS)

    1991-01-01

    The objective of this activity was to provide a white paper that identifies, collects information, and presents a preliminary evaluation of ''core'' thermal technologies that could be applied to RWMC stored and buried mixed waste. This paper presents the results of the following activities: General thermal technology identification, collection of technical and cost information on each technology, identification of thermal technologies applicable to RWMC waste, evaluation of each technology as applied to RWMC waste in seven process attributes, scoring each technology on a one to five scale (five highest) in each process attribute. Reaching conclusions about the superiority of one technology over others is not advised based on this preliminary study alone. However, the highly rated technologies (i.e., overall score of 2.9 or better) are worthy of a more detailed evaluation. The next step should be a more detailed evaluation of the technologies that includes onsite visits with operational facilities, preconceptual treatment facility design analysis, and visits with developers for emerging technologies. 2 figs., 6 tabs

  7. A comprehensive inventory of radiological and nonradiological contaminants in waste buried or projected to be buried in the subsurface disposal area of the INEL RWMC during the years 1984-2003, Volume 2

    International Nuclear Information System (INIS)

    1995-05-01

    This is the second volume of this comprehensive report of the inventory of radiological and nonradiological contaminants in waste buried or projected to be buried in the subsurface disposal area of the Idaho National Engineering Laboratory. Appendix B contains a complete printout of contaminant inventory and other information from the CIDRA Database and is presented in volumes 2 and 3 of the report

  8. Criticality safety evaluation for TRU waste in storage at the RWMC

    International Nuclear Information System (INIS)

    Shaw, M.E.; Briggs, J.B.; Atkinson, C.A.; Briscoe, G.J.

    1993-11-01

    Stored containers (drums, boxes, and bins) of transuranic waste at the Radioactive Waste Management Complex (RWMC) facility located at the Idaho National Engineering Laboratory (INEL) were evaluated based on inherent neutron absorption characteristics of the waste materials. It was demonstrated that these properties are sufficient to preclude an accidental criticality accident at the actual fissile levels present in the waste stored at the RWMC. Based on the database information available, the results reported herein confirm that the waste drums, boxes, and bins currently stored at the RWMC will remain safely subcritical if rearranged, restacked, or otherwise handled. Acceptance criteria for receiving future drum shipments were established based on fully infinite systems

  9. The role of performance assessment in the evaluation of remedial action alternatives for the Radioactive Waste Management Complex (RWMC) at the Idaho National Engineering Laboratory

    International Nuclear Information System (INIS)

    Rood, A.S.; Case, M.J.

    1988-01-01

    The Idaho National Engineering Laboratory (INEL) is operated by the Department of Energy (DOE) and is involved in nuclear research and development. The Radioactive Waste Management Complex (RWMC) at the INEL serves as a disposal facility for low level radioactive wastes generated onsite. Transuranic (TRU) wastes received from other DOE sites are currently stored at the RWMC, but were buried at the facility from 1952 until 1970. Recent findings of the Subsurface Investigations Program have determined that migration of TRU nuclides and hazardous materials from the RWMC has occurred. The primary source of organics in the buried TRU waste was generated by the Rocky Flats Plant. The INEL has proposed an aggressive four-year action plan for buried TRU waste. As a part of this plan, a task has been identified to evaluate existing remedial technologies for preventing further contaminant migration or removing the source of TRU radionuclides and nonradioactive hazardous material from the RWMC. A systems approach is being applied to evaluate, compare and recommend technologies or combinations of technologies. One criterion used in the evaluation is the net risk reduction afforded by each proposed remedial action. The method used to develop the criterion relies on models to assess the potential pathways and scenarios for the migration of radioactive and nonradioactive materials and the subsequent exposure of individuals to those materials. This paper describes the approach used to assess the performance of various remedial actions and the results obtained to date

  10. Geologic processes in the RWMC area, Idaho National Engineering Laboratory: Implications for long term stability and soil erosion at the radioactive waste management complex

    International Nuclear Information System (INIS)

    Hackett, W.R.; Tullis, J.A.; Smith, R.P.

    1995-09-01

    The Radioactive Waste Management Complex (RWMC) is the disposal and storage facility for low-level radioactive waste at the Idaho National Engineering Laboratory (INEL). Transuranic waste and mixed wastes were also disposed at the RWMC until 1970. It is located in the southwestern part of the INEL about 80 km west of Idaho Falls, Idaho. The INEL occupies a portion of the Eastern Snake River Plain (ESRP), a low-relief, basalt, and sediment-floored basin within the northern Rocky Mountains and northeastern Basin and Range Province. It is a cool and semiarid, sagebrush steppe desert characterized by irregular, rolling terrain. The RWMC began disposal of INEL-generated wastes in 1952, and since 1954, wastes have been accepted from other Federal facilities. Much of the waste is buried in shallow trenches, pits, and soil vaults. Until about 1970, trenches and pits were excavated to the basalt surface, leaving no sediments between the waste and the top of the basalt. Since 1970, a layer of sediment (about 1 m) has been left between the waste and the basalt. The United States Department of Energy (DOE) has developed regulations specific to radioactive-waste disposal, including environmental standards and performance objectives. The regulation applicable to all DOE facilities is DOE Order 5820.2A (Radioactive Waste Management). An important consideration for the performance assessment of the RWMC is the long-term geomorphic stability of the site. Several investigators have identified geologic processes and events that could disrupt a radioactive waste disposal facility. Examples of these open-quotes geomorphic hazardsclose quotes include changes in stream discharge, sediment load, and base level, which may result from climate change, tectonic processes, or magmatic processes. In the performance assessment, these hazards are incorporated into scenarios that may affect the future performance of the RWMC

  11. In situ vitrification on buried waste

    International Nuclear Information System (INIS)

    Bates, S.O.

    1992-01-01

    In situ vitrification (ISV) is being evaluated as a remedial treatment technology for buried mixed and transuranic (TRU) wastes at the Subsurface Disposal Area (SDA) at Idaho National Engineering Laboratory (INEL) and can be related to buried wastes at other Department of Energy (DOE) sites. There are numerous locations around the DOE Complex where wastes were buried in the ground or stored for future burial. The Buried Waste Program (BWP) is conducting a comprehensive Environmental Response, Compensation, and Liability Act (CERCLA) remedial investigation/feasibility study (RI/FS) for the Department of Energy - Field Office Idaho (DOE-ID). As part of the RI/FS, an ISV scoping study on the treatability of the SDA mixed low-level and mixed TRU waste is being performed for applicability to remediation of the waste at the Radioactive Waste Management Complex (RWMC). The ISV project being conducted at the INEL by EG ampersand G Idaho, Inc. consists of a treatability investigation to collect data to satisfy nine CERCLA criteria with regards to the SDA. This treatability investigation involves a series of experiments and related efforts to study the feasibility of ISV for remediation of mixed and TRU waste disposed of at the SDA

  12. Buried Waste Integrated Demonstration

    International Nuclear Information System (INIS)

    1994-03-01

    The Buried Waste Integrated Demonstration (BWID) supports the applied research, development, demonstration, and evaluation of a suite of advanced technologies that offer promising solutions to the problems associated with the remediation of buried waste. BWID addresses the difficult remediation problems associated with DOE complex-wide buried waste, particularly transuranic (TRU) contaminated buried waste. BWID has implemented a systems approach to the development and demonstration of technologies that will characterize, retrieve, treat, and dispose of DOE buried wastes. This approach encompasses the entire remediation process from characterization to post-monitoring. The development and demonstration of the technology is predicated on how a technology fits into the total remediation process. To address all of these technological issues, BWID has enlisted scientific expertise of individuals and groups from within the DOE Complex, as well as experts from universities and private industry. The BWID mission is to support development and demonstration of a suite of technologies that, when integrated with commercially-available technologies, forms a comprehensive, remediation system for the effective and efficient remediation of buried waste throughout the DOE Complex. BWID will evaluate and validate demonstrated technologies and transfer this information and equipment to private industry to support the Office of Environmental Restoration (ER), Office of Waste Management (WM), and Office of Facility Transition (FT) remediation planning and implementation activities

  13. Training requirements and responsibilities for the Buried Waste Integrated Demonstration at the Radioactive Waste Management Complex

    International Nuclear Information System (INIS)

    Vega, H.G.; French, S.B.; Rick, D.L.

    1992-09-01

    The Buried Waste Integrated Demonstration (BWID) is scheduled to conduct intrusive (hydropunch screening tests, bore hole installation, soil sampling, etc.) and nonintrusive (geophysical surveys) studies at the Radioactive Waste Management Complex (RWMC). These studies and activities will be limited to specific locations at the RWMC. The duration of these activities will vary, but most tasks are not expected to exceed 90 days. The BWID personnel requested that the Waste Management Operational Support Group establish the training requirements and training responsibilities for BWID personnel and BWID subcontractor personnel. This document specifies these training requirements and responsibilities. While the responsibilities of BWID and the RWMC are, in general, defined in the interface agreement, the training elements are based on regulatory requirements, DOE orders, DOE-ID guidance, state law, and the nature of the work to be performed

  14. The buried waste integrated demonstration

    International Nuclear Information System (INIS)

    Kostelnik, K.M.

    1991-01-01

    There are numerous locations throughout the Department of Energy (DOE) Complex where wastes have been buried in the ground or stored for future disposal. Much of this buried waste is contaminated with hazardous and radioactive materials. An extensive research program has been initiated at the Idaho National Engineering Laboratory (INEL) to develop and demonstrate advanced remediation techniques for DOE Complex buried waste. The purpose of the Buried Waste Integrated Demonstration (BWID), is to develop a scientifically sound and deployable remediation system consisting of advanced technologies which address the buried waste characteristics of the DOE Complex. This comprehensive remediation system win include technologies for the entire remediation cycle (cradle-to-grave). Technologies developed and demonstrated within the BWID will be transferred to the DOE Complex sites with buried waste, to private industry, and to universities. Multidirectional technology transfer is encouraged by the BWID. Identification and evaluation of plausible technological solutions are an ongoing activity of the BWID. A number of technologies are currently under development throughout the DOE Complex, private industry, and universities. Technology integration mechanisms have been established by BWID to facilitate collaborative research and demonstration of applicable remedial technologies for buried waste. Successful completion of the BWID will result in the development of a proven and deployable system at the INEL and other DOE Complex buried waste sites, thereby supporting the DOE Complex's environmental restoration objectives

  15. Buried Waste Program (BWP) data qualification manual

    International Nuclear Information System (INIS)

    Casey, C.; Larson, R.A.; Harris, G.A.

    1989-06-01

    The Data Qualification Manual (DQM) has been developed to discuss the process required to qualify data generated for the Buried Waste Program (BWP). The data from the BWP tasks conducted at the Radioactive Waste Management Complex (RWMC) and elsewhere will lead to remedial decisions being made which are governed by federal regulations administered by the Environmental Protection Agency (EPA). Data qualification is the process of insuring that only data of planned and known qualities are used to make a decision or answer a question. Although it is the Data Integrity Review Committee's (DIRC) responsibility to insure that the quality of all BWP data is ultimately verified and validated, all personnel who participate in the data gathering process will affect the quality of the data and must be responsible for knowing what is required to produce data of the planned quality. Therefore this manual is addressed to all participants in a data-gathering task. This manual discusses requirements to support data qualification in several areas, including: the sampling and analysis plan; data quality objectives and PARCC goals; sample custody documentation; quality assurance; assembly of the data qualification package; and existing data. 23 refs., 4 figs., 6 tabs

  16. Annual technology assessment and progress report for the Buried Transuranic Waste Studies Program at the Idaho National Engineering Laboratory (1987)

    International Nuclear Information System (INIS)

    Loomis, G.G.; Low, J.O.

    1988-01-01

    This report presents FY-87 activities for the Buried Transuranic (TRU) Waste Studies Program at the Idaho National Engineering Laboratory (INEL). This program investigates techniques to provide long-term confinement of buried TRU waste, as well as methods of retrieval. The confinement method of in situ grouting was examined in a simulated shallow-land buried TRU waste pit constructed adjacent to the RWMC TRU waste burial pits. The in situ grouting technique involved an experimental dyanmic compaction process which simultaneously grouts and compacts the waste. The simulated waste pit consisted of regions of randomly dumped drums, stacked boxes, and stacked drums, thus representing the various conditions of buried waste at the RWMC. Simulated waste and airborne tracers were loaded into the various simulated buried waste containers. Pregrouting and post-grouting data, such as hydraulic conductivity, were obtained to assess the hydrological integrity of the grouted waste material. In addition, post-grouting destructive examinations were performed and the results analyzed. Retrieval and processing of the TRU buried waste is also being examined at the INEL. At a conceptual level, retrieval of TRU buried waste involves a movable containment building to confine airborne particulate, heavy equipment to remove the waste, processing equipment, and equipment to control the air quality within the building. Studies were performed in FY-87 to identify containment building requirements such as type, mobility, and ventilation. An experimental program to demonstrate the retrieval technique using existing INEL heavy equipment has also been identified. 11 refs., 17 figs., 11 tabs

  17. Field application of innovative grouting agents for in situ stabilization of buried waste sites

    International Nuclear Information System (INIS)

    Loomis, G.G.; Farnsworth, R.K.

    1997-01-01

    This paper presents field applications for two innovative grouting agents that were used to in situ stabilize buried waste sites, via jet grouting. The two grouting agents include paraffin and a proprietary iron oxide based cement grout called TECT. These materials were tested in specially designed cold test pits that simulate buried transuranic waste at the Idaho National Engineering Laboratory (INEL). The field demonstrations were performed at the INEL in an area referred to as the Cold Test Pit, which is adjacent to the INEL Radioactive Waste Management Complex (RWMC). At the RWMC, 56,000 m 3 of transuranic (TRU) waste is co-mingled with over 170,000 m 3 of soil in shallow land burial. Improving the confinement of this waste is one of the options for final disposition of this waste. Using jet-grouting technology to inject these materials into the pore spaces of buried waste sites results in the creation of buried monolithic waste forms that simultaneously protect the waste from subsidence, while eliminating the migratory potential of hazardous and radioactive contaminants in the waste

  18. Performance test of a gamma/neutron mapper on stored TRU waste durms at the RWMC

    International Nuclear Information System (INIS)

    Gehrke, R.J.; Josten, N.E.; Lawrence, R.S.

    1995-01-01

    The results from a performance test of a γ- and neutron-radiation measurement instrument used to provide two-dimensional radiation field maps are reported. The performance test was conducted at the Transuranic Storage Area of the Radioactive Waste Management Complex (RWMC) where interim storage is provided for 55-gal. drums of TRU waste from the Department of Energy's Rocky Flats Plant. The performance test consisted of scanning drums stacked five high and five wide to identify high radiation areas and possible discrepancies with the waste manifest. Scans were taken at standoff distances of 15 cm, 30 cm, 45 cm and 90 cm. Data were acquired at scan speeds of 7.5 cm/s and 15 cm/s. The results of these scans are presented as one, two and three dimensional contour plots of the radiation fields. A comparison of these results with manifests of these drums are compared and discussed. While the T-radiation fields as measured by the Health Physicist and by the radiation maps are in general in agreement, the TRU content as given in the manifest did not often correlate with the neutron map

  19. Geophysical surveys for buried waste detection at the Idaho National Engineering Laboratory

    International Nuclear Information System (INIS)

    Sandness, G.A.; Rising, J.L.; Kimbrough, J.R.

    1979-12-01

    This report describes a series of geophysical surveys performed at the Idaho National Engineering Laboratory (INEL). The main purpose of the surveys was to evaluate techniques, principally ground-penetrating radar, for detecting and mapping radioactive wastes buried in shallow trenches and pits. A second purpose was to determine the feasibility of using ground-penetrating radar to measure the depth of basalt bedrock. A prototype geophyscal survey system developed by the US Department of Energy's Pacific Northwest Laboratory was used for this study. Radar, magnetometer, and metal detector measurements were made at three sites in the Radioactive Waste Management Complex (RWMC) at INEL. Radar measurements were made at fourth site adjacent to the RWMC. The combination of three geophysical methods was shown to provide considerable information about the distribution of buried waste materials. The tests confirmed the potential effectiveness of the radar method, but they also pointed out the need for continued research and development in ground-penetrating radar technology. The radar system tested in this study appears to be capable of measuring the depth to basalt in the vicinity of the RWMC

  20. Buried Waste Integrated Demonstration Plan

    International Nuclear Information System (INIS)

    Kostelnik, K.M.

    1991-12-01

    This document presents the plan of activities for the Buried Waste Integrated Demonstration (BWID) program which supports the environmental restoration (ER) objectives of the Department of Energy (DOE) Complex. Discussed in this plan are the objectives, organization, roles and responsibilities, and the process for implementing and managing BWID. BWID is hosted at the Idaho National Engineering Laboratory (INEL), but involves participants from throughout the DOE Complex, private industry, universities, and the international community. These participants will support, demonstrate, and evaluate a suite of advanced technologies representing a comprehensive remediation system for the effective and efficient remediation of buried waste. The processes for identifying technological needs, screening candidate technologies for applicability and maturity, selecting appropriate technologies for demonstration, field demonstrating, evaluation of results and transferring technologies to environmental restoration programs are also presented. This document further describes the elements of project planning and control that apply to BWID. It addresses the management processes, operating procedures, programmatic and technical objectives, and schedules. Key functions in support of each demonstration such as regulatory coordination, safety analyses, risk evaluations, facility requirements, and data management are presented

  1. Removal of overburden soils from buried waste sites

    International Nuclear Information System (INIS)

    Rice, P.M.

    1994-01-01

    Transuranic (TRU) waste buried in pits and trenches is covered with a soil cap, or overburden, to shed water. During retrieval operations, the overburden (expected to be clean) must be removed carefully to avoid breaching the soil/waste matrix within a pit or trench and to confine any possible local spot contamination. This necessitates removal in precise (7.6- to 15.25-cm) increments with a high degree of accuracy. In addition, during overburden removal the overburden must be characterized to a depth that exceeds each cut of soil. A field demonstration was conducted to evaluate a technology for removing overburden soils a the Radioactive Waste Management Complex (RWMC), Subsurface Disposal Area (SDA) at the Idaho National Engineering Laboratory (INEL). The demonstration evaluated equipment performance and techniques for removing overburden soil and controlling contamination and dust. To evaluate the performance of these techniques during removal operations, personnel took air particulate samples, physical measurements of the soil cuts, maneuverability measurements, and rate of soil removal data. The overburden was spiked at specific locations and depths with rare earth tracers to provide a medium for evaluating samples. Analysis to determine the precision and accuracy of the soil removal, amount of dust generated, and potential spread of contamination was performed

  2. Implementation of the buried waste integrated demonstration

    International Nuclear Information System (INIS)

    Kostelnik, K.M.; Merrill, S.K.

    1992-01-01

    The Department of Energy (DOE), Office of Technology Development (OTD) has initiated the Buried Waste Integrated Demonstration (BWID) to resolve technological deficiencies associated with the remediation of radioactive and hazardous buried waste. The BWID mission is to identify, demonstrate, and transfer innovative technologies for the remediation of DOE buried waste. To accomplish the mission, BWID is using a systems approach which supports the development of a suite of advanced and innovative technologies for the effective and efficient remediation of buried waste. This systems approach includes technologies for theentire remediation cycle. Specifically, BWID sponsors technology development in the following technology categories: site and waste characterization, retrieval, preprocessing, ex situ treatment, packaging, transportation, storage, disposal, and post-disposal monitoring

  3. APNEA/WIT system nondestructive assay capability evaluation plan for select accessibly stored INEL RWMC waste forms

    International Nuclear Information System (INIS)

    Becker, G.K.

    1997-01-01

    Bio-Imaging Research Inc. (BIR) and Lockheed Martin Speciality Components (LMSC) are engaged in a Program Research and Development Agreement and a Rapid Commercialization Initiative with the Department of Energy, EM-50. The agreement required BIR and LMSC to develop a data interpretation method that merges nondestructive assay and nondestructive examination (NDA/NDE) data and information sufficient to establish compliance with applicable National TRU Program (Program) waste characterization requirements and associated quality assurance performance criteria. This effort required an objective demonstration of the BIR and LMSC waste characterization systems in their standalone and integrated configurations. The goal of the test plan is to provide a mechanism from which evidence can be derived to substantiate nondestructive assay capability and utility statement for the BIT and LMSC systems. The plan must provide for the acquisition, compilation, and reporting of performance data thereby allowing external independent agencies a basis for an objective evaluation of the standalone BIR and LMSC measurement systems, WIT and APNEA respectively, as well as an expected performance resulting from appropriate integration of the two systems. The evaluation is to be structured such that a statement regarding select INEL RWMC waste forms can be made in terms of compliance with applicable Program requirements and criteria

  4. Remote technologies for buried waste retrieval

    International Nuclear Information System (INIS)

    Smith, A.M.; Rice, P.

    1995-01-01

    The DOE is evaluating what should be done with this buried waste. Although the radioactive waste is not particularly mobile unless airborne, some of it was buried with volatile organics and/or other substances that tend to spread easily to surrounding soil or water tables. Volatile organics are hazardous materials (such as trichloroethylene) and require clean-up at certain levels in drinking water. There is concern that the buried volatile organics will spread into the water table and contaminate drinking water. Because of this, the DOE is considering options for handling this buried waste and reducing the risks of spreading or exposure. There are two primary options: containment and stabilization, or retrieval. Containment and stabilization systems would include systems that would leave the waste where it is, but contain and stabilize it so that the radioactive and hazardous materials would not spread to the surrounding soil, water, or air. For example, an in situ vitrification system could be used to melt the waste into a composite glass-like material that would not leach into the surrounding soil, water, or air. Retrieval systems are those that would remove the waste from its burial location for treatment and/or repackaging for long term storage. The objective of this project was to develop and demonstrate remote technologies that would minimize dust generation and the spread of airborne contaminants during buried waste retrieval. Remote technologies are essential for the retrieval of buried waste because they remove workers from the hazardous environment and provide greater automation, reducing the chances of human error. Minimizing dust generation is also essential to increased safety for the workers and the environment during buried waste retrieval. The main contaminants within the waste are micron-sized particles of plutonium and americium oxides, chlorides, and hydroxides, which are easily suspended in air and spread if disturbed

  5. In situ vitrification: Application to buried waste

    International Nuclear Information System (INIS)

    Callow, R.A.; Thompson, L.E.

    1991-01-01

    Two in situ vitrification field tests were conducted in June and July 1990 at Idaho National Engineering Laboratory. In situ vitrification is a technology for in-place conversion of contaminated soils into a durable glass and crystalline waste form and is being investigated as a potential remediation technology for buried waste. The overall objective of the two tests was to assess the general suitability of the process to remediate buried waste structures found at Idaho National Engineering Laboratory. In particular, these tests were designed as part of a treatability study to provide essential information on field performance of the process under conditions of significant combustible and metal wastes, and to test a newly developed electrode feed technology. The tests were successfully completed, and the electrode feed technology provided valuable operational control for successfully processing the high metal content waste. The results indicate that in situ vitrification is a feasible technology for application to buried waste. 2 refs., 5 figs., 2 tabs

  6. In situ vitrification of buried waste sites

    International Nuclear Information System (INIS)

    Shade, J.W.; Thompson, L.E.; Kindle, C.H.

    1991-04-01

    In situ vitrification (ISV) is a remedial technology initially developed to treat soils contaminated with a variety of organics, heavy metals, and/or radioactive materials. Recent tests have indicated the feasibility of applying the process to buried wastes including containers, combustibles, and buried metals. In addition, ISV is being considered for application to the emplacement of barriers and to the vitrification of underground tanks. This report provides a review of some of the recent experiences of applying ISV in engineering-scale and pilot-scale tests to wastes containing organics, the Environmental Protection Agency (EPA) Toxic metals buried in sealed containers, and buried ferrous metals, with emphasis on the characteristics of the vitrified product and adjacent soil. 9 refs., 2 figs., 3 tabs

  7. Buried Waste Integrated Demonstration stakeholder involvement model

    International Nuclear Information System (INIS)

    Kaupanger, R.M.; Kostelnik, K.M.; Milam, L.M.

    1994-04-01

    The Buried Waste Integrated Demonstration (BWID) is a program funded by the US Department of Energy (DOE) Office of Technology Development. BWID supports the applied research, development, demonstration, and evaluation of a suite of advanced technologies that together form a comprehensive remediation system for the effective and efficient remediation of buried waste. Stakeholder participation in the DOE Environmental Management decision-making process is critical to remediation efforts. Appropriate mechanisms for communication with the public, private sector, regulators, elected officials, and others are being aggressively pursued by BWID to permit informed participation. This document summarizes public outreach efforts during FY-93 and presents a strategy for expanded stakeholder involvement during FY-94

  8. DOE complex buried waste characterization assessment

    International Nuclear Information System (INIS)

    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 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)

  9. Buried Waste Integrated Demonstration Strategy Plan

    International Nuclear Information System (INIS)

    Kostelnik, K.M.

    1993-02-01

    The Buried Waste Integrated Demonstration (BWID) supports the applied research, development, demonstration, and evaluation of a suite of advanced technologies that form a comprehensive remediation system for the effective and efficient remediation of buried waste. These efforts are identified and coordinated in support of the US Department of Energy (DOE), Environmental Restoration and Waste Management (ERWM) needs and objectives. The present focus of BWID is to support retrieval and ex situ treatment configuration options. Future activities will explore and support containment and stabilization efforts in addition to the retrieval/ex situ treatment options. Long and short term strategies of the BWID are provided. Processes for identifying technological needs, screening candidate technologies for BWID applicability, researching technical issues, field demonstrating technologies, evaluating demonstration results to determine each technology's threshold of capability, and commercializing successfully demonstrated technologies for implementation for environmental restoration also are presented in this report

  10. Detection and mapping of buried waste

    International Nuclear Information System (INIS)

    Stahl, G.; Odenweller, J.; Huff, D.

    1996-01-01

    A major environmental concern today is the characterization, remediation, and monitoring of Federal waste sites, such as those operated by the Department of Energy (DOE). A significant amount of hazardous waste is buried at known sites on DOE reservations. Determining the exact location of buried waste trenches is an important step in the characterization and remediation of these sites. Remotely sensed imagery offers a rich source of information for accomplishing this task. This paper presents a case study conducted at Solid Waste Storage Area 4 (SWSA 4) at Oak Ridge National Laboratory. Historical aerial photography and recently collected multispectral imagery were analyzed to determine the precise locations of the buried trenches. A comparison of the results to recent ground measurements indicates the strengths and weaknesses of the remote sensing approach. Further analysis of these ground data also provides an understanding of the phenomenology that gives rise to the imagery signatures associated with the trenches. Application of these techniques can significantly reduce the costs of site remediation. By knowing the trench locations precisely, rather than the general locations, remediation alternatives to contain and isolate the waste materials can be tailored appropriately

  11. The Environmental and ethical basis of the geological disposal of long-lived radioactive waste. A collective opinion by the Radioactive Waste Management Committee (RWMC) of the OECD Nuclear Energy Agency

    International Nuclear Information System (INIS)

    1995-01-01

    The report presents a consensus position of the national authorities in their search for appropriate solutions in the safe disposal of radioactive wastes in the form of a Collective Opinion of the Radioactive waste Management Committee (RWMC) of the OECD Nuclear Energy Agency. The Collective Opinion addresses the strategy for the final disposal of long-lived radioactive wastes seen from an environmental and ethical perspective, including considerations of equity and fairness within and between generations. (7 refs.)

  12. Retrieval of buried waste using conventional equipment

    International Nuclear Information System (INIS)

    Valentich, D.J.

    1994-01-01

    A field test was conducted to determine the effectiveness of using conventional type construction equipment for the retrieval of buried transuranic (TRU) waste. A cold (nonhazardous and nonradioactive test pit 841 m 3 in volume) was constructed with boxes and drums filled with simulated waste materials, such as metal, plastic, wood, concrete, and sludge. Large objects, including truck beds, vessels, vaults, pipes, and beams were also placed in the pit. These materials were intended to simulate the type of waste found in existing TRU buried waste pits and trenches. A series of commercially available equipment items, such as excavators and tracked loaders outfitted with different end effectors, were used to remove the simulated waste. Work was performed from both the abovegrade and belowgrade positions. During the demonstration, a number of observations, measurements, and analyses were performed to determine which equipment was the most effective in removing the waste. The retrieval rates for the various excavation techniques were recorded. The inherent dust control capabilities of the excavation methods used were also observed

  13. Virtual environmental applications for buried waste characterization technology evaluation report

    International Nuclear Information System (INIS)

    1995-05-01

    The project, Virtual Environment Applications for Buried Waste Characterization, was initiated in the Buried Waste Integrated Demonstration Program in fiscal year 1994. This project is a research and development effort that supports the remediation of buried waste by identifying and examining the issues, needs, and feasibility of creating virtual environments using available characterization and other data. This document describes the progress and results from this project during the past year

  14. Virtual environmental applications for buried waste characterization technology evaluation report

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1995-05-01

    The project, Virtual Environment Applications for Buried Waste Characterization, was initiated in the Buried Waste Integrated Demonstration Program in fiscal year 1994. This project is a research and development effort that supports the remediation of buried waste by identifying and examining the issues, needs, and feasibility of creating virtual environments using available characterization and other data. This document describes the progress and results from this project during the past year.

  15. In situ grouting of buried transuranic waste

    International Nuclear Information System (INIS)

    Spalding, B.P.; Lee, S.Y.

    1987-01-01

    This task is a demonstration and evaluation of the in situ hydrologic stabilization of buried transuranic waste at a humid site via grout injection. Two small trenches, containing buried transuranic waste, were filled with 34,000 liters of polyacrylamide grout. Initial field results have indicated that voids within the trenches were totally filled by the grout and that the intratrench hydraulic conductivity was reduced to below field-measurable values. The grout was also completely contained within the two trenches as no grout constituents were observed in the 12 perimeter ground water monitoring wells. Polyacrylamide grout was selected for field demonstration over polyacrylate grout because of its superior performance in laboratory degradation studies. Also supporting the selection of polyacrylamide was the difficulty of controlling the set time of the acrylate polymerization process in the presence of potassium ferricyanide. Based on preliminary degradation monitoring, polyacrylamide was estimated to have a microbiological half-life of 115 years in the test soil. However, this calculated value is likely to be conservatively low because microbial degradation of the grout set accelerator or residual monomer may be contributing most to the measured microbial respiration. Addition work, using 14 C-labeled acrylate and acrylamide grouts, is being carried out to more accurately estimate the grouts' microbiological half-life

  16. DOE's plan for buried transuranic (TRU) contaminated waste

    International Nuclear Information System (INIS)

    Mathur, J.; D'Ambrosia, J.; Sease, J.

    1987-01-01

    Prior to 1970, TRU-contaminated waste was buried as low-level radioactive waste. In the Defense Waste Management Plan issued in 1983, the plan for this buried TRU-contaminated waste was to monitor the buried waste, take remedial actions, and to periodically evaluate the safety of the waste. In March 1986, the General Accounting Office (GAO) recommended that the Department of Energy (DOE) provide specific plans and cost estimates related to buried TRU-contaminated waste. This plan is in direct response to the GAO request. Buried TRU-contaminated waste and TRU-contaminated soil are located in numerous inactive disposal units at five DOE sites. The total volume of this material is estimated to be about 300,000 to 500,000 m 3 . The DOE plan for TRU-contaminated buried waste and TRU-contaminated soil is to characterize the disposal units; assess the potential impacts from the waste on workers, the surrounding population, and the environment; evaluate the need for remedial actions; assess the remedial action alternatives; and implement and verify the remedial actions as appropriate. Cost estimates for remedial actions for the buried TRU-contaminated waste are highly uncertain, but they range from several hundred million to the order of $10 billion

  17. Buried waste integrated demonstration technology integration process

    International Nuclear Information System (INIS)

    Ferguson, J.S.; Ferguson, J.E.

    1992-04-01

    A Technology integration Process was developed for the Idaho National Energy Laboratories (INEL) Buried Waste Integrated Demonstration (BWID) Program to facilitate the transfer of technology and knowledge from industry, universities, and other Federal agencies into the BWID; to successfully transfer demonstrated technology and knowledge from the BWID to industry, universities, and other Federal agencies; and to share demonstrated technologies and knowledge between Integrated Demonstrations and other Department of Energy (DOE) spread throughout the DOE Complex. This document also details specific methods and tools for integrating and transferring technologies into or out of the BWID program. The document provides background on the BWID program and technology development needs, demonstrates the direction of technology transfer, illustrates current processes for this transfer, and lists points of contact for prospective participants in the BWID technology transfer efforts. The Technology Integration Process was prepared to ensure compliance with the requirements of DOE's Office of Technology Development (OTD)

  18. Method of burying vessel containing radioactive waste

    International Nuclear Information System (INIS)

    Koga, Yoshihito.

    1989-01-01

    A float having an inert gas sealed therein is attached to a tightly closed vessel containing radioactive wastes. The vessel is inserted and kept in a small hole for burying the tightly closed vessel in an excavated shaft in rocks such as of granite or rock salts, while filling bentonite as shielding material therearound. In this case, the float is so adjusted that the apparent specific gravity is made equal or nearer between the tightly closed vessel and the bentonite, so that the rightly closed vessel does not sink and cause direct contact with the rocks even if bentonite flows due to earthquakes, etc. This can prevent radioactivity contamination through water in the rocks. (S.K.)

  19. Integrated test schedule for buried waste integrated demonstration

    International Nuclear Information System (INIS)

    Brown, J.T.; McDonald, J.K.

    1992-05-01

    The Integrated Test Schedule incorporates the various schedules the Buried Waste Integrated Demonstration (BWID) supports into one document. This document contains the Federal Facilities Agreement and Consent Order schedules for the Idaho National Engineering Laboratory, Hanford Reservation, Oak Ridge Reservation, and Fernald Environmental Materials Center. Included in the Integrated Test Schedule is the Buried Waste Integrated Demonstration ''windows of opportunity'' schedule. The ''windows of opportunity'' schedule shows periods of time in which Buried Waste Integrated Demonstration Program-sponsored technology demonstrations could support key decisions in the Federal Facilities Agreement and Consent Order. Schedules for the Buried Waste Integrated Demonstration-sponsored technology task plans are categorized by technology area and divided by current fiscal year and out-year. Total estimated costs for Buried Waste Integrated Demonstration-sponsored Technology Task Plans for FY-92 through FY-97 are $74.756M

  20. Buried waste containment system materials. Final Report

    International Nuclear Information System (INIS)

    Weidner, J.R.; Shaw, P.G.

    1997-10-01

    This report describes the results of a test program to validate the application of a latex-modified cement formulation for use with the Buried Waste Containment System (BWCS) process during a proof of principle (POP) demonstration. The test program included three objectives. One objective was to validate the barrier material mix formulation to be used with the BWCS equipment. A basic mix formula for initial trials was supplied by the cement and latex vendors. The suitability of the material for BWCS application was verified by laboratory testing at the Idaho National Engineering and Environmental Laboratory (INEEL). A second objective was to determine if the POP BWCS material emplacement process adversely affected the barrier material properties. This objective was met by measuring and comparing properties of material prepared in the INEEL Materials Testing Laboratory (MTL) with identical properties of material produced by the BWCS field tests. These measurements included hydraulic conductivity to determine if the material met the US Environmental Protection Agency (EPA) requirements for barriers used for hazardous waste sites, petrographic analysis to allow an assessment of barrier material separation and segregation during emplacement, and a set of mechanical property tests typical of concrete characterization. The third objective was to measure the hydraulic properties of barrier material containing a stop-start joint to determine if such a feature would meet the EPA requirements for hazardous waste site barriers

  1. Remediating the INEL's buried mixed waste tanks

    International Nuclear Information System (INIS)

    Kuhns, D.J.; Matthern, G.E.; Reese, C.L.

    1996-01-01

    The Idaho National Engineering Laboratory (INEL), formerly the National Reactor Testing Station (NRTS), encompasses 890 square miles and is located in southeast Idaho. In 1949, the United States Atomic Energy Commission, now the Department of Energy (DOE), established the NRTS as a site for the building and testing of nuclear facilities. Wastes generated during the building and testing of these nuclear facilities were disposed within the boundaries of the site. These mixed wastes, containing radionuclides and hazardous materials, were often stored in underground tanks for future disposal. The INEL has 11 buried mixed waste storage tanks regulated under the Comprehensive Environmental Response, Compensation and Liability Act (CERCLA) ranging in size from 400 to 50,000 gallons. These tanks are constructed of either stainless or carbon steel and are located at 3 distinct geographic locations across the INEL. These tanks have been grouped based on their similarities in an effort to save money and decrease the time required to complete the necessary remediation. Environmental Restoration and Technology Development personnel are teaming in an effort to address the remediation problem systematically

  2. Nuclear waste--does burying it bury the problem

    International Nuclear Information System (INIS)

    Thomas, R.A.

    1979-01-01

    This article discusses the Department of Energy (DOE)'s undergrounsd nuclear waste repository which is scheduled for startup in 1981 in New Mexico, and tries to explain why this project is being plagued by delays and uncertainties. The facility, known as the Waste Isolation Pilot Plant (WIPP), faces such problems as the question of the geologic security of the tentative site, citizens' objections about the location, as well as some licensing problems and concerns about overland transport of the large amounts of highly radioactive wastes that will fill the repository

  3. Buried waste remediation: A new application for in situ vitrification

    International Nuclear Information System (INIS)

    Kindle, C.H.; Thompson, L.E.

    1991-04-01

    Buried wastes represent a significant environmental concern and a major financial and technological challenge facing many private firms, local and state governments, and federal agencies. Numerous radioactive and hazardous mixed buried waste sites managed by the US Department of Energy (DOE) require timely clean up to comply with state or federal environmental regulations. Hazardous wastes, biomedical wastes, and common household wastes disposed at many municipal landfills represent a significant environmental health concern. New programs and regulations that result in a greater reduction of waste via recycling and stricter controls regarding generation and disposal of many wastes will help to stem the environmental consequences of wastes currently being generated. Groundwater contamination, methane generation, and potential exposures to biohazards and chemically hazardous materials from inadvertent intrusion will continue to be potential environmental health consequences until effective and permanent closure is achieved. In situ vitrification (ISV) is being considered by the DOE as a permanent closure option for radioactive buried waste sites. The results of several ISV tests on simulated and actual buried wastes conducted during 1990 are presented here. The test results illustrate the feasibility of the ISV process for permanent remediation and closure of buried waste sites in commercial landfills. The tests were successful in immobilizing or destroying hazardous and radioactive contaminants while providing up to 75 vol % waste reduction. 6 refs., 7 figs., 5 tabs

  4. ISV technology development plan for buried waste

    International Nuclear Information System (INIS)

    Nickelson, D.F.; Callow, R.A.; Luey, J.K.

    1992-07-01

    This report identifies the main technical issues facing the in situ vitrification (ISV) application to buried waste, and presents a plan showing the top-level schedule and projected resources needed to develop and demonstrate the technology for meeting Environmental Restoration Department (ERD) needs. The plan also proposes a model strategy for the technology transfer from the Department of Energy's Office of Technology Development (DOE-OTD) to the Office of Environmental Restoration (DOE-ER) as the technology proceeds from issues resolution (development) to demonstration and remedial readiness. Implementation of the plan would require $34,91 1K in total funding to be spread in the years FY-93 through FY-98. Of this amount, $10,183K is planned to be funded by DOE-OTD through the ISV Integrated Program. The remaining amount, $24,728K, is recommended to be split between the Department of Energy (DOE) Office of Technology Development ($6,670K) and DOE Office of Environmental Restoration ($18,058K)

  5. End effectors and attachments for buried waste excavation equipment

    International Nuclear Information System (INIS)

    King, R.H.

    1993-09-01

    The Buried Waste Integrated Demonstration (BWID) supports the applied research, development, demonstration, and evaluation of a suite of advanced technologies that form a comprehensive remediation system for the effective and efficient remediation of buried waste. Their efforts are identified and coordinated in support of the U.S. Department of Energy (DOE), Environmental Restoration and Waste Management (ER ampersand WM) Department's needs and objectives. The present focus of BWID is to support retrieval and ex-situ treatment configuration options. Future activities will explore and support containment, and stabilization efforts in addition to the retrieval/ex situ treatment options. This report presents a literature search on the state-of-the-art in end effectors and attachments in support of excavator of buried transuranic waste. Included in the report are excavator platforms and a discussion of the various attachments. Also included is it list of vendors and specifications

  6. Buried waste integrated demonstration FY 94 deployment plan

    International Nuclear Information System (INIS)

    Hyde, R.A.; Walker, S.; Garcia, M.M.

    1994-05-01

    The Buried Waste Integrated Demonstration (BWID) is a program funded by the U.S. Department of Energy Office of Technology Development. BWID supports the applied research, development, demonstration, testing, and evaluation of a suite of advanced technologies that together form a comprehensive remediation system for the effective and efficient remediation of buried waste. The fiscal year (FY) 1994 effort will fund thirty-eight technologies in five areas of buried waste site remediation: site characterization, waste characterization, retrieval, treatment, and containment/stabilization. This document is the basic operational planning document for deployment of all BWID projects. Discussed in this document are the BWID preparations for INEL field demonstrations, INEL laboratory demonstrations, non-INEL demonstrations, and paper studies. Each technology performing tests will prepare a test plan to detail the specific procedures, objectives, and tasks of each test. Therefore, information specific to testing each technology is intentionally omitted from this document

  7. Risk and cost tradeoffs for remote retrieval of buried waste

    International Nuclear Information System (INIS)

    Hyde, R.A.; Grienbenow, B.E.; Nickelson, D.F.

    1994-01-01

    The Buried Waste Integrated Demonstration is supporting the development, demonstration, testing, and evaluation of a suite of technologies that, when integrated with commercially available technologies, form a comprehensive system for the remediation of radioactive and hazardous buried waste. As a part of the program's technology development, remote retrieval equipment is being developed and tested for the remediation of buried waste. During remedial planning, several factors are considered when choosing remote versus manual retrieval systems. Time that workers are exposed to radioactivity, chemicals, air particulate, and industrial hazards is one consideration. The generation of secondary waste is also a consideration because it amounts to more waste to treat and some wastes may require special handling or treatment. Cost is also a big factor in determining whether remote or manual operations will be used. Other considerations include implementability, effectiveness, and the number of required personnel. This paper investigates each of these areas to show the risk and cost benefits and limitations for remote versus manual retrieval of buried waste

  8. Risk and cost tradeoffs for remote retrieval of buried waste

    Energy Technology Data Exchange (ETDEWEB)

    Hyde, R.A.; Grienbenow, B.E.; Nickelson, D.F.

    1994-12-31

    The Buried Waste Integrated Demonstration is supporting the development, demonstration, testing, and evaluation of a suite of technologies that, when integrated with commercially available technologies, form a comprehensive system for the remediation of radioactive and hazardous buried waste. As a part of the program`s technology development, remote retrieval equipment is being developed and tested for the remediation of buried waste. During remedial planning, several factors are considered when choosing remote versus manual retrieval systems. Time that workers are exposed to radioactivity, chemicals, air particulate, and industrial hazards is one consideration. The generation of secondary waste is also a consideration because it amounts to more waste to treat and some wastes may require special handling or treatment. Cost is also a big factor in determining whether remote or manual operations will be used. Other considerations include implementability, effectiveness, and the number of required personnel. This paper investigates each of these areas to show the risk and cost benefits and limitations for remote versus manual retrieval of buried waste.

  9. Development of a teleoperated backhoe for buried waste excavation

    International Nuclear Information System (INIS)

    Burks, B.L.; Killough, S.M.; Thompson, D.H.

    1992-01-01

    For nearly five decades the United States (US) Department of Energy (DOE) and its predecessor agencies have engaged in broad-based research and development activities as well as nuclear weapons component production. As a by-product of these activities, large quantities of waste materials have been granted. One of the most common approaches used for solid waste storage was to bury waste containers in pits and trenches. With the current emphasis on environmental restoration, DOE now plans to either retrieve much of the legacy of buried waste or stabilize the waste in place via in situ vitrification or other means. Because of the variety of materials that have been buried over the years, the hazards of retrieval are significant if performed using conventional manned operations. The potential hazards, in addition to radiation exposure, include pyrophorics, toxic chemicals, and explosives. Although manifests exist for much of the buried waste, these records are often incomplete compared to today's requirements. Because of the potential hazards and uncertainty about waste contents and container integrity, it is highly desirable to excavate these wastes using remotely operated equipment. In this paper the authors describe the development of a teleoperated military tractor called the Small Emplacement Excavator (SEE). Development of the SEE is being funded jointly by both DOE and the US Army. The DOE sponsor is the Office of Technology Development (OTD) Robotics Program. The US Army sponsor is the Program Manager for Ammunition Logistics, Picatinny Arsenal. The primary interest for DOE is in the application to remote excavation of buried waste, while the primary emphasis for the US Army is in the remote retrieval of unexploded ordnance. Technical requirements for these two tasks are very similar and, therefore, justify a joint development project. 1 ref

  10. Test plan for buried waste containment system materials

    International Nuclear Information System (INIS)

    Weidner, J.; Shaw, P.

    1997-03-01

    The objectives of the FY 1997 barrier material work at the Idaho National Engineering and Environmental Laboratory are to (1) select a waste barrier material and verify that it is compatible with the Buried Waste Containment System Process, and (2) determine if, and how, the Buried Waste Containment System emplacement process affects the material properties and performance (on proof of principle scale). This test plan describes a set of measurements and procedures used to validate a waste barrier material for the Buried Waste Containment System. A latex modified proprietary cement manufactured by CTS Cement Manufacturing Company will be tested. Emplacement properties required for the Buried Waste Containment System process are: slump between 8 and 10 in., set time between 15 and 30 minutes, compressive strength at set of 20 psi minimum, and set temperature less than 100 degrees C. Durability properties include resistance to degradation from carbonate, sulfate, and waste-site soil leachates. A set of baseline barrier material properties will be determined to provide a data base for comparison with the barrier materials when tested in the field. The measurements include permeability, petrographic analysis to determine separation and/or segregation of mix components, and a set of mechanical properties. The measurements will be repeated on specimens from the field test material. The data will be used to determine if the Buried Waste Containment System equipment changes the material. The emplacement properties will be determined using standard laboratory procedures and instruments. Durability of the barrier material will be evaluated by determining the effect of carbonate, sulfate, and waste-site soil leachates on the compressive strength of the barrier material. The baseline properties will be determined using standard ASTM procedures. 9 refs., 1 fig., 2 tabs

  11. Exhumation of radioactive solid wastes buried for fourteen years

    International Nuclear Information System (INIS)

    Horton, J.H.

    1977-03-01

    Twenty-five linear feet of a low-level beta-gamma waste trench was excavated fourteen years after the waste was buried. The waste included wood, steel, plastics, cotton cloth, rubber, and paper. Cardboard boxes not enclosed in plastic were the only materials to deteriorate visibly. Apparently, decades would be required for all cellulose materials to decompose, and plastics and metals would survive indefinitely

  12. Buried Waste Integrated Demonstration Technology Preparedness and Status Report Guidance

    International Nuclear Information System (INIS)

    Blacker, P.B.; Bonnenberg, R.W.; Cannon, P.G.; Hyde, R.A.; Watson, L.R.

    1994-04-01

    A Technology Preparedness and Status Report is required for each Technical Task Plan funded by the Buried Waste Integrated Demonstration. This document provides guidance for the preparation of that report. Major sections of the report will include a subset of the need for the technology, objectives of the demonstration, technology description and readiness evaluation, demonstration requirements, and preparedness checklist and action plan

  13. Radiotoxic hazard measure for buried solid radioactive waste

    International Nuclear Information System (INIS)

    Hamstra, J.

    1975-01-01

    The radiotoxic hazards resulting from the disposal of highlevel reprocessing wastes into a deep geological formation are reviewed. The term radiotoxic hazard measure (RHM), used to measure the hazard from buried radioactive wastes, is based on the maximum radionuclide concentration permissible in water. Calculations are made of the RHM levels for the high-level reprocessing wastes of both light-water-reactor and fast breeder reactor fuels. In comparing these RHM levels with that for the natural activity of an equivalent amount of uranium ore and its mill tailings, it is concluded that an actual additional radiotoxic hazard for buried high-level reprocessing waste only exists for the first 300 to 500 years after burial. (U.S.)

  14. 'Hydrotechnical' problems of burying radioactive waste

    International Nuclear Information System (INIS)

    Nagy, Z.; Buday, G.

    2008-01-01

    The paper describes the design and construction problems of an underground storage facility of nuclear wastes. Special attention ids paid to the role of underground water. After detailed surveys the construction works of the Hungarian Radioactive Waste Storage Facility at Bataapati begun in 2005. The construction of the two 1700 m long inclines are near to the level of the planned storage chambers, today. (TRA)

  15. FY-94 buried waste integrated demonstration program report

    International Nuclear Information System (INIS)

    1994-01-01

    The Buried Waste Integrated Demonstration (BWID) supports the applied research, development, demonstration, and evaluation of a multitude of advanced technologies. These technologies are being integrated to form a comprehensive remediation system for the effective and efficient remediation of buried waste. These efforts are identified and coordinated in support of the U.S. Department of Energy (DOE), Environmental Restoration and Waste Management (ER/WM) needs and objectives. This document summarizes previous demonstrations and describes the FY-94 BWID technology development and demonstration activities. Sponsored by the DOE Office of Technology Development (OTD), BWID works with universities and private industry to develop these technologies, which are being transferred to the private sector for use nationally and internationally. A public participation policy has been established to provide stakeholders with timely and accurate information and meaningful opportunities for involvement in the technology development and demonstration process

  16. Field test plan: Buried waste technologies, Fiscal Year 1995

    International Nuclear Information System (INIS)

    Heard, R.E.; Hyde, R.A.; Engleman, V.S.; Evans, J.D.; Jackson, T.W.

    1995-06-01

    The US Department of Energy, Office of Technology Development, supports the applied research, development, demonstration, testing, and evaluation of a suite of advanced technologies that, when integrated with commercially available baseline technologies, form a comprehensive remediation system for the effective and efficient remediation of buried waste. The Fiscal Year 1995 effort is to deploy and test multiple technologies from four functional areas of buried waste remediation: site characterization, waste characterization, retrieval, and treatment. This document is the basic operational planning document for the deployment and testing of the technologies that support the field testing in Fiscal Year 1995. Discussed in this document are the scope of the tests; purpose and objective of the tests; organization and responsibilities; contingency plans; sequence of activities; sampling and data collection; document control; analytical methods; data reduction, validation, and verification; quality assurance; equipment and instruments; facilities and utilities; health and safety; residuals management; and regulatory management

  17. FY-95 technology catalog. Technology development for buried waste remediation

    International Nuclear Information System (INIS)

    1995-01-01

    The US Department of Energy's (DOE) Buried Waste Integrated Demonstration (BWID) program, which is now part of the Landfill Stabilization Focus Area (LSFA), supports applied research, development, demonstration, and evaluation of a multitude of advanced technologies dealing with underground radioactive and hazardous waste remediation. These innovative technologies are being developed as part of integrated comprehensive remediation systems for the effective and efficient remediation of buried waste sites throughout the DOE complex. These efforts are identified and coordinated in support of Environmental Restoration (EM-40) and Waste Management (EM-30) needs and objectives. Sponsored by the DOE Office of Technology Development (EM-50), BWID and LSFA work with universities and private industry to develop technologies that are being transferred to the private sector for use nationally and internationally. This report contains the details of the purpose, logic, and methodology used to develop and demonstrate DOE buried waste remediation technologies. It also provides a catalog of technologies and capabilities with development status for potential users. Past FY-92 through FY-94 technology testing, field trials, and demonstrations are summarized. Continuing and new FY-95 technology demonstrations also are described

  18. FY-95 technology catalog. Technology development for buried waste remediation

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1995-10-01

    The US Department of Energy`s (DOE) Buried Waste Integrated Demonstration (BWID) program, which is now part of the Landfill Stabilization Focus Area (LSFA), supports applied research, development, demonstration, and evaluation of a multitude of advanced technologies dealing with underground radioactive and hazardous waste remediation. These innovative technologies are being developed as part of integrated comprehensive remediation systems for the effective and efficient remediation of buried waste sites throughout the DOE complex. These efforts are identified and coordinated in support of Environmental Restoration (EM-40) and Waste Management (EM-30) needs and objectives. Sponsored by the DOE Office of Technology Development (EM-50), BWID and LSFA work with universities and private industry to develop technologies that are being transferred to the private sector for use nationally and internationally. This report contains the details of the purpose, logic, and methodology used to develop and demonstrate DOE buried waste remediation technologies. It also provides a catalog of technologies and capabilities with development status for potential users. Past FY-92 through FY-94 technology testing, field trials, and demonstrations are summarized. Continuing and new FY-95 technology demonstrations also are described.

  19. Buried Waste Integrated Demonstration FY-93 Deployment Plan

    International Nuclear Information System (INIS)

    Bonnenberg, R.W.; Heard, R.E.; Milam, L.M.; Watson, L.R.

    1993-02-01

    The Buried Waste Integrated Demonstration (BWID) is a program funded by the US Department of Energy Office of Technology Development. BWID supports the applied research, development, demonstration, and evaluation of a suite of advanced technologies that together form a comprehensive remediation system for the effective and efficient remediation of buried waste. The fiscal year 1993 effort will deploy seven major field demonstrations at the Idaho National Engineering Laboratory's (INEL's) Radioactive Waste Management Complex Cold Test Pit. These major demonstrations are Remote Characterization System, Remote Excavation System, Overburden Removal, Waste Isolation, Contamination Control Unit, Rapid Monitoring Unit, and Fixation of Soil Surface Contamination. This document is the basic operational planning document for BWID deployment of the INEL field demonstrations. Additional sections deal briefly with four nonINEL field and laboratory demonstrations (Buried Waste Retrieval, Arc Melter Vitrification, Graphite DC Plasma Arc Melter, and Fixed Hearth Plasma Process) and with four INEL laboratory demonstrations (Electrostatic Curtain, Thermal Kinetics, Multiaxis Crane Control System, and Dig-Face Characterization)

  20. Hanford site implementation plan for buried, transuranic-contaminated waste

    International Nuclear Information System (INIS)

    1987-05-01

    The GAO review of DOE's Defense Waste Management Plan (DWMP) identified deficiencies and provided recommendations. This report responds to the GAO recommendations with regard to the Hanford Site. Since the issuance of the DWMP, an extensive planning base has been developed for all high-level and transuranic waste at the Hanford Site. Thirty-three buried sites have been identified as possibly containing waste that can be classified as transuranic waste. Inventory reports and process flowsheets were used to provide an estimate of the radionuclide and hazardous chemical content of these sites and approximately 370 additional sites that can be classified as low-level waste. A program undertaken to characterize select sites suspected of having TRU waste to refine the inventory estimates. Further development and evaluation are ongoing to determine the appropriate remedial actions, with the objectives of balancing long-term risks with costs and complying with regulations. 18 refs., 7 figs., 6 tabs

  1. Freeze block testing of buried waste lines

    International Nuclear Information System (INIS)

    Robbins, E.D.; Willi, J.C.

    1976-01-01

    An investigation was conducted to demonstrate application of freeze blocking in waste transfer lines such that a hydrostatic pressure test can be applied. A shop test was conducted on a 20-foot length, 3-inch schedule 40, carbon steel pipe using a coolant of dry ice and Freon. The positive results from these tests prompted a similar employment of the freeze block method in hydrostatic pressure testing the feed inlet leading to 241-S-101 Waste Tank. This pipeline is a 3-inch schedule 10, stainless steel pipe approximately 800 feet long. The freeze block was formed near the lower end of the pipe as it entered the 101-S Waste Tank and a pressure hold test was applied to this pipeline. This test proved the integrity of the pipeline in question, and demonstrated the validity of freeze blocking an open-ended pipeline which could not be hydrotested in other conventional ways. The field demonstration facility, costing $30,200 was completed late in 1975

  2. Buried Waste Integrated Demonstration FY-95 Deployment Plan

    Energy Technology Data Exchange (ETDEWEB)

    Stacey, D.E.

    1995-03-01

    The Buried Waste Integrated Demonstration (BWID) is a program funded by the U.S. Department of Energy Office of Technology Development. BWID supports the applied research, development, demonstration, testing, and evaluation of a suite of advanced technologies that together form a comprehensive remediation system for the effective and efficient remediation of buried waste. The FY-95 effort will fund 24 technologies in five areas of buried waste site remediation: site characterization, waste characterization, retrieval, treatment, and containment/stabilization. Ten of these technologies will take part in the integrated field demonstration that will take place at the Idaho National Engineering Laboratory (INEL) facilities in the summer of 1995. This document is the basic operational planning document for deployment of all BWID projects funded in FY-95. Discussed in this document are the BWID preparations for the INEL integrated field demonstration, INEL research and development (R&D) demonstrations, non-INEL R&D demonstrations, and office research and technical review meetings. Each project will have a test plan detailing the specific procedures, objectives, and tasks of the test. Therefore, information that is specific to testing each technology is intentionally limited in this document.

  3. Buried Waste Integrated Demonstration FY-95 Deployment Plan

    International Nuclear Information System (INIS)

    Stacey, D.E.

    1995-03-01

    The Buried Waste Integrated Demonstration (BWID) is a program funded by the U.S. Department of Energy Office of Technology Development. BWID supports the applied research, development, demonstration, testing, and evaluation of a suite of advanced technologies that together form a comprehensive remediation system for the effective and efficient remediation of buried waste. The FY-95 effort will fund 24 technologies in five areas of buried waste site remediation: site characterization, waste characterization, retrieval, treatment, and containment/stabilization. Ten of these technologies will take part in the integrated field demonstration that will take place at the Idaho National Engineering Laboratory (INEL) facilities in the summer of 1995. This document is the basic operational planning document for deployment of all BWID projects funded in FY-95. Discussed in this document are the BWID preparations for the INEL integrated field demonstration, INEL research and development (R ampersand D) demonstrations, non-INEL R ampersand D demonstrations, and office research and technical review meetings. Each project will have a test plan detailing the specific procedures, objectives, and tasks of the test. Therefore, information that is specific to testing each technology is intentionally limited in this document

  4. Buried Waste Integrated Demonstration lessons learned: 1993 technology demonstrations

    International Nuclear Information System (INIS)

    Kostelnik, K.M.; Owens, K.J.

    1994-01-01

    An integrated technology demonstration was conducted by the Buried Waste Integrated Demonstration (BWID) at the Idaho National Engineering Laboratory Cold Test Pit in the summer of 1993. This program and demonstration was sponsored by the US Department of Energy Office of Technology Development. The demonstration included six technologies representing a synergistic system for the characterization and retrieval of a buried hazardous waste site. The integrated technology demonstration proved very successful and a summary of the technical accomplishments is presented. Upon completion of the integrated technology demonstration, cognizant program personnel participated in a lessons learned exercise. This exercise was conducted at the Simplot Decision Support Center at Idaho State University and lessons learned activity captured additional information relative to the integration of technologies for demonstration purposes. This information will be used by BWID to enhance program planning and strengthen future technology demonstrations

  5. In situ grouting of buried transuranic waste with polyacrylamide

    International Nuclear Information System (INIS)

    Spalding, B.P.; Lee, S.Y.; Farmer, C.D.; Hyder, L.K.; Supaokit, P.

    1987-01-01

    This project is a demonstration and evaluation of the in situ hydrologic stabilization of buried transuranic waste at a humid site via grout injection. Two small trenches, containing buried transuranic waste, were filled with 34.000 L of polyacrylamide grout. Initial field results have indicated that voids within the trenches were totally filled by the grout and that the intratrench hydraulic conductivity was reduced to below field-measurable values. No evidence of grout constituents were observed in twelve perimeter groundwater monitoring wells indicating that grout was contained completely within the two trenches. Polyacrylamide grout was selected for field demonstration over the polyacrylate grout due to its superior performance in laboratory degradation studies. Also supporting the selection of polyacrylamide was the difficulty in controlling the set time of the acrylate polymerization. Based on preliminary degradation monitoring, the polyacrylamide was estimated to have a microbiological half-life of 362 years in the test soil. 15 refs., 9 figs., 12 tabs

  6. In situ grouting of buried transuranic waste with polyacrylamide

    Energy Technology Data Exchange (ETDEWEB)

    Spalding, B.P.; Lee, S.Y.; Farmer, C.D.; Hyder, L.K.; Supaokit, P.

    1987-01-01

    This project is a demonstration and evaluation of the in situ hydrologic stabilization of buried transuranic waste at a humid site via grout injection. Two small trenches, containing buried transuranic waste, were filled with 34.000 L of polyacrylamide grout. Initial field results have indicated that voids within the trenches were totally filled by the grout and that the intratrench hydraulic conductivity was reduced to below field-measurable values. No evidence of grout constituents were observed in twelve perimeter groundwater monitoring wells indicating that grout was contained completely within the two trenches. Polyacrylamide grout was selected for field demonstration over the polyacrylate grout due to its superior performance in laboratory degradation studies. Also supporting the selection of polyacrylamide was the difficulty in controlling the set time of the acrylate polymerization. Based on preliminary degradation monitoring, the polyacrylamide was estimated to have a microbiological half-life of 362 years in the test soil. 15 refs., 9 figs., 12 tabs.

  7. Strategic management of health risks posed by buried transuranic wastes

    International Nuclear Information System (INIS)

    Jump, R.A.

    1994-01-01

    A strategy is presented for reducing health risks at sites contaminated with buried transuranic (TRU) wastes by first taking measures to immobilize the contaminants until the second step, final action, becomes cost-effective and poses less risk to the remediation workers. The first step of this strategy does not preclude further action if it is warranted and is in harmony with environmental laws and regulations

  8. Full-scale retrieval of simulated buried transuranic waste

    International Nuclear Information System (INIS)

    Valentich, D.J.

    1993-09-01

    This report describes the results of a field test conducted to determine the effectiveness of using conventional type construction equipment for the retrieval of buried transuranic (TRU) waste. A cold (nonhazardous and nonradioactive) test pit (1,100 yd 3 volume) was constructed with boxes and drums filled with simulated waste materials, such as metal, plastic, wood, concrete, and sludge. Large objects, including truck beds, tanks, vaults, pipes, and beams, were also placed in the pit. These materials were intended to simulate the type of wastes found in TRU buried waste pits and trenches. A series of commercially available equipment items, such as excavators and tracked loaders outfitted with different end effectors, were used to remove the simulated waste. Work was performed from both the abovegrade and belowgrade positions. During the demonstration, a number of observations, measurements, and analyses were performed to determine which equipment was the most effective in removing the waste. The retrieval rates for the various excavation techniques were recorded. The inherent dust control capabilities of the excavation methods used were observed. The feasibility of teleoperating reading equipment was also addressed

  9. In situ vitrification of buried waste: Containment issues and suppression systems

    International Nuclear Information System (INIS)

    Luey, J.; Powell, T.D.

    1992-03-01

    Pacific Northwest Laboratory (PNL) and Idaho National Engineering Laboratory (INEL) are developing a remedial action technology for buried waste through the adaptation of the in situ vitrification (ISV) process. The ISV process is a thermal treatment process originally developed for the US Department of Energy (DOE) to stabilize soils contaminated with transuranic waste. ISV tests with buried waste forms have demonstrated that the processing of buried waste is more dynamic than the processing of soils. This paper will focus on the issue of containment of the gases released during the processing of buried waste and on engineered suppression systems to alleviate transient events associated with dynamic off-gassing from the ISV melt

  10. Implementation plans for buried transuranic waste and stored special-case waste at the Idaho National Engineering Laboratory

    International Nuclear Information System (INIS)

    Bullock, M.G.; Rodriguez, R.R.

    1987-05-01

    This document presents the current implementation plans for buried transuranic waste and stored special-case waste at the Idaho National Engineering Laboratory. Information contained in this report was also included in several Department of Energy (DOE) planning documents for the Defense Transuranic Waste Program. This information can be found in the following DOE documents: Comprehensive Implementation Plan for the DOE Defense Buried TRU Waste Program; Defense Waste Management Plan for Buried Transuranic-Contaminated Waste, Transuranic-Contaminated Waste, Transuranic-Contaminated Soil, and Difficult-to-Certify Transuranic Waste; and Defense Special-Case Transuranic Waste Implementation Plan. 11 refs

  11. Remote Excavation System technology evaluation report: Buried Waste Robotics Program

    International Nuclear Information System (INIS)

    1993-09-01

    This document describes the results from the Remote Excavation System demonstration and testing conducted at the Idaho National Engineering Laboratory during June and July 1993. The purpose of the demonstration was to ascertain the feasibility of the system for skimming soil and removing various types of buried waste in a safe manner and within all regulatory requirements, and to compare the performances of manual and remote operation of a backhoe. The procedures and goals of the demonstration were previously defined in The Remote Excavation System Test Plan, which served as a guideline for evaluating the various components of the system and discussed the procedures used to conduct the tests

  12. Analyses of SRS waste glass buried in granite in Sweden and salt in the United States

    International Nuclear Information System (INIS)

    Williams, J.P.; Wicks, G.G.; Clark, D.E.; Lodding, A.R.

    1991-01-01

    Simulated Savannah River Site (SRS) waste glass forms have been buried in the granite geology of the Stirpa mine in Sweden for two years. Analyses of glass surfaces provided a measure of the performance of the waste glasses as a function of time. Similar SRS waste glass compositions have also been buried in salt at the WIPP facility in Carlsbad, New Mexico for a similar time period. Analyses of the SRS waste glasses buried in-situ in granite will be presented and compared to the performance of these same compositions buried in salt at WIPP

  13. Review Of Concrete Biodeterioration In Relation To Buried Nuclear Waste

    International Nuclear Information System (INIS)

    Turick, C.

    2012-01-01

    Long-term storage of low level radioactive material in below ground concrete disposal units (DUs) (Saltstone Disposal Facility) is a means of depositing wastes generated from nuclear operations of the U.S. Department of Energy. Based on the currently modeled degradation mechanisms, possible microbial induced effects on the structural integrity of buried low level wastes must be addressed. Previous international efforts related to microbial impacts on concrete structures that house low level radioactive waste showed that microbial activity can play a significant role in the process of concrete degradation and ultimately structural deterioration. This literature review examines the recent research in this field and is focused on specific parameters that are applicable to modeling and prediction of the fate of concrete vaults housing stored wastes and the wastes themselves. Rates of concrete biodegradation vary with the environmental conditions, illustrating a need to understand the bioavailability of key compounds involved in microbial activity. Specific parameters require pH and osmotic pressure to be within a certain range to allow for microbial growth as well as the availability and abundance of energy sources like components involved in sulfur, iron and nitrogen oxidation. Carbon flow and availability are also factors to consider in predicting concrete biodegradation. The results of this review suggest that microbial activity in Saltstone, (grouted low level radioactive waste) is unlikely due to very high pH and osmotic pressure. Biodegradation of the concrete vaults housing the radioactive waste however, is a possibility. The rate and degree of concrete biodegradation is dependent on numerous physical, chemical and biological parameters. Results from this review point to parameters to focus on for modeling activities and also, possible options for mitigation that would minimize concrete biodegradation. In addition, key chemical components that drive microbial

  14. Review of Concrete Biodeterioration in Relation to Buried Nuclear Waste

    Energy Technology Data Exchange (ETDEWEB)

    Turick, C; Berry, C.

    2012-10-15

    Long-term storage of low level radioactive material in below ground concrete disposal units (DUs) (Saltstone Disposal Facility) is a means of depositing wastes generated from nuclear operations of the U.S. Department of Energy. Based on the currently modeled degradation mechanisms, possible microbial induced effects on the structural integrity of buried low level wastes must be addressed. Previous international efforts related to microbial impacts on concrete structures that house low level radioactive waste showed that microbial activity can play a significant role in the process of concrete degradation and ultimately structural deterioration. This literature review examines the recent research in this field and is focused on specific parameters that are applicable to modeling and prediction of the fate of concrete vaults housing stored wastes and the wastes themselves. Rates of concrete biodegradation vary with the environmental conditions, illustrating a need to understand the bioavailability of key compounds involved in microbial activity. Specific parameters require pH and osmotic pressure to be within a certain range to allow for microbial growth as well as the availability and abundance of energy sources like components involved in sulfur, iron and nitrogen oxidation. Carbon flow and availability are also factors to consider in predicting concrete biodegradation. The results of this review suggest that microbial activity in Saltstone, (grouted low level radioactive waste) is unlikely due to very high pH and osmotic pressure. Biodegradation of the concrete vaults housing the radioactive waste however, is a possibility. The rate and degree of concrete biodegradation is dependent on numerous physical, chemical and biological parameters. Results from this review point to parameters to focus on for modeling activities and also, possible options for mitigation that would minimize concrete biodegradation. In addition, key chemical components that drive microbial

  15. In-situ containment and stabilization of buried waste

    International Nuclear Information System (INIS)

    Allan, M.L.; Kukacka, L.E.

    1993-10-01

    In FY 1993 research continued on development and testing of grout materials for in-situ containment and stabilization of buried waste. Specifically, the work was aimed at remediation of the Chemical Waste Landfill (CWL) at Sandia National Laboratories (SNL) in Albuquerque, New Mexico as part of the Mixed Waste Landfill Integrated Demonstration (MWLID). The work on grouting materials was initiated in FY 1992 and the accomplishments for that year are documented in the previous annual report (Allan, Kukacka and Heiser, 1992). The remediation plan involves stabilization of the chromium plume, placement of impermeable vertical and horizontal barriers to isolate the landfill and installation of a surface cap. The required depth of subsurface barriers is approximately 33 m (100 ft). The work concentrated on optimization of grout formulations for use as grout and soil cement barriers and caps. The durability of such materials was investigated, in addition to shrinkage cracking resistance, compressive and flexural strength and permeability. The potential for using fibers in grouts to control cracking was studied. Small scale field trials were conducted to test the practicality of using the identified formulations and to measure the long term performance. Large scale trials were conducted at Sandia as part of the Subsurface Barrier Emplacement Technology Program. Since it was already determined in FY 1992 that cementitious grouts could effectively stabilize the chromium plume at the CWL after pre-treatment is performed, the majority of the work was devoted to the containment aspect

  16. Graphite electrode DC arc technology program for buried waste treatment

    International Nuclear Information System (INIS)

    Wittle, J.K.; Hamilton, R.A.; Cohn, D.R.; Woskov, P.P.; Thomas, P.; Surma, J.E.; Titus, C.H.

    1994-01-01

    The goal of the program is to apply EPI's Arc Furnace to the processing of Subsurface Disposal Area (SDA) waste from Idaho National Engineering Laboratory. This is being facilitated through the Department of Energy's Buried Waste Integrated Demonstration (BWID) program. A second objective is to apply the diagnostics capability of MIT's Plasma Fusion Center to the understanding of the high temperature processes taking place in the furnace. This diagnostics technology has promise for being applicable in other thermal treatment processes. The program has two parts, a test series in an engineering-scale DC arc furnace which was conducted in an EPI furnace installed at the Plasma Fusion Center and a pilot-scale unit which is under construction at MIT. This pilot-scale furnace will be capable of operating in a continuous feed and continuous tap mode. Included in this work is the development and implementation of diagnostics to evaluate high temperature processes such as DC arc technology. This technology can be used as an effective stabilization process for Superfund wastes

  17. Analysis of the low-level waste radionuclide inventory for the Radioactive Waste Management Complex performance assessment

    Energy Technology Data Exchange (ETDEWEB)

    Plansky, L.E.; Hoiland, S.A.

    1992-02-01

    This report summarizes the results of a study to improve the estimates of the radionuclides in the low-level radioactive waste (LLW) inventory which is buried in the Idaho National Engineering Laboratory (INEL) Radioactive Waste Management Complex (RWMC) Subsurface Disposal Area (SDA). The work is done to support the RWMC draft performance assessment (PA). Improved radionuclide inventory estimates are provided for the INEL LLW generators. Engineering, environmental assessment or other research areas may find use for the information in this report. It may also serve as a LLW inventory baseline for data quality assurance. The individual INEL LLW generators, their history and their activities are also described in detail.

  18. Analysis of the low-level waste radionuclide inventory for the Radioactive Waste Management Complex performance assessment

    International Nuclear Information System (INIS)

    Plansky, L.E.; Hoiland, S.A.

    1992-02-01

    This report summarizes the results of a study to improve the estimates of the radionuclides in the low-level radioactive waste (LLW) inventory which is buried in the Idaho National Engineering Laboratory (INEL) Radioactive Waste Management Complex (RWMC) Subsurface Disposal Area (SDA). The work is done to support the RWMC draft performance assessment (PA). Improved radionuclide inventory estimates are provided for the INEL LLW generators. Engineering, environmental assessment or other research areas may find use for the information in this report. It may also serve as a LLW inventory baseline for data quality assurance. The individual INEL LLW generators, their history and their activities are also described in detail

  19. In situ vitrification of buried waste: Containment issues and suppression systems

    International Nuclear Information System (INIS)

    Luey, J.; Powell, T.D.

    1992-01-01

    Pacific Northwest Laboratory (PNL) and Idaho National Engineering Laboratory (INEL) are developing a remedial action technology for buried waste through the adaptation of the in situ vitrification (ISV) process. The ISV process is a thermal treatment process originally developed for the U.S. Department of Energy (DOE) to stabilize soils contaminated with transuranic waste. ISV tests with buried waste forms have demonstrated that the processing of buried waste is more dynamic than the processing of soils. This paper will focus on the issue of containment of the gases released during the processing of buried waste and on engineered suppression systems to alleviate transient events associated with dynamic off-gassing from the ISV melt. (author)

  20. A process for ensuring regulatory compliance at the INEL`s buried waste integrated demonstrations

    Energy Technology Data Exchange (ETDEWEB)

    Cannon, P.G.; Watson, L.R.; Blacker, P.B. [EG and G Idaho, Inc., Idaho Falls, ID (United States). Idaho National Engineering Lab.

    1993-03-01

    The Buried Waste Integrated Demonstration Program is funded by the Department of Energy Office of Technology Development. The mission of this Integrated Demonstration is to identify, evaluate, and demonstrate a suite of innovative technologies for the remediation of radioactive and hazardous waste buried throughout the DOE complex between 1950 and 1970. The program approach to development of a long-range strategy for improving buried waste remediation capabilities is to combine systems analysis with already identified remediation needs for DOE complex buried waste. The systems analysis effort has produced several configuration options (a top-level block diagram of a cradle-to-grave remediation system) capable of remediating the transuranic-contaminated waste pits and trenches at the Idaho National Engineering Laboratory. Technologies for demonstration are selected using three criteria: (a) the ability to satisfy a specific buried waste need, (b) the ability to satisfy functional and operational requirements defined for functional sub-elements in a configuration option, and (c) performance against Comprehensive Environmental Restoration and Compensation Liability Act selection criteria, such as effectiveness, implementability, and cost. Early demonstrations experienced problems with missed requirements, prompting the Buried Waste Integrated Demonstration Program Office to organize a Corrective Action Team to identify the cause and recommend corrective actions. The result of this team effort is the focus of this paper.

  1. Preservation of Records, Knowledge and Memory across generations. An International Project of the NEA/RWMC. Foundations and guiding principles for the preservation of records, knowledge and memory across generations: A focus on the post-closure phase of geological repositories. A Collective Statement of the NEA Radioactive Waste Management Committee

    International Nuclear Information System (INIS)

    2011-11-01

    Preservation of Records, Knowledge and Memory (RK and M) across generations is needed to support lengthy and complex decision-making processes across long operational and post-operational lifetimes of radioactive waste repositories. It is a recognised management task that spans unprecedented time-horizons in which technical, scientific, societal and cultural information is interwoven. Experience indicates that RK and M need to be actively managed from the start of the waste management programmes. Several radioactive waste disposal programmes are now approaching implementation. The NEA Radioactive Waste Management Committee (RWMC) has created an international project addressing the preservation of RK and M across generations. This collective statement summarises the current understanding of the relevant needs and challenges to be faced. It underscores the willingness of the RWMC member organisations to work together and support national programmes to move forward in this area. Research and development underway on the disposal of long-lived radioactive waste in engineered facilities or repositories located in deep geological formations has confirmed this form of disposal as the ultimate solution for the long-term protection of human beings and the environment, eliminating the need for human intervention and maintenance. While the intention is not to abandon repositories for geological disposal of radioactive waste, either before or after closure, as with many long-term projects, it is a question of minimising the risks of losing records, knowledge and memory (RK and M). The international community of radioactive waste professionals is leading advanced work in this important area. At the end of its first phase of RK and M work, the RWMC observed that the context has changed considerably since the 1980's, when RK and M preservation was thought to serve the sole function of deterring intrusion into a repository. The goal today is to preserve information for future

  2. Latex-modified grouts for in-situ stabilization of buried transuranic/mixed waste

    International Nuclear Information System (INIS)

    Allan, M.L.

    1996-06-01

    The Department of Applied Science at Brookhaven national Laboratory was requested to investigate latex-modified grouts for in-situ stabilization of buried TRU/mixed waste for INEL. The waste exists in shallow trenches that were backfilled with soil. The objective was to formulate latex-modified grouts for use with the jet grouting technique to enable in-situ stabilization of buried waste. The stabilized waste was either to be left in place or retrieved for further processing. Grouting prior to retrieval reduces the potential release of contaminants. Rheological properties of latex-modified grouts were investigated and compared with those of conventional neat cement grouts used for jet grouting

  3. MCNP Modeling Results for Location of Buried TRU Waste Drums

    International Nuclear Information System (INIS)

    Steinman, D K; Schweitzer, J S

    2006-01-01

    In the 1960's, fifty-five gallon drums of TRU waste were buried in shallow pits on remote U.S. Government facilities such as the Idaho National Engineering Laboratory (now split into the Idaho National Laboratory and the Idaho Completion Project [ICP]). Subsequently, it was decided to remove the drums and the material that was in them from the burial pits and send the material to the Waste Isolation Pilot Plant in New Mexico. Several technologies have been tried to locate the drums non-intrusively with enough precision to minimize the chance for material to be spread into the environment. One of these technologies is the placement of steel probe holes in the pits into which wireline logging probes can be lowered to measure properties and concentrations of material surrounding the probe holes for evidence of TRU material. There is also a concern that large quantities of volatile organic compounds (VOC) are also present that would contaminate the environment during removal. In 2001, the Idaho National Engineering and Environmental Laboratory (INEEL) built two pulsed neutron wireline logging tools to measure TRU and VOC around the probe holes. The tools are the Prompt Fission Neutron (PFN) and the Pulsed Neutron Gamma (PNG), respectively. They were tested experimentally in surrogate test holes in 2003. The work reported here estimates the performance of the tools using Monte-Carlo modelling prior to field deployment. A MCNP model was constructed by INEEL personnel. It was modified by the authors to assess the ability of the tools to predict quantitatively the position and concentration of TRU and VOC materials disposed around the probe holes. The model was used to simulate the tools scanning the probe holes vertically in five centimetre increments. A drum was included in the model that could be placed near the probe hole and at other locations out to forty-five centimetres from the probe-hole in five centimetre increments. Scans were performed with no chlorine in the

  4. Concerning enactment of regulations on burying of waste of nuclear fuel material or waste contaminated with nuclear fuel material

    International Nuclear Information System (INIS)

    1988-01-01

    The Atomic Safety Commission of Japan, after examining a report submitted by the Science and Technology Agency concerning the enactment of regulations on burying of waste of nuclear fuel material or waste contaminated with nuclear fuel material, has approved the plan given in the report. Thus, laws and regulations concerning procedures for application for waste burying business, technical standards for implementation of waste burying operation, and measures to be taken for security should be established to ensure the following. Matters to be described in the application for the approval of such business and materials to be attached to the application should be stipulated. Technical standards concerning inspection of waste burying operation should be stipulated. Measures to be taken for the security of waste burying facilities and security concerning the transportation and disposal of nuclear fuel material should be stipulated. Matters to be specified in the security rules should be stipulated. Matters to be recorded by waste burying business operators, measures to be taken to overcome dangers and matters to be reported to the Science and Technology Agency should be stipulated. (Nogami, K.)

  5. Investigation of the subsurface environment at the Idaho National Engineering Laboratory Radioactive Waste Management Complex

    International Nuclear Information System (INIS)

    Russell, B.F.; Mizell, S.A.; Hull, L.C.; Smith, T.H.; Lewis, B.D.; Barraclough, J.T.; Humphrey, T.G.

    1984-01-01

    A comprehensive, 10-year plan to investigate radionuclide migration in the subsurface at the Radioactive Waste Management Complex (RWMC) has been prepared and initiated (in FY-84). The RWMC Subsurface Investigation is designed to address two objectives set forth by the DOE Idaho Operations Office: (1) determine the extent of radionuclide migration, if any, from the buried waste, and (2) develop and calibrate a computer model to simulate long-term radionuclide migration. At the RWMC, the Snake River Plain Aquifer underlies about 177 m of partially saturated, fractured basalts and thin sedimentary units. Three sedimentary units, accounting for no more than 20 m of the partially saturated thickness, appear to be continuous throughout the area. Thinner sedimentary units are discontinuous. Low-level waste and (prior to 1970) transuranic waste have been buried in the surficial sediments at the RWMC. The first burials took place in 1952. Due to the complicated disposal system, a comprehensive review of state-of-the-art vadose zone monitoring instrumentation and techniques, an analysis of conceptual migration pathways, and an evaluation of potential hazard from buried radionuclides were conducted to guide preparation of the investigation plan. The plan includes an overview of the RWMC facility, subsurface work conducted to date at the RWMC and other DOE laboratory facilities, an evaluation and selection of the methods and studies to be used, a radionuclide hazard evaluation, a cost analysis, and external peer review results. In addition, an Appendix contains the details for each method/study to be employed. 4 references, 5 figures, 1 table

  6. Evaluation of the graphite electrode DC arc furnace for the treatment of INEL buried wastes

    International Nuclear Information System (INIS)

    Surma, J.E.; Freeman, C.J.; Powell, T.D.; Cohn, D.R.; Smatlak, D.L.; Thomas, P.; Woskov, P.P.

    1993-06-01

    The past practices of DOE and its predecessor agencies in burying radioactive and hazardous wastes have left DOE with the responsibility of remediating large volumes of buried wastes and contaminated soils. The Buried Waste Integrated Demonstration (BWID), has chosen to evaluate treatment of buried wastes at the Idaho National Engineering Laboratory (INEL). Because of the characteristics of the buried wastes, the potential for using high-temperature thermal treatment technologies is being evaluated. The soil-waste mixture at INEL, when melted or vitrified, produces a glass/ceramic referred to as iron-enriched basalt (IEB). One potential problem with producing the IEB material is the high melting temperature of the waste and soil (1,400-1,600 degrees C). One technology that has demonstrated capabilities to process high melting point materials is the plasma arc heated furnace. A three-party program was initiated and the program involved testing an engineering-scale DC arc furnace to gain preliminary operational and waste processibility information. It also included the design, fabrication, and evaluation of a second-generation, pilot-scale graphite electrode DC arc furnace. Widely ranging simulants of INEL buried waste were prepared and processed in the Mark I furnace. The tests included melting of soils with metals, sludges, combustibles, and simulated drums. Very promising results in terms of waste product quality, volume reduction, heating efficiency, and operational reliability and versatility were obtained. The results indicate that the graphite electrode DC arc technology would be very well suited for treating high melting point wastes such as those found at INEL. The graphite electrode DC arc furnace has been demonstrated to be very simple, yet effective, with excellent prospects for remote or semi-remote operation

  7. Field-scale permeation testing of jet-grouted buried waste sites

    International Nuclear Information System (INIS)

    Loomis, G.G.; Zdinak, A.P.

    1996-01-01

    The Idaho National Engineering Laboratory (INEL) conducted field-scale hydraulic conductivity testing of simulated buried waste sites with improved confinement. The improved confinement was achieved by jet grouting the buried waste, thus creating solid monoliths. The hydraulic conductivity of the monoliths was determined using both the packer technique and the falling head method. The testing was performed on simulated buried waste sites utilizing a variety of encapsulating grouts, including high-sulfate-resistant Portland cement, TECT, (a proprietary iron oxide cement) and molten paraffin. By creating monoliths using in-situ jet grouting of encapsulating materials, the waste is simultaneously protected from subsidence and contained against further migration of contaminants. At the INEL alone there is 56,000 m 3 of buried transuranic waste commingled with 170,000--224,000 m 3 of soil in shallow land burial. One of the options for this buried waste is to improve the confinement and leave it in place for final disposal. Knowledge of the hydraulic conductivity for these monoliths is important for decision-makers. The packer tests involved coring the monolith, sealing off positions within the core with inflatable packers, applying pressurized water to the matrix behind the seal, and observing the water flow rate. The falling head tests were performed in full-scale 3-m-diameter, 3-m-high field-scale permeameters. In these permeameters, both water inflow and outflow were measured and equated to a hydraulic conductivity

  8. Long-range plan for buried transuranic waste studies at the Idaho National Engineering Laboratory

    International Nuclear Information System (INIS)

    Low, J.O.

    1985-12-01

    This document presents a plan to perform detailed studies of alternatives considered for the long-term management of buried transuranic waste at the Idaho National Engineering Laboratory (INEL). The studies will provide the technical basis for DOE to make a decision on the future management of that waste. Although the waste is currently being handled in an acceptable manner, new solutions are continually being researched to improve management techniques. Three alternatives are being considered: (a) leave the waste as is; (b) improve in situ confinement of the waste; and (c) retrieve, process, and certify the waste for disposal at a federal repository. Fourteen studies are described in this plan for Alternatives 2 and 3. The leave-as-is alternative involves continuing present procedures for managing the buried waste. An ongoing environmental surveillance program, a low-level-waste stabilization program, and enhanced subsurface migration studies begun in FY-1984 at the INEL will provide data for the decision-making process for the INEL buried TRU waste. These ongoing studies for the leave-as-is alternative are summarized in this plan in limited detail. The improved-confinement alternative involves leaving the waste in place, but providing additional protection against wind, water penetration, erosion, and plant and animal intrusion. Several studies proposed under this alternative will examine special techniques to immobilize or encapsulate the buried waste. An in situ grouting study was implemented at the INEL starting in FY-1985 and will be completed at the end of FY-1986 with the grouting of a simulated INEL buried TRU waste trench. Studies of the third alternative will investigate improved retrieval, processing, and certification techniques. New equipment, such as industrial manipulators and excavating machinery, will be tested in the retrieval studies. Processing and certification studies will examine rapidly changing or new technologies

  9. Transuranic waste management program and facilities

    International Nuclear Information System (INIS)

    Clements, T.L. Jr.; Cook, L.A.; Stallman, R.M.; Hunter, E.K.

    1986-01-01

    Since 1954, defense-generated transuranic (TRU) waste has been received at the Radioactive Waste Management Complex (RWMC) at the Idaho National Engineering Laboratory (INEL). Prior to 1970, approximately 2.2 million cubic feet of transuranic waste were buried in shallow-land trenches and pits at the RWMC. Since 1970, an additional 2.1 million cubic feet of waste have been retrievably stored in aboveground engineered confinement. A major objective of the Department of Energy (DOE) Nuclear Waste Management Program is the proper management of defense-generated transuranic waste. Strategies have been developed for managing INEL stored and buried transuranic waste. These strategies have been incorporated in the Defense Waste Management Plan and are currently being implemented with logistical coordination of transportation systems and schedules for the Waste Isolation Pilot Plant (WIPP). The Stored Waste Examination Pilot Plant (SWEPP) is providing nondestructive examination and assay of retrievably stored, contact-handled TRU waste. Construction of the Process Experimental Pilot Plant (PREPP) was recently completed, and PREPP is currently undergoing system checkout. The PRFPP will provide processing capabilities for contact-handled waste not meeting WIPP-Waste Acceptance Criteria (WAC). In addition, ongoing studies and technology development efforts for managing the TRU waste such as remote-handled and buried TRU waste, are being conducted

  10. Transuranic Waste Management Program and Facilities

    International Nuclear Information System (INIS)

    Clements, T.L. Jr.; Cook, L.A.; Stallman, R.M.; Hunter, E.K.

    1986-02-01

    Since 1954, defense-generated transuranic (TRU) waste has been received at the Radioactive Waste Management Complex (RWMC) at the Idaho National Engineering Laboratory (INEL). Prior to 1970, approximately 2.2 million cubic feet of transuranic waste were buried in shallow-land trenches and pits at the RWMC. Since 1970, an additional 2.1 million cubic feet of waste have been retrievably stored in aboveground engineered confinement. A major objective of the Department of Energy (DOE) Nuclear Waste Management Program is the proper management of defense-generated transuranic waste. Strategies have been developed for managing INEL stored and buried transuranic waste. These strategies have been incorporated in the Defense Waste Management Plan and are currently being implemented with logistical coordination of transportation systems and schedules for the Waste Isolation Pilot Plant (WIPP). The Stored Waste Examination Pilot Plant (SWEPP) is providing nondestructive examination and assay of retrievably stored, contact-handled TRU waste. Construction of the Process Experimental Pilot Plant (PREPP) was recently completed, and PREPP is currently undergoing system checkout. The PREPP will provide processing capabilities for contact-handled waste not meeting WIPP-Waste Acceptance Criteria (WAC). In addition, ongoing studies and technology development efforts for managing the TRU waste such as remote-handled and buried TRU waste, are being conducted

  11. Tests of a system to exclude roots from buried radioactive waste in a warm, humid climate

    International Nuclear Information System (INIS)

    Murphy, C.E. Jr.; Corey, J.C.; Adriano, D.C.; Decker, O.D.; Griggs, R.D.

    1989-01-01

    Vegetation is commonly used to stabilize the ground covering buried waste sites. However, constituents of buried waste can be brought to the surface if the waste is penetrated by plant roots. An ideal waste burial system would allow the use of vegetation to stabilize the soil above the buried waste but would exclude roots from the waste. One system that shows considerable promise is a slow release encapsulation of a root growth inhibitor (Trifluralin). Projected lifetimes of the capsule are in the order of 100 years. The capsule is bonded to a geotextile, which provides an easy means of distributing the capsule evenly over the area to be protected. Vegetation grown in the soil above the barrier has provided good ground cover, although some decrease in growth has been found in some species. Of the species tested the sensitivity to the biobarrier, as measured by the distance root growth stops near the barrier, is bamboo> bahia grass> bermuda grass> soybean. Potential uses for the biobarrier at the Savannah River Site (SRS) include the protection of clay caps over buried, low-level saltstone and protection of gravel drains and clay caps over decommissioned seepage basins. Trails of the biobarrier as part of waste site caps are scheduled to begin during the next 12 months

  12. Super analog computer for evaluating the safety of buried radioactive waste

    International Nuclear Information System (INIS)

    Cohen, B.L.

    1980-01-01

    It is argued that the past use of digital computer programs for evaluating the safety of buried radioactive waste has been largely wasteful and dangerously delusive. It is suggested to use actual rocks as the analog of buried waste. The problem of comparable rates of leaching of radioactive waste and of natural rock is discussed. Two examples are given of the use of natural rock as an ''analog computer'': one for high-level radioactive waste, and one for low-level radioactive waste. Digital computers have not contributed anything to two crucial questions: Can shafts be securely sealed. Does the heat crack the rock or have important effects on its chemistry. 4 refs

  13. Defense Waste Management Plan for buried transuranic-contaminated waste, transuranic-contaminated soil, and difficult-to-certify transuranic waste

    International Nuclear Information System (INIS)

    1987-06-01

    GAO recommended that DOE provide specific plans for permanent disposal of buried TRU-contaminated waste, TRU-contaminated soil, and difficult-to-certify TRU waste; cost estimates for permanent disposal of all TRU waste, including the options for the buried TRU-contaminated waste, TRU-contaminated soil, and difficult-to-certify TRU waste; and specific discussions of environmental and safety issues for the permanent disposal of TRU waste. Purpose of this document is to respond to the GAO recommendations by providing plans and cost estimates for the long-term isolation of the buried TRU-contaminated waste, TRU-contaminated soil, and difficult-to-certify TRU waste. This report also provides cost estimates for processing and certifying stored and newly generated TRU waste, decontaminating and decommissioning TRU waste processing facilities, and interim operations

  14. Buried waste integrated demonstration fiscal year 1992 close-out report

    International Nuclear Information System (INIS)

    Cannon, P.G.; Kostelnik, K.M.; Owens, K.J.

    1993-02-01

    The mission of the Buried Waste Integrated Demonstration Program (BWID) is to support the development and demonstration of a suite of technologies that when integrated with commercially-available baseline technologies form a comprehensive remediation system for the effective and efficient remediation of buried waste disposed of throughout the US Department of Energy complex. To accomplish this mission of identifying technological solutions for remediation deficiencies, the Office of Technology Development initiated the BWID at the Idaho National Engineering Laboratory in fiscal year (FY)-91. This report summarizes the activities of the BWID Program during FY-92

  15. Performance-Based Technology Selection Filter description report. INEL Buried Waste Integrated Demonstration System Analysis project

    Energy Technology Data Exchange (ETDEWEB)

    O`Brien, M.C.; Morrison, J.L.; Morneau, R.A.; Rudin, M.J.; Richardson, J.G.

    1992-05-01

    A formal methodology has been developed for identifying technology gaps and assessing innovative or postulated technologies for inclusion in proposed Buried Waste Integrated Demonstration (BWID) remediation systems. Called the Performance-Based Technology Selection Filter, the methodology provides a formalized selection process where technologies and systems are rated and assessments made based on performance measures, and regulatory and technical requirements. The results are auditable, and can be validated with field data. This analysis methodology will be applied to the remedial action of transuranic contaminated waste pits and trenches buried at the Idaho National Engineering Laboratory (INEL).

  16. Long-range plan for buried transuranic waste studies at the Idaho National Engineering Laboratory

    International Nuclear Information System (INIS)

    Berreth, P.D.; Fischer, D.K.; Suckel, R.A.

    1984-11-01

    This document presents a plan to perform detailed studies of alternatives considered for the long-term management of buried transuranic waste at the INEL. The studies will provide the technical basis for DOE to make a decision on the future management of that waste. Although the waste is currently being handled in an acceptable manner, new solutions are continually being researched to improve handling techniques. Three alternatives are being considered: (a) leave the waste as is; (b) improve in situ confinement of the waste; (c) retrieve, process, and certify the waste for disposal at a federal repository. Fifteen studies are described in this plan for the latter two alternatives. The leave-as-is alternative involves continuing present procedures for managing the buried waste. An ongoing environmental surveillance program, a low-level-waste stabilization program, and enhanced subsurface migration studies begun in FY-1984 at the INEL will provide data for the decision-making process for INEL buried TRU waste. These ongoing studies for the leave-as-is alternative are summarized in this plan in limited detail. The improved-confinement alternative involves leaving the waste in place, but providing additional protection against wind water penetration, erosion, and plant and animal intrusion. Several studies proposed will examine special techniques to immobilize or encapsulate the buried waste. Studies of the third alternative will investigate improved retrieval, processing and certification techniques. New equipment, such as industrial manipulators and excavating machinery, will be tested in the retrieval studies. Processing and certification studies will examine rapidly changing or new technologies. 19 references, 8 figures, 4 tables

  17. Definition and compositions of standard wastestreams for evaluation of Buried Waste Integrated Demonstration treatment technologies

    International Nuclear Information System (INIS)

    Bates, S.O.

    1993-06-01

    The Buried Waste Integrated Demonstration (BWID) Project was organized at the Idaho National Engineering Laboratory to support research, development, demonstration, testing, and evaluation of emerging technologies that offer promising solutions to remediation of buried waste. BWID will identify emerging technologies, screen them for applicability to the identified needs, select technologies for demonstration, and then evaluate the technologies based on prescribed performance objectives. The technical objective of the project is to establish solutions to Environmental Restoration and Waste Management's technological deficiencies and improve baseline remediation systems. This report establishes a set of standard wastestream compositions that will be used by BWID to evaluate the emerging technologies. Five wastestreams are proposed that use four types of waste and a nominal case that is a homogenized combination of the four wastes. The five wastestreams will provide data on the compositional extremes and indicate the technologies' effectiveness over the complete range of expected wastestream compositions

  18. Successfully burying low-level waste for fun and profit

    International Nuclear Information System (INIS)

    Strong, T.R.; Kirner, N.P.

    1984-01-01

    The state of Washington, now receiving more than half the nation's waste, is here to provide a practical review of the benefits of having a low-level waste disposal site and to provide our perspective on how the state of Washington carries out its responsibilities through regulation of that disposal site. This information is offered in the hope that it may be useful to other states when they accept their responsibility to provide for the disposal of their low-level radioactive waste. The 1980 Low-Level Waste Policy Act very directly gave the responsibility for finding and developing new waste disposal capacity to the states. Through the process of compacting, the states have begun to accept this responsibility. From Washington's perspective, however, the progress shown to date, especially in some states generating very large amounts of waste, has not been adequate to meet the 1986 deadline

  19. Radioactive waste management complex low-level waste radiological composite analysis

    Energy Technology Data Exchange (ETDEWEB)

    McCarthy, J.M.; Becker, B.H.; Magnuson, S.O.; Keck, K.N.; Honeycutt, T.K.

    1998-05-01

    The composite analysis estimates the projected cumulative impacts to future members of the public from the disposal of low-level radioactive waste (LLW) at the Idaho National Engineering and Environmental Laboratory (INEEL) Radioactive Waste Management Complex (RWMC) and all other sources of radioactive contamination at the INEEL that could interact with the LLW disposal facility to affect the radiological dose. Based upon the composite analysis evaluation, waste buried in the Subsurface Disposal Area (SDA) at the RWMC is the only source at the INEEL that will significantly interact with the LLW facility. The source term used in the composite analysis consists of all historical SDA subsurface disposals of radionuclides as well as the authorized LLW subsurface disposal inventory and projected LLW subsurface disposal inventory. Exposure scenarios evaluated in the composite analysis include all the all-pathways and groundwater protection scenarios. The projected dose of 58 mrem/yr exceeds the composite analysis guidance dose constraint of 30 mrem/yr; therefore, an options analysis was conducted to determine the feasibility of reducing the projected annual dose. Three options for creating such a reduction were considered: (1) lowering infiltration of precipitation through the waste by providing a better cover, (2) maintaining control over the RWMC and portions of the INEEL indefinitely, and (3) extending the period of institutional control beyond the 100 years assumed in the composite analysis. Of the three options investigated, maintaining control over the RWMC and a small part of the present INEEL appears to be feasible and cost effective.

  20. Radioactive waste management complex low-level waste radiological composite analysis

    International Nuclear Information System (INIS)

    McCarthy, J.M.; Becker, B.H.; Magnuson, S.O.; Keck, K.N.; Honeycutt, T.K.

    1998-05-01

    The composite analysis estimates the projected cumulative impacts to future members of the public from the disposal of low-level radioactive waste (LLW) at the Idaho National Engineering and Environmental Laboratory (INEEL) Radioactive Waste Management Complex (RWMC) and all other sources of radioactive contamination at the INEEL that could interact with the LLW disposal facility to affect the radiological dose. Based upon the composite analysis evaluation, waste buried in the Subsurface Disposal Area (SDA) at the RWMC is the only source at the INEEL that will significantly interact with the LLW facility. The source term used in the composite analysis consists of all historical SDA subsurface disposals of radionuclides as well as the authorized LLW subsurface disposal inventory and projected LLW subsurface disposal inventory. Exposure scenarios evaluated in the composite analysis include all the all-pathways and groundwater protection scenarios. The projected dose of 58 mrem/yr exceeds the composite analysis guidance dose constraint of 30 mrem/yr; therefore, an options analysis was conducted to determine the feasibility of reducing the projected annual dose. Three options for creating such a reduction were considered: (1) lowering infiltration of precipitation through the waste by providing a better cover, (2) maintaining control over the RWMC and portions of the INEEL indefinitely, and (3) extending the period of institutional control beyond the 100 years assumed in the composite analysis. Of the three options investigated, maintaining control over the RWMC and a small part of the present INEEL appears to be feasible and cost effective

  1. Thermal processing systems for TRU mixed waste

    International Nuclear Information System (INIS)

    Eddy, T.L.; Raivo, B.D.; Anderson, G.L.

    1992-01-01

    This paper presents preliminary ex situ thermal processing system concepts and related processing considerations for remediation of transuranic (TRU)-contaminated wastes (TRUW) buried at the Radioactive Waste Management Complex (RWMC) of the Idaho National Engineering Laboratory (INEL). Anticipated waste stream components and problems are considered. Thermal processing conditions required to obtain a high-integrity, low-leachability glass/ceramic final waste form are considered. Five practical thermal process system designs are compared. Thermal processing of mixed waste and soils with essentially no presorting and using incineration followed by high temperature melting is recommended. Applied research and development necessary for demonstration is also recommended

  2. Buried for ever. The US experience of radioactive waste disposal

    International Nuclear Information System (INIS)

    Resnikoff, Marvin.

    1987-01-01

    The United States is the largest producer of radioactive wastes and has considerable experience, not all good, of shallow disposal methods for low level wastes. Indeed, as a result of leakage and contamination, three sites have been closed down and there is concern over another site, at Barnwell in South Carolina. This chapter analyses the geological and technical problems of each of the sites from the viewpoint of the environmental pressure group, the Sienna Club. The sites are at Maxey Flats, Kentucky; Sheffield, Illinois; West Valley, New York; Barnwell; Richland, Washington and Beatly, Nevada. The problems have been those situated in the humid, northern regions where there has been excessive ground water, degradation of waste containers, subsidence and erosion, the presence of chelating agents and a lack of stabilisation and funding for long-term care. In the semi-arid western sites the problems are fewer. However, the cost of transporting the waste to them is high. It is suggested that some of the low-level wastes should be reclassified as high-level wastes and should be disposed of deep underground. (UK)

  3. Buried transuranic wastes at ORNL: Review of past estimates and reconciliation with current data

    International Nuclear Information System (INIS)

    Trabalka, J.R.

    1997-09-01

    Inventories of buried (generally meaning disposed of) transuranic (TRU) wastes at Oak Ridge National Laboratory (ORNL) have been estimated for site remediation and waste management planning over a period of about two decades. Estimates were required because of inadequate waste characterization and incomplete disposal records. For a variety of reasons, including changing definitions of TRU wastes, differing objectives for the estimates, and poor historical data, the published results have sometimes been in conflict. The purpose of this review was (1) to attempt to explain both the rationale for and differences among the various estimates, and (2) to update the estimates based on more recent information obtained from waste characterization and from evaluations of ORNL waste data bases and historical records. The latter included information obtained from an expert panel's review and reconciliation of inconsistencies in data identified during preparation of the ORNL input for the third revision of the Baseline Inventory Report for the Waste Isolation Pilot Plant. The results summarize current understanding of the relationship between past estimates of buried TRU wastes and provide the most up-to-date information on recorded burials thereafter. The limitations of available information on the latter and thus the need for improved waste characterization are highlighted

  4. Buried waste integrated demonstration Fiscal Year 1993 close-out report

    International Nuclear Information System (INIS)

    Owens, K.J.; Hyde, R.A.

    1994-04-01

    The Buried Waste Integrated Demonstration (BWID) supports the applied research, development, demonstration, and evaluation of a multitude of advanced technologies. These technologies are being integrated to form a comprehensive remediation system for the effective and efficient remediation of buried waste. These efforts are identified and coordinated in support of the U.S. Department of Energy Environmental Restoration and Waste Management needs and objectives. BWID works with universities and private industry to develop these technologies, which are being transferred to the private sector for use nationally and internationally. A public participation policy has been established to provide stakeholders with timely and accurate information and meaningful opportunities for involvement in the technology development and demonstration process. To accomplish this mission of identifying technological solutions for remediation deficiencies, the Office of Technology Development initiated BWID at the Idaho National Engineering Laboratory. This report summarizes the activities of the BWID program during FY-93

  5. Technology evaluation report for the Buried Waste Robotics Program Subsurface Mapping Project

    International Nuclear Information System (INIS)

    Griebenow, B.E.

    1992-01-01

    This document presents a summary of the work performed in support of the Buried Waste Robotics Program Subsurface Mapping Project. The project objective was to demonstrate the feasibility of remotely characterizing buried waste sites. To fulfill this objective, a remotely-operated vehicle, equipped with several sensors, was deployed at the Idaho National Engineering Laboratory. Descriptions of the equipment and areas involved in the project are included in this report. Additionally, this document provides data that was obtained during characterization operations at the Cold Test Pit and the Subsurface Disposal Area, both at the Idaho National Engineering Laboratory's Radioactive Waste Management Complex, and at the Idaho Chemical Processing Plant. The knowledge gained from the experience, that can be applied to the next generation remote-characterization system, is extensive and is presented in this report

  6. Annual technology assessment and progress report for the buried transuranic waste program at the Idaho National Engineering Laboratory

    International Nuclear Information System (INIS)

    Berreth, P.D.

    1984-11-01

    The US Department of Energy (DOE) is responsible for developing and implementing methods for the safe and environmentally acceptable disposal of radioactive waste. In 1983, DOE formulated a comprehensive plan to manage transuranic (TRU) defense waste. The DOE plan for buried TRU waste is to monitor it, take remedial actions as necessary, and reevaluate its safety periodically. The DOE strategy reflects concern that, based on present technology, retrieval and processing of buried waste may be risky and costly. To implement the DOE plan, EG and G Idaho, Inc., prime contractor at the Idaho National Engineering Laboratory (INEL), has developed a strategy for long-term management of the 2 million cubic feet of INEL buried TRU waste. That strategy involves four main activities: (a) environmental monitoring, (b) remedial action if necessary, (c) assimilation of data from both special studies and ongoing waste management activities, and (d) selection of a long-term management alternative in 1995. This report, submitted as the first in a series of annual reports, summarizes the buried TRU waste activities performed in fiscal year (FY) 1984 at the INEL in response to the DOE plan. Specifically, technologies applicable to buried waste confinement, retrieval, certification, and processing have been assessed, a long-range plan to conduct buried wasted studies over the next ten years has been prepared, and retrieval and soil management alternatives have been evaluated. 17 references, 7 figures, 1 table

  7. System to control contamination during retrieval of buried TRU waste

    Science.gov (United States)

    Menkhaus, Daniel E.; Loomis, Guy G.; Mullen, Carlan K.; Scott, Donald W.; Feldman, Edgar M.; Meyer, Leroy C.

    1993-01-01

    A system to control contamination during the retrieval of hazardous waste comprising an outer containment building, an inner containment building, within the outer containment building, an electrostatic radioactive particle recovery unit connected to and in communication with the inner and outer containment buildings, and a contaminate suppression system including a moisture control subsystem, and a rapid monitoring system having the ability to monitor conditions in the inner and outer containment buildings.

  8. Buried for ever: The US experience of radioactive waste disposal

    International Nuclear Information System (INIS)

    Resnikoff, M.

    1987-01-01

    The United States is the largest producer of radioactive wastes, and has considerable experience with shallow disposal methods. This experience is mixed, with major problems of leakage and contamination occurring in those sites in the wetter eastern part of the country. As a result three sites have been closed down, and there is concern about the potential hazards at the remaining eastern site at Barnwell, South Carolina. This paper, written from the perspective of the national environmental pressure group, the Sierra Club, analyses the geological and technical problems at each of the sites, and suggests the lessons that can be learned from this experience

  9. Rapid monitoring for transuranic contaminants during buried waste retrieval

    International Nuclear Information System (INIS)

    McIsaac, C.V.; Sill, C.W.; Gehrke, R.J.; Shaw, P.G.; Randolph, P.D.; Amaro, C.R.; Pawelko, R.J.; Thompson, D.N.; Loomis, G.G.

    1991-03-01

    This document reports results of research performed in support of possible future transuranic waste retrieval operations at the Idaho National Engineering Laboratory Radioactive Waste Management Complex. The focus of this research was to evaluate various methods of performing rapid and, as much as possible, ''on-line'' quantitative measurements of 239 Pu or 241 Am, either as airborne or loose contamination. Four different alpha continuous air monitors were evaluated for lower levels of detection of airborne 239 Pu. All of the continuous air monitors were evaluated by sampling ambient air. In addition, three of the continuous air monitors were evaluated by sampling air synthetically laden with clean dust and dust spiked with 239 Pu. Six methods for making quantitative measurements of loose contamination were investigated. They were: (1) microwave digestion followed by counting in a photon electron rejecting alpha liquid scintillation spectrometer, (2) rapid radiochemical separation followed by alpha spectrometry, (3) measurement of the 241 Am 59 keV gamma ray using a thin window germanium detector, (4) measurement of uranium L-shell x-rays, (5) gross alpha counting using a large-area Ag activated ZnS scintillator, and (6) direct counting of alpha particles using a large-area ionization chamber. 40 refs., 42 figs., 24 tabs

  10. Buried waste remote survey of the Idaho National Engineering Laboratory subsurface disposal area

    International Nuclear Information System (INIS)

    Richardson, B.S.; Noakes, M.W.; Griebenow, B.E.; Josten, N.E.

    1991-01-01

    Burial site characterization is an important first step in the restoration of subsurface disposal sites. Testing and demonstration of technology for remote buried waste site characterization were performed at the Idaho National Engineering Laboratory (INEL) by a team from five US Department of Energy (DOE) laboratories. The US Army's Soldier Robot Interface Project (SRIP) vehicle, on loan to the Oak Ridge National Laboratory (ORNL), was used as a remotely operated sensor platform. The SRIP was equipped with an array of sensors including terrain conductivity meter, magnetometer, ground-penetrating radar (GPR), organic vapor detector, gamma-based radar detector, and spectrum analyzer. The testing and demonstration were successfully completed and provided direction for future work in buried waste site characterization

  11. Environment, Safety, Health, and Quality Plan for the Buried Waste Integrated Demonstration Program

    International Nuclear Information System (INIS)

    Walker, S.

    1994-05-01

    The Buried Waste Integrated Demonstration (BWID) is a program funded by the US Department of Energy Office of Technology Development. BWID supports the applied research, development, demonstration, testing, and evaluation of a suite of advanced technologies that together form a comprehensive remediation system for the effective and efficient remediation of buried waste. This document describes the Environment, Safety, Health, and Quality requirements for conducting BWID activities at the Idaho National Engineering Laboratory. Topics discussed in this report, as they apply to BWID operations, include Federal, State of Idaho, and Environmental Protection Agency regulations, Health and Safety Plans, Quality Program Plans, Data Quality Objectives, and training and job hazard analysis. Finally, a discussion is given on CERCLA criteria and System and Performance audits as they apply to the BWID Program

  12. Basic prerequisites and the practice of using deep water tables for burying liquid radioactive wastes

    International Nuclear Information System (INIS)

    Spitsyn, V.I.; Pimenov, M.K.; Balukova, V.D.; Leontichuk, A.S.; Kokorin, I.N.; Yudin, F.P.; Rakov, N.A.

    In the USSR, creating reservoirs for liquid radioactive wastes is one of the promising methods of safely disposing of them in deep water tables, in zones with a standing regime or a slow rate of subterranean water exchange. The results of investigations and the practice of burying (the wastes) indicate the reliability and effectiveness of such a method of final waste disposal when the basic requirements of environmental protection are observed. Geological formations and collector strata that guarantee the localization of the liquid radioactive wastes placed in them for many tens and even hundreds of thousands of years can be studied and chosen in different regions. The basic requirements and criteria to which the geological structures and collector strata must correspond for ensuring the safe burial of wastes have been formulated. Wastes are buried only after a comprehensive, scientifically based evaluation of the sanitary-radiation safety for this generation and future ones, taking into account the burial regime and the physico-chemical processes that accompany combining wastes with rocks and stratal waters, as well as the time of holding wastes to maximum permissible concentrations. Positive and negative factors that characterize the method are analyzed. Possible emergency situations with subterranean burial are evaluated. The composition and methods of the geological survey, hydrodynamic, geophysical, physico-chemical and sanitary-radiation investigations; methods of calculating and predicting the movement of wastes underground;methods of preparing wastes for burial and chemical methods of restoring the suitability of wells; design characteristics and conditions of preparing wells for use; methods of estimating heating and processes of radiolysis for a medium containing highly radioactive wastes; methods of operational and remote control of the burial process and the condition of the ambient medium, etc. are briefly examined

  13. In situ vitrification application to buried waste: Interim report of intermediate field tests at Idaho National Engineering Laboratory

    International Nuclear Information System (INIS)

    Callow, R.A.; Weidner, J.R.; Thompson, L.E.

    1991-02-01

    This report describes the two in situ vitrification field tests conducted in June and July 1990 at Idaho National Engineering Laboratory. In situ vitrification, an emerging technology for in- place conversion of contaminated soils into a durable glass and crystalline waste form, is being investigated as a potential remediation technology for buried waste. The overall objective of the two tests was to assess the general suitability of the process to remediate waste structures representative of buried waste found at Idaho National engineering Laboratory. In particular, these tests, as part of a treatability study, were designed to provide essential information on the field performance of the process under conditions of significant combustible and metal wastes and to test a newly developed electrode feed technology. The tests were successfully completed, and the electrode feed technology successfully processed the high metal content waste, indicating the process is a feasible technology for application to buried waste

  14. In situ vitrification application to buried waste: Interim report of intermediate field tests at Idaho National Engineering Laboratory

    International Nuclear Information System (INIS)

    Callow, R.A.; Weidner, J.R.; Thompson, L.E.

    1991-01-01

    This report describes the two in situ vitrification field tests conducted in July and July 1990 at Idaho National Engineering Laboratory. In situ vitrification, an emerging technology for in-place conversion of contaminated soils into a durable glass and crystalline waste form, is being investigated as a potential remediation technology for buried waste. The overall objective of the two tests was to assess the general suitability of the process to remediate waste structures representative of buried waste found at Idaho National Engineering Laboratory. In particular, these tests, as part of a treatability study, were designed to provide essential information field performance of the process under conditions of significant combustible and metal wastes and to test a newly developed electrode feed technology. The tests were successfully completed, and the electrode feed technology successfully processed the high metal content waste, indicating the process is a feasible technology for application to buried waste. 8 refs., 91 figs., 13 tabs

  15. The development of permanent isolation barriers for buried wastes in cool deserts: Hanford, Washington

    International Nuclear Information System (INIS)

    Link, S.O.; Gee, G.W.; Wing, N.R.

    1993-12-01

    The purpose of this report is to present the results of research on surface hydrology and the role of plants and animals on permanent isolation barrier effectiveness at Hanford. These topics are a subset of a larger set of studies on permanent isolation barriers. A complete review of these tasks has been documented. We also discuss current work that tests our integrated scientific and engineering concepts on a large prototype barrier to determine if it can isolate buried wastes from environmental dispersion

  16. Cryofracture as a tool for preprocessing retrieved buried and stored transuranic waste

    International Nuclear Information System (INIS)

    Loomis, G.G.; Winberg, M.R.; Ancho, M.L.; Osborne, D.

    1992-01-01

    This paper summarizes important features of an experimental demonstration of applying the Cryofracture process to size-reduce retrieved buried and stored transuranic-contaminated wastes. By size reducing retrieved buried and stored waste, treatment technologies such as thermal treatment can be expedited. Additionally, size reduction of the waste can decrease the amount of storage space required by reducing the volume requirements of storage containers. A demonstration program was performed at the Cryofracture facility by Nuclear Remedial Technologies for the Idaho National Engineering Laboratory. Cryofracture is a size-reducing process whereby objects are frozen to liquid nitrogen temperatures and crushed in a large hydraulic press. Material s at cryogenic temperatures have low ductility and are easily size-reduced by fracturing. Six 55-gallon drums and six 2 x 2 x 8 ft boxes containing simulated waste with tracers were subjected to the Cryofracture process. Data was obtained on (a) cool-down time, (b) yield strength of the containers, (c) size distribution of the waste before and after the Cryofracture process, (d) volume reduction of the waste, and (e) sampling of air and surface dusts for spread of tracers to evaluate potential contamination spread. The Cryofracture process was compared to conventional shredders and detailed cost estimates were established for construction of a Cryofracture facility at the Idaho National Engineering Laboratory

  17. Fate of gaseous tritium and carbon-14 released from buried low-level radioactive waste

    International Nuclear Information System (INIS)

    Striegl, R.G.

    1988-01-01

    Microbial decomposition, chemical degradation, and volatilization of buried low-level radioactive waste results in the release of gases containing tritium ( 3 H) and carbon-14 ( 14 C) to the surrounding environment. Water vapor, carbon dioxide, and methane that contain 3 H or 14 C are primary products of microbial decomposition of the waste. Depending on the composition of the waste source, chemical degradation and volatilization of waste also may result in the production of a variety of radioactive gases and organic vapors. Movement of the gases in materials that surround waste trenches is affected by physical, geochemical, and biological mechanisms including sorption, gas-water-mineral reactions, isotopic dilution, microbial consumption, and bioaccumulation. These mechanisms either may transfer 3 H and 14 C to solids and infiltrating water or may result in the accumulation of the radionuclides in plant or animal tissue. Gaseous 3 H or 14 C that is not transferred to other forms is ultimately released to the atmosphere

  18. Solute travel time in the vadose zone under RWMC at INEL

    International Nuclear Information System (INIS)

    Liou, J.C.P.; Tian, J.

    1995-01-01

    Solute transport in the vadose zone under the Radioactive Waste Management Complex (RWMC) at the Idaho National Engineering Laboratory (INEL) is considered. The objective is to assess the relative importance of variables involved in modeling the travel time of a conservative solute from ground surface to water table. The vadose zone under RWMC is composed of several layers of basalt flows interceded with sediment layers. The thickness of the layers varies with location. The hydraulic properties also vary. The extents of the variations are large, with standard deviations exceed mean in some instances. The vadose zone is idealized as composed of horizontal layers. Solute transport starts at the ground surface and moves vertically downwards to the water table. The perceived process is one-dimensional. This study used VS2DT, a computer code developed by the US Geological Survey, for simulating solute transport in variably saturated porous media

  19. Soil Sampling Plan for the transuranic storage area soil overburden and final report: Soil overburden sampling at the RWMC transuranic storage area

    International Nuclear Information System (INIS)

    Stanisich, S.N.

    1994-12-01

    This Soil Sampling Plan (SSP) has been developed to provide detailed procedural guidance for field sampling and chemical and radionuclide analysis of selected areas of soil covering waste stored at the Transuranic Storage Area (TSA) at the Idaho National Engineering Laboratory's (INEL) Radioactive Waste Management Complex (RWMC). The format and content of this SSP represents a complimentary hybrid of INEL Waste Management--Environmental Restoration Program, and Comprehensive Environmental Response, Compensation and Liability Act (CERCLA) Remedial Investigation/Feasibility Study (RI/FS) sampling guidance documentation. This sampling plan also functions as a Quality Assurance Project Plan (QAPP). The QAPP as a controlling mechanism during sampling to ensure that all data collected are valid, reliabile, and defensible. This document outlines organization, objectives and quality assurance/quality control (QA/QC) activities to achieve the desired data quality goals. The QA/QC requirements for this project are outlined in the Data Collection Quality Assurance Plan (DCQAP) for the Buried Waste Program. The DCQAP is a program plan and does not outline the site specific requirements for the scope of work covered by this SSP

  20. A proposed alternative approach for protection of inadvertent human intruders from buried Department of Energy low level radioactive wastes

    International Nuclear Information System (INIS)

    Cochran, J.R.

    1995-01-01

    The burial of radioactive wastes creates a legacy. To limit the impact of this legacy on future generations, we establish and comply with performance objectives. This paper reviews performance objectives for the long-term isolation of buried radioactive wastes; identifies regulatorly-defined performance objectives for protecting the inadvertent human intruder (IHI) from buried low-level radioactive waste (LLW); (3) discusses a shortcoming of the current approach; and (4) offers an alternative approach for protecting the IHI. This alternative approach is written specifically for the burial of US Department of Energy (DOE) wastes at the Nevada Test Site (NTS), although the approach might be applied at other DOE burial sites

  1. Comprehensive implementation plan for the DOE defense buried TRU- contaminated waste program

    International Nuclear Information System (INIS)

    Everette, S.E.; Detamore, J.A.; Raudenbush, M.H.; Thieme, R.E.

    1988-02-01

    In 1970, the US Atomic Energy Commission established a ''transuranic'' (TRU) waste classification. Waste disposed of prior to the decision to retrievably store the waste and which may contain TRU contamination is referred to as ''buried transuranic-contaminated waste'' (BTW). The DOE reference plan for BTW, stated in the Defense Waste Management Plan, is to monitor it, to take such remedial actions as may be necessary, and to re-evaluate its safety as necessary or in about 10-year periods. Responsibility for management of radioactive waste and byproducts generated by DOE belongs to the Secretary of Energy. Regulatory control for these sites containing mixed waste is exercised by both DOE (radionuclides) and EPA (hazardous constituents). Each DOE Operations Office is responsible for developing and implementing plans for long-term management of its radioactive and hazardous waste sites. This comprehensive plan includes site-by-site long-range plans, site characteristics, site costs, and schedules at each site. 13 figs., 15 tabs

  2. Report for slot cutter proof-of-principle test, Buried Waste Containment System project. Revision 1

    International Nuclear Information System (INIS)

    1998-01-01

    Several million cubic feet of hazardous and radioactive waste was buried in shallow pits and trenches within many US Department of Energy (US DOE) sites. The pits and trenches were constructed similarly to municipal landfills with both stacked and random dump waste forms such as barrels and boxes. Many of the hazardous materials in these waste sites are migrating into groundwater systems through plumes and leaching. On-site containment is one of the options being considered for prevention of waste migration. This report describes the results of a proof-of-principle test conducted to demonstrate technology for containing waste. This proof-of-principle test, conducted at the RAHCO International, Inc., facility in the summer of 1997, evaluated equipment techniques for cutting a horizontal slot beneath an existing waste site. The slot would theoretically be used by complementary equipment designed to place a cement barrier under the waste. The technology evaluated consisted of a slot cutting mechanism, muck handling system, thrust system, and instrumentation. Data were gathered and analyzed to evaluate the performance parameters

  3. Report for slot cutter proof-of-principle test, Buried Waste Containment System project. Revision 1

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1998-05-21

    Several million cubic feet of hazardous and radioactive waste was buried in shallow pits and trenches within many US Department of Energy (US DOE) sites. The pits and trenches were constructed similarly to municipal landfills with both stacked and random dump waste forms such as barrels and boxes. Many of the hazardous materials in these waste sites are migrating into groundwater systems through plumes and leaching. On-site containment is one of the options being considered for prevention of waste migration. This report describes the results of a proof-of-principle test conducted to demonstrate technology for containing waste. This proof-of-principle test, conducted at the RAHCO International, Inc., facility in the summer of 1997, evaluated equipment techniques for cutting a horizontal slot beneath an existing waste site. The slot would theoretically be used by complementary equipment designed to place a cement barrier under the waste. The technology evaluated consisted of a slot cutting mechanism, muck handling system, thrust system, and instrumentation. Data were gathered and analyzed to evaluate the performance parameters.

  4. Development of robotics technology for remote characterization and remediationof buried waste

    International Nuclear Information System (INIS)

    Noakes, M.W.; Richardson, B.S.; Burks, B.L.; Sandness, G.R.

    1992-01-01

    Detection, characterization, and excavation of buried objects and materials are important steps in the restoration of subsurface disposal sites. The US Department of Energy (DOE), through its Buried Waste Robotics Program, is developing a Remote Characterization System (RCS) to address the needs of remote subsurface characterization and, in a joint program with the US Army, is developing a teleoperated excavator. Development of the RCS is based on recent DOE remote characterization testing and demonstrations performed at Oak Ridge National Laboratory and Idaho National Engineering Laboratory. The RCS, which will be developed and refined over a two- to three-year period, is designed to (1) increase safety by removing on-site personnel from hazardous areas, (2) remotely acquire real-time data from multiple sensors, (3) increase cost-effectiveness and productivity by partial automation of the data collection process and by gathering and evaluating data from multiple sensors in real time, and (4) reduce costs for other waste-related development programs through joint development efforts and reusable standardized subsystems. For retrieval of characterized waste, the Small Emplacement Excavator, an existing US Army backhoe that is being converted to teleoperated control, will be used to demonstrate the feasibility of retrofitting commercial equipment for high-performance remote operations

  5. Buried Waste Integrated Demonstration fiscal Year 1994 close-out report

    International Nuclear Information System (INIS)

    Owen, K.J.

    1995-07-01

    The Buried Waste integrated Demonstration (BWID) supports the applied research, development, demonstration, and evaluation of a multitude of advanced technologies. These technologies are being integrated to form a comprehensive remediation system for the effective and efficient remediation of buried waste. These efforts are identified and coordinated in support of the US Department of Energy Environmental Restoration and Waste Management needs and objectives. BWID works with universities and private industry to develop these technologies, which are being transferred to the private sector for use nationally and internationally. A public participation policy has been established to provide stakeholders with timely and accurate information and meaningful opportunities for involvement in the technology development and demonstration process. To accomplish this mission of identifying technological solutions for remediation deficiencies, the Department of Energy Office of Technology Development initiated BMD at the Idaho National Engineering Laboratory. This report summarizes the activities of the BWID program during Fiscal Year 1994. In Fiscal Year 1995, these activities are transitioning into the Landfill Stabilization Focus Area

  6. In situ vitrification application to buried waste: Final report of intermediate field tests at Idaho National Engineering Laboratory

    International Nuclear Information System (INIS)

    Callow, R.A.; Weidner, J.R.; Loehr, C.A.; Bates, S.O.; Thompson, L.E.; McGrail, B.P.

    1991-08-01

    This report describes two in situ vitrification field tests conducted on simulated buried waste pits during June and July 1990 at the Idaho National Engineering Laboratory. In situ vitrification, an emerging technology for in place conversion of contaminated soils into a durable glass and crystalline waste form, is being investigated as a potential remediation technology for buried waste. The overall objective of the two tests was to access the general suitability of the process to remediate waste structures representative of buried waste found at Idaho National Engineering Laboratory. In particular, these tests, as part of a treatability study, were designed to provide essential information on the field performance of the process under conditions of significant combustible and metal wastes and to test a newly developed electrode feed technology. The tests were successfully completed, and the electrode feed technology successfully processed the high metal content waste. Test results indicate the process is a feasible technology for application to buried waste. 33 refs., 109 figs., 39 tabs

  7. Ultra wide band radar holographic imaging of buried waste at DOE sites

    International Nuclear Information System (INIS)

    Collins, H.D.; Gribble, R.P.; Hall, T.E.; Lechelt, W.M.

    1995-04-01

    Ultra wideband linear array holography is a unique real-time imaging technique for in-situ inspection of buried waste at various DOE sites. The array can be mounted on various platforms such as crane booms, pickup trucks, ATVs, and scanned generating ''3-D'' subsurface images in real time. Inspection speeds are 0.5 to 2 meters/sec, if the image is viewed in real time, greater for off-line processing. The Ground Penetrating Holographic (GPH) system developed for inspection of DOE sites employs two 32element arrays of tapered-slot antenna operating at 5-GHz and 2.5-GHz center frequencies. The GPH system, which is mounted on a small trailer with a computer image processor, display, and power supply, is capable of imaging a wide swath (1 to 2 meters) with its linear arrays. The lower frequency array will be used at INEL (for greater depth penetration) because of high soil attenuation. Recent holographic ''3-D'' images of buried waste container lids and dielectrics obtained in Hanford sand and INEL soils at various depths graphically illustrate the unique image resolution capabilities of the system. Experimental results using the 5-GHz array will be presented showing the excellent holographic image quality of various subsurface targets in sand and INEL soil

  8. Buried Waste Integrated Demonstration Commercialization Action Plans second quarter, FY-94

    International Nuclear Information System (INIS)

    Kaupanger, R.M.

    1994-06-01

    The Federal Government is extremely good at creating knowledge and developing new technology. However, our declining market share in many industries points to a weakness in our ability to successfully commercialize new discoveries. BWID assembled a team of qualified experts with expertise in technology transfer and broad-based technology knowledge to assist with this effort. Five new technologies were chosen to develop commercialization action plans. They include Dig-Face Characterization, Imaging Infrared Interferometer for Waste Characterization, Tensor Magnetic Gradiometer, Very Early Time Electromagnetic System, and Virtual Environment Generation of Buried Waste. Each plan includes a short description of the technology, a market overview, a list of potential customers, a description of competitors and the technology's competitive advantage, the status of intellectual property, the status of technology transfer, a table of action items, commercialization contacts, and program contacts

  9. Performance of a buried radioactive high level waste (HLW) glass after 24 years

    International Nuclear Information System (INIS)

    Jantzen, Carol M.; Kaplan, Daniel I.; Bibler, Ned E.; Peeler, David K.; John Plodinec, M.

    2008-01-01

    A radioactive high level waste glass was made in 1980 with Savannah River Site (SRS) Tank 15 waste. This glass was buried in a lysimeter in the SRS burial ground for 24 years. Lysimeter leachate data was available for the first 8 years. The glass was exhumed in 2004. The glass was predicted to be very durable and laboratory tests confirmed this. Scanning electron microscopy of the glass burial surface showed no significant glass alteration consistent with results of other laboratory and field tests. Radionuclide profiling for alpha, beta, and 137 Cs indicated that Pu was not enriched in the soil while 137 Cs and 9 deg. C Sr were enriched in the first few centimeters surrounding the glass. Lysimeter leachate data indicated that 9 deg. C Sr and 137 Cs leaching from the glass was diffusion controlled

  10. Treatment of simulated INEL buried wastes using a graphite electrode DC arc furnace

    International Nuclear Information System (INIS)

    Surma, J.E.; Lawrence, W.E.; Titus, C.H.; Wittle, J.K.; Hamilton, R.A.; Cohn, D.R.; Rhea, D.; Thomas, P.; Woskov, P.P.

    1994-08-01

    A program has been established under the auspices of the Department of Energy (DOE), Office of Technology Development (OTD), to develop the graphite electrode DC arc technology for the application of treating buried heterogenous solid wastes. A three way open-quotes National Laboratory-University-Industryclose quotes partnership was formed to develop this technology in the most timely and cost effective manner. This program is presently testing a newly fabricated pilot-scale DC arc furnace with associated diagnostics at the Plasma Fusion Center at the Massachusetts Institute of Technology. Initial testing in a smaller engineering scale furnace has established the viability of this technology for the treatment of solid heterogeneous wastes. Two diagnostic tools were developed under this program which support the evaluation of the DC arc technology. The diagnostics provide for both spatially resolved temperature measurements within the furnace and real time monitoring of the furnace metal emissions

  11. Managing previously disposed waste to today's standards

    International Nuclear Information System (INIS)

    1990-01-01

    A Radioactive Waste Management Complex (RWMC) was established at the Idaho National Engineering Laboratory (INEL) in 1952 for controlled disposal of radioactive waste generated at the INEL. Between 1954 and 1970 waste characterized by long lived, alpha emitting radionuclides from the Rocky Flats Plant was also buried at this site. Migration of radionuclides and other hazardous substances from the buried Migration of radionuclides and other hazardous substances from the buried waste has recently been detected. A Buried Waste Program (BWP) was established to manage cleanup of the buried waste. This program has four objectives: (1) determine contaminant sources, (2) determine extent of contamination, (3) mitigate migration, and (4) recommend an alternative for long term management of the waste. Activities designed to meet these objectives have been under way since the inception of the program. The regulatory environment governing these activities is evolving. Pursuant to permitting activities under the Resource Conservation and Recovery Act (RCRA), the Department of Energy (DOE) and the Environmental Protection Agency (EPA) entered into a Consent Order Compliance Agreement (COCA) for cleanup of past practice disposal units at the INEL. Subsequent to identification of the RWMC as a release site, cleanup activities proceeded under dual regulatory coverage of RCRA and the Atomic Energy Act. DOE, EPA, and the State of Idaho are negotiating a RCRA/Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA) Interagency Agreement (IAG) for management of waste disposal sites at the INEL as a result of the November 1989 listing of the INEL on the National Priority List (NPL). Decision making for selection of cleanup technology will be conducted under the CERCLA process supplemented as required to meet the requirements of the National Environmental Policy Act (NEPA). 7 figs

  12. A remote characterization system for subsurface mapping of buried waste sites

    International Nuclear Information System (INIS)

    Sandness, G.A.; Bennett, D.W.

    1992-10-01

    Mapping of buried objects and regions of chemical and radiological contamination is required at US Department of Energy (DOE) buried waste sites. The DOE Office of Technology Development Robotics Integrated Program has initiated a project to develop and demonstrate a remotely controlled subsurface sensing system, called the Remote Characterization System (RCS). This project, a collaborative effort by five of the National Laboratories, involves the development of a unique low-signature survey vehicle, a base station, radio telemetry data links, satellite-based vehicle tracking, stereo vision, and sensors for non-invasive inspection of the surface and subsurface. To minimize interference with on-board sensors, the survey vehicle has been constructed predominatantly of non-metallic materials. The vehicle is self-propelled and will be guided by an operator located at a remote base station. The RCS sensors will be environmentally sealed and internally cooled to preclude contamination during use. Ground-penetrating radar, magnetometers, and conductivity devices are planned for geophysical surveys. Chemical and radiological sensors will be provided to locate hot spots and to provide isotopic concentration data

  13. Technical report for a fluidless directional drilling system demonstrated at Solid Waste Storage Area 6 shallow buried waste sites

    International Nuclear Information System (INIS)

    1995-09-01

    The purpose of the research was to demonstrate a fluidless directional drilling and monitoring system (FDD) specifically tailored to address environmental drilling concerns for shallow buried wasted. The major concerns are related to worker exposure, minimizing waste generation, and confining the spread of contamination. The FDD is potentially applicable to Environmental Restoration (ER) activities for the Oak Ridge National Laboratory Waste Area Grouping 6 (WAG 6) shallow buried waste disposed in unlined trenches. Major ER activities for directional drilling are to develop a drilling system for leachate collection directly beneath trenches, and to provide localized control over leachate release to the environment. Other ER FDD activities could include vadose zone and groundwater monitoring of contaminant transport. The operational constraints pointed the research in the direction of purchasing a steerable impact hammer, or mole, manufactured by Steer-Rite Ltd. of Racine, Wisconsin. This drill was selected due to the very low cost ($25,000) associated with procuring the drill, steering module, instrumentation and service lines. The impact hammer is a self propelled drill which penetrates the soil by compacting cut material along the sidewalls of the borehole. Essentially, it forces its way through the subsurface. Although the pneumatic hammer exhausts compressed air which must be handled at the borehole collar, it does not generate soil cuttings or liquids. This is the basis for the term fluidless. A stub casing muffler was attached to the entrance hole for controlling exhaust gas and any airborne releases. Other environmental compliance modifications made to the equipment included operating the tool without lubrication, and using water instead of hydraulic fluid to actuate the steering fins on the tool

  14. Graphite electrode dc arc technology development for treatment of buried wastes

    International Nuclear Information System (INIS)

    Surma, J.E.; Cohn, D.R.; Smatlak, D.L.; Thomas, P.; Woskov, P.P.

    1993-02-01

    A ''National Laboratory-University-Industrial'' three-way partnership has been established between the Pacific Northwest Laboratory (PNL), Massachusetts Institute of Technology (MIT), and Electro-Pyrolysis, Inc. (EPI) to develop graphite electrode DC arc technology for the treatment of buried wastes. This paper outlines the PNL-MIT-EPI program describing a series of engineering-scale DC arc furnace tests conducted in an EPI furnace at the Plasma Fusion Center at MIT, and a description of the second phase of this program involving the design, fabrication, and testing of a pilot-scale DC arc furnace. Included in this work is the development and implementation of diagnostics to evaluate and optimize high temperature thermal processes such as the DC arc technology

  15. Grouting as a remedial technique for buried low-level radioactive wastes

    International Nuclear Information System (INIS)

    Spalding, B.P.; Hyder, L.K.; Munro, I.L.

    1985-01-01

    Seven grout formulations were tested in the laboratory for their ability to penetrate and to reduce the hydraulic conductivities of soils used as backfills for shallow land burial trenches. Soils from two sites, in Oak Ridge, TN, and Maxey Flats, KY were used and both are classified as Typic Dystrochrepts. Three soluble grout formulations (sodium silicate, polypropenamide [polyacrylamide], and 1,3-Benzenediol [resorcinol]-formaldehyde) were able to both penetrate soil and sand columns and reduce hydraulic conductivities from initial values of ca. 10 -4 m s -1 to -8 m s -1 . Three particulate grouts (lime [calcium oxide]-fly ash, fly ash-cement-bentonite, and bentonite alone) could not penetrate columns; such formulations would, therefore, be difficult to inject into closed burial trenches. Field demonstrations with both sodium silicate and polyacrylamide showed that grout could be distributed throughout a burial trench and that waste-backfill hydraulic conductivity could be reduced several orders of magnitude. Field grouting with polyacrylamide reduced the mean hydraulic conductivity of nine intratrench monitoring wells from 10 -4 to 10 -8 m s -1 . Grouting of low-level radioactive solid waste in situ, therefore, should be an effective technique to correct situations where leaching of buried wastes has or will result in groundwater contamination

  16. Annual technology assessment and progress report for the Buried Transuranic Waste Program at the Idaho National Engineering Laboratory

    International Nuclear Information System (INIS)

    Low, J.O.

    1985-12-01

    An improved-confinement technology as applied to the Idaho National Engineering Laboratory (INEL) shallow-land-buried transuranic (TRU) waste is being investigated. An improved-confinement technology, in situ grouting, is being demonstrated in a 2-year engineering feasibility test at the INEL. Grout formulation and development were completed by Oak Ridge National Laboratory in Tennessee to support the in situ grouting test. Three grout formulations have been adapted to the arid, unsaturated soil conditions at the INEL: ordinary particulate grout; microfine penetration grout; soil grout. Three test trenches were constructed north of the INEL's Subsurface Disposal Area (SDA). Nonradioactive waste forms closely resembling TRU waste buried at the INEL have been fabricated and are ready for emplacement into these test trenches. A literature search for a simulated (analog) TRU tracer was completed as well as a chemical characterization of the INEL soil. Data developed from the chemistry characterization and literature search have been inputed into the selection and laboratory testing of the TRU analog tracers. Simulated TRU tracers will be loaded into waste forms prior to emplacement into the test trenches. Test trench data acquisition instrumentation will be installed during waste form emplacement. Instrumentation will monitor for moisture movement and tracer detection. Plans for test completion in FY-1986 are also shown. Various buried waste improved-confinement technologies performed by other Department of Energy sites were assessed for applicability to the INEL buried TRU waste. Primary demonstrations were performed at the Hanford site in Washington and at ORNL. This report also includes information on accomplishments of related activities at the INEL such as the program for Environmental Surveillance of the Radioactive Waste Management complex as well as the Subsurface Migration Studies. 18 refs., 11 figs., 12 tabs

  17. SEARCH AND MAPPING OF THE OLD BURIED TAILINGS WITH RADIOACTIVE WASTES AT THE URBAN TERRITORY.

    Science.gov (United States)

    Molchanov, O I; Soroka, Y N; Podrezov, A A; Soroka, M N

    2017-11-01

    The article presents results of investigation on search and mapping of the old buried tailings with radioactive wastes on the territory of Kamianske City. For solving the problem used complex of methods. These methods are as follows: soil-gas 222Rn measurement and measurement of 222Rn flux density from the ground surface, gamma-radiation survey, prospecting drilling, gamma-ray logging and laboratory analysis of radionuclides. The leading method in this complex was the method of soil-gas 222Rn measurement. Using this method location of the tailings has been precisely defined. The tailings boundaries have been contoured in the plan. Other methods permitted to define such parameters as thickness of the wastes, their volume (~330 000 m3), radionuclide and chemical composition. It was found that radioactive residues occur at a depth from 2 to 11 m and contain in its composition 226Ra, 210Pb and 210Po in the range from 8370 to 37 270 Bq kg-1. © The Author 2017. Published by Oxford University Press. All rights reserved. For Permissions, please email: journals.permissions@oup.com.

  18. Search and mapping of the old buried tailings with radioactive wastes at the urban territory

    International Nuclear Information System (INIS)

    Molchanov, O. I.; Soroka, Y. N.; Podrezov, A. A.; Soroka, M. N.

    2017-01-01

    The article presents results of investigation on search and mapping of the old buried tailings with radioactive wastes on the territory of Kamianske City. For solving the problem used complex of methods. These methods are as follows: soil-gas 222 Rn measurement and measurement of 222 Rn flux density from the ground surface, gamma-radiation survey, prospecting drilling, gamma-ray logging and laboratory analysis of radionuclides. The leading method in this complex was the method of soil-gas 222 Rn measurement. Using this method location of the tailings has been precisely defined. The tailings boundaries have been contoured in the plan. Other methods permitted to define such parameters as thickness of the wastes, their volume (∼330 000 m 3 ), radionuclide and chemical composition. It was found that radioactive residues occur at a depth from 2 to 11 m and contain in its composition 226 Ra, 210 Pb and 210 Po in the range from 8370 to 37270 Bq kg -1 .(authors)

  19. Fifth in situ vitrification engineering-scale test of simulated INEL buried waste sites

    International Nuclear Information System (INIS)

    Bergsman, T.M.; Shade, J.W.; Farnsworth, R.K.

    1992-06-01

    In September 1990, an engineering-scale in situ vitrification (ISV) test was conducted on sealed canisters containing a combined mixture of buried waste materials expected to be present at the Idaho National Engineering Laboratory (INEL) Subsurface Disposal Area (SDA). The test was part of a Pacific Northwest Laboratory (PNL) program to assist INEL in treatability studies of the potential application of ISV to mixed transuranic wastes at the INEL SDA. The purpose of this test was to determine the effect of a close-packed layer of sealed containers on ISV processing performance. Specific objectives included determining (1) the effect of releases from sealed containers on hood plenum pressure and temperature, (2) the release pressure ad temperatures of the sealed canisters, (3) the relationships between canister depressurization and melt encapsulation, (4) the resulting glass and soil quality, (5) the potential effects of thermal transport due to a canister layer, (6) the effects on particle entrainment of differing angles of approach for the ISV melt front, and (7) the effects of these canisters on the volatilization of voltatile and semivolatile contaminants into the hood plenum

  20. Regulatory issues and assumptions associated with barriers in the vadose zone surrounding buried waste

    International Nuclear Information System (INIS)

    Siskind, B.; Heiser, J.

    1993-02-01

    One of the options for control of contaminant migration from buried waste sites is the construction of a subsurface barrier that consists of a wall of low permeability material. The barrier material should be compatible with soil and waste conditions specific to the site and have as low an effective diffusivity as is reasonably achievable to minimize or inhibit transport of moisture and contaminants. This report addresses the regulatory issues associated with the use of non-traditional organic polymer barriers as well as the use of soil-bentonite or cement-bentonite mixtures for such barriers, considering barriers constructed from these latter materials to be a regulatory baseline. The regulatory issues fall into two categories. The first category consists of issues associated with the acceptability of such barriers to the EPA as a method for achieving site or performanceimprovement. The second category encompasses those regulatory issues concerning health, safety and the environment which must be addressed regarding barrier installation and performance, especially if non-traditional materials are to be used

  1. Buried Transuranic Waste Studies Program at the Idaho National Engineering Laboratory: Annual technology assessment and progress report

    International Nuclear Information System (INIS)

    Low, J.O.; Allman, D.W.; Shaw, P.G.; Sill, C.W.

    1987-01-01

    In-situ grouting, an improved-confinement technology that could be applied to the Idaho National Engineering Laboratory (INEL) shallow-land-buried transuranic (TRU) waste, is being investigated by EG and G Idaho, Inc. In situ grouting has been demonstrated as the culmination of a two-year engineering feasibility test at the INEL. In situ stabilization and hydrologic isolation of a simulated buried TRU waste trench at an arid site were performed using an experimental dynamic compaction in situ grouting process developed by Rockwell Hanford Operations (RHO). A series of laboratory evaluations relative to the grout permeation characteristics of microfine particulate cements with INEL-type soil was performed prior to the grouting operations. In addition, an extensive pre-grouting hydrologic assessment of the test trench was performed to support the performance assessment analysis. Laboratory testing of various chemical materials yielded a suitable hydrologic tracer for use in the hydrologic monitoring phase of the experiment. Various plutonium transport laboratory evaluations were performed to assess the plutonium retention capabilities of a microfine grout/INEL-soil waste product similar to that expected to result if the grout is injected in situ into the INEL test trench. The test trench will be hydrologically assessed in FY 1987 to determine if the RHO grouting system attained the performance acceptance criteria of the experiment. The report includes a technology assessment of buried waste technologies developed by other DOE sites. Field demonstrations at ORNL and Hanford are reported under this technology assessment. Also included is information on activities related to buried waste management at the INEL. These include environmental surveillance of the Radioactive Waste Management Complex and the Subsurface Migration Studies Program

  2. Baseline tests for arc melter vitrification of INEL buried wastes. Volume 1: Facility description and summary data report

    International Nuclear Information System (INIS)

    Oden, L.L.; O'Connor, W.K.; Turner, P.C.; Soelberg, N.R.; Anderson, G.L.

    1993-01-01

    This report presents field results and raw data from the Buried Waste Integrated Demonstration (BWID) Arc Melter Vitrification Project Phase 1 baseline test series conducted by the Idaho National Engineering Laboratory (INEL) in cooperation with the U.S. Bureau of Mines (USBM). The baseline test series was conducted using the electric arc melter facility at the USBM Albany Research Center in Albany, Oregon. Five different surrogate waste feed mixtures were tested that simulated thermally-oxidized, buried, TRU-contaminated, mixed wastes and soils present at the INEL. The USBM Arc Furnace Integrated Waste Processing Test Facility includes a continuous feed system, the arc melting furnace, an offgas control system, and utilities. The melter is a sealed, 3-phase alternating current (ac) furnace approximately 2 m high and 1.3 m wide. The furnace has a capacity of 1 metric ton of steel and can process as much as 1,500 lb/h of soil-type waste materials. The surrogate feed materials included five mixtures designed to simulate incinerated TRU-contaminated buried waste materials mixed with INEL soil. Process samples, melter system operations data and offgas composition data were obtained during the baseline tests to evaluate the melter performance and meet test objectives. Samples and data gathered during this program included (a) automatically and manually logged melter systems operations data, (b) process samples of slag, metal and fume solids, and (c) offgas composition, temperature, velocity, flowrate, moisture content, particulate loading and metals content. This report consists of 2 volumes: Volume I summarizes the baseline test operations. It includes an executive summary, system and facility description, review of the surrogate waste mixtures, and a description of the baseline test activities, measurements, and sample collection. Volume II contains the raw test data and sample analyses from samples collected during the baseline tests

  3. Radionuclide-migration model for buried waste at the Savannah River Plant

    International Nuclear Information System (INIS)

    King, C.M.; Root, R.W. Jr.

    1982-01-01

    Solid waste has been buried at the Savannah River Plant burial ground since 1953. The solid waste is contaminated with alpha-emitting transuranium (TRU) nuclides, with beta-gamma-emitting activation and fission products, and with tritium. To provide guidance for the current use and eventual permanent retirement of the burial site from active service, a radionuclide environmental transport model has been used to project the potential influence on man if the burial site were occupied after decommissioning. The model used to simulate nuclide migration includes the various hydrological, animal, vegetative, atmospheric, and terrestrial pathways in estimating dose to man as a function of time. Specific scenarios include a four-person home farm on the 195-acre burial ground. Key input to the model includes site-specific nuclide migration rates through soil, nuclide distribution coefficients, and site topography. Coupled with literature data on plant and animal concentration factors, transfer coefficients reflecting migration routes are input to a set of linear differential equations for subsequent matrix solution. Output from the model is the nuclide-specific decayed curie intake by man. To discern principal migration routes, model-compartment inventories with time can also be displayed. Dose projections subsequently account for organ concentrations in man for the nuclide of interest. Radionuclide migration has been examined in depth with the dose-to-man model. Movement by vegetative pathways is the primary route for potential dose to man for short-lived isotopes. Hydrological routes provide a secondary scheme for long-lived nuclides. Details of model methodology are reviewed

  4. Regulatory issues and assumptions associated with polymers for subsurface barriers surrounding buried waste

    International Nuclear Information System (INIS)

    Heiser, J.; Siskind, B.

    1993-01-01

    One of the options for control of contaminant migration from buried waste sites is the construction of a subsurface barrier that consists of a wall of low permeability material. Subsurface barriers will improve remediation performance by removing pathways for contaminant transport due to groundwater movement, meteorological water infiltration, vapor- and gas-phase transport, transpiration, etc. Subsurface barriers may be used to open-quotes directclose quotes contaminant movement to collection sumps/lysimeters in cases of unexpected remediation failures or transport mechanisms, to contain leakage from underground storage tanks, and to restrict in-situ soil cleanup operation and chemicals. Brookhaven National Laboratory is currently investigating advanced polymer materials for subsurface barriers. This report addresses the regulatory aspects of using of non-traditional polymer materials as well as soil-bentonite or cement-bentonite mixtures for such barriers. The regulatory issues fall into two categories. The first category consists of issues associated with the acceptability of subsurface barriers to the Environmental Protection Agency (EPA) as a method for achieving waste site performance improvement. The second category encompasses those regulatory issues concerning health, safety and the environment which must be addressed regarding barrier installation and performance, especially if non-traditional materials are to be used. Since many of EPA's concerns regarding subsurface barriers focus on the chemicals used during installation of these barriers the authors discuss the results of a search of the Federal Register and the Code of Federal Regulations for references in Titles 29 and 40 pertaining to key chemicals likely to be utilized in installing non-traditional barrier materials. The use of polymeric materials in the construction industry has been accomplished with full compliance with the applicable health, safety, and environmental regulations

  5. On permission of waste-burying business in Tokai Research Establishment, Japan Atomic Energy Research Institute (Answer)

    International Nuclear Information System (INIS)

    1995-01-01

    As to this case written in the title which was inquired on July 19, 1994, from the prime minister, and changed partly on November 21, 1994, the Nuclear Safety Commission answered to the prime minister as follows after the prudent deliberation. As for the application of the criteria for permission, the technical capability is adequate, and the results of the examination of safety by the expert committee for examining nuclear fuel safety is adequate. It was judged that the safety after the permission of this waste-burying business can be secured. The expert committee reported on the policy of the investigation and deliberation, and the contents of the investigation and deliberation, such as the basic location conditions, namely, site, weather, ground, hydraulics, earthquakes and social environment, the radioactive wastes to be buried, the method of determining radioactivity concentration, the expected time of changing the measures to be taken for security, the safety design for the waste-burying facility related to radiation control, environment safety, earthquakes, fires and explosion, the loss of electric power and the standards and criteria to be conformed, and the assessment of dose equivalent in normal state, after finishing the period of control and safety evaluation, and the course of the investigation and deliberation. (K.I.)

  6. INEL cold test pit demonstration of improvements in information derived from non-intrusive geophysical methods over buried waste sites

    International Nuclear Information System (INIS)

    1993-01-01

    The objectives of this research project were to lay the foundation for further improvement in the use of geophysical methods for detection of buried wastes, and to increase the information content derived from surveys. Also, an important goal was to move from mere detection to characterization of buried wastes. The technical approach to achieve these objectives consisted of: (1) Collect a data set of high spatial density; (2) Acquire data with multiple sensors and integrate the interpretations inferred from the various sensors; (3) Test a simplified time domain electromagnetic system; and (4) Develop imaging and display formats of geophysical data readily understood by environmental scientists and engineers. The breadth of application of this work is far reaching. Not only are uncontrolled waste pits and trenches, abandoned underground storage tanks, and pipelines found throughout most US DOE facilities, but also at military installations and industrial facilities. Moreover, controlled land disposal sites may contain ''hot spots'' where drums and hazardous material may have been buried. The technologies addressed by the R ampersand D will benefit all of these activities

  7. Vision for the RWMC Project on 'Preservation of RK and M Across Generations'

    International Nuclear Information System (INIS)

    2011-01-01

    Disposal of long-lived radioactive waste in engineered facilities built in stable, deep geological formations is the reference means for permanently isolating the waste from the biosphere. Although this management method is conceived to be intrinsically safe and final, i.e., not depending on the presence and intervention of man for fulfilling its safety goal, there is no intention to forgo, at any time, knowledge and awareness either of the repository or of the waste that it contains. As repository development is reaching industrial maturity, means are being studied to maintain indirect forms of oversight once the repository is closed including monitoring, applying safeguards according to international agreements, maintaining records, and ultimately maintaining memory. Institutional arrangements need be integral part of those provisions, as continuity of records, knowledge and memory (RK and M) will require, in the first place, identifying a chain of responsibilities. At the same time, novel methods ought also to be studied and applied that are less vulnerable to changes in socio-economic conditions and may be less reliant on institutional presence. Overall, this is a multidisciplinary work area in which much learning is expected over the coming years. In this document a vision for the RWMC project on 'Preservation of RK and M across generations' is described covering the period 2011-2014. The document represents the shared vision of the project members and incorporates the RWMC comments at their latest meeting in March 2011. It is understood that it will be necessary to update this document regularly in the course of the project

  8. INEL cold test pit demonstration of improvements in information derived from non-intrusive geophysical methods over buried waste sites

    International Nuclear Information System (INIS)

    1994-01-01

    Under contract between US DOE Idaho National Engineering Laboratory (INEL) and the Blackhawk Geosciences Division of Coleman Research Corporation (BGD-CRC), geophysical investigations were conducted to improve the detection of buried wastes. Over the Cold Test Pit (CTP) at INEL, data were acquired with multiple sensors on a dense grid. Over the CTP the interpretations inferred from geophysical data are compared with the known placement of various waste forms in the pit. The geophysical sensors employed were magnetics, frequency and time domain electromagnetics, and ground penetrating radar. Also, because of the high data density acquired, filtering and other data processing and imaging techniques were tested. After completion and analysis of the survey and interpretation over the CTP, the second phase of investigation consisted of testing geophysical methods over the Idaho Chemical Processing Plant (ICPP). The sections of the ICPP surveyed are underlain by a complex network of buried utility lines of different dimensions and composition, and with placement at various depths up to 13 ft. Further complications included many metallic objects at the surface, such as buildings, reinforced concrete pads, and debris. Although the multiple geophysical sensor approach mapped many buried utilities, they mapped far from all utilities shown on the facility drawings. This report consists of data collected from these geophysical surveys over the ICPP

  9. INEL cold test pit demonstration of improvements in information derived from non-intrusive geophysical methods over buried waste sites

    International Nuclear Information System (INIS)

    1994-01-01

    Under Contract between US DOE Idaho National Engineering Laboratory (INEL) and the Blackhawk Geosciences Division of Coleman Research Corporation (BGD-CRC), geophysical investigations were conducted to improve the detection of buried wastes. Site characterization is a costly and time consuming process with the most costly components being drilling, sampling, and chemical analysis of samples. There is a focused effort at US DOE and other agencies to investigate methodologies that reduce costs and shorten the time between characterization and clean-up. These methodologies take the form of employing non-invasive (geophysical) and minimal invasive (e.g., cone penetrometer driving) techniques of characterization, and implementing a near real-time, rational decision-making process (Expedited Site Characterization). Over the Cold Test Pit (CTP) at INEL, data were acquired with multiple sensors on a dense grid. Over the CTP the interpretations inferred from geophysical data are compared with the known placement of various waste forms in the pit. The geophysical sensors employed were magnetics, frequency and time domain electromagnetics, and ground penetrating radar. Also, because of the high data density acquired, filtering and other data processing and imaging techniques were tested. The conclusions derived from the geophysical surveys were that pit boundaries, berms between cells within the pit, and individual objects placed in the pit were best mapped by the new Geonics EM61 time domain EM metal detector. Part of the reason for the effectiveness of the time domain metal detector is that objects buried in the pit are dominantly metallic. Also, the utility of geophysical data is significantly enhanced by dimensional and 3-dimensional imaging formats. These images will particularly assist remediation engineers in visualizing buried wastes

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

    International Nuclear Information System (INIS)

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

    1995-02-01

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

  11. A Title 40 Code of Federal Regulations Part 191 Evaluation of Buried Transuranic Waste at the Nevada Test Site - 8210

    International Nuclear Information System (INIS)

    G J Shott; V Yucel; L Desotell

    2008-01-01

    In 1986, 21 m 3 of transuranic (TRU) waste was inadvertently buried in a shallow land burial trench at the Area 5 Radioactive Waste Management Site on the Nevada Test Site (NTS). The U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office is considered five options for management of the buried TRU waste. One option is to leave the waste in-place if the disposal can meet the requirements of Title 40 Code of Federal Regulations (CFR) Part 191, 'Environmental Radiation Protection Standard for Management and Disposal of Spent Nuclear Fuel, High-Level, and Transuranic Radioactive Wastes'. This paper describes analyses that assess the likelihood that TRU waste in shallow land burial can meet the 40 CFR 191 standards for a geologic repository. The simulated probability of the cumulative release exceeding 1 and 10 times the 40 CFR 191.13 containment requirements is estimated to be 0.009 and less than 0.0001, respectively. The cumulative release is most sensitive to the number of groundwater withdrawal wells drilled through the disposal trench. The mean total effective dose equivalent for a member of the public is estimated to reach a maximum of 0.014 milliSievert (mSv) at 10,000 years, or approximately 10 percent of the 0.15 mSv 40 CFR 191.15 individual protection requirement. The dose is predominantly from inhalation of short-lived Rn-222 progeny in air produced by low-level waste disposed in the same trench. The transuranic radionuclide released in greatest amounts, Pu-239, contributes only 0.4 percent of the dose. The member of public dose is most sensitive to the U-234 inventory and the radon emanation coefficient. Reasonable assurance of compliance with the Subpart C groundwater protection standard is provided by site characterization data and hydrologic processes modeling which support a conclusion of no groundwater pathway within 10,000 years. Limited quantities of transuranic waste in a shallow land burial trench at the NTS can meet

  12. Hydrological, meteorological and geohydrological data for an unsaturated zone study near the Radioactive Waste Management Complex, Idaho National Engineering Laboratory, Idaho - 1987

    International Nuclear Information System (INIS)

    Davis, L.C.; Pittman, J.R.

    1990-01-01

    Since 1952, radioactive waste has been buried at the RWMC (Radioactive Waste Management Complex) at the Idaho National Engineering Laboratory in southeastern Idaho. In 1985, the US Geological Survey, in cooperation with the US Department of Energy, began a study of the geohydrology of the RWMC to provide a basis for estimating the extent of and the potential for migration of radionuclides in the unsaturated zone beneath the waste burial trenches and pits. This study is being conducted to provide hydrological, meteorological and geohydrological data for the test trench area adjacent to the northern boundary of the RWMC. During 1987, data were collected from the test trench area, where several types of instrumentation were installed in the surficial sediment in 1985. Hydrological data collected from both disturbed and undisturbed soil included measurements, from 28 thermocouple psychrometers placed at selected depths to about 6m. Soil moisture content measurements were collected bi-weekly in 9 neutron-probe access holes with a neutron moisture depth gage. Meteorological data summarized daily included: (1) incoming and emitted long-wave radiation; (2) incoming and reflected short-wave radiation; (3) air temperature; (4) relative humidity; (5) wind speed; (6) wind direction; and (7) precipitation. To describe grain-size distribution with depth, 17 samples were analyzed using sieve and pipette methods. Statistical parameters, carbonate content, color, particle roundness and sphericity, and mineralogic and clastic constituents were determined for each sample. Some samples were analyzed by x-ray diffraction techniques to determine bulk and clay mineralogy

  13. MANAGEING THE RETRIEVAL RISK OF BURIED TRANSURANIC (TRU) WASTE WITH UNIQUE CHARACTERISTICS

    International Nuclear Information System (INIS)

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

    2005-01-01

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

  14. Future strategic directions for radioactive waste management programmes

    International Nuclear Information System (INIS)

    Anon.

    1999-01-01

    The NEA Radioactive Waste Management Committee (RWMC) has identified six strategic areas as priorities for work in the coming years. These strategic areas, listed in this paper, are described in a NEA publication (Strategic Areas in Waste Management: the viewpoint and work orientations of the NEA RWMC

  15. A demonstration of remote survey and characterization of a buried waste site using the SRIP [Soldier Robot Interface Project] testbed

    International Nuclear Information System (INIS)

    Burks, B.L.; Richardson, B.S.; Armstrong, G.A.; Hamel, W.R.; Jansen, J.F.; Killough, S.M.; Thompson, D.H.; Emery, M.S.

    1990-01-01

    During FY 1990, the Oak Ridge National Laboratory (ORNL) supported the Department of Energy (DOE) Environmental Restoration and Waste Management (ER ampersand WM) Office of Technology Development through several projects including the development of a semiautonomous survey of a buried waste site using a remotely operated all-terrain robotic testbed borrowed from the US Army. The testbed was developed for the US Army's Human Engineering Laboratory (HEL) for the US Army's Soldier Robot Interface Project (SRIP). Initial development of the SRIP testbed was performed by a team including ORNL, HEL, Tooele Army Depot, and Odetics, Inc., as an experimental testbed for a variety of human factors issues related to military applications of robotics. The SRIP testbed was made available to the DOE and ORNL for the further development required for a remote landfill survey. The robot was modified extensively, equipped with environmental sensors, and used to demonstrate an automated remote survey of Solid Waste Storage Area No. 3 (SWSA 3) at ORNL on Tuesday, September 18, 1990. Burial trenches in this area containing contaminated materials were covered with soil nearly twenty years ago. This paper describes the SRIP testbed and work performed in FY 1990 to demonstrate a semiautonomous landfill survey at ORNL. 5 refs

  16. Development and demonstration of a stabilization system for buried mixed waste tanks: Initital results of the tank V-9 hot demonstration

    International Nuclear Information System (INIS)

    Matthern, G.E.; Kuhns, D.J.; Meservey, R.H.; Farnsworth, R.K.

    1996-01-01

    This paper describes a systematic approach for the stabilization of buried mixed waste tanks and presents the status of an application of this approach to a specific hot waste tank demonstration to be performed in FY-96. The approach uses the cradle-to-grave concept and includes technical, health and safety, and regulatory considerations and requirements. It starts with the identification of the tank and continues to the final disposition and monitoring of the tank

  17. Burying uncertainty: Risk and the case against geological disposal of nuclear waste

    International Nuclear Information System (INIS)

    Shrader-Frechette, K.S.

    1996-01-01

    The author of this book asserts that moral and ethical issues must be considered in the development of nuclear waste disposal policies. The book develops this theme showing that to date no technology has provided a fool-proof method of isolating high-level nuclear wastes and that technological advances alone will not increase public acceptance. She supports a plan for the federal government to negotiate construction of MRS facilities that would safely house high-level nuclear waste for about 100 years, providing a temporary solution and a moral and ethical alternative to permanent storage

  18. Preparations for Retrieval of Buried Waste at Material Disposal Area B

    International Nuclear Information System (INIS)

    Chaloupka, A.B.; Criswell, C.W.; Goldberg, M.S.; Gregory, D.R.; Worth, E.P.

    2009-01-01

    Material Disposal Area B, a hazard category 3 nuclear facility, is scheduled for excavation and the removal of its contents. Wastes and excavated soils will be characterized for disposal at approved off-site waste disposal facilities. Since there were no waste disposal records, understanding the context of the historic operations at MDA B was essential to understanding what wastes were disposed of and what hazards these would pose during retrieval. The operational history of MDA B is tied to the earliest history of the Laboratory, the scope and urgency of World War II, the transition to the Atomic Energy Commission in January 1947, and the start of the cold war. A report was compiled that summarized the development of the process chemistry, metallurgy, and other research and production activities at the Laboratory during the 1944 to 1948 time frame that provided a perspective of the work conducted; the scale of those processes; and the handling of spent chemicals and contaminated items in lieu of waste disposal records. By 1947, all laboratories had established waste disposal procedures that required laboratory and salvage wastes to be boxed and sealed. Large items or equipment were to be wrapped with paper or placed in wooden crates. Most wastes were placed in cardboard boxes and were simply piled into the active trench. Bulldozers were used to cover the material with fill dirt on a weekly basis. No effort was made to separate waste types or loads, or to compact the wastes under the soil cover. Using the historical information and a statistical analysis of the plutonium inventory, LANL prepared a documented safety analysis for the waste retrieval activities at MDA B, in accordance with DOE Standard 1120-2005, Integration of Environment, Safety, and Health into Facility Disposition Activities, and the provisions of 29 CFR 1910.120, Hazardous Waste Operations and Emergency Response. The selected hazard controls for the MDA B project consist of passive design

  19. COMBINED GEOPHYSICAL INVESTIGATION TECHNIQUES TO IDENTIFY BURIED WASTE IN AN UNCONTROLLED LANDFILL AT THE PADUCAH GASEOUS DIFFUSION PLANT, KENTUCKY

    International Nuclear Information System (INIS)

    Miller, Peter T.; Starmer, R. John

    2003-01-01

    The primary objective of the investigation was to confirm the presence and determine the location of a cache of 30 to 60 buried 55-gallon drums that were allegedly dumped along the course of the pre-existing, northsouth diversion ditch (NSDD) adjacent to permitted landfills at the Paducah Gaseous Diffusion Plant, Kentucky. The ditch had been rerouted and was being filled and re-graded at the time of the alleged dumping. Historic information and interviews with individuals associated with alleged dumping activities indicated that the drums were dumped prior to the addition of other fill materials. In addition, materials alleged to have been dumped in the ditch, such as buried roofing materials, roof flashing, metal pins, tar substances, fly ash, and concrete rubble complicated data interpretation. Some clean fill materials have been placed over the site and graded. This is an environment that is extremely complicated in terms of past waste dumping activities, construction practices and miscellaneous landfill operations. The combination of site knowledge gained from interviews and research of existing site maps, variable frequency EM data, classical total magnetic field data and optimized GPR lead to success where a simpler less focused approach by other investigators using EM-31 and EM-61 electromagnetic methods and unfocused ground penetrating radar (GPR)did not produce results and defined no real anomalies. A variable frequency electromagnetic conductivity unit was used to collect the EM data at 3,030 Hz, 5,070 Hz, 8,430 Hz, and 14,010 Hz. Both in-phase and quadrature components were recorded at each station point. These results provided depth estimates for targets and some information on the subsurface conditions. A standard magnetometer was used to conduct the magnetic survey that showed the locations and extent of buried metal, the approximate volume of ferrous metal present within a particular area, and allowed estimation of approximate target depths. The GPR

  20. COMBINED GEOPHYSICAL INVESTIGATION TECHNIQUES TO IDENTIFY BURIED WASTE IN AN UNCONTROLLED LANDFILL AT THE PADUCAH GASEOUS DIFFUSION PLANT, KENTUCKY

    Energy Technology Data Exchange (ETDEWEB)

    Miller, Peter T.; Starmer, R. John

    2003-02-27

    The primary objective of the investigation was to confirm the presence and determine the location of a cache of 30 to 60 buried 55-gallon drums that were allegedly dumped along the course of the pre-existing, northsouth diversion ditch (NSDD) adjacent to permitted landfills at the Paducah Gaseous Diffusion Plant, Kentucky. The ditch had been rerouted and was being filled and re-graded at the time of the alleged dumping. Historic information and interviews with individuals associated with alleged dumping activities indicated that the drums were dumped prior to the addition of other fill materials. In addition, materials alleged to have been dumped in the ditch, such as buried roofing materials, roof flashing, metal pins, tar substances, fly ash, and concrete rubble complicated data interpretation. Some clean fill materials have been placed over the site and graded. This is an environment that is extremely complicated in terms of past waste dumping activities, construction practices and miscellaneous landfill operations. The combination of site knowledge gained from interviews and research of existing site maps, variable frequency EM data, classical total magnetic field data and optimized GPR lead to success where a simpler less focused approach by other investigators using EM-31 and EM-61 electromagnetic methods and unfocused ground penetrating radar (GPR)did not produce results and defined no real anomalies. A variable frequency electromagnetic conductivity unit was used to collect the EM data at 3,030 Hz, 5,070 Hz, 8,430 Hz, and 14,010 Hz. Both in-phase and quadrature components were recorded at each station point. These results provided depth estimates for targets and some information on the subsurface conditions. A standard magnetometer was used to conduct the magnetic survey that showed the locations and extent of buried metal, the approximate volume of ferrous metal present within a particular area, and allowed estimation of approximate target depths. The GPR

  1. Demonstration of close-coupled barriers for subsurface containment of buried waste

    International Nuclear Information System (INIS)

    Dwyer, B.P.; Heiser, J.; Stewart, W.

    1996-01-01

    The primary objective of this project is to develop and demonstrate a close-coupled barrier for the containment of subsurface waste or contaminant migration. A close-coupled barrier is produced by first installing a conventional cement grout curtain followed by a thin inner lining of a polymer grout. The resultant barrier is a cement polymer composite that has economic benefits derived from the cement and performance benefits from the durable and resistant polymer layer. Close-coupled barrier technology is applicable for final, interim, or emergency containment of subsurface waste forms. Consequently, when considering the diversity of technology application, the construction emplacement and material technology maturity, general site operational requirements, and regulatory compliance incentives, the close-coupled barrier system provides an alternative for any hazardous or mixed waste remediation plan. This paper discusses the installation of a close-coupled barrier and the subsequent integrity verification

  2. Demonstration of close-coupled barriers for subsurface containment of buried waste. Conceptual test plan

    Energy Technology Data Exchange (ETDEWEB)

    Heiser, J. [Brookhaven National Laboratory, Upton, NY (United States); Dwyer, B. [Sandia National Laboratory, Albuquerque, NM (United States)

    1995-07-01

    Over the past five decades, the US Department of Energy (DOE) Complex sites have experienced numerous loss of confinement failures from underground storage tanks (USTs), piping systems, vaults, landfills, and other structures containing hazardous and mixed wastes. Consequently, efforts are being made to devise technologies that provide interim containment of waste sites while final remediation alternatives are developed. Barrier materials consisting of cement and polymer which will be emplaced beneath a 7500 liter tank. The stresses around the tank shall be evaluated during barrier construction.

  3. Environmental surveillance for the INEL radioactive waste management complex. Annual report, 1979

    International Nuclear Information System (INIS)

    Wickham, L.E.; Janke, D.H.

    1980-12-01

    This document is the 1979 annual environmental surveillance report for the Radioactive Waste Management Complex (RWMC) of the Idaho National Engineering Laboratory. Included are tabulated data from and discussions about routine radiological monitoring of atmospheric, hydrologic, geologic, and biotic environments of the RWMC. Also included are discussions of selected nonradiological pollutants (e.g., sodium, etc.). It is concluded that (a) RWMC operations have not adversely affected local, existing environments; (b) environmental conditions within the Transuranic Storage Area are not corrosive enough to adversely affect transuranic waste storage containers, and (c) the addition of lakebed soil to pit, trench, and soil test plot areas has altered the moisture cycle characteristic of RWMC soil

  4. Nuclear waste and radioactive cleanup: An issue that won't stay buried

    International Nuclear Information System (INIS)

    Mausshardt, D.

    1996-01-01

    For the past eight years and the DOE has embarked on the major initiative to clean up the nation's waste sites. Despite these efforts, positive environmental results have been severely restricted due to unrealistic expectations, impossible compliance milestones, and a fiscal and legal quagmire born from an expanding bureaucratic and regulatory process. This describes the road blocks, the challenges, and recommendations for the future

  5. Is It Better to Burn or Bury Waste for Clean Electricity Generation?

    Science.gov (United States)

    The generation of electricity through renewables has increased 5% since 2002. Although considerably less prominent than solar and wind, the use of municipal solid waste (MSW) to generate electricity represents roughly 14 percent of U.S. non-hydro renewable electricity generation....

  6. In situ vitrification demonstration for the stabilization of buried wastes at the Oak Ridge National Laboratory

    International Nuclear Information System (INIS)

    Jacobs, G.K.; Spalding, B.P.; Carter, J.G.; Koegler, S.S.

    1987-01-01

    A demonstration of In Situ Vitrification (ISV) technology for the stabilization of radioactively contaminated soil sites at the Oak Ridge National Laboratory (ORNL) was successfully completed during July 1987. This demonstration is the first application of the ISV process not performed at the Hanford Site, where the technology was developed and patented by Pacific Northwest Laboratory (PNL). The joint ORNL-PNL pilot-scale demonstration was performed on a 3/8-scale trench (2 m deep x 1 m wide x 10 m long) that was constructed to simulate a typical seepage trench used for liquid low-level radioactive waste disposal at ORNL from 1951 to 1966. In the ISV process, electrodes are inserted around a volume of contaminated soil, power is applied to the electrodes, and the entire mass is melted from the surface of the soil down through the contaminated zone, thus making a glassy-to-microcrystalline waste form that incorporates the contaminants. Gases produced during the melting are collected, treated, monitored, and released through an off-gas process trailer. In the ORNL demonstration, a 25-t mass of melted rock approximately 1.2 m thick x 2.1 m wide x 4.9 m long was formed during 110 h of operation that consumed approximately 29 MWh of power. Data obtained on the operational performance of the test and waste-form durability will be used to assess the feasibility of applying the ISV technology to an actual waste trench

  7. Radionuclide transport modelling for a buried near surface low level radioactive waste

    International Nuclear Information System (INIS)

    Terzi, R.

    2004-01-01

    The disposal of radioactive waste, which is the last step of any radioactive waste management policy, has not yet been developed in Turkey. The existing legislation states only the discharge limits for the radioactive wastes to be discharged to the environment. The objective of this modelling study is to assist in safety assessment and selecting disposal site for gradually increasing non-nuclear radioactive wastes. This mathematical model has been developed for the environmental radiological assessment of near surface disposal sites for the low and intermediate level radioactive wastes. The model comprised of three main components: source term, geosphere transport and radiological assessment. Radiation dose for the babies (1 years age) and adults (≥17 years age) have been computed for the radionuclides Cesium 137 (Cs-137) and Strontium 90 (Sr-90), having the activity of 1.10 12 Becquerel(Bq), in radioactive waste through transport of radionuclide in liquid phase with the various pathways. The model consisted of first order ordinary differential equations was coded as a TCODE file in MATLAB program. The radiation dose to man for the realist case and low probability case have been calculated by using Runge-Kutta solution method in MATLAB programme for radionuclide transport from repository to soil layer and then to the ground water(saturated zone) through drinking water directly and consuming agricultural and animal products pathways in one year period. Also, the fatal cancer risk assessment has been made by taking into account the annual dose received by people. Various dose values for both radionuclides have been found which depended on distribution coefficient, retardation factor and dose conversion factors. The most important critical parameters on radiological safety assessment are the distribution coefficient in soil layer, seepage velocity in unsaturated zone and thickness of the unsaturated zone (soil zone). The highest radiation dose and average dose to

  8. Demonstration of close-coupled barriers for subsurface containment of buried waste

    International Nuclear Information System (INIS)

    Dwyer, B.P.

    1996-05-01

    A close-coupled barrier is produced by first installing a conventional cement grout curtain followed by a thin inner lining of a polymer grout. The resultant barrier is a cement polymer composite that has economic benefits derived from the cement and performance benefits from the durable and resistant polymer layer. Close-coupled barrier technology is applicable for final, interim, or emergency containment of subsurface waste forms. Consequently, when considering the diversity of technology application, the construction emplacement and material technology maturity, general site operational requirements, and regulatory compliance incentives, the close-coupled barrier system provides an alternative for any hazardous or mixed waste remediation plan. This paper discusses the installation of a close-coupled barrier and the subsequent integrity verification. The demonstration was installed at a benign site at the Hanford Geotechnical Test Facility, 400 Area, Hanford, Washington. The composite barrier was emplaced beneath a 7,500 liter tank. The tank was chosen to simulate a typical DOE Complex waste form. The stresses induced on the waste form were evaluated during barrier construction. The barrier was constructed using conventional jet grouting techniques. Drilling was completed at a 45 degree angle to the ground, forming a conical shaped barrier with the waste form inside the cone. Two overlapping rows of cylindrical cement columns were grouted in a honeycomb fashion to form the secondary backdrop barrier layer. The primary barrier, a high molecular weight polymer manufactured by 3M Company, was then installed providing a relatively thin inner liner for the secondary barrier. The primary barrier was emplaced by panel jet grouting with a dual wall drill stem, two phase jet grouting system

  9. Quality assurance on the Idaho National Engineering Laboratory Buried Waste Program

    International Nuclear Information System (INIS)

    Rasmussen, T.L.

    1989-01-01

    This paper discusses the clean-up of an Idaho National Engineering Laboratory (INEL) site utilized for disposal of transuranic contaminated waste from 1954 until 1970. The author presents requirements of the environmental protection statutes that have generated quality assurance requirements in addition to those historically implemented as a part of facility design, construction and operation. A hierarchy of program guidance quality documentation and procedures is discussed. Data qualification and computer database management are identified as requirements

  10. A Remote Characterization System for subsurface mapping of buried waste sites

    International Nuclear Information System (INIS)

    Sandness, G.A.; Bennett, D.W.; Martinson, L.

    1992-06-01

    This paper describes a development project that will provide new technology for characterizing hazardous waste burial sites. The project is a collaborative effort by five of the national laboratories, involving the development and demonstration of a remotely controlled site characterization system. The Remote Characterization System (RCS) includes a unique low-signature survey vehicle, a base station, radio telemetry data links, satellite-based vehicle tracking, stereo vision, and sensors for non-invasive inspection of the surface and subsurface

  11. Infiltration properties of covering soil into the void of buried concrete waste due to fluctuation of ground water level and its prevention

    International Nuclear Information System (INIS)

    Takatsu, Tadashi; Tadano, Hideki; Abe, Satoshi; Imai, Jun; Yanagisawa, Eiji; Mitachi, Toshiyuki

    1999-01-01

    Low level radioactive concrete waste will be produced in future by breaking up the nuclear facilities, and the waste will be disposed in shallow depth of ground. In order to prepare for those situation, it is needed to clarify the infiltration properties of the covering soil into the void of buried concrete waste due to the fluctuation of ground water level and to develop the prevention methods against the infiltration of the covering soil. In this study, full-scale concrete structure specimens were broken up, and were compacted in large scale testing boxes and a series tests changing water level up and down in the concrete waste and covering soil were performed. From the test results, it was found that the appropriate filter installed between the covering soil and the concrete waste, enable us to prevent the infiltration of covering soil into the void of concrete waste. (author)

  12. Demonstration of close-coupled barriers for subsurface containment of buried waste

    International Nuclear Information System (INIS)

    Heiser, J.; Dwyer, B.

    1995-01-01

    The primary objective of this project is to develop and demonstrate a close-coupled barrier for the containment of subsurface waste or contaminant migration. A close-coupled barrier is produced by first installing a conventional cement grout curtain followed by a thin lining of a polymer grout. The resultant barrier is a cement polymer composite that has economic benefits derived from the cement and performance benefits from the durable and resistant polymer layer. Close-coupled barrier technology is applicable for final, interim, or emergency containment of subsurface waste forms. Consequently, when considering the diversity of technology application, the construction emplacement and material technology maturity, general site operational requirements, and regulatory compliance incentives, the close-coupled barrier system provides an alternative for any hazardous or mixed waste remediation plan. This paper will discuss the installation of a close-coupled barrier and the subsequent integrity verification. The demonstration will take place at a cold site at the Hanford Geotechnical Test Facility, 400 Area, Hanford, Washington

  13. Use of a Paraffin Based Grout to Stabilize Buried Beryllium and Other Wastes

    International Nuclear Information System (INIS)

    Gretchen Matthern; Duane Hanson; Neal Yancey; Darrell Knudson

    2005-01-01

    The long term durability of WAXFIXi, a paraffin based grout, was evaluated for in situ grouting of activated beryllium wastes in the Subsurface Disposal Area (SDA), a radioactive landfill at the Radioactive Waste Management Complex, part of the Idaho National Laboratory (INL). The evaluation considered radiological and biological mechanisms that could degrade the grout using data from an extensive literature search and previous tests of in situ grouting at the INL. Conservative radioactive doses for WAXFIX were calculated from the ''hottest'' (i.e., highest-activity) Advanced Test Reactor beryllium block in the SDA.. These results indicate that WAXFIX would not experience extensive radiation damage for many hundreds of years. Calculation of radiation induced hydrogen generation in WAXFIX indicated that grout physical performance should not be reduced beyond the effects of radiation dose on the molecular structure. Degradation of a paraffin-based grout by microorganisms in the SDA is possible and perhaps likely, but the rate of degradation will be at a slower rate than found in the literature reviewed. The calculations showed the outer 0.46 m (18 in.) layer of each monolith, which represents the minimum expected distance to the beryllium block, was calculated to require 1,000 to 3,600 years to be consumed. The existing data and estimations of biodegradation and radiolysis rates for WAXFIX/paraffin do not indicate any immediate problems with the use of WAXFIX for grouting beryllium or other wastes in the SDA

  14. Engineering-scale in situ vitrification tests of simulated Oak Ridge National Laboratory buried wastes

    International Nuclear Information System (INIS)

    1996-12-01

    As part of the Comprehensive Environmental Response, Compensation, and Liability Act process for remediation of Waste Area Grouping (WAG) 6 at Oak Ridge National Laboratory, a public meeting was held on the proposed plan. It was recognized that contaminant releases from WAG 6 posed minimal potential risk to the public and environment. The US Department of Energy (DOE) in conjunction with the US Environmental Protection Agency and the Tennessee Department of Environment and Conservation agreed to defer remedial action at WAG 6 until higher risk release sites were first remediated

  15. In-situ stabilization of radioactively contaminated low-level solid wastes buried in shallow trenches: an assessment

    International Nuclear Information System (INIS)

    Arora, H.S.; Tamura, T.; Boegly, W.J.

    1980-09-01

    The potential effectiveness of materials for in-situ encapsulation of low-level, radioactively contaminated solid waste buried in shallow trenches is enumerated. Cement, clay materials, and miscellaneous sorbents, aqueous and nonaqueous gelling fluids and their combinations are available to solidify contaminated free water in trenches, to fill open voids, and to minimize radionuclide mobility. The success of the grouting technique will depend on the availability of reliable geohydrologic data and laboratory development of a mix with enhanced sorption capacity for dominant radionuclides present in the trenches. A cement-bentonite-based grout mix with low consistency for pumping, several hours controlled rate of hardening, negligible bleeding, and more than 170 kPa (25 psi) compressive strength are a few of the suggested parameters in laboratory mix development. Cost estimates of a cement-bentonite-based grout mix indicate that effective and durable encapsulation can be accomplished at a reasonable cost (about $113 per cubic meter). However, extensive implementation of the method suggests the need for a field demonstration of the method. 53 references

  16. In-situ containment and stabilization of buried waste: Annual report FY 1994

    International Nuclear Information System (INIS)

    Allan, M.L.; Kukacka, L.E.

    1994-10-01

    The two landfills of specific interest are the Chemical Waste Landfill (CWL) and the Mixed Waste Landfill (MWL), both located at Sandia National Laboratory. The work is comprised of two subtasks: (1) In-Situ Barriers and (2) In-Situ Stabilization of Contaminated Soils. The main environmental concern at the CWL is a chromium plume resulting from disposal of chromic acid and chromic sulfuric acid into unlined pits. This program has investigated means of in-situ stabilization of chromium contaminated soils and placement of containment barriers around the CWL. The MWL contains a plume of tritiated water. In-situ immobilization of tritiated water with cementitious grouts was not considered to be a method with a high probability of success and was not pursued. This is discussed further in Section 5.0. Containment barriers for the tritium plume were investigated. FY 94 work focused on stabilization of chromium contaminated soil with blast furnace slag modified grouts to bypass the stage of pre-reduction of Cr(6), barriers for tritiated water containment at the MWL, continued study of barriers for the CWL, and jet grouting field trials for CWL barriers at an uncontaminated site at SNL. Cores from the FY 93 permeation grouting field trails were also tested in FY 94

  17. Use of a Paraffin Based Grout to Stabilize Buried Beryllium and Other Wastes

    Energy Technology Data Exchange (ETDEWEB)

    Gretchen Matthern; Duane Hanson; Neal Yancey; Darrell Knudson

    2005-12-01

    The long term durability of WAXFIXi, a paraffin based grout, was evaluated for in situ grouting of activated beryllium wastes in the Subsurface Disposal Area (SDA), a radioactive landfill at the Radioactive Waste Management Complex, part of the Idaho National Laboratory (INL). The evaluation considered radiological and biological mechanisms that could degrade the grout using data from an extensive literature search and previous tests of in situ grouting at the INL. Conservative radioactive doses for WAXFIX were calculated from the "hottest" (i.e., highest-activity) Advanced Test Reactor beryllium block in the SDA.. These results indicate that WAXFIX would not experience extensive radiation damage for many hundreds of years. Calculation of radiation induced hydrogen generation in WAXFIX indicated that grout physical performance should not be reduced beyond the effects of radiation dose on the molecular structure. Degradation of a paraffin-based grout by microorganisms in the SDA is possible and perhaps likely, but the rate of degradation will be at a slower rate than found in the literature reviewed. The calculations showed the outer 0.46 m (18 in.) layer of each monolith, which represents the minimum expected distance to the beryllium block, was calculated to require 1,000 to 3,600 years to be consumed. The existing data and estimations of biodegradation and radiolysis rates

  18. Application of centrifuge modelling and radiotracers to migration studies of buried toxic waste

    International Nuclear Information System (INIS)

    Villar, H.P.

    1995-01-01

    A new technique to study the migration of souble waste components in soils, based on the application of centrifugue modelling and of selected short-lived radiotracers, is presented. The technique is based on the acceleration of the migration proceses of a specific tracer in a soil model, with simple and well-established scaling laws being used to interpret the results. The use of radiotracers allows geat flexibility and the adoption of a wide range of concentrations. Demosntrations of the technique have been carried out with two elements of radically distinct behaviour: iodine noted for its mobility in soils, and thallium, which tends to be strongly sorbed. Two different soil types have been used. The results semed to confirm what is known about the behaviour of both elements, so that the feasibility of the technique for such studies has been concluded. (author). 7 refs, 4 figs, 1 tab

  19. Corrective Action Investigation Plan for Corrective Action Unit 545: Dumps, Waste Disposal Sites, and Buried Radioactive Materials Nevada Test Site, Nevada

    International Nuclear Information System (INIS)

    Alfred Wickline

    2007-01-01

    Corrective Action Unit 545, Dumps, Waste Disposal Sites, and Buried Radioactive Materials, consists of seven inactive sites located in the Yucca Flat area and one inactive site in the Pahute Mesa area. The eight CAU 545 sites consist of craters used for mud disposal, surface or buried waste disposed within craters or potential crater areas, and sites where surface or buried waste was disposed. The CAU 545 sites were used to support nuclear testing conducted in the Yucca Flat area during the 1950s through the early 1990s, and in Area 20 in the mid-1970s. This Corrective Action Investigation Plan has been developed in accordance with the Federal Facility Agreement and Consent Order that was agreed to by the State of Nevada, the U.S. Department of Energy, and the U.S. Department of Defense. Under the Federal Facility Agreement and Consent Order, this Corrective Action Investigation Plan will be submitted to the Nevada Division of Environmental Protection for approval. Fieldwork will be conducted following approval

  20. In-situ containment of buried waste at Brookhaven National Laboratory

    International Nuclear Information System (INIS)

    Dwyer, B.P.; Heiser, J.; Stewart, W.; Phillips, S.

    1997-01-01

    The primary objective of this project was to further develop close-coupled barrier technology for the containment of subsurface waste or contaminant migration. A close-coupled barrier is produced by first installing a conventional cement grout curtain followed by a thin inner lining of a polymer grout. The resultant barrier is a cement polymer composite that has economic benefits derived from the cement and performance benefits from the durable and chemically resistant polymer layer. The technology has matured from a regulatory investigation of issues concerning barriers and barrier materials to a pilot-scale, multiple individual column injections at Sandia National Labs (SNL) to full scale demonstration. The feasibility of this barrier concept was successfully proven in a full scale 'cold test' demonstration at Hanford, WA. Consequently, a full scale deployment of the technology was conducted at an actual environmental restoration site at Brookhaven National Lab (BNL), Long Island, NY. This paper discusses the installation and performance of a technology deployment implemented at OU-1 an Environmental Restoration Site located at BNL

  1. Active waste disposal monitoring at the Radioactive Waste Management Complex, Idaho National Engineering Laboratory

    International Nuclear Information System (INIS)

    Hubbell, J.M.

    1990-10-01

    This report describes an active waste disposal monitoring system proposed to be installed beneath the low-level radioactive disposal site at the Radioactive Waste Management Complex (RWMC), Idaho National Engineering Laboratory, Idaho. The monitoring instruments will be installed while the waste is being disposed. Instruments will be located adjacent to and immediately beneath the disposal area within the unsaturated zone to provide early warning of contaminant movement before contaminants reach the Snake River Plain Aquifer. This study determined the optimum sampling techniques using existing monitoring equipment. Monitoring devices were chosen that provide long-term data for moisture content, movement of gamma-emitting nuclides, and gas concentrations in the waste. The devices will allow leachate collection, pore-water collection, collection of gasses, and access for drilling through and beneath the waste at a later time. The optimum monitoring design includes gas sampling devices above, within, and below the waste. Samples will be collected for methane, tritium, carbon dioxide, oxygen, and volatile organic compounds. Access tubes will be utilized to define the redistribution of radionuclides within, above, and below the waste over time and to define moisture content changes within the waste using spectral and neutron logging, respectively. Tracers will be placed within the cover material and within waste containers to estimate transport times by conservative chemical tracers. Monitoring the vadose zone below, within, and adjacent to waste while it is being buried is a viable monitoring option. 12 refs., 16 figs., 1 tab

  2. RWMC support to member countries and relationship with the IAEA, EC and other organisations

    International Nuclear Information System (INIS)

    2006-01-01

    This documents provides information on how the work of the NEA/RWMC supports the needs of NEA member countries and how it differs from, and complements, the related work of the IAEA and EC. In particular, the document reviews the respective roles and specificities of these organisations and their modus operandi, including co-operation and co-ordination mechanisms. (authors)

  3. Subsurface Investigations Program at the radioactive waste management complex of the Idaho National Engineering Laboratory. Annual progress report, FY-1985

    International Nuclear Information System (INIS)

    Hubbell, J.M.; Hull, L.C.; Humphrey, T.G.; Russell, B.F.; Pittman, J.R.; Cannon, K.M.

    1985-12-01

    This report describes work conducted in FY-85 in support of the Subsurface Investigation Program at the Radioactive Waste Management Complex of the Idaho National Engineering Laboratory. The work is part of a continuing effort to define and predict radionuclide migration from buried waste. The Subsurface Investigation Program is a cooperative study conducted by EG and G Idaho and the US Geological Survey, INEL Office. EG and G is responsible for the shallow drilling, solution chemistry, and net downward flux portions of this program, while the US Geological Survey is responsible for the weighing lysimeters and test trench. Data collection was initiated by drilling, sampling, and instrumenting shallow wells, continuing the installation of test trenches, and modifying the two weighing lysimeters. Twenty-one shallow auger holes were around the Radioactive Waste Management Complex (RWMC) to evaluate radionuclide content in the surficial sediments, to determine the geologic and hydrologic characteristics of the surficial sediments, and to provide as monitoring sites for moisture in these sediments. Eighteen porous cup lysimeters were installed in 12 auger holes to collect soil water samples from the surficial sediments. Fourteen auger holes were instrumented with tensiometers, gypsum blocks and/or psychrometers at various depths throughout the RWMC. Readings from these instruments are taken on a monthly basis

  4. Decontamination and decommissioning of TAN radioactive liquid-waste-evaporator system (PM-2A). Final report

    International Nuclear Information System (INIS)

    Smith, D.L.

    1983-03-01

    This report describes the decontamination and decommissioning of the Test Area North (TAN) liquid waste evaporator (PM-2A). The PM-2A facility included the aboveground evaporator system, two underground holding tanks and feedlines, an electrical distribution subsystem, and one above ground concrete tank. Much surface soil of the PM-2A area was also radioactively contaminated. Stabilization of the liquid and sludge in the holding tanks, a major task, was achieved by pumping most of the liquid into 55-gal drums and mixing it with cement. The drums were buried in the Radioactive Waste Management Complex (RWMC). The remaining liquid and sludge were dried in place by layers of diatomaceous earth. The most contaminated surface soil was removed, and the area backfilled with clean topsoil and graded, reducing the surface radiation field to background. A 6-ft-high chain link fence now surrounds the area. Most of the area was seeded to crested wheatgrass. 46 figures, 9 tables

  5. Development and testing of techniques for in-ground stabilization, size reduction, and safe removal of radioactive wastes stored in containments buried in ground

    International Nuclear Information System (INIS)

    Halliwell, Stephen; Christodoulou, Apostolos

    2013-01-01

    Since the 1950's radioactive wastes from a number of laboratories have been stored below ground at the Hanford site, Washington State, USA, in vertical pipe units (VPUs) made of five 200 litre drums without tops or bottoms, and in caissons, made out of corrugated pipe, or concrete and typically 2,500 mm in diameter. The VPU's are buried of the order of 2,100 mm below grade, and the caissons are buried of the order of 6,000 mm below grade. The waste contains fuel pieces, fission products, and a range of chemicals used in the laboratory processes. This can include various energetic reactants such as un-reacted sodium potassium (NaK), potassium superoxide (KO 2 ), and picric acid, as well as quantities of other liquids. The integrity of the containments is considered to present unacceptable risks from leakage of radioactivity to the environment. This paper describes the successful development and full scale testing of in-ground augering equipment, grouting systems and removal equipment for remediation and removal of the VPUs, and the initial development work to test the utilization of the same basic augering and grouting techniques for the stabilization, size reduction and removal of caissons. (authors)

  6. Summary of northern Atlantic coastal plain hydrology and its relation to disposal of high-level radioactive waste in buried crystalline rock; a preliminary appraisal

    Science.gov (United States)

    Lloyd, O.B.; Larson, J.D.; Davis, R.W.

    1985-01-01

    Interpretation of available hydrologic data suggests that some areas beneath the Coastal Plain in the States of Delaware, Maryland, New Jersey, North Carolina, and Virginia might have some potential for the disposal of nuclear waste in crystalline rock that is buried beneath the Coastal Plain sediments. The areas of major interest occur where the top of the basement rock lies between 1,000 and 4,000 feet below sea level, the aquifer(s) immediately above the basement rock are saturated with saline water, confining material overlies the saline water bearing aquifer(s), and groundwater flow in the saline water aquifer(s) can be established. Preliminary data on (1) the distribution and thickness of the lowermost aquifers and confining beds, (2) the distribution of hydraulic conductivity in the lowermost aquifers, (3) estimated hydraulic heads and inferred direction of lateral groundwater flow for 1980, and (4) the distribution of saline water and brine, indicate eastern parts of the study area relatively best meet most of the criteria proposed for sediments that would overlie any potential buried crystalline-rock disposal site.

  7. In situ technology evaluation and functional and operational guidelines for treatability studies at the radioactive waste management complex at the Idaho National Engineering Laboratory

    International Nuclear Information System (INIS)

    Hyde, R.A.; Donehey, A.J.; Piper, R.B.; Roy, M.W.; Rubert, A.L.; Walker, S.

    1991-07-01

    The purpose of this document is to provide EG ampersand G Idaho's Waste Technology Development Department with a basis for selection of in situ technologies for demonstration at the Radioactive Waste Management Complex (RWMC) of the Idaho National Engineering Laboratory (INEL) and to provide information for Feasibility Studies to be performed according to the Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA). The demonstrations will aid in meeting Environmental Restoration/Waste Management (ER/WM) schedules for remediation of waste at Waste Area Group (WAG) 7. This report is organized in six sections. Section 1, summarizes background information on the sites to be remediated at WAG-7, specifically, the acid pit, soil vaults, and low-level pits and trenches. Section 2 discusses the identification and screening of in situ buried waste remediation technologies for these sites. Section 3 outlines the design requirements. Section 4 discusses the schedule [in accordance with Buried Waste Integrated Demonstration (BWID) scoping]. Section 5 includes recommendations for the acid pit, soil vaults, and low-level pits and trenches. A listing of references used to compile the report is given in Section 6. Detailed technology information is included in the Appendix section of this report

  8. Aggradational and erosional history of the Radioactive Waste Management Complex at the Idaho National Engineering Laboratory

    Energy Technology Data Exchange (ETDEWEB)

    Dechert, T.V.; McDaniel, P.A.; Falen, A.L. [Idaho Univ., Moscow, ID (United States)

    1994-09-01

    Long-term performance of the low-level waste disposal site at the Radioactive Waste Management Complex (RWMC) is partially dependent on the stability of the land surface with respect to erosion of cover materials. This document discusses the aggradational and erosional history of the naturally occurring sediments and soils in and around the RWMC, focusing on the late-Pleistocene and Holocene epochs. Other related issues include the ages of the various deposits, the extent to which they have been altered by soil formation and other processes, their relationships to the basalt flows in the area, and the impact of human activity on the materials at the RWMC.

  9. Aggradational and erosional history of the Radioactive Waste Management Complex at the Idaho National Engineering Laboratory

    International Nuclear Information System (INIS)

    Dechert, T.V.; McDaniel, P.A.; Falen, A.L.

    1994-09-01

    Long-term performance of the low-level waste disposal site at the Radioactive Waste Management Complex (RWMC) is partially dependent on the stability of the land surface with respect to erosion of cover materials. This document discusses the aggradational and erosional history of the naturally occurring sediments and soils in and around the RWMC, focusing on the late-Pleistocene and Holocene epochs. Other related issues include the ages of the various deposits, the extent to which they have been altered by soil formation and other processes, their relationships to the basalt flows in the area, and the impact of human activity on the materials at the RWMC

  10. Multi-point injection demonstration for solidification of shallow buried waste at Oak Ridge Reservation, Oak Ridge, Tennessee

    International Nuclear Information System (INIS)

    1996-10-01

    The multi-point injection (MPI) technology is a precision, high-velocity jetting process for the in situ delivery of various agents to treat radiological and/or chemical wastes. A wide variety of waste forms can be treated, varying from heterogeneous waste dumped into shallow burial trenches to contaminated soils consisting of sands/gravels, silts/clays and soft rock. The robustness of the MPI system is linked to its broad range of applications which vary from in situ waste treatment to creation of both vertical and horizontal barriers. The only major constraint on the type of in situ treatment which can be delivered by the NTI system is that agents must be in a slurry form

  11. TNX Burying Ground: Environmental information document

    International Nuclear Information System (INIS)

    Dunaway, J.K.W.; Johnson, W.F.; Kingley, L.E.; Simmons, R.V.; Bledsoe, H.W.

    1987-03-01

    The TNX Burying Ground, located within the TNX Area of the Savannah River Plant (SRP), was originally built to dispose of debris from an experimental evaporator explosion at TNX in 1953. This evaporator contained approximately 590 kg of uranyl nitrate. From 1980 to 1984, much of the waste material buried at TNX was excavated and sent to the SRP Radioactive Waste Burial Grounds for reburial. An estimated 27 kg of uranyl nitrate remains buried at TNX. The TNX Burying Ground consists of three sites known to contain waste and one site suspected of containing waste material. All four sites are located within the TNX security fenceline. Groundwater at the TNX Burying Ground was not evaluated because there are no groundwater monitoring wells installed in the immediate vicinity of this waste site. The closure options considered for the TNX Burying Ground are waste removal and closure, no waste removal and closure, and no action. The predominant pathways for human exposure to chemical and/or radioactive constituents are through surface, subsurface, and atmospheric transport. Modeling calculations were made to determine the risks to human population via these general pathways for the three postulated closure options. An ecological assessment was conducted to predict the environmental impacts on aquatic and terrestrial biota. The relative costs for each of the closure options were estimated

  12. Thermal performance of a buried nuclear waste storage container storing a hybrid mix of PWR and BWR spent fuel rods

    International Nuclear Information System (INIS)

    Johnson, G.L.

    1988-09-01

    Lawrence Livermore National Laboratory will design, model, and test nuclear waste packages for use at the Nevada Nuclear Waste Storage Repository at Yucca Mountain, Nevada. One such package would store lightly packed spent fuel rods from both pressurized and boiling water reactors. The storage container provides the primary containment of the nuclear waste and the spent fuel rod cladding provides secondary containment. A series of transient conduction and radiation heat transfer analyses was run to determine for the first 1000 yr of storage if the temperature of the tuff at the borehole wall ever falls below 97/degree/C and whether the cladding of the stored spent fuel ever exceeds 350/degree/C. Limiting the borehole to temperatures of 97/degree/C or greater helps minimize corrosion by assuring that no condensed water collects on the container. The 350/degree/C cladding limit minimizes the possibility of creep-related failure in the spent fuel rod cladding. For a series of packages stored in a 8 x 30 m borehole grid where each package contains 10-yr-old spent fuel rods generating 4.74 kW or more, the borehole wall stays above 97/degree/C for the full 1000-yr analysis period

  13. Strategic areas in radioactive waste management. The viewpoint and work orientations of the Nea radioactive waste management committee

    International Nuclear Information System (INIS)

    1999-01-01

    The NEA Radioactive Waste Management Committee (RWMC) is a forum of senior operators, regulators, policy makers, and senior representatives of R and D institutions in the field of radioactive waste management. The Committee assists Member countries by providing objective guidance on the solution of radioactive waste problems, and promotes Safety in the short- and long-term management of radioactive waste. This report identifies some of the major challenges currently faced by national waste management programmes, and describes the strategic areas in which the RWMC should focus its efforts in future years. (author)

  14. Thermal performance of a buried nuclear waste storage container storing a hybrid mix of PWR and BWR spent fuel rods

    International Nuclear Information System (INIS)

    Johnson, G.L.

    1991-11-01

    Lawrence Livermore National Laboratory will design, model, and test nuclear waste packages for use at the Nevada Nuclear Waste Storage Repository at Yucca Mountain, Nevada. On such package would store tightly packed spent fuel rods from both pressurized and boiling water reactors. The storage container provides the primary containment of the nuclear waste and the spent fuel rod cladding provides secondary containment. A series of transient conduction and radiation heat transfer analyses was run to determine for the first 1000 yr of storage if the temperature of the tuff at the borehole wall ever falls below 97 degrees C and whether the cladding of the stored spent fuel ever exceeds 350 degrees C. Limiting the borehole to temperatures of 97 degrees C or greater helps minimize corrosion by assuring that no condensed water collects on the container. The 350 degrees C cladding limit minimizes the possibility of creep- related failure in the spent fuel rod cladding. For a series of packages stored in a 8 x 30 m borehole grid where each package contains 10-yr-old spent fuel rods generating 4.74 kW or more, the borehole wall stays above 97 degrees C for the full 10000-yr analysis period. For the 4.74-kW load, the peak cladding temperature rises to just below the 350 degrees C limit about 4 years after emplacement. If the packages are stored using the spacing specified in the Site Characterization Plan (15 ft x 126 ft), a maximum of 4.1 kW per container may be stored. If the 0.05-m-thick void between the container and the borehole wall is filled with loosely packed bentonite, the peak cladding temperature rises more than 40 degrees C above the allowed cladding limit. In all cases the dominant heat transfer mode between container components is thermal radiation

  15. Enhanced research in ground-penetrating radar and multisensor fusion with application to the detection and visualization of buried waste. Final report

    Energy Technology Data Exchange (ETDEWEB)

    Devney, A.J.; DiMarzio, C.; Kokar, M.; Miller, E.L.; Rappaport, C.M.; Weedon, W.H.

    1996-05-14

    Recognizing the difficulty and importance of the landfill remediation problems faced by DOE, and the fact that no one sensor alone can provide complete environmental site characterization, a multidisciplinary team approach was chosen for this project. The authors have developed a multisensor fusion approach that is suitable for the wide variety of sensors available to DOE, that allows separate detection algorithms to be developed and custom-tailored to each sensor. This approach is currently being applied to the Geonics EM-61 and Coleman step-frequency radar data. High-resolution array processing techniques were developed for detecting and localizing buried waste containers. A soil characterization laboratory facility was developed using a HP-8510 network analyzer and near-field coaxial probe. Both internal and external calibration procedures were developed for de-embedding the frequency-dependent soil electrical parameters from the measurements. Dispersive soil propagation modeling algorithms were also developed for simulating wave propagation in dispersive soil media. A study was performed on the application of infrared sensors to the landfill remediation problem, particularly for providing information on volatile organic compounds (VOC`s) in the atmosphere. A dust-emission lidar system is proposed for landfill remediation monitoring. Design specifications are outlined for a system which could be used to monitor dust emissions in a landfill remediation effort. The detailed results of the investigations are contained herein.

  16. Enhanced research in ground-penetrating radar and multisensor fusion with application to the detection and visualization of buried waste. Final report

    International Nuclear Information System (INIS)

    Devney, A.J.; DiMarzio, C.; Kokar, M.; Miller, E.L.; Rappaport, C.M.; Weedon, W.H.

    1996-01-01

    Recognizing the difficulty and importance of the landfill remediation problems faced by DOE, and the fact that no one sensor alone can provide complete environmental site characterization, a multidisciplinary team approach was chosen for this project. The authors have developed a multisensor fusion approach that is suitable for the wide variety of sensors available to DOE, that allows separate detection algorithms to be developed and custom-tailored to each sensor. This approach is currently being applied to the Geonics EM-61 and Coleman step-frequency radar data. High-resolution array processing techniques were developed for detecting and localizing buried waste containers. A soil characterization laboratory facility was developed using a HP-8510 network analyzer and near-field coaxial probe. Both internal and external calibration procedures were developed for de-embedding the frequency-dependent soil electrical parameters from the measurements. Dispersive soil propagation modeling algorithms were also developed for simulating wave propagation in dispersive soil media. A study was performed on the application of infrared sensors to the landfill remediation problem, particularly for providing information on volatile organic compounds (VOC's) in the atmosphere. A dust-emission lidar system is proposed for landfill remediation monitoring. Design specifications are outlined for a system which could be used to monitor dust emissions in a landfill remediation effort. The detailed results of the investigations are contained herein

  17. A Remote Characterization System and a fault-tolerant tracking system for subsurface mapping of buried waste sites

    International Nuclear Information System (INIS)

    Sandness, G.A.; Bennett, D.W.; Martinson, L.; Bingham, D.N.; Anderson, A.A.

    1992-08-01

    This paper describes two closely related projects that will provide new technology for characterizing hazardous waste burial sites. The first project, a collaborative effort by five of the national laboratories, involves the development and demonstration of a remotely controlled site characterization system. The Remote Characterization System (RCS) includes a unique low-signature survey vehicle, a base station, radio telemetry data links, satellite-based vehicle tracking, stereo vision, and sensors for noninvasive inspection of the surface and subsurface. The second project, conducted by the Idaho National Engineering Laboratory (INEL), involves the development of a position sensing system that can track a survey vehicle or instrument in the field. This system can coordinate updates at a rate of 200/s with an accuracy better than 0.1% of the distance separating the target and the sensor. It can employ acoustic or electromagnetic signals in a wide range of frequencies and can be operated as a passive or active device

  18. Environmental and other evaluations of alternatives for long-term management of stored INEL transuranic waste

    International Nuclear Information System (INIS)

    1979-02-01

    This study identifies, develops, and evaluates, in a preliminary manner, alternatives for long-term management of TRU waste stored at the Radioactive Waste Management Complex (RWMC) at the INEL. The evaluations concern waste currently at the RWMC and waste expected to be received by the beginning of the year 1985. The effects of waste that might be received after that date are addressed in an appendix. The technology required for managing the waste, the environmental effects, the risks to the public, the radiological and nonradiological hazards to workers, and the estimated costs are discussed

  19. Environmental and other evaluations of alternatives for long-term management of stored INEL transuranic waste

    International Nuclear Information System (INIS)

    1979-12-01

    This study identifies, develops, and evaluates, in a preliminary manner, alternatives for long-term management of TRU waste stored at the Radioactive Waste Management Complex (RWMC) at the INEL. The evaluations concern waste currently at the RWMC and waste expected to be received by the beginning of the year 1985. The effects of waste that might be received after that data are addressed in an appendix. The technology required for managing the waste, the environmental effects, the risks to the public, the radiological and nonradiological hazards to workers, and the estimated costs are discussed

  20. Environmental and other evaluations of alternatives for long-term management of stored INEL transuranic waste

    Energy Technology Data Exchange (ETDEWEB)

    1979-02-01

    This study identifies, develops, and evaluates, in a preliminary manner, alternatives for long-term management of TRU waste stored at the Radioactive Waste Management Complex (RWMC) at the INEL. The evaluations concern waste currently at the RWMC and waste expected to be received by the beginning of the year 1985. The effects of waste that might be received after that date are addressed in an appendix. The technology required for managing the waste, the environmental effects, the risks to the public, the radiological and nonradiological hazards to workers, and the estimated costs are discussed.

  1. Black-tailed jack rabbit movements and habitat utilization at the Idaho National Engineering Laboratory radioactive waste management complex

    International Nuclear Information System (INIS)

    Grant, J.C.

    1983-01-01

    In June 1982, a study of black-tailed jack rabbit (Lepus californicus) ecology was initiated at the Idaho National Engineering Laboratory Radioactive Waste Management Complex (RWMC). This study will provide data necessary to evaluate the role of jack rabbits in radionuclide transport away from the Subsurface Disposal Area of the RWMC. Primary goals are to document radionuclide concentrations in jack rabbit tissues, and determine population size, movement patterns, habitat use, and food habits of jack rabbits inhabiting the RWMC area. Study design and prelimianry results are discussed

  2. Feasibility of disposal of high-level radioactive waste into the seabed. Volume 8: Review of processes near a buried waste canister

    International Nuclear Information System (INIS)

    Lanza, F.

    1988-01-01

    One of the options suggested for disposal of high-level radioactive waste resulting from the generation of nuclear power is burial beneath the deep ocean floor in geologically stable sediment formations which have no economic value. The 8-volume series provides an assessment of the technical feasibility and radiological safety of this disposal concept based on the results obtained by ten years of co-operation and infomation exchange among the Member countries participating in the NEA Seabed Working Group. This report investigates the phenomena arriving in the proximity of the waste package immersed in the sea sediments

  3. Topical Session on Liabilities identification and long-term management at national level - Topical Session held during the 36. Meeting of the RWMC

    International Nuclear Information System (INIS)

    2003-01-01

    These proceedings cover a topical session that was held at the March 2003 meeting of the Radioactive Waste Management Committee. The topical session focused on liability assessment and management for decommissioning of all types of nuclear installations, including decontamination of historic sites and waste management, as applicable. The presentations covered the current, national situations. The first oral presentation, from Switzerland, set the scene by providing a broad coverage of the relevant issues. The subsequent presentations - five from Member countries and one from the EC - described additional national positions and the evolving EC proposed directives. Each oral presentation was followed by a brief period of Q and As for clarification only. A plenary discussion took place on the ensemble of presentations and a Rapporteur provided a report on points made and lessons learnt. Additionally, written contributions were provided by RWMC delegates from several other countries. These are included in the proceedings as are the papers from the oral sessions, and the Rapporteur's report. These papers are not intended to be exhaustive, but to give an informed glimpse of NEA countries' approaches to liability identification and management in the context of nuclear facilities decommissioning and dismantling

  4. Corrective Action Decision Document/Closure Report for Corrective Action Unit 545: Dumps, Waste Disposal Sites, and Buried Radioactive Materials Nevada Test Site, Nevada, Revision 0

    Energy Technology Data Exchange (ETDEWEB)

    Alfred Wickline

    2008-04-01

    This Corrective Action Decision Document (CADD)/Closure Report (CR) has been prepared for Corrective Action Unit (CAU) 545, Dumps, Waste Disposal Sites, and Buried Radioactive Materials, in Areas 2, 3, 9, and 20 of the Nevada Test Site, Nevada, in accordance with the Federal Facility Agreement and Consent Order that was agreed to by the State of Nevada; U.S. Department of Energy (DOE), Environmental Management; U.S. Department of Defense; and DOE, Legacy Management (1996, as amended February 2008). Corrective Action Unit 545 is comprised of the following eight Corrective Action Sites (CASs): • 02-09-01, Mud Disposal Area • 03-08-03, Mud Disposal Site • 03-17-01, Waste Consolidation Site 3B • 03-23-02, Waste Disposal Site • 03-23-05, Europium Disposal Site • 03-99-14, Radioactive Material Disposal Area • 09-23-02, U-9y Drilling Mud Disposal Crater • 20-19-01, Waste Disposal Site While all eight CASs are addressed in this CADD/CR, sufficient information was available for the following three CASs; therefore, a field investigation was not conducted at these sites: • For CAS 03-08-03, though the potential for subsidence of the craters was judged to be extremely unlikely, the data quality objective (DQO) meeting participants agreed that sufficient information existed about disposal and releases at the site and that a corrective action of close in place with a use restriction is recommended. Sampling in the craters was not considered necessary. • For CAS 03-23-02, there were no potential releases of hazardous or radioactive contaminants identified. Therefore, the Corrective Action Investigation Plan for CAU 545 concluded that: “Sufficient information exists to conclude that this CAS does not exist as originally identified. Therefore, there is no environmental concern associated with CAS 03-23-02.” This CAS is closed with no further action. • For CAS 03-23-05, existing information about the two buried sources and lead pig was considered to be

  5. Evaluation of isotopic diagnostics for subsurface characterization and monitoring: Field experiments at the TAN and RWMC (SDA) Sites, INEEL. 1997 annual progress report

    International Nuclear Information System (INIS)

    DePaolo, D.J.; Kennedy, B.M.

    1997-01-01

    'This research is aimed at improving methods for characterizing underground contamination sites and for monitoring how they change with time. Particular emphasis is placed on identifying and quantifying the effects of intrinsic remediation and verifying the efficacy of engineered remediation activities. Isotopic measurements of elements such as C, O, H, He, Cl, and Sr, which are present in groundwater and soil gas, provide a quantitative measure of material balance. They can be used to identify the sites of origin of contaminants in groundwater, and to determine if contaminants are being destroyed as a result of natural processes or engineered processes. Isotope ratios also can be used to trace the migration of fluids that underground contaminants, such as steam and chemical reactions are occurring underground destruction of TCE usually produces carbon dissolution of calcite. are pumped down wells to destroy or confine grout, and they can be utilized to diagnose what and what materials are reacting. For example, dioxide, but carbon dioxide can also come from There are many isotopic ratios that can be measured in groundwater and vadose zone gas that could be valuable for characterizing remediation sites and monitoring remediation activities; The authors concentrate on a few that are particularly useful for the problems being addressed at the TAN (Test Area North) and RWMC (Radioactive Waste Management Complex) sites of the Idaho National Engineering Lab.. The isotopes the authors are using are 13 C, 14 C, 3 He, 87 Sr, 37 Cl, and 18 O.'

  6. Electromagnetic scattering from buried objects

    International Nuclear Information System (INIS)

    Brock, B.C.; Sorensen, K.W.

    1994-10-01

    Radar imaging and detection of objects buried in soil has potentially important applications in the areas of nonproliferation of weapons, environmental monitoring, hazardous-waste site location and assessment, and even archeology. In order to understand and exploit this potential, it is first necessary to understand how the soil responds to an electromagnetic wave, and how targets buried within the soil scatter the electromagnetic wave. We examine the response of the soil to a short pulse, and illustrate the roll of the complex dielectric permittivity of the soil in determining radar range resolution. This leads to a concept of an optimum frequency and bandwidth for imaging in a particular soil. We then propose a new definition for radar cross section which is consistent with the modified radar equation for use with buried targets. This radar cross section plays the same roll in the modified radar equation as the traditional radar cross section does in the free-space radar equation, and is directly comparable to it. The radar cross section of several canonical objects in lossy media is derived, and examples are given for several object/soil combinations

  7. Impact of surface water recharge on the design of a groundwater monitoring system for the Radioactive Waste Management Complex, Idaho National Engineering Laboratory

    International Nuclear Information System (INIS)

    Wood, T.R.

    1990-01-01

    Recent hydrogeologic studies have been initiated to characterize the hydrogeologic conditions at the Radioactive Waste Management Complex (RWMC) at the Idaho National Engineering Laboratory (INEL). Measured water levels in wells penetrating the Snake River Plain aquifer near the RWMC and the corresponding direction of flow show change over time. This change is related to water table mounding caused by recharge from excess water diverted from the Big Lost River for flood protection during high flows. Water levels in most wells near the RWMC rise on the order of 10 ft (3 m) in response to recharge, with water in one well rising over 60 ft (18 m). Recharge changes the normal south-southwest direction of flow to the east. Design of the proposed groundwater monitoring network for the RWMC must account for the variable directions of groundwater flow. 11 refs., 9 figs., 2 tabs

  8. Buried Craters of Utopia

    Science.gov (United States)

    2003-01-01

    MGS MOC Release No. MOC2-365, 19 May 2003Beneath the northern plains of Mars are numerous buried meteor impact craters. One of the most heavily-cratered areas, although buried, occurs in Utopia Planitia, as shown in this Mars Global Surveyor (MGS) Mars Orbiter Camera (MOC) image. The history of Mars is complex; impact craters provide a tool by which to understand some of that history. In this case, a very ancient, cratered surface was thinly-buried by younger material that is not cratered at all. This area is near 48.1oN, 228.2oW; less than 180 km (112 mi) west of the Viking 2 lander site. Sunlight illuminates the scene from the lower left.

  9. Permanent burying method for product

    International Nuclear Information System (INIS)

    Sakai, Goro; Sakata, Noboru; Hironaka, Yoshikazu; Shigematsu, Kazuo; Yurugi, Masahiro; Minami, Masayoshi; Yoshisaki, Masato.

    1995-01-01

    In a method of permanently burying an object by filling and solidifying a cement mortar in gaps between each of objects to be buried underground, cement mortar is filled into gaps, which comprises water at a unit amount determined as from 200 to 250kg/m 3 , a cement at low water/cement ratio (%) of from 70 to 400%, and contains fine powder having an average grain size of not greater than 100μm (not containing cement) of 50 to 800kg/m 3 , fine aggregates of 800 to 1200kg/m 3 , UERAN gum (a bio-gum powder produced by aerobic fermentation of alcaligenes-bacteria) of 20g/m 3 to 1.3kg/m 3 , a dispersing agent of 0 to 40kg/m 3 , a swelling agent of 0 to 40kg/m 3 . Then if the mortar blended with the UERAN gum is injected, any gaps can be filled tightly, no breeding is caused and since the amount of cement is small, it does not suffer from temperature cracking. Therefore, the state of filling is kept permanently, and environmental pollution caused by radioactive wastes can be prevented. (N.H.)

  10. Remote waste handling at the Hot Fuel Examination Facility

    International Nuclear Information System (INIS)

    Vaughn, M.E.

    1982-01-01

    Radioactive solid wastes, some of which are combustible, are generated during disassembly and examination of irradiated fast-reactor fuel and material experiments at the Hot Fuel Examination Facility (HFEF). These wastes are remotely segregated and packaged in doubly contained, high-integrity, clean, retrievable waste packages for shipment to the Radioactive Waste Management Complex (RWMC) at the Idaho National Engineering Laboratory (INEL). This paper describes the equipment and techniques used to perform these operations

  11. Radioactive Waste Management Strategy

    International Nuclear Information System (INIS)

    2002-01-01

    This strategy defines methods and means how collect, transport and bury radioactive waste safely. It includes low level radiation waste and high level radiation waste. In the strategy are foreseen main principles and ways of storage radioactive waste

  12. SRL in-situ tests in the United Kingdom: Part 2, Surface analyses of SRS waste glass buried for one and two years in limestone at Ballidon, UK

    International Nuclear Information System (INIS)

    Namboodri, C.G. Jr.; Wicks, G.G.

    1991-01-01

    A multiphase experimental program to assess and understand waste glass behavior under a wide range of conditions has been in progress at the Savannah River Laboratory (SRL) for over a decade. An important part of this experimental effort is to assess the effects of repository relevant conditions on performance of SRS waste glass, in both controlled laboratory tests, as well as in actual field experiments. In laboratory test, SRS waste glass, simulated and in many cases also fully radioactive, has been tested in environments of salt, basalt, shale, granite, clay and tuff. In field experiments, there are four joint international programs being conducted in four different countries, involving burial of SRS simulated waste glass in granite, limestone, clay and salt geologies. This report discusses the SRS waste glass studies in limestone at Ballidon, UK

  13. INEL waste reduction: summary paper

    International Nuclear Information System (INIS)

    Rhoades, W.A.

    1987-01-01

    The Idaho National Engineering Laboratory (INEL) is a Department of Energy (DOE) facility located in southeastern Idaho. Located at the INEL are a Waste Experimental Reduction Facility (WERF) which processes low level radioactive waste (LLW) materials and a Radioactive Waste Management Complex (RWMC) which provides for disposal of radioactive waste materials. There are currently 9 active facilities (waste generators) at the INEL which produce an average total volume of about 5000 cubic meters of solid LLW annually. This boxed or bulk waste is ultimately disposed of at the RWMC Subsurface Disposal Area (SDA). The SDA is currently the only active LLW disposal site at the INEL, and the prospects for opening another shallow land burial disposal facility are uncertain. Therefore, it has become imperative that EG and G Idaho Waste Management Department make every reasonable effort to extend the disposal life of the SDA. Among Waste Management Department's principal efforts to extend the SDA disposal life are operation of the Waste Experimental Reduction Facility (WERF) and administration of the INEL Waste Reduction Program. The INEL Waste Reduction Program is charged with providing assistance to all INEL facilities in reducing LLW generation rates to the lowest practical levels while at the same time encouraging optimum utilization of the volume reduction capabilities of WERF. Both waste volume and waste generation reductions are discussed

  14. Demonstration of In-Situ Stabilization of Buried Waste at Pit G-11 at the Brookhaven National laboratory Glass Pits Disposal Site

    International Nuclear Information System (INIS)

    Dwyer, B.P.; Gilbert, J.; Heiser, J.

    1999-01-01

    In 1989 BNL was added to the EPAs National Priorities List. The site is divided into seven operable units (OU). OU-I includes the former landfill area. The field task site is noted as the AOC 2C Glass Holes location. Beginning in the 1960s and continuing into the 1980s, BNL disposed of laboratory waste (glassware, chemicals and animal carcasses) in numerous shallow pits. The drivers for remediating the pits are; historical records that indicate hazardous materials may have been disposed of in the pits; ground water contamination down gradient of the pits; a test excavation of one of the glass holes that unearthed laboratory glass bottles with unidentified liquids still contained; and the fact that BNL rests atop an EPA designated sole-source aquifer. The specific site chosen for this demonstration was pit G-11. The requirements that lead to choosing this pit were; a well characterized pit and a relatively isolated pit where our construction operations would not impact on adjacent pits. The glass holes area, including pit G-11, was comprehensively surveyed using a suite of geophysical techniques (e.g., EM-31, EM-61, GPR). Prior to stabilizing the waste form a subsurface barrier was constructed to contain the entire waste pit. The pit contents were then stabilized using a cement grout applied via jet grouting. The stabilization was performed to make removal of the waste from the pit easier and safer in terms of worker exposure. The grouting process would mix and masticate the waste and grout and form a single monolithic waste form. This large monolith would then be subdivided into smaller 4 foot by 4 foot by 10-12 foot block using a demolition grout. The smaller blocks would then be easily removed from the site and disposed of in a CERCLA waste site

  15. Nevada Test Site Waste Acceptance Criteria

    International Nuclear Information System (INIS)

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

    2005-01-01

    This document establishes the U.S. Department of Energy (DOE), National Nuclear Security Administration Nevada Site Office (NNSA/NSO) waste acceptance criteria (WAC). The WAC provides the requirements, terms, and conditions under which the Nevada Test Site (NTS) will accept low-level radioactive (LLW) and mixed waste (MW) for disposal. It includes requirements for the generator waste certification program, characterization, traceability, waste form, packaging, and transfer. The criteria apply to radioactive waste received at the NTS Area 3 and Area 5 Radioactive Waste Management Complex (RWMC) for storage or disposal

  16. Seismic induced earth pressures in buried vaults

    International Nuclear Information System (INIS)

    Miller, C.A.; Costantino, C.J.

    1994-01-01

    The magnitude and distribution of earth pressures acting on buried structures and induced by a seismic event are considered in this paper. A soil-structure-interaction analysis is performed for typical Department of Energy high level waste storage tanks using a lumped parameter model. The resulting soil pressure distributions are determined and compared with the static soil pressure to assess the design significance of the seismic induced soil pressures. It is found that seismic pressures do not control design unless the peak ground acceleration exceeds about 0.3 G. The effect of soil non linearities (resulting from local soil failure) are also found to have little effect on the predictions of the seismic response of the buried structure. The seismic induced pressures are found to be very similar to those predicted using the elastic model in ASCE 4-86

  17. Results of the gamma-neutron mapper performance test on 55-gallon drums at the RWMC

    International Nuclear Information System (INIS)

    Gehrke, R.J.; Lawrence, R.S.; Roybal, L.G.; Svoboda, J.M.; Harker, D.J.; Thompson, D.N.; Carpenter, M.V.; Josten, N.E.

    1995-07-01

    The primary purpose of the gamma-neutron mapper (G at sign) is to provide accurate and quantitative spatial information of the gamma-ray and neutron radiation fields as a function of position about the excavation of a radioactive waste site. The GNM is designed to operate remotely and can be delivered to any point on an excavation by the robotic gantry crane developed by the dig-face project at the Idaho National Engineering Laboratory (INEL). It can also be easily adapted to other delivery systems. The GNM can be deployed over a waste site at a predetermined scan rate and has sufficient accuracy to identify and quantify radioactive contaminants of importance. The results reported herein are from a performance test conducted at the Transuranic Storage Area, Building 628, of the Radioactive Waste Management Complex located at the INEL. This building is an active interim-storage area for 55-gal drums of transuranic waste from the Department of Energy's Rocky Flats Plant. The performance test consisted of scanning a stack of drums five high by five wide. Prior to the test, radiation fields were measured by a health physicist at the center of the drums and ranged from 0.5 mR/h to 35 mR/h. Scans of the drums using the GNM were taken at standoff distances from the vertical drum stack of 15 cm, 30 cm, 45 cm, and 90 cm. Data were acquired at scan speeds of 7.5 cm/s and 15 cm/s. The results of these scans and a comparison of these results with the manifests of these drums are compared and discussed

  18. 2010 Survey on long-term preservation of information and memory for geological disposal of radioactive waste

    International Nuclear Information System (INIS)

    2011-01-01

    Preservation of information and memory across generations is a cross-cutting theme of increasing importance for radioactive waste management. Because of the experience accumulated by the advanced national programmes that the RWMC represents, and the breadth of its related high-level initiatives, the Committee is uniquely placed internationally to combine resources and help develop state-of-the-art guidance on the long-term preservation of information and memory. In the context of fostering knowledge consolidation and transfer (KCT), the RWMC has already identified - in its reference document on KCT - the area of inter-generational transfer of knowledge as one of two areas needing development. In 2009, the RWMC decided to implement its programme of work in the area of information preservation and long-term memory as a series of projects or lines of actions opened by the RWMC and supervised by its Bureau. In order to better define its first series of projects the RWMC preformed a survey of its organisations needs and available materials and experience. At its meeting in 2010 the RWMC determined that the survey materials provided by organisations from 12 NEA countries constitute a good contribution to the literature in this field, and certainly to the upcoming projects. They provide as well a good baseline of information against which to measure progress a few years hence. This document reports the answers provided by organisations from 12 countries (Belgium, Canada, Finland, France, Hungary, Japan, Korea, Spain, Sweden, Switzerland, United Kingdom, and the USA,) to five questions related to long-term preservation of information and memory in the field of geological disposal. The questions are as follows: o What specific priority areas for long-term memory development have been identified in your agencies/countries? Which are the time scales of largest interest? o Do these priority proceed from good practice or/and from specific laws, regulations, policies exist in

  19. Operational and engineering developments in the management of low-level radioactive waste at the Idaho National Engineering Laboratory

    International Nuclear Information System (INIS)

    Kendall, E.W.; McKinney, J.D.; Wehmann, G.

    1979-01-01

    The Radioactive Waste Management Complex (RWMC) of the Idaho National Engineering Laboratory is a site for shallow land disposal and storage of solid radioactive waste. It is currently operated for ERDA by EG and G Idaho, Inc. The facility has accepted radioactive waste since July 1952. Both transuranic and non-transuranic wastes are handled at the complex. This document describes the operational and engineering developments in waste handling and storage practices that have been developed during the 25 years of waste handling operations. Emphasis is placed on above-ground transuranic waste storage, subsurface transuranic waste retrieval, and beta/gamma compaction disposal. The proposed future programs for the RWMC including a Molten Salt Combustion Facility and Production Scale Retrieval Project are described

  20. Field demonstration of in situ treatment of buried low-level radioactive solid waste with caustic soda and soda ash to immobilize 90Sr

    International Nuclear Information System (INIS)

    Spalding, B.P.

    1984-02-01

    A low-level radioactive solid waste disposal trench was injected on four occasions with solutions of caustic soda, soda ash, caustic soda, and lime/soda ash, respectively. Because investigations had indicated that 90 Sr could be coprecipitated with soil calcium carbonate by treatment with soda ash, this demonstration was undertaken as a test of its technical feasibility. After concentrations of 90 Sr and water hardness decreased within the intratrench monitoring wells; one well at the foot of the trench decreased from over 100 to a persistent level of less than 10 kBq of 90 Sr per liter. Recharge of 90 Sr from the trench to a sump immediately below was reduced by about 90%. Water hardness and 90 Sr concentrations were strongly correlated through time within each monitoring well, indicating that 90 Sr behaved as a tracer for soil calcium and magnesium. The disappearance of 90 Sr from the trench water, therefore, was an in situ water softening. Soil samples retrieved from the trench indicated that as much as 98% of the total 90 Sr was present as a coprecipitate with calcium carbonate. The hydrologic characterization of this trench indicated an average void space of 41% and an average trench-wall hydraulic conductivity of 3.4 x 10 -7 m/s. Sampling of the trench's discharge contamination plume indicated that it had resulted from a combination of subsurface seepage and bathtub overflow during infrequent periods of intense precipitation. A generic assessment of soda ash treatment indicated that treatment would be most effective for soils of high cation exchange capacity with either low ( 80%) basic cation saturation of that cation exchange capacity

  1. Update on Waste Management Policies and Programmes

    International Nuclear Information System (INIS)

    Anon.

    1988-01-01

    In addition to the regular items on national, international and NEA programme activities, this edition of the Bulletin contains two special contributions. First, a special editorial by Dr. Rudolf Rometsch, President of the Swiss National Cooperative for the Storage of Radioactive Waste (NAGRA) and current Chairman of the NEA Radioactive Waste Management Committee (RWMC), provides his personal reflections on the significance and relevance of the recent ''TRANSNUKLEAR AFFAIR'' to the waste management community. Secondly, the recently released Goguel Report from France is featured in the ''Topical Report'' section. This report provides a useful examination of site selection criteria for geological waste repositories [fr

  2. Performance of buried pipe installation.

    Science.gov (United States)

    2010-05-01

    The purpose of this study is to determine the effects of geometric and mechanical parameters : characterizing the soil structure interaction developed in a buried pipe installation located under : roads/highways. The drainage pipes or culverts instal...

  3. Failure analysis of buried tanks

    International Nuclear Information System (INIS)

    Watkins, R.K.

    1994-01-01

    Failure of a buried tank can be hazardous. Failure may be a leak through which product is lost from the tank; but also through which contamination can occur. Failures are epidemic -- because buried tanks are out of sight, but also because designers of buried tanks have adopted analyses developed for pressure tanks. So why do pressure tanks fail when they are buried? Most failures of buried tanks are really soil failures. Soil compresses, or slips, or liquefies. Soil is not only a load, it is a support without which the tank deforms. A high water table adds to the load on the tank. It also reduces the strength of the soil. Based on tests, structural analyses are proposed for empty tanks buried in soils of various quality, with the water table at various levels, and with internal vacuum. Failure may be collapse tank. Such collapse is a sudden, audible inversion of the cylinder when the sidefill soil slips. Failure may be flotation. Failure may be a leak. Most leaks are fractures in the welds in overlap seams at flat spots. Flat spots are caused by a hard bedding or a heavy surface wheel load. Because the tank wall is double thick at the overlap, shearing stress in the weld is increased. Other weld failures occur when an end plate shears down past a cylinder; or when the tank is supported only at its ends like a beam. These, and other, failures can be analyzed with justifiable accuracy using basic principles of mechanics of materials. 10 figs

  4. Continuum soil modeling in the static analysis of buried structures

    International Nuclear Information System (INIS)

    Julyk, L.J.; Marlow, R.S.; Moore, C.J.; Day, J.P.; Dyrness, A.D.

    1993-10-01

    Soil loading traditionally has been modeled as a hydrostatic pressure, a practice acceptable for many design applications. In the analyses of buried structure with predictive goals, soil compliance and load redistribution in the presence of soil plasticity are important factors to consider in determining the appropriate response of the structure. In the analysis of existing buried waste-storage tanks at the US Department of Energy's Hanford Site, three soil-tank interaction modeling considerations are addressed. First, the soil interacts with the tank as the tank expands and contracts during thermal cycles associated with changes in the heat generated by the waste material as a result of additions and subtractions of the waste. Second, the soil transfers loads from the surface to the tank and provides support by resisting radial displacement of the tank haunch. Third, conventional finite-element mesh development causes artificial stress concentrations in the soil associated with differential settlement

  5. Buried oxide layer in silicon

    Science.gov (United States)

    Sadana, Devendra Kumar; Holland, Orin Wayne

    2001-01-01

    A process for forming Silicon-On-Insulator is described incorporating the steps of ion implantation of oxygen into a silicon substrate at elevated temperature, ion implanting oxygen at a temperature below 200.degree. C. at a lower dose to form an amorphous silicon layer, and annealing steps to form a mixture of defective single crystal silicon and polycrystalline silicon or polycrystalline silicon alone and then silicon oxide from the amorphous silicon layer to form a continuous silicon oxide layer below the surface of the silicon substrate to provide an isolated superficial layer of silicon. The invention overcomes the problem of buried isolated islands of silicon oxide forming a discontinuous buried oxide layer.

  6. Locating a buried magnetic dipole

    Energy Technology Data Exchange (ETDEWEB)

    Caffey, T.W.H.

    1977-01-01

    The theoretical basis and required computations for locating a buried magnetic dipole are outlined. The results are compared with measurements made with a tiltable coil lowered to a depth of 20 m in a vertical borehole within a three-layered earth. this work has application to the rescue of trapped miners. 3 figures, 1 table. (RWR)

  7. The Buried Town of Beaver.

    Science.gov (United States)

    Jostad, Karen

    Local history as source material for environmental education is uniquely portrayed in this resource kit. Utilizing a Winona County Historical Society publication, "The Beaver Story" and accompanied by a teacher's guide, "The Buried Town of Beaver," and other teaching aids, a case study of the area can be developed. Based on the reminiscences of…

  8. Design of buried concrete encasements

    International Nuclear Information System (INIS)

    Drake, R.M.

    1989-01-01

    The operation of many Department of Energy (DOE) sites requires the transfer of radioactive liquid products from one location to another. DOE Order 6430.1A requires that the transfer pipelines be designed and constructed so that any leakage can be detected and contained before it reaches the environment. One design option often considered to meet this requirement is to place the pipeline in a stainless steel-lined, buried concrete encasement. This provides the engineer with the design challenge to integrate standard structural design principles with unique DOE requirements. The complete design of a buried concrete encasement must consider seismic effects, leak detection, leak confinement, radiation shielding, thermal effects, pipe supports, and constructability. This paper contains a brief discussion of each of these design considerations, based on experience gained during the design of concrete encasements for the Process Facilities Modifications (PFM) project at Hanford

  9. Vadose zone monitoring at the Radioactive Waste Management Complex at the Idaho National Engineering Laboratory, 1985--1989

    International Nuclear Information System (INIS)

    McElroy, D.L.

    1990-12-01

    Vadose zone monitoring at the Radioactive Waste Management Complex (RWMC) of the Idaho National Engineering Laboratory (INEL) was implemented under the Subsurface Investigation Program Plan. The objective of the Subsurface Investigation Program was to characterize the subsurface at the RWMC in order to measure and predict radionuclide transport. Soil moisture sensors were installed to characterize the uniformity of water entry to the surficial sediments and moisture flux in the surficial sediments and the deeper stratigraphic units. From 1985 to 1987, a network of vadose zone instruments was installed in sediments at the RWMC. The instruments included psychrometers, gypsum blocks, heat-dissipation sensors (HDSs), tensiometers, lysimeters, and neutron access tubes. These instruments were placed at depths up to 230 ft below land surface (BLS) in a heterogeneous geologic system comprised of sediments that overlie and are intercalated with basalt flows. After organic contaminants were detected in the subsurface at the RWMC in 1988, the vadose zone monitoring project was incorporated into a broader characterization effort. This report presents the analyses of the vadose zone monitoring data collected from FY-1985 to FY-1989. The performance of the instruments are compared. Matric potential ranges and trends in the surficial sediments and interbeds are discussed. Hydraulic gradients are calculated to determine the direction of moisture movement. Using the neutron logging data in conjunction with the matric potential and hydraulic gradient data, infiltration is examined with respect to seasonal nature and source. 14 refs., 19 figs., 4 tabs

  10. Commercial disposal options for Idaho National Engineering Laboratory low-level radioactive waste

    International Nuclear Information System (INIS)

    Porter, C.L.; Widmayer, D.A.

    1995-09-01

    The Idaho National Engineering Laboratory (INEL) is a Department of Energy (DOE)-owned, contractor-operated site. Significant quantities of low-level radioactive waste (LLW) have been generated and disposed of onsite at the Radioactive Waste Management Complex (RWMC). The INEL expects to continue generating LLW while performing its mission and as aging facilities are decommissioned. An on-going Performance Assessment process for the RWMC underscores the potential for reduced or limited LLW disposal capacity at the existing onsite facility. In order to properly manage the anticipated amount of LLW, the INEL is investigating various disposal options. These options include building a new facility, disposing the LLW at other DOE sites, using commercial disposal facilities, or seeking a combination of options. This evaluation reports on the feasibility of using commercial disposal facilities

  11. BATATA: a buried muon hodoscope

    International Nuclear Information System (INIS)

    Sanchez, F.; Supanitsky, A. D.; Medina-Tanco, G.; Paic, G.; Salazar, M. E. Patino; D'Olivo, J. C.; Molina, R. Alfaro

    2009-01-01

    Muon hodoscopes have several applications, ranging from astrophysics to fundamental particle physics. In this work, we present a detector dedicated to the study, at ground level, of the main signals of cosmic-ray induced showers above 6 PeV. The whole detector is composed by a set of three parallel dual-layer scintillator planes buried at fix depths ranging from 120 g/cm 2 to 600 g/cm 2 and by a triangular array of water cerenkov detectors located nearby on ground.

  12. Fire hazards analysis of the Radioactive Waste Management Complex Air Support Buildings

    Energy Technology Data Exchange (ETDEWEB)

    Davis, M.L.; Satterwhite, D.G.

    1989-09-01

    This report describes the methods, analyses, results, and conclusions of a fire hazards risk analysis performed for the RWMC Air Support Buildings. An evaluation of the impact for adding a sprinkler system is also presented. Event and fault trees were used to model and analyze the waste storage process. Tables are presented indicating the fire initiators providing the highest potential for release of radioactive materials into the environment. Engineering insights drawn form the data are also provided.

  13. Environmental surveillance for the INEL Radioactive-Waste-Management complex. Annual report 1981

    International Nuclear Information System (INIS)

    Janke, D.H.; Zahn, T.P.

    1982-09-01

    The 1981 environmental surveillance report for the Radioactive Waste Management Complex of the Idaho National Engineering Laboratory contains data and discussions about routine radiological monitoring of the atmospheric, hydrologic, and geologic environments of the RWMC. Additional discussions include results of routine monitoring of two surplus facilities, the Stationary Low-Power Reactor No. 1 Surplus Area and the Organic Moderated Reactor Experiment. Each area has produced localized effects on the environment, but containment is well within the INEL site boundary

  14. Fire hazards analysis of the Radioactive Waste Management Complex Air Support Buildings

    International Nuclear Information System (INIS)

    Davis, M.L.; Satterwhite, D.G.

    1989-09-01

    This report describes the methods, analyses, results, and conclusions of a fire hazards risk analysis performed for the RWMC Air Support Buildings. An evaluation of the impact for adding a sprinkler system is also presented. Event and fault trees were used to model and analyze the waste storage process. Tables are presented indicating the fire initiators providing the highest potential for release of radioactive materials into the environment. Engineering insights drawn form the data are also provided

  15. Inspection device for buried equipment

    International Nuclear Information System (INIS)

    Hanawa, Jun.

    1994-01-01

    In an inspection device for a buried equipment, a rail is suspended at the upper portion of a vessel of a pit-vessel type pump buried in a plant building floor, and a truck movable vertical in the vessel along the rail, and an ultrasonic wave probe contained in the truck and urged to the vessel by an electromagnet are disposed. In addition, an elevator moving vertically along a shaft is disposed, and an arm having the ultrasonic probe disposed at the end portion and driven by a piston are disposed to the elevator. The ultrasonic wave probe moves vertically together with the truck along the rail in the vessel while being urged to the vessel by the electromagnet to inspect and measure the state at the inner and outer surfaces of the vessel. Further, the length of the arm is controlled so as to set a predetermined distance between the ultrasonic wave probe and the vessel. Subsequently, the elevator is moved vertically along a shaft passing through a shaft hole of a mount, and the shaft is rotated thereby enabling to inspect and measure the state of the inner and outer surfaces of the vessel. (N.H.)

  16. Buried penis: classification surgical approach.

    Science.gov (United States)

    Hadidi, Ahmed T

    2014-02-01

    The purpose of this study was to describe morphological classification of congenital buried penis (BP) and present a versatile surgical approach for correction. Sixty-one patients referred with BP were classified into 3 grades according to morphological findings: Grade 1-29 patients with Longer Inner Prepuce (LIP) only, Grade II-20 patients who presented with LIP associated with indrawn penis that required division of the fundiform and suspensory ligaments, and Grade III-12 patients who had in addition to the above, excess supra-pubic fat. A ventral midline penile incision extending from the tip of prepuce down to the penoscrotal junction was used in all patients. The operation was tailored according to the BP Grade. All patients underwent circumcision. Mean follow up was 3 years (range 1 to 10). All 61 patients had an abnormally long inner prepuce (LIP). Forty-seven patients had a short penile shaft. Early improvement was noted in all cases. Satisfactory results were achieved in all 29 patients in grade I and in 27 patients in grades II and III. Five children (Grades II and III) required further surgery (9%). Congenital buried penis is a spectrum characterized by LIP and may include in addition; short penile shaft, abnormal attachment of fundiform, and suspensory ligaments and excess supra-pubic fat. Congenital Mega Prepuce (CMP) is a variant of Grade I BP, with LIP characterized by intermittent ballooning of the genital area. Copyright © 2014 Elsevier Inc. All rights reserved.

  17. Environmental surveillance for the EG and G Idaho Radioactive Waste Management areas at the Idaho National Engineering Laboratory. Annual report 1985

    International Nuclear Information System (INIS)

    Reyes, B.D.; Case, M.J.; Wilhelmsen, R.N.

    1986-08-01

    The 1985 environmental surveillance report for the EG and G Idaho, Inc., radioactive waste management areas at the Idaho National Engineering Laboratory describes the environmental monitoring activities at the Radioactive Waste Management Complex (RWMC), the Waste Experimental Reduction Facility (WERF), the Process Experimental Pilot Plant (PREPP), and two surplus facilities. The purpose of these monitoring activities is to provide for continuous evaluation and awareness of environmental conditions resulting from current operations, to detect significant trends, and to project possible future conditions. This report provides a public record comparing RWMC, WERF, PREPP, and surplus facility environmental data with past results and radiation protection standards or concentration guides established for operation of Department of Energy facilities

  18. Technical report from Radioactive Waste Management Funding and Research Center

    International Nuclear Information System (INIS)

    2007-10-01

    As the only one Japanese organization specialized in radioactive waste, RWMC (Radioactive Waste Management Funding and Research Center) has been conducting the two major roles; R and D and the fund administration for radioactive waste management. The focus of its studies includes land disposal of LLW (Low-level radioactive wastes) and it has gradually extended to research on management and disposal techniques for high-level (HLW) and TRU wastes and studies on securing and managing the funds required for disposal of these wastes. The present document is the yearly progress report of 2006 and the main activities and research results are included on spent fuel disposal techniques including radon diffusion and emanation problem, performance studies on underground facilities for radioactive waste disposal and its management, technical assessment for geological environment, remote control techniques, artificial barrier systems proposed and its monitoring systems, and TRU disposals. (S. Ohno)

  19. 4th Quarter Transportation Report FY 2014: Radioactive Waste Shipments to and from the Nevada National Security Site (NNSS)

    International Nuclear Information System (INIS)

    Gregory, Louis

    2014-01-01

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

  20. The diffusion of buried matter and possible pollution of aquifers in presence of hydrodynamic dispersion

    International Nuclear Information System (INIS)

    Bestman, A.R.

    1990-11-01

    The problem of diffusion of buried waste in a moist soil is formulated in cylindrical coordinates and solved by means of integral transform techniques after appropriate asymptotic approximations. The model is then used to predict the possible contamination of aquifers situated at a given depth. (author). 2 refs, 2 figs

  1. Surgical treatment of buried penis.

    Science.gov (United States)

    Lipszyc, E; Pfister, C; Liard, A; Mitrofanoff, P

    1997-10-01

    The buried penis is a rare congenital entity, whose treatment is surgical. There are few publications concerning this matter. The authors report on their experience in 10 cases (1990-1995). In this abnormality, the tip of the glans does not project from the pubic or scrotal skin. It is due to: 1) an excessive development of the penile fascia which retracts the penis; 2) insufficient attachment of the penile skin at the base of the penis; 3) often excessive prepubic fat worsens the appearance of the abnormality but does not by itself totally explain it; 4) a tight phimosis is often present. Surgical treatment is necessary because this aspect tends to persist even after puberty. One cannot indeed count on the development at the age of puberty, neither on the diminution of the fat, nor on the simple cure of the phimosis. One must above all ban circumcision which causes the risk of eliminating the skin necessary for reconstruction. The surgical procedure will comprise: 1) a longitudinal dorsal incision extended circumferentially; 2) resection of the thickened fascia penis; 3) anchoring of the deep face of the dermis to the proximal part of the fascia penis at the base of the penis. This surgical procedure has always brought a significant improvement to the appearance of the penis.

  2. Decomposition of forest products buried in landfills

    International Nuclear Information System (INIS)

    Wang, Xiaoming; Padgett, Jennifer M.; Powell, John S.; Barlaz, Morton A.

    2013-01-01

    Highlights: • This study tracked chemical changes of wood and paper in landfills. • A decomposition index was developed to quantify carbohydrate biodegradation. • Newsprint biodegradation as measured here is greater than previous reports. • The field results correlate well with previous laboratory measurements. - Abstract: The objective of this study was to investigate the decomposition of selected wood and paper products in landfills. The decomposition of these products under anaerobic landfill conditions results in the generation of biogenic carbon dioxide and methane, while the un-decomposed portion represents a biogenic carbon sink. Information on the decomposition of these municipal waste components is used to estimate national methane emissions inventories, for attribution of carbon storage credits, and to assess the life-cycle greenhouse gas impacts of wood and paper products. Hardwood (HW), softwood (SW), plywood (PW), oriented strand board (OSB), particleboard (PB), medium-density fiberboard (MDF), newsprint (NP), corrugated container (CC) and copy paper (CP) were buried in landfills operated with leachate recirculation, and were excavated after approximately 1.5 and 2.5 yr. Samples were analyzed for cellulose (C), hemicellulose (H), lignin (L), volatile solids (VS), and organic carbon (OC). A holocellulose decomposition index (HOD) and carbon storage factor (CSF) were calculated to evaluate the extent of solids decomposition and carbon storage. Samples of OSB made from HW exhibited cellulose plus hemicellulose (C + H) loss of up to 38%, while loss for the other wood types was 0–10% in most samples. The C + H loss was up to 81%, 95% and 96% for NP, CP and CC, respectively. The CSFs for wood and paper samples ranged from 0.34 to 0.47 and 0.02 to 0.27 g OC g −1 dry material, respectively. These results, in general, correlated well with an earlier laboratory-scale study, though NP and CC decomposition measured in this study were higher than

  3. Decomposition of forest products buried in landfills

    Energy Technology Data Exchange (ETDEWEB)

    Wang, Xiaoming, E-mail: xwang25@ncsu.edu [Department of Civil, Construction, and Environmental Engineering, Campus Box 7908, North Carolina State University, Raleigh, NC 27695-7908 (United States); Padgett, Jennifer M. [Department of Civil, Construction, and Environmental Engineering, Campus Box 7908, North Carolina State University, Raleigh, NC 27695-7908 (United States); Powell, John S. [Department of Chemical and Biomolecular Engineering, Campus Box 7905, North Carolina State University, Raleigh, NC 27695-7905 (United States); Barlaz, Morton A. [Department of Civil, Construction, and Environmental Engineering, Campus Box 7908, North Carolina State University, Raleigh, NC 27695-7908 (United States)

    2013-11-15

    Highlights: • This study tracked chemical changes of wood and paper in landfills. • A decomposition index was developed to quantify carbohydrate biodegradation. • Newsprint biodegradation as measured here is greater than previous reports. • The field results correlate well with previous laboratory measurements. - Abstract: The objective of this study was to investigate the decomposition of selected wood and paper products in landfills. The decomposition of these products under anaerobic landfill conditions results in the generation of biogenic carbon dioxide and methane, while the un-decomposed portion represents a biogenic carbon sink. Information on the decomposition of these municipal waste components is used to estimate national methane emissions inventories, for attribution of carbon storage credits, and to assess the life-cycle greenhouse gas impacts of wood and paper products. Hardwood (HW), softwood (SW), plywood (PW), oriented strand board (OSB), particleboard (PB), medium-density fiberboard (MDF), newsprint (NP), corrugated container (CC) and copy paper (CP) were buried in landfills operated with leachate recirculation, and were excavated after approximately 1.5 and 2.5 yr. Samples were analyzed for cellulose (C), hemicellulose (H), lignin (L), volatile solids (VS), and organic carbon (OC). A holocellulose decomposition index (HOD) and carbon storage factor (CSF) were calculated to evaluate the extent of solids decomposition and carbon storage. Samples of OSB made from HW exhibited cellulose plus hemicellulose (C + H) loss of up to 38%, while loss for the other wood types was 0–10% in most samples. The C + H loss was up to 81%, 95% and 96% for NP, CP and CC, respectively. The CSFs for wood and paper samples ranged from 0.34 to 0.47 and 0.02 to 0.27 g OC g{sup −1} dry material, respectively. These results, in general, correlated well with an earlier laboratory-scale study, though NP and CC decomposition measured in this study were higher than

  4. A summary of the environmental restoration program Retrieval Demonstration Project at the Idaho National Engineering Laboratory

    International Nuclear Information System (INIS)

    McQuary, J.

    1991-01-01

    This document summarizes the of retrieval techniques developed to excavate buried transuranic (TRU) mixed waste from the Subsurface Disposal Area (SDA). The SDA is located at the Idaho National Engineering Laboratory (INEL) in the Radioactive Waste Management Complex (RWMC). 31 refs., 1 fig

  5. Performance evaluation of buried pipe installation.

    Science.gov (United States)

    2010-05-01

    The purpose of this study is to determine the effects of geometric and mechanical parameters characterizing the soil structure interaction developed in a buried pipe installation located under roads/highways. The drainage pipes or culverts installed ...

  6. 47 CFR 32.2423 - Buried cable.

    Science.gov (United States)

    2010-10-01

    ... FOR TELECOMMUNICATIONS COMPANIES Instructions for Balance Sheet Accounts § 32.2423 Buried cable. (a... of cleaning manholes and ducts in connection with construction work and the cost of permits and...

  7. RCRA Part A and Part B Permit Application for Waste Management Activities at the Nevada Test Site: Proposed Mixed Waste Disposal Unit (MWSU)

    Energy Technology Data Exchange (ETDEWEB)

    NSTec Environmental Management

    2010-07-19

    The proposed Mixed Waste Storage Unit (MWSU) will be located within the Area 5 Radioactive Waste Management Complex (RWMC). Existing facilities at the RWMC will be used to store low-level mixed waste (LLMW). Storage is required to accommodate offsite-generated LLMW shipped to the Nevada Test Site (NTS) for disposal in the new Mixed Waste Disposal Unit (MWDU) currently in the design/build stage. LLMW generated at the NTS (onsite) is currently stored on the Transuranic (TRU) Pad (TP) in Area 5 under a Mutual Consent Agreement (MCA) with the Nevada Division of Environmental Protection, Bureau of Federal Facilities (NDEP/BFF). When the proposed MWSU is permitted, the U.S. Department of Energy (DOE) will ask that NDEP revoke the MCA and onsite-generated LLMW will fall under the MWSU permit terms and conditions. The unit will also store polychlorinated biphenyl (PCB) waste and friable and non-friable asbestos waste that meets the acceptance criteria in the Waste Analysis Plan (Exhibit 2) for disposal in the MWDU. In addition to Resource Conservation and Recovery Act (RCRA) requirements, the proposed MWSU will also be subject to Department of Energy (DOE) orders and other applicable state and federal regulations. Table 1 provides the metric conversion factors used in this application. Table 2 provides a list of existing permits. Table 3 lists operational RCRA units at the NTS and their respective regulatory status.

  8. RCRA Part A and Part B Permit Application for Waste Management Activities at the Nevada Test Site: Proposed Mixed Waste Disposal Unit (MWSU)

    International Nuclear Information System (INIS)

    2010-01-01

    The proposed Mixed Waste Storage Unit (MWSU) will be located within the Area 5 Radioactive Waste Management Complex (RWMC). Existing facilities at the RWMC will be used to store low-level mixed waste (LLMW). Storage is required to accommodate offsite-generated LLMW shipped to the Nevada Test Site (NTS) for disposal in the new Mixed Waste Disposal Unit (MWDU) currently in the design/build stage. LLMW generated at the NTS (onsite) is currently stored on the Transuranic (TRU) Pad (TP) in Area 5 under a Mutual Consent Agreement (MCA) with the Nevada Division of Environmental Protection, Bureau of Federal Facilities (NDEP/BFF). When the proposed MWSU is permitted, the U.S. Department of Energy (DOE) will ask that NDEP revoke the MCA and onsite-generated LLMW will fall under the MWSU permit terms and conditions. The unit will also store polychlorinated biphenyl (PCB) waste and friable and non-friable asbestos waste that meets the acceptance criteria in the Waste Analysis Plan (Exhibit 2) for disposal in the MWDU. In addition to Resource Conservation and Recovery Act (RCRA) requirements, the proposed MWSU will also be subject to Department of Energy (DOE) orders and other applicable state and federal regulations. Table 1 provides the metric conversion factors used in this application. Table 2 provides a list of existing permits. Table 3 lists operational RCRA units at the NTS and their respective regulatory status.

  9. Discarding processing method for radioactive waste

    International Nuclear Information System (INIS)

    Komura, Shiro; Kato, Hiroaki; Hatakeyama, Takao; Oura, Masato.

    1992-01-01

    At first, in a discrimination step, extremely low level radioactive wastes are discriminated to metals and concretes and further, the metal wastes are discriminated to those having hollow portions and those not having hollow portions, and the concrete wastes are discriminated to those having block-like shape and those having other shapes respectively. Next, in a processing step, the metal wastes having hollow portions are applied with cutting, devoluming or packing treatment and block-like concrete wastes are applied with surface solidification treatment, and concrete wastes having other shapes are applied with crushing treatment respectively. Then, the extremely low level radioactive wastes contained in a container used exclusively for transportation are taken out, in a movable burying facility with diffusion inhibiter kept at a negative pressure as required, in a field for burying operation, and buried in a state that they are isolated from the outside. Accordingly, they can be buried safely and efficiently. (T.M.)

  10. The Blackfoot 111 buried geophone experiment

    Energy Technology Data Exchange (ETDEWEB)

    Cieslewicz, D.; Lawton, D.C. [Calgary Univ., AB (Canada). Dept. of Geology and Geophysics

    1999-07-01

    As an important difference between a VSP and a conventional survey is the presence of the near-surface layer in the latter, it is possible that overburden materials are particularly attenuative to shear waves, causing an observed narrower bandwidth of converted waves in a seismic experiment conducted in the Blackfoot oil field. The Blackfoot III buried geophone experiment tested this hypothesis by recording data with three component geophones buried to various depths in the near surface. By avoiding a portion of the near surface, buried geophones might avoid a certain amount of attenuation, resulting in a better bandwidth and hence vertical resolution for P-S reflections in particular. Accessory seismic studies of near-surface velocity and impedance were made using the buried geophone data, made possible by the unique geometry of the experiment. The P-P processed data had comparable data quality at all geophone depths, whereas the processed surface P-S data had superior quality over data from the buried phones. This was a result of greater amounts of mode leakage and lower raw reflection amplitudes in the buried phones. No systematic improvement in P-S or P-P reflection bandwidth was noted for deeper geophones; inconsistent geophone coupling was partly a factor in this observation. Raw reflection amplitudes through the near surface are controlled mainly by the impedance of near-surface sediments. Near-surface velocities are typical for unconsolidated overburden for the western 2/3 of the buried receiver line, but increases to values more typical of unweathered bedrock for the eastern 1/3. This probably shows a thinning of the overburden layer in this area. 2 refs.

  11. Characterization of INEL compactible wastes, compactor options study, and recommendations

    International Nuclear Information System (INIS)

    Gillins, R.L.; Larsen, M.M.; Aldrich, W.C.

    1986-03-01

    This report provides the results of a detailed characterization and evaluation of low-level radioactive waste generated at the Idaho National Engineering Laboratory (INEL) and an evaluation of compactors available commercially. The results of these evaluations formed the basis for a study of compactor options suitable for compacting INEL-generated low-level waste. Seven compactor options were evaluated. A decision analysis performed on the results of the compactor option study and cost analysis showed that a 200-ton box compactor and a 5000-ton box supercompactor were the best options for an INEL compaction facility other than the RWMC. Two compactor locations were considered: WERF and CPP. The WERF location is recommended on the basis of existing facilities to house the compactor and store the waste, the presence of a trained waste-handling staff, and the desirability of maintaining a single location for processing INEL-generated low-level waste

  12. Concealed epispadias associated with a buried penis.

    Science.gov (United States)

    Sol Melgar, Ricardo; Gorduza, Daniela; Demède, Delphine; Mouriquand, Pierre

    2016-12-01

    The aim was to describe the clinical presentation and the surgical management of penile epispadias associated with a buried penis in five children. This is a 5-year retrospective review of patients presenting with a buried penis, a congenital defect of the penile skin shaft associated with an unretractable foreskin for whom a penile epispadias was found at the time of surgery. All had undergone surgery combining a Cantwell-Ransley procedure and refashioning of the penile skin following the authors' technique. Three children had a glanular epispadias and two had a midshaft epispadias. Four had a satisfactory outcome, and one required a complementary urethroplasty for glanular dehiscence. Buried penis and epispadias are usually isolated congenital anomalies, although they can be associated. It is therefore recommended to warn parents about the possibility of underlying penile anomaly in children with buried penises and unretractable foreskin. Careful palpation of the dorsum of the glans through the foreskin looking for a dorsal cleft could indicate an associated epispadiac urethra. Surgical correction of both anomalies can be done at the same time. Parents of boys with buried penises should be warned that underlying penile anomaly may exist. Copyright © 2016 Journal of Pediatric Urology Company. Published by Elsevier Ltd. All rights reserved.

  13. The environmental and ethical basis of the geological disposal of long-lived radioactive waste

    International Nuclear Information System (INIS)

    Vuori, S.

    1995-01-01

    This partial translation into Finnish of the recently issued Collective Opinion of the Radioactive Waste Management Committee (RWMC) of the OECD Nuclear Energy Agency is published here to provide general information to the members of the Finnish Nuclear Society. Full translation will be published later by the Ministry of Trade and Industry. The collective opinion addresses the strategy for the final disposal of long-lived radioactive wastes seen from an environmental and ethical perspective, including considerations of equity and fairness within and between generations

  14. Buried Landmines in Libya and Detection Technologies

    International Nuclear Information System (INIS)

    El-Bakkoush, F.A.

    2015-01-01

    In this Article, presentation and discussion of the impact of detonated buried land mines in vast areas of land in Libya are given, especially from economical and social point of view. The methods and techniques which are currently used to allocate the positions of buried land mines during de mining operations are mentioned and discussed with emphasize on their strength and weakness. These include mechanical removing methods, prodders, metal detectors, ground penetrating radar and sniffing dogs. Furthermore, the novel and most developed detection techniques invented to detect land mines using SQUDS and neutron techniques based on thermal neutron backscattering and elemental analysis by fast and thermal neutrons are given and discussed.

  15. Radioactive waste management and decommissioning at the NEA

    International Nuclear Information System (INIS)

    2010-11-01

    The OECD Nuclear Energy Agency (NEA) seeks to assist its member countries in developing safe, sustainable and societally acceptable strategies for the management of all types of radioactive materials, with particular emphasis on the management of long-lived waste and spent fuel and on decommissioning of disused nuclear facilities. The programme of work in these areas is carried out for the most part by the Radioactive Waste Management Committee (RWMC) assisted by three working parties: - The Forum on Stakeholder Confidence (FSC). - The Integration Group for the Safety Case (IGSC). - The Working Party on Decommissioning and Dismantling (WPDD). Other NEA Committees also have interests in this field: the Committee on Radiation Protection and Public Health (CRPPH) and the Nuclear Development Committee (NDC). The OECD/NEA is at the forefront in addressing both the technical and societal requirements for durable and sustainable waste management and decommissioning solutions. Through the RWMC it provides a neutral forum where policy makers, regulators and implementing organisations can discuss issues of common interest and develop solutions that meet the diverse needs of its member countries

  16. Wastes

    International Nuclear Information System (INIS)

    Bovard, Pierre

    The origin of the wastes (power stations, reprocessing, fission products) is determined and the control ensuring the innocuity with respect to man, public acceptance, availability, economics and cost are examined [fr

  17. Burying nuclear trash where it will stay put. Second of four articles

    International Nuclear Information System (INIS)

    Faltermayer, E.

    1979-01-01

    The issue of radioactive waste disposal threatening the growth of fission power is discussed. The challenge of burying such waste material has turned into an emotional debate by alarmists and it is feared that the government, which is responsible for waste disposal, may foul the job; e.g., the burial of wastes from atomic weapons programs has been postponed, and wastes have leaked into the ground from poorly designed temporary storage tanks. California, Maine, Wisconsin, and Iowa have imposed moratoria on new reactor starts until a satisfactory method of waste disposal has been demonstrated. The first demonstration of deep burial is scheduled for the mid- or late 1980s in a salt deposit near Carlsbad, New Mexico. The Federal government will then have to decide where to put permanent repositories, and 9 states have prohibited the burial of radioactive wastes within their borders. It takes centuries for radioactives wastes to decay, but they do decay. The industrial world routinely uses hundreds of dangerous materials (mercury, arsenic, etc.) that stay at full strength forever. These are usually dumped carelessly. Radioactive waste disposal will be far underground and sites carefully chosen. Some opponents of fission power agree that radioactive wastes can be interred safely. The only reason for hurrying a demonstration burial of reactor wastes is political. It would undercut the moratorium movement, and it will be at least 10 years before the results can be appraised. Various rock formations for storage have been assessed, with emphasis on the thick, flat beds of salt in Southwest US. Muchenergy remains in radioactive wastes, leading the author to say that burying fuel is foolish, since it may later have to be exhumed

  18. Supplement analysis of transuranic waste characterization and repackaging activities at the Idaho National Engineering Laboratory in support of the Waste Isolation Pilot Plant test program

    International Nuclear Information System (INIS)

    1991-03-01

    This supplement analysis has been prepared to describe new information relevant to waste retrieval, handling, and characterization at the Idaho National Engineering Laboratory (INEL) and to evaluate the need for additional documentation to satisfy the National Environmental Policy Act (NEPA). The INEL proposes to characterize and repackage contact-handled transuranic waste to support the Waste Isolation Pilot Plant (WIPP) Test Phase. Waste retrieval, handling and processing activities in support of test phase activities at the WIPP were addressed in the Supplemental Environmental Impact Statement (SEIS) for the WIPP. To ensure that test-phase wastes are properly characterized and packaged, waste containers would be retrieved, nondestructively examined, and transported from the Radioactive Waste Management Complex (RWMC) to the Hot-Fuel Examination Facility for headspace gas analysis, visual inspections to verify content code, and waste acceptance criteria compliance, then repackaging into WIPP experimental test bins or returned to drums. Following repackaging the characterized wastes would be returned to the RWMC. Waste characterization would help DOE determine WIPP compliance with US Environmental Protection Agency regulations governing disposal of transuranic waste and hazardous waste. Additionally, this program supports onsite compliance with Resource Conservation and Recovery Act (RCRA) requirements, compliance with the terms of the No-Migration Variance at WIPP, and provides data to support future waste shipments to WIPP. This analysis will help DOE determine whether there have been substantial changes made to the proposed action at the INEL, or if preparation of a supplement to the WIPP Final Environmental Impact Statement (DOE, 1980) and SEIS (DOE, 1990a) is required. This analysis is based on current information and includes details not available to the SEIS

  19. 7 CFR 1755.505 - Buried services.

    Science.gov (United States)

    2010-01-01

    ... using the recommendations in RUS Bulletin 1751F-640, “Design of Buried Plant—Physical Considerations... water, oil, sewer) and structures 4 2 [50.8] Wires or cables of another communications system 2 [50.8] 1... wire or cable size and type of surface shall be in accordance with the manufacturer's recommendation...

  20. Analysis of buried pipelines at Kozloduy

    International Nuclear Information System (INIS)

    Asfura, A.

    1999-01-01

    This paper describes the analysis of the buried pipelines at Kozloduy NPP. It involves the description of the studied pipelines, their properties, a detailed description of the methodology applied, and the evaluation of the soil strain field as well as the graphical representation of the results obtained

  1. Detection of Buried Objects : The MUD Project

    NARCIS (Netherlands)

    Quesson, B.A.J.; Vossen, R. van; Zampolli, M.; Beckers, A.L.D.

    2011-01-01

    The aim of the Mine Underwater Detection (MUD) project at TNO is to experimentally investigate the acoustic and magnetic detection of explosives underwater, buried in a soft sediment layer. This problem is relevant for the protection of harbors and littoral assets against terrorist attacks and for

  2. Micromachining of buried micro channels in silicon

    NARCIS (Netherlands)

    de Boer, Meint J.; Tjerkstra, R.W.; Berenschot, Johan W.; Jansen, Henricus V.; Burger, G.J.; Burger, G.J.; Gardeniers, Johannes G.E.; Elwenspoek, Michael Curt; van den Berg, Albert

    A new method for the fabrication of micro structures for fluidic applications, such as channels, cavities, and connector holes in the bulk of silicon wafers, called buried channel technology (BCT), is presented in this paper. The micro structures are constructed by trench etching, coating of the

  3. Summary of INEL research on the iron-enriched basalt waste form

    International Nuclear Information System (INIS)

    Reimann, G.A.; Grandy, J.D.; Eddy, T.L.; Anderson, G.L.

    1992-01-01

    This report summarizes the knowledge base on the iron-enriched basalt (IEB) waste form developed at the Idaho National Engineering Laboratory (INEL) during 1979--1982. The results presented discuss the applicability of IEB in converting retrieved transuranic (TRU) waste from INEL's Radioactive Waste Management Complex (RWMC) into a vitreous/ceramic (glassy/rock) stable waste form suitable for permanent disposal in an appropriate repository, such as the Waste Isolation Pilot Plant (WIPP) in New Mexico. Borosilicate glass (BSG), the approved high-level waste form, appears unsuited for this application. Melting the average waste-soil mix from the RWMC produces the IEB composition and attempting to convert IEB to the BSG composition would require additions of substantial B 2 0 3 , Na, and SiO 2 (glass frit). IEB requires processing temperatures of 1400 to 1600 degrees C, depending upon the waste composition. Production of the IEB waste form, using Joule heated melters, has proved difficult in the past because of electrode and refractory corrosion problems associated with the high temperature melts. Higher temperature electric melters (arc and plasma) are available to produce this final waste form. Past research focused on extensive slag property measurements, waste form leachability tests, mechanical, composition, and microstructure evaluations, as well as a host of experiments to improve production of the waste form. Past INEL studies indicated that the IEB glass-ceramic is a material that will accommodate and stabilize a wide range of heterogeneous waste materials, including long lived radionuclides and scrap metals, while maintaining a superior level of chemical and physical performance characteristics. Controlled cooling of the molten IEB and subsequent heat treatment will produce a glass-ceramic waste form with superior leach resistance

  4. Determination of acceleration and stabilization indicators for buried municipal wastes. Study of leachates recirculation impact on waste columns; Determination d'indicateurs d'acceleration et de stabilisation de dechets menagers enfouis. Etude de l'impact de la recirculation de lixiviats sur colonnes de dechets

    Energy Technology Data Exchange (ETDEWEB)

    Francois, V.

    2004-05-15

    The main goal of this research work was to study the stabilisation processes of municipal solid waste (MSW). Representative parameters, which are required to evaluate the stabilization state of wastes, were applied to study the acceleration of the degradation processes in lab-scale landfill anaerobic bioreactors operated with leachate recirculation. The characterisation of the wastes solid phase (i.e., volatile solids, organic carbon, fines, paper-cardboard and degraded component contents) is necessary to assess its degradation state. However, additional parameters are required such as the characterisation of water extracted from the waste (i.e., Chemical Oxygen Content (COD), Dissolved Oxygen Content (DOC) and ions content) and biogas composition (methane potential). Those parameters are nevertheless complementary to conclude on its polluting feature. The analysis of more specific indicators such as the organic macromolecules content in leachates and the evaluation of the metal contamination level in solid waste and its potential remobilization was showed to be consistent for the evaluation of waste stabilisation state. The composition of leachates used during recirculation influences greatly the waste leaching behaviour. For instance, the recirculation of a stabilised leachate containing organic macromolecules can increase the release of pollutants (organics and minerals) if contacted with young waste or on the other hand the release of pollutant is reduced when the leachate composition is similar to the organic species, which are expected to be released by the wastes. Due to the experimental limits of the leaching tests, several lab-scale landfill anaerobic bioreactors containing different wastes types (height of 1 m and mass of waste varying from 28 kg to 65 kg) were operated to study the effects of recirculation on the waste degradation at flow rate of 540 mL per day. The speed-up of waste degradation was clearly established from global parameters measured on

  5. Determination of acceleration and stabilization indicators for buried municipal wastes. Study of leachates recirculation impact on waste columns; Determination d'indicateurs d'acceleration et de stabilisation de dechets menagers enfouis. Etude de l'impact de la recirculation de lixiviats sur colonnes de dechets

    Energy Technology Data Exchange (ETDEWEB)

    Francois, V

    2004-05-15

    The main goal of this research work was to study the stabilisation processes of municipal solid waste (MSW). Representative parameters, which are required to evaluate the stabilization state of wastes, were applied to study the acceleration of the degradation processes in lab-scale landfill anaerobic bioreactors operated with leachate recirculation. The characterisation of the wastes solid phase (i.e., volatile solids, organic carbon, fines, paper-cardboard and degraded component contents) is necessary to assess its degradation state. However, additional parameters are required such as the characterisation of water extracted from the waste (i.e., Chemical Oxygen Content (COD), Dissolved Oxygen Content (DOC) and ions content) and biogas composition (methane potential). Those parameters are nevertheless complementary to conclude on its polluting feature. The analysis of more specific indicators such as the organic macromolecules content in leachates and the evaluation of the metal contamination level in solid waste and its potential remobilization was showed to be consistent for the evaluation of waste stabilisation state. The composition of leachates used during recirculation influences greatly the waste leaching behaviour. For instance, the recirculation of a stabilised leachate containing organic macromolecules can increase the release of pollutants (organics and minerals) if contacted with young waste or on the other hand the release of pollutant is reduced when the leachate composition is similar to the organic species, which are expected to be released by the wastes. Due to the experimental limits of the leaching tests, several lab-scale landfill anaerobic bioreactors containing different wastes types (height of 1 m and mass of waste varying from 28 kg to 65 kg) were operated to study the effects of recirculation on the waste degradation at flow rate of 540 mL per day. The speed-up of waste degradation was clearly established from global parameters measured on

  6. Subsurface Investigations Program at the Radioactive Waste Management Complex of the Idaho National Engineering Laboratory: Annual progress report, FY-1987

    International Nuclear Information System (INIS)

    Laney, P.T.; Minkin, S.C.; Baca, R.G.; McElroy, D.L.; Hubbell, J.M.; Hull, L.C.; Russell, B.F.; Stormberg, G.J.; Pittman, J.T.

    1988-04-01

    The Subsurface Investigations Program is obtaining program objectives of a field calibration of a model to predict long-term radionuclide migration and measurement of the actual migration to date. Three deep boreholes were drilled at the Radioactive Waste Management Complex (RWMC) to collect sample material for evaluation of radionuclide content in the interbeds, to determine geologic and hydrologic characteristics of the sediments, and to provide monitoring sites for moisture movement in these sediments. Suction lysimeters and heat dissipation sensors were installed in two deep boreholes to collect moisture data. Data from the moisture sensing instruments installed at the RWMC continued to be collected during FY-1987. Because of the large volume of collected data, the RWMC Data Management System was developed and implemented to facilitate the storage, retrieval, and manipulation of the database. Work on the Computer Model Development task focused on a detailed review of previous vadose zone modeling studies at INEL, acquisition and installation of a suite of computer models for unsaturated flow and contaminant transport, and preliminary applications of computer models using site-specific data. Computer models installed on the INEL CRAY computer for modeling transport through the subsurface pathway include SEMTRA, FEMTRA, TRACR3D, MAGNUM, and CHAINT. In addition to the major computer models, eight other codes, referred to as support codes and models, have been acquired and implemented. 27 refs., 70 figs., 22 tabs

  7. Waste inventory, waste characteristics and waste repositories in Japan

    International Nuclear Information System (INIS)

    Shimooka, K.

    1997-01-01

    There are two types of repositories for the low level radioactive wastes in Japan. One is a trench type repository only for concrete debris generated from the dismantling of the research reactor. According to the safety assurance system, Japan Atomic Energy Research Institute (JAERI) has disposed of the concrete debris arose from the dismantling of the Japan Power Demonstration Reactor (JPDR). The other type is the concreted pit with engineered barriers. Rokkasho Low Level Radioactive Waste Disposal Center has this type of repository mainly for the power plant wastes. Japan Nuclear Fuel Ltd. (JNFL) established by electric power companies is the operator of the LLW disposal project. JNFL began the storage operation in 1992 and buried approximately 60,000 drums there. Two hundred thousand drums of uniformly solidified, waste may be buried ultimately. 4 refs, 3 tabs

  8. CONCRETE CONTAINERS FOR LONG TERM STORAGE AND FINAL DISPOSAL OF TRU WASTE AND LONG LIVED ILW

    International Nuclear Information System (INIS)

    Sakamoto, H.; Asano, H.; Tunaboylu, K.; Mayer, G.; Klubertanz, G.; Kobayashi, S.; Komuro, T.; Wagner, E.

    2003-01-01

    Transuranic (TRU) waste packaging development has been conducted since 1998 by the Radioactive Waste Management Funding and Research Centre (RWMC) to support the TRU waste disposal concept in Japan. In this paper, the overview of development status of the reinforced concrete package is introduced. This package has been developed in order to satisfy the Japanese TRU waste disposal concept based on current technology and to provide a low cost package. Since 1998, the basic design work (safety evaluation, manufacturing and handling procedure, economic evaluation, elemental tests etc.) have been carried out. As a result, the basic specification of the package was decided. This report presents the concept as well as the results of basic design, focused on safety analysis and handling procedure of the package. Two types of the packages exist: - Package-A: for non-heat generating TRU waste from reprocessing in 200 l drums and - Package-B: for heat generating TRU-waste from reprocessing

  9. Contemporary Management of Adult Acquired Buried Penis.

    Science.gov (United States)

    Jun, M S; Gallegos, M A; Santucci, R A

    2018-04-06

    In 2014, The World Health Organization reported that 1.9 billion adults, 39% of the population, were overweight or obese [1]. Unlike most complications of obesity, adult acquired buried penis is an uncomfortable topic which may be overlooked. Patients are often encouraged to lose weight, but this is futile. Simple weight loss will not cure buried penis, as it is a multifactorial condition caused by a combination of: a) overhanging escutcheon from overweight, b) lichen sclerosus, which often contracts and destroys the penile shaft skin, and c) loss of normal penile shaft attachments to the penile skin. This article is protected by copyright. All rights reserved. This article is protected by copyright. All rights reserved.

  10. Radioactive wastes - inventories and classification

    International Nuclear Information System (INIS)

    Brennecke, P.; Hollmann, A.

    1992-01-01

    A survey is given of the origins, types, conditioning, inventories, and expected abundance of radioactive wastes in the future in the Federal Republic of Germany. The Federal Government's radioactive waste disposal scheme provides that radioactive wastes be buried in deep geological formations which are expected to ensure a maintenance-free, unlimited and safe disposal without intentional excavation of the wastes at a later date. (orig./BBR) [de

  11. A Novel Method for Remote Depth Estimation of Buried Radioactive Contamination.

    Science.gov (United States)

    Ukaegbu, Ikechukwu Kevin; Gamage, Kelum A A

    2018-02-08

    Existing remote radioactive contamination depth estimation methods for buried radioactive wastes are either limited to less than 2 cm or are based on empirical models that require foreknowledge of the maximum penetrable depth of the contamination. These severely limits their usefulness in some real life subsurface contamination scenarios. Therefore, this work presents a novel remote depth estimation method that is based on an approximate three-dimensional linear attenuation model that exploits the benefits of using multiple measurements obtained from the surface of the material in which the contamination is buried using a radiation detector. Simulation results showed that the proposed method is able to detect the depth of caesium-137 and cobalt-60 contamination buried up to 40 cm in both sand and concrete. Furthermore, results from experiments show that the method is able to detect the depth of caesium-137 contamination buried up to 12 cm in sand. The lower maximum depth recorded in the experiment is due to limitations in the detector and the low activity of the caesium-137 source used. Nevertheless, both results demonstrate the superior capability of the proposed method compared to existing methods.

  12. Buried waste integrated demonstration human engineered control station. Final report

    Energy Technology Data Exchange (ETDEWEB)

    1994-09-01

    This document describes the Human Engineered Control Station (HECS) project activities including the conceptual designs. The purpose of the HECS is to enhance the effectiveness and efficiency of remote retrieval by providing an integrated remote control station. The HECS integrates human capabilities, limitations, and expectations into the design to reduce the potential for human error, provides an easy system to learn and operate, provides an increased productivity, and reduces the ultimate investment in training. The overall HECS consists of the technology interface stations, supporting engineering aids, platform (trailer), communications network (broadband system), and collision avoidance system.

  13. Buried waste integrated demonstration human engineered control station. Final report

    International Nuclear Information System (INIS)

    1994-09-01

    This document describes the Human Engineered Control Station (HECS) project activities including the conceptual designs. The purpose of the HECS is to enhance the effectiveness and efficiency of remote retrieval by providing an integrated remote control station. The HECS integrates human capabilities, limitations, and expectations into the design to reduce the potential for human error, provides an easy system to learn and operate, provides an increased productivity, and reduces the ultimate investment in training. The overall HECS consists of the technology interface stations, supporting engineering aids, platform (trailer), communications network (broadband system), and collision avoidance system

  14. Probabilistic Modeling of Landfill Subsidence Introduced by Buried Structure Collapse - 13229

    International Nuclear Information System (INIS)

    Foye, Kevin; Soong, Te-Yang

    2013-01-01

    The long-term reliability of land disposal facility final cover systems - and therefore the overall waste containment - depends on the distortions imposed on these systems by differential settlement/subsidence. The evaluation of differential settlement is challenging because of the heterogeneity of the waste mass and buried structure placement. Deterministic approaches to long-term final cover settlement prediction are not able to capture the spatial variability in the waste mass and sub-grade properties, especially discontinuous inclusions, which control differential settlement. An alternative is to use a probabilistic model to capture the non-uniform collapse of cover soils and buried structures and the subsequent effect of that collapse on the final cover system. Both techniques are applied to the problem of two side-by-side waste trenches with collapsible voids. The results show how this analytical technique can be used to connect a metric of final cover performance (inundation area) to the susceptibility of the sub-grade to collapse and the effective thickness of the cover soils. This approach allows designers to specify cover thickness, reinforcement, and slope to meet the demands imposed by the settlement of the underlying waste trenches. (authors)

  15. Recycling waste

    Energy Technology Data Exchange (ETDEWEB)

    Smith, P I.S.

    1976-01-01

    It is being realized that if environmental quality is to be improved the amount of waste generated by man has to be substantially reduced. There are two ways this can be achieved. First, by conserving materials and energy, and sacrificing economic growth, a solution that is completely unacceptable because it would mean some form of rationing, mass unemployment, and collapse of society as it is known. The second way to reduce the volume of waste is by planned recycling, re-use, and recovery. Already the reclamation industry recovers, processes, and turns back for re-use many products used by industry and thereby reduces the UK's import bill for raw materials. In the book, the author sets out the various ways materials may be recovered from industrial and municipal wastes. The broad technology of waste management is covered and attention is focused on man's new resources lying buried in the mountains of industrial wastes, the emissions from stocks, the effluents and sludges that turn rivers into open sewers, and municipal dumps in seventeen chapters. The final chapter lists terms and concepts used in waste technology, organizations concerned with waste management, and sources of information about recycling waste. (MCW)

  16. Reversibility of Decisions and Retrievability of Radioactive Waste: An Overview of Regulatory Positions and Issues

    International Nuclear Information System (INIS)

    Ruiz-Lopez, Carmen; Pescatore, Claudio

    2015-02-01

    The Radioactive Waste Management Committee (RWMC) of the NEA has been at the forefront worldwide in examining the topic of Reversibility and Retrievability (R and R). As early as 2001, an NEA survey-based report entitled 'Reversibility and Retrievability in Geological Disposal of Radioactive Waste' provided an overview of R and R by an ad-hoc group of experts from 11 NEA Member countries. The 2001 report (NEA 2001) observed that national safety regulations dealt mainly with operational safety and design targets for long-term (post-closure) safety and relatively little consideration was given to retrievability/reversibility or its implications. Yet, policy frames saw benefits from retrievability. In 2007, the RWMC launched the NEA R and R project with participation from 15 countries and two international organisations. The project included, amongst its members, representatives of six organisations involved in regulation, five regulatory authorities of five countries and one technical support organisation to the safety authorities. The project aimed to improve awareness amongst the RWMC constituency of the breadth of issues and positions regarding the concepts of R and R with the goal of providing a neutral overview of relevant issues and viewpoints in OECD countries. Hence substantial attention was given to R and R regulatory issues mainly in the context of decision making for repository development. The report (NEA 2011) points out regulatory issues, including safety criteria and licensing considerations. The present document presents an overview of findings, positions, boundary conditions and issues based on the results of the R and R project of 2007-2011 (stepwise decision making and reversibility, regulatory authorisations and R and R, decision making for retrieval) and of the Reims conference of December 2010 (terminology and definitions, legal and policy context, motivations for R and R, practical aspects, stakeholders confidence aspects)

  17. Nuclear fuel waste disposal

    International Nuclear Information System (INIS)

    1982-01-01

    This film for a general audience deals with nuclear fuel waste management in Canada, where research is concentrating on land based geologic disposal of wastes rather than on reprocessing of fuel. The waste management programme is based on cooperation of the AECL, various universities and Ontario Hydro. Findings of research institutes in other countries are taken into account as well. The long-term effects of buried radioactive wastes on humans (ground water, food chain etc.) are carefully studied with the help of computer models. Animated sequences illustrate the behaviour of radionuclides and explain the idea of a multiple barrier system to minimize the danger of radiation hazards

  18. Learning and adapting to societal requirements for radioactive waste management. Key findings and experience of the forum on stakeholder confidence

    International Nuclear Information System (INIS)

    2004-01-01

    The Forum on Stakeholder Confidence (FSC) is an ongoing initiative of the Nea Radioactive Waste Management Committee (RWMC). The FSC is composed of nominees from Nea member countries and consists mostly of representatives of national organisations (implementers, regulators, policy makers, research and development personnel) with responsibility for, and experience of, interacting with stakeholders. The FSC mandate includes the following: to define, oversee and carry out work programme activities in the strategic area of public perception and stakeholder confidence, as assigned by the RWMC; to advise the RWMC on major and emerging issues in the area of public perception and stakeholder confidence related to waste management; to act as a forum to share experience in achieving stakeholder confidence and, in particular, in how to obtain the confidence of local communities and their representatives and intermediaries with the technical decision makers; to analyse today processes for embedding waste management programmes into a socio-political, decision-making context; to identify opportunities for harmonized views of member countries regarding successful and unsuccessful experiences in interacting with stakeholders, technical concerns of stakeholders, effective means of communicating with technical and nontechnical audiences. This report presents the key FSC findings based on the substantial documentation and experience developed by the Forum during its first four years of activity (2000-2004). The historical context within which the FSC was established is also described and provides a perspective to those findings. An appendix recounts the collective experience of the FSC members, including their views of the impact of FSC activities on participating organisations. The FSC will build upon the present findings during its next phase of work. (author)

  19. Technical appraisal of the current situation in the field of radioactive waste management

    International Nuclear Information System (INIS)

    1985-01-01

    Industrial activities are regarded as safe even though a small risk always exists. The philosophy of radiation protection accepts this and recognises that some level of risk will also be associated with safe radioactive waste management. Therefore the objective of radioactive waste management is to look for a strategy which, taken as a whole, is considered safe and provides an acceptable balance of all the radiological, technical, social, political and economic considerations. The RWMC's appraisal underlines the need for such a balance while concentrating on radiological and technical factors, particularly on the long term safety aspects of radioactive waste management. The fundamental conclusion is that detailed short and long term safety assessments can now be made which give confidence that radiation protection objectives can be met with currently available technology for most waste types, and at a cost which is only a small fraction of the overall cost of nuclear-generated power

  20. Managing soil moisture on waste burial sites

    International Nuclear Information System (INIS)

    Anderson, J.E.; Ratzlaff, T.D.

    1991-11-01

    Shallow land burial is a common method of disposing of industrial, municipal, and low-level radioactive waste. The exclusion of water from buried wastes is a primary objective in designing and managing waste disposal sites. If wastes are not adequately isolated, water from precipitation may move through the landfill cover and into the wastes. The presence of water in the waste zone may promote the growth of plant roots to that depth and result in the transport of toxic materials to above-ground foliage. Furthermore, percolation of water through the waste zone may transport contaminants into ground water. This report presents results from a field study designed to assess the the potential for using vegetation to deplete soil moisture and prevent water from reaching buried wastes at the Idaho National Engineering Laboratory (INEL). Our results show that this approach may provide an economical means of limiting the intrusion of water on waste sites

  1. The surgical correction of buried penis: a new technique

    NARCIS (Netherlands)

    Boemers, T. M.; de Jong, T. P.

    1995-01-01

    We report a new surgical technique for the correction of buried penis. The study comprised 10 boys with buried penis. The technique consisted of resection of abnormal dartos attachments, unfurling of the prepuce and correction of the deficient shaft skin by reapproximation of the preputial skin

  2. Buried injector logic, a vertical IIL using deep ion implantation

    NARCIS (Netherlands)

    Mouthaan, A.J.

    1987-01-01

    A vertically integrated alternative for integrated injection logic has been realized, named buried injector logic (BIL). 1 MeV ion implantations are used to create buried layers. The vertical pnp and npn transistors have thin base regions and exhibit a limited charge accumulation if a gate is

  3. Buried nodules from the central Indian Ocean basin

    Digital Repository Service at National Institute of Oceanography (India)

    Pattan, J.N.; Parthiban, G.

    . Of these, 13 buried nodules are from two sediment cores in siliceous ooze and seven from two sediment cores in a red clay area. The morphology, size, surface texture and chemical composition of buried nodules from two different sediment type have been...

  4. USA - Paper provided by the US delegation to the RWMC. Site Decontamination and Clean-up Under the U.S. EPA 'Superfund'

    International Nuclear Information System (INIS)

    2003-01-01

    Contaminated and hazardous waste sites, including nuclear facilities, may be subject to clean-up under the U.S. Environmental Protection Agency (EPA). The Comprehensive Environmental Response, Compensation, and Liabilities Act (CERCLA), commonly known as 'Superfund', authorises EPA to respond to releases or threatened releases of hazardous substances, pollutants, or contaminants that may endanger public health or the environment. The legislation defines hazardous substances to include radiation. Entry into Superfund: The EPA may be notified of a site potentially requiring clean up from any source. Potential sites are evaluated under a numerical hazard ranking system, and are then included on the clean-up list ('National Priorities List') if they meet an established threshold. Nuclear Facilities and Radioactively Contaminated Sites under Superfund: Any site may be subject to CERCLA action if EPA determines that it poses a hazard. There are three major types of sites that have been or are subject to action under this program: Federal nuclear facilities, Decommissioned facilities, Privately-owned, unlicensed sites Liabilities Under Superfund: The authorising legislation specifically provided for liability of persons responsible for releases of hazardous waste at uncontrolled sites. Liability under CERCLA is 'strict,' 'retroactive,' and 'joint and several'. Thus, the burden of proof for disproving liability is quite high, and that the extent of the liability is not limited to the share of the waste or hazardous substance contributed by a party. The EPA may pursue liable parties to recover past and future costs associated with clean-up, including direct costs and indirect costs incurred by both EPA and its contractors. Clean-Up Levels: Clean-up goals and technologies are established on a site-specific basis. In general, clean-up goals must meet risk requirements and be consistent with applicable standards. Other factors such as community acceptance, volume reduction

  5. Bench-scale arc melter for R ampersand D in thermal treatment of mixed wastes

    International Nuclear Information System (INIS)

    Kong, P.C.; Grandy, J.D.; Watkins, A.D.; Eddy, T.L.; Anderson, G.L.

    1993-05-01

    A small dc arc melter was designed and constructed to run bench-scale investigations on various aspects of development for high-temperature (1,500-1,800 degrees C) processing of simulated transuranic-contaminated waste and soil located at the Radioactive Waste Management Complex (RWMC). Several recent system design and treatment studies have shown that high-temperature melting is the preferred treatment. The small arc melter is needed to establish techniques and procedures (with surrogates) prior to using a similar melter with the transuranic-contaminated wastes in appropriate facilities at the site. This report documents the design and construction, starting and heating procedures, and tests evaluating the melter's ability to process several waste types stored at the RWMC. It is found that a thin graphite strip provides reliable starting with initial high current capability for partially melting the soil/waste mixture. The heating procedure includes (1) the initial high current-low voltage mode, (2) a low current-high voltage mode that commences after some slag has formed and arcing dominates over the receding graphite conduction path, and (3) a predominantly Joule heating mode during which the current can be increased within the limits to maintain relatively quiescent operation. Several experiments involving the melting of simulated wastes are discussed. Energy balance, slag temperature, and electrode wear measurements are presented. Recommendations for further refinements to enhance its processing capabilities are identified. Future studies anticipated with the arc melter include waste form processing development; dissolution, retention, volatilization, and collection for transuranic and low-level radionuclides, as well as high vapor pressure metals; electrode material development to minimize corrosion and erosion; refractory corrosion and/or skull formation effects; crucible or melter geometry; metal oxidation; and melt reduction/oxidation (redox) conditions

  6. Bench-scale arc melter for R&D in thermal treatment of mixed wastes

    Energy Technology Data Exchange (ETDEWEB)

    Kong, P.C.; Grandy, J.D.; Watkins, A.D.; Eddy, T.L.; Anderson, G.L.

    1993-05-01

    A small dc arc melter was designed and constructed to run bench-scale investigations on various aspects of development for high-temperature (1,500-1,800{degrees}C) processing of simulated transuranic-contaminated waste and soil located at the Radioactive Waste Management Complex (RWMC). Several recent system design and treatment studies have shown that high-temperature melting is the preferred treatment. The small arc melter is needed to establish techniques and procedures (with surrogates) prior to using a similar melter with the transuranic-contaminated wastes in appropriate facilities at the site. This report documents the design and construction, starting and heating procedures, and tests evaluating the melter`s ability to process several waste types stored at the RWMC. It is found that a thin graphite strip provides reliable starting with initial high current capability for partially melting the soil/waste mixture. The heating procedure includes (1) the initial high current-low voltage mode, (2) a low current-high voltage mode that commences after some slag has formed and arcing dominates over the receding graphite conduction path, and (3) a predominantly Joule heating mode during which the current can be increased within the limits to maintain relatively quiescent operation. Several experiments involving the melting of simulated wastes are discussed. Energy balance, slag temperature, and electrode wear measurements are presented. Recommendations for further refinements to enhance its processing capabilities are identified. Future studies anticipated with the arc melter include waste form processing development; dissolution, retention, volatilization, and collection for transuranic and low-level radionuclides, as well as high vapor pressure metals; electrode material development to minimize corrosion and erosion; refractory corrosion and/or skull formation effects; crucible or melter geometry; metal oxidation; and melt reduction/oxidation (redox) conditions.

  7. INEL test plan for evaluating waste assay systems

    International Nuclear Information System (INIS)

    Mandler, J.W.; Becker, G.K.; Harker, Y.D.; Menkhaus, D.E.; Clements, T.L. Jr.

    1996-09-01

    A test bed is being established at the Idaho National Engineering Laboratory (INEL) Radioactive Waste Management Complex (RWMC). These tests are currently focused on mobile or portable radioassay systems. Prior to disposal of TRU waste at the Waste Isolation Pilot Plant (WIPP), radioassay measurements must meet the quality assurance objectives of the TRU Waste Characterization Quality Assurance Program Plan. This test plan provides technology holders with the opportunity to assess radioassay system performance through a three-tiered test program that consists of: (a) evaluations using non-interfering matrices, (b) surrogate drums with contents that resemble the attributes of INEL-specific waste forms, and (c) real waste tests. Qualified sources containing a known mixture and range of radionuclides will be used for the non-interfering and surrogate waste tests. The results of these tests will provide technology holders with information concerning radioassay system performance and provide the INEL with data useful for making decisions concerning alternative or improved radioassay systems that could support disposal of waste at WIPP

  8. INEL test plan for evaluating waste assay systems

    Energy Technology Data Exchange (ETDEWEB)

    Mandler, J.W.; Becker, G.K.; Harker, Y.D.; Menkhaus, D.E.; Clements, T.L. Jr.

    1996-09-01

    A test bed is being established at the Idaho National Engineering Laboratory (INEL) Radioactive Waste Management Complex (RWMC). These tests are currently focused on mobile or portable radioassay systems. Prior to disposal of TRU waste at the Waste Isolation Pilot Plant (WIPP), radioassay measurements must meet the quality assurance objectives of the TRU Waste Characterization Quality Assurance Program Plan. This test plan provides technology holders with the opportunity to assess radioassay system performance through a three-tiered test program that consists of: (a) evaluations using non-interfering matrices, (b) surrogate drums with contents that resemble the attributes of INEL-specific waste forms, and (c) real waste tests. Qualified sources containing a known mixture and range of radionuclides will be used for the non-interfering and surrogate waste tests. The results of these tests will provide technology holders with information concerning radioassay system performance and provide the INEL with data useful for making decisions concerning alternative or improved radioassay systems that could support disposal of waste at WIPP.

  9. Hydrologic and Meteorological Data for an Unsaturated-Zone Study Area near the Radioactive Waste Management Complex, Idaho National Engineering and Environmental Laboratory, Idaho, 1990-96

    International Nuclear Information System (INIS)

    Perkins, K. S.; Nimmo, J. R.; Pittman, J. R.

    1998-01-01

    Trenches and pits at the Radioactive Waste Management Complex (RWMC) Subsurface Disposal Area (SDA) at the Idaho National Engineering and Environmental Laboratory (formerly known as the Idaho National Engineering Laboratory) have been used for burial of radioactive waste since 1952. In 1985, the U.S. Geological Survey (USGS), in cooperation with the U.S. Department of Energy, began a multi-phase study of the geohydrology of the RWMC to provide a basis for estimating the extent of and the potential for migration of radionuclides in the unsaturated zone beneath the waste trenches and pits. This phase of the study provides hydrologic and meteorological data collected at a designated test trench area adjacent to the northern boundary of the RWMC SDA from 1990 through 1996. The test trench area was constructed by the USGS in 1985. Hydrologic data presented in this report were collected during 1990-96 in the USGS test trench area. Soil-moisture content measurement from disturbed and undisturbed soil were collected approximately monthly during 1990-96 from 11 neutron-probe access holes with a neutron moisture gage. In 1994, three additional neutron access holes were completed for monitoring. A meteorological station inside the test trench area provided data for determination of evapotranspiration rates. The soil-moisture and meteorological data are contained in files on 3-1/2 inch diskettes (disks 1 and 2) included with this report. The data are presented in simple American Standard Code for Information Interchange (ASCII) format with tab-delimited fields. The files occupy a total of 1.5 megabytes of disk space

  10. Dual-band infrared capabilities for imaging buried object sites

    Energy Technology Data Exchange (ETDEWEB)

    Del Grande, N.K.; Durbin, P.F.; Gorvad, M.R.; Perkins, D.E.; Clark, G.A.; Hernandez, J.E.; Sherwood, R.J.

    1993-04-02

    We discuss dual-band infrared (DBIR) capabilities for imaging buried object sizes. We identify physical features affecting thermal contrast needed to distinguish buried object sites from undisturbed sites or surface clutter. Apart from atmospheric transmission and system performance, these features include: object size, shape, and burial depth; ambient soil, disturbed soil and object site thermal diffusivity differences; surface temperature, emissivity, plant-cover, slope, albedo and roughness variations; weather conditions and measurement times. We use good instrumentation to measure the time-varying temperature differences between buried object sites and undisturbed soil sites. We compare near surface soil temperature differences with radiometric infrared (IR) surface temperature differences recorded at 4.7 {plus_minus} 0.4 {mu}m and at 10.6 {plus_minus} 1.0 {mu}m. By producing selective DBIR image ratio maps, we distinguish temperature-difference patterns from surface emissivity effects. We discuss temperature differences between buried object sites, filled hole site (without buried objects), cleared (undisturbed) soil sites, and grass-covered sites (with and without different types of surface clutter). We compare temperature, emissivity-ratio, visible and near-IR reflectance signatures of surface objects, leafy plants and sod. We discuss the physical aspects of environmental, surface and buried target features affecting interpretation of buried targets, surface objects and natural backgrounds.

  11. Compact Buried Ducts in a Hot-Humid Climate House

    Energy Technology Data Exchange (ETDEWEB)

    Mallay, Dave [Home Innovation Research Labs, Upper Marlboro, MD (United States)

    2016-01-07

    "9A system of compact, buried ducts provides a high-performance and cost-effective solution for delivering conditioned air throughout the building. This report outlines research activities that are expected to facilitate adoption of compact buried duct systems by builders. The results of this research would be scalable to many new house designs in most climates and markets, leading to wider industry acceptance and building code and energy program approval. The primary research question with buried ducts is potential condensation at the outer jacket of the duct insulation in humid climates during the cooling season. Current best practices for buried ducts rely on encapsulating the insulated ducts with closed-cell spray polyurethane foam insulation to control condensation and improve air sealing. The encapsulated buried duct concept has been analyzed and shown to be effective in hot-humid climates. The purpose of this project is to develop an alternative buried duct system that performs effectively as ducts in conditioned space - durable, energy efficient, and cost-effective - in a hot-humid climate (IECC warm-humid climate zone 3A) with three goals that distinguish this project: 1) Evaluation of design criteria for buried ducts that use common materials and do not rely on encapsulation using spray foam or disrupt traditional work sequences; 2) Establishing design criteria for compact ducts and incorporate those with the buried duct criteria to further reduce energy losses and control installed costs; 3) Developing HVAC design guidance for performing accurate heating and cooling load calculations for compact buried ducts.

  12. Buried plastic scintillator muon telescope (BATATA)

    International Nuclear Information System (INIS)

    Alfaro, R.; De Donato, C.; D'Olivo, J.C.; Guzman, A.; Medina-Tanco, G.; Moreno Barbosa, E.; Paic, G.; Patino Salazar, E.; Salazar Ibarguen, H.; Sanchez, F.A.; Supanitsky, A.D.; Valdes-Galicia, J.F.; Vargas Trevino, A.D.; Vergara Limon, S.; Villasenor, L.M.

    2010-01-01

    Muon telescopes have multiple applications in the area of cosmic ray research. We are currently building such a detector with the objective of comparing the ground penetration of muon vs. electron-gamma signals originated in cosmic ray showers. The detector is composed by a set of three parallel dual-layer scintillator planes, buried at fixed depths ranging from 120 to 600g/cm 2 . Each layer is 4m 2 and is composed by 49 rectangular strips of 4cmx2m, oriented at a 90 0 angle with respect to its companion layer, which gives an xy-coincidence pixel of 4x4cm 2 . The scintillators are MINOS extruded polystyrene strips, with an embedded Bicron BC92 wavelength shifting (WLS) fibers, of 1.5 mm in diameter. Light is collected by Hamamatsu H7546B multi-anode PMTs of 64 pixels. The front-end (FE) electronics works in counting mode and signals are transmitted to the surface DAQ stage using low-voltage differential signaling (LVDS). Any strip signal above threshold opens a GPS-tagged 2μs data collection window. Data, including signal and background, are acquired by a system of FPGA (Spartan 2E) boards and a single-board computer (TS7800).

  13. Buried plastic scintillator muon telescope (BATATA)

    Energy Technology Data Exchange (ETDEWEB)

    Alfaro, R. [Inst. de Fisica, Universidad Nacional Autonoma de Mexico, Mexico, D.F., C.P. 04510 (Mexico); De Donato, C.; D' Olivo, J.C.; Guzman, A.; Medina-Tanco, G. [Inst. de Ciencias Nucleares, Universidad Nacional Autonoma de Mexico, Mexico, D.F., C.P. 04510 (Mexico); Moreno Barbosa, E. [Fac. de Ciencias Fisico Matematicas, Benemerita Universidad Autonoma de Puebla, Puebla (Mexico); Paic, G.; Patino Salazar, E. [Inst. de Ciencias Nucleares, Universidad Nacional Autonoma de Mexico, Mexico, D.F., C.P. 04510 (Mexico); Salazar Ibarguen, H. [Fac. de Ciencias Fisico Matematicas, Benemerita Universidad Autonoma de Puebla, Puebla (Mexico); Sanchez, F.A., E-mail: federico.sanchez@nucleares.unam.m [Inst. de Ciencias Nucleares, Universidad Nacional Autonoma de Mexico, Mexico, D.F., C.P. 04510 (Mexico); Supanitsky, A.D. [Inst. de Ciencias Nucleares, Universidad Nacional Autonoma de Mexico, Mexico, D.F., C.P. 04510 (Mexico); Valdes-Galicia, J.F. [Inst. de Geofisica, Universidad Nacional Autonoma de Mexico, Mexico, D.F., C.P. 04510 (Mexico); Vargas Trevino, A.D.; Vergara Limon, S. [Fac. de Ciencias de la Electronica, Benemerita Universidad Autonoma de Puebla, Puebla (Mexico); Villasenor, L.M. [Inst. de Fisica y Matematicas, Universidad Michoacana de San Nicolas Hidalgo Morelia (Mexico); Observatorio Pierre Auger, Av. San Martin Norte 304 (5613) Malarguee, Prov. Mendoza (Argentina)

    2010-05-21

    Muon telescopes have multiple applications in the area of cosmic ray research. We are currently building such a detector with the objective of comparing the ground penetration of muon vs. electron-gamma signals originated in cosmic ray showers. The detector is composed by a set of three parallel dual-layer scintillator planes, buried at fixed depths ranging from 120 to 600g/cm{sup 2}. Each layer is 4m{sup 2} and is composed by 49 rectangular strips of 4cmx2m, oriented at a 90{sup 0} angle with respect to its companion layer, which gives an xy-coincidence pixel of 4x4cm{sup 2}. The scintillators are MINOS extruded polystyrene strips, with an embedded Bicron BC92 wavelength shifting (WLS) fibers, of 1.5 mm in diameter. Light is collected by Hamamatsu H7546B multi-anode PMTs of 64 pixels. The front-end (FE) electronics works in counting mode and signals are transmitted to the surface DAQ stage using low-voltage differential signaling (LVDS). Any strip signal above threshold opens a GPS-tagged 2{mu}s data collection window. Data, including signal and background, are acquired by a system of FPGA (Spartan 2E) boards and a single-board computer (TS7800).

  14. RWMC Related Work in the Areas of RK and M and the Connection to the 'Added Value' Concepts and the 'Memory' Aspects of the FSC Programme of Work

    International Nuclear Information System (INIS)

    Pescatore, Claudio; Mays, C.; )

    2012-01-01

    For geological disposal sites, the time scales over which the hazard exists are enormous. It must be accepted that the current generation's capacity to assure continued integrity cannot be projected indefinitely into the future, but rather diminishes with time. At the same time there is a common understanding that we should neither 'walk away' from these facilities nor to hide them, even when we think they will be safe. In fact, the sense of safety will be coming from continuing, over time, some element of familiarity and control. Hence the need to conceptualise a 'rolling future' in which each generation takes responsibility to provide continuity and safety for the succeeding several generations, including a need for flexibility and adaptability to circumstances as they change. The idea of archives and markers that last as long as possible (the technological approach) continues to be central. However, we are beginning to understand today that physical markers and archives may need to be complemented by - or integrated within - a cultural tradition that could be sustained over time starting with the planning of a repository and continuing through its implementation and beyond its closure. The mandated need to install 'permanent' records and markers can only be fulfilled if one aims to make them become part of the local, subsequent cultures, and ideally be renewed as their materials are degraded, or as their significance evolves. Because a radioactive waste repository and site will be a permanent presence in a host community for a very long time, a fruitful, positive relationship must be established with those residing there, now and in the future. Simply put, designers have to make the facility and site to suit people's present needs, ambitions and likings, and provide for evolutions to match, at reasonable cost, the needs and desires of future generations. The challenge is to design and implement a facility (with its surroundings) that is not only accepted, but in

  15. New paradigms in radioactive waste management

    International Nuclear Information System (INIS)

    Bertel, Evelyne; Pescatore, Claudio; Riotte, Hans

    2005-01-01

    The social dimension of nuclear power has so far been seen as mostly a communication problem and has been addressed, as such, periodically over the years in workshops, conferences and studies. It is only in the last years in relation to the siting of waste repositories, that this issue is more broadly understood as stakeholder involvement, and finally as an element of participatory democracy. Based on work of various standing technical committees of the OECD Nuclear Energy Agency (NEA), and in particular the Radioactive Waste Management Committee's (RWMC) Forum on Stakeholder Confidence (FSC), the paper reviews the recent development from public risk communication to stakeholder involvement in the area of waste management. Key findings of the FSC national workshops in Finland, Canada, Belgium and Germany are presented and main factors influencing the debate and public acceptance of waste facilities are identified. The need for clarifying the role of all actors in this dialog and the particular challenges for regulatory institutions in a stakeholder dialogue are addressed. (author)

  16. Exhumation test with aged radioactive solid wastes

    International Nuclear Information System (INIS)

    Horton, J.H.

    1977-01-01

    The deterioration of solid radioactive waste buried in soil is an important consideration when estimating the migration of radionuclides from the burial site, planning procedures for exhuming buried waste, and evaluating hazards caused by intentional or unintentional uncovering of the waste. This report presents observations during the excavation of low-level waste buried for 14 years in the humid environment of the Savannah River Plant. The radiation dose rates that were used to define the limits for low-level beta-gamma wastes were <50 mR/hr from an unshielded package or <50 mR/hr at 10 feet from a truck load. The waste was buried in sandy clay soil trenches more than 20 feet above the water table and covered with soil soon after burial. Rainfall for the area averages 47 inches per year. Because of the higher water permeability in backfilled soil than in undisturbed soil, perched water was sometimes found in the bottom of some trenches. However, the duration and/or extent of perched water is limited so that most waste is not subjected to water-saturated soil. The waste uncovered included wood, steel, plastics, cotton cloth, rubber, and paper. Cardboard boxes not enclosed in plastic were the only materials that deteriorated visibly. Apparently, decades would be required for all cellulose materials to decompose; plastics, rubber, and metals will probably survive indefinitely

  17. Safety in depth for nuclear waste disposal

    Energy Technology Data Exchange (ETDEWEB)

    Ringwood, T [Australian National Univ., Canberra. Research School of Earth Sciences

    1980-11-27

    A nuclear waste disposal strategy is described in which the radionuclides are immobilised in widely-dispersed drill holes in an extremely stable and leach resistant titanate ceramic form (SYNROC) at depths of 1500 to 4000 metres. The advantages of this method over that of burying such wastes in large centralised mined repositories at 500 to 700 metres in suitable geological strata are examined.

  18. Evaluation of overweight load routing on buried utility facilities

    Science.gov (United States)

    2011-02-01

    Overweight traffic movements can negatively affect pavement integrity and quality. However, it is less : known to what degree buried utility plant along and across the right of way is affected by these overweight : loads, especially if the utility fa...

  19. Detection of Buried Mines and Unexploded Ordnance (UXO)

    National Research Council Canada - National Science Library

    Heberlein, David; Balko, Bohdan; Chappell, Isaac; Biddle, John

    2007-01-01

    ... [and/or their explosive-related compounds (ERCs)] concentrated in the top soil, and radiation techniques, which uses radiation to probe beneath the earth's surface to provide bulk detection of buried explosive devices...

  20. Transuranic waste examination quality assurance at the Idaho National Engineering Laboratory

    International Nuclear Information System (INIS)

    Bower, J.M.

    1987-01-01

    Since 1954, defense-generated transuranic (TRU) waste has been received at the Radioactive Waste Management Complex (RWMC) at the Idaho National Engineering Laboratory (INEL). A major objective of the Department of Energy (DOE) Nuclear Waste Management Programs is the proper management of the defense-generated TRU waste. The Stored Waste Examination Pilot Plant (SWEPP) is providing nondestructive examination and assay of retrievably stored contact handled TRU waste in order to certify it to the Waste Isolation Pilot Plant Waste Acceptance Crtieria (WIPP-WAC). SWEPP's capabilities for certifying contact handled waste containers include weighing, real-time radiographic examination, fissile material assay examination, container integrity examination, radiological surveys and labeling of waste containers. These processes involve not only instrument accuracy but also a wide range of technician interpretation from moderate on the assay to 100% on the radiograph. This, therefore, requires a variety of quality assurance techniques to ensure that the examinations and certifications are being performed correctly. The purpose of this paper is to discuss the methods utilized by SWEPP for checking on the examination process and to ensure that waste certifications are being properly performed. Included is the application of the quality assurance techniques to each examination system, the management of the data generated by the examination, and the verifications to ensure accurate certification. 1 ref

  1. Record Blizzard Buries U.S. Northeast

    Science.gov (United States)

    2005-01-01

    After two days of blustery weather, the skies cleared over Massachusetts on January 24, 2005. Along with other northeastern U.S. states, Massachusetts was slammed with a powerful blizzard on January 22 and 23 that shut down travel and businesses and extinguished power. The storm brought record snow to many places, but Massachusetts topped the list. The cities of Salem and Plymouth were buried in 38 inches (96.5 cm) of snow, and strong winds created drifts up to seven feet (2 meters) high, according to the National Weather Service. For Boston, the storm was the fifth worst blizzard to hit the city since 1892, dumping 22.5 inches (57 cm) of snow in two days. Of that, 13.4 inches (34 cm) fell on January 23' the most snow to fall on the city in a single day since records began. These totals gave Boston nearly twice its average snowfall for January (the average is 13.5 inches, 34.3 cm), and over half its annual average snow of 41.8 inches (106 cm). This Moderate Resolution Imaging Spectroradiometer (MODIS) image, taken on January 24 by NASA's Terra satellite, shows the effects of the storm on Massachusetts and its southern neighbors, Connecticut (left) and Rhode Island (right). New York's Long Island is in the lower left corner of the image. The entire region is coated with snow, though clouds obscure the ground on the left side of the image. The snow was accompanied by powerful hurricane-force winds that helped create white-out conditions and large snowdrifts. The wind also churned ocean waters around Cape Cod, leaving them milky with sediment. NASA image courtesy the MODIS Rapid Response Team at NASA GSFC.

  2. Response of buried pipes to missile impact

    International Nuclear Information System (INIS)

    Vardanega, C.; Cremonini, M.G.; Mirone, M.; Luciani, A.

    1989-01-01

    This paper presents the methodology and results of the analyses carried out to determine an effective layout and the dynamic response of safety related cooling water pipes, buried in backfill, for the Alto Lazio Nuclear Power Plant in Italy, subjected to missile impact loading at the backfill surface. The pipes are composed of a steel plate encased in two layers of high-quality reinforced concrete. The methodology comprises three steps. The first step is the definition of the 'free-field' dynamic response of the backfill soil, not considering the presence of the pipes, through a dynamic finite element direct integration analysis utilizing an axisymmetric model. The second step is the pipe-soil interaction analysis, which is conducted by utilizing the soil displacement and stress time-histories obtained in the previous steps. Soil stress time-histories, combined with the geostatic and other operational stresses (such as those due to temperature and pressure), are used to obtain the actions in the pipe walls due to ring type deformation. For the third step, the analysis of the beam type response, a lumped parameter model is developed which accounts for the soil stiffness, the pipe characteristics and the position of the pipe with respect to the impact area. In addition, the effect of the presence of large concrete structures, such as tunnels, between the ground surface and the pipe is evaluated. The results of the structural analyses lead to defining the required steel thickness and also allow the choice of appropriate embedment depth and layout of redundant lines. The final results of the analysis is not only the strength verification of the pipe section, but also the definition of an effective layout of the lines in terms of position, depth, steel thickness and joint design. (orig.)

  3. Compact Buried Ducts in a Hot-Humid Climate House

    Energy Technology Data Exchange (ETDEWEB)

    Mallay, D. [Home Innovation Research Labs, Upper Marlboro, MD (United States)

    2016-01-01

    A system of compact, buried ducts provides a high-performance and cost-effective solution for delivering conditioned air throughout the building. This report outlines research activities that are expected to facilitate adoption of compact buried duct systems by builders. The results of this research would be scalable to many new house designs in most climates and markets, leading to wider industry acceptance and building code and energy program approval.

  4. Regulatory research for waste disposal - Objectives and international approaches

    International Nuclear Information System (INIS)

    Wanner, Hans; Fischer-Appelt, Klaus; Pescatore, Claudio

    2011-01-01

    The question of active involvement of nuclear regulatory and supervisory bodies in research and development (R and D) projects has become a topic of increasing interest in recent years. The way in which research is included in regulatory activities varies from country to country, ranging from countries with no regulatory R and D activities to countries with extensive activities which are often carried out by independent research organisations acting on behalf of the regulatory body. The present report outlines (part 1) the potential merits of R and D work carried out by the regulator, and summarizes (part 2) the results of a questionnaire that was circulated among the members of the Regulators' Forum of NEA's Radioactive Waste Management Committee in 2009. Part 3 presents the conclusions of discussions within the RWMC-RF. The detailed answers to the questionnaire are also provided

  5. Research on advanced technology of performance assessment for geological disposal of high-level radioactive waste (Joint research)

    International Nuclear Information System (INIS)

    2006-12-01

    JAEA and RWMC have carried out a joint research program on advanced technologies that could be used to support performance assessments of geological disposal concepts for high-level radioactive waste. The following 5 items were considered in the program: 1) planning of a basic strategy for the development of analysis technologies on nuclide migration over various spatial and temporal scales; 2) development of analysis technologies for vitrified waste scale; 3) development of analysis technologies for repository scale; 4) development of integration technologies for geochemical information; and 5) development of technologies to promote the logical understanding of repository performance and safety. The above items were discussed in the context of technological experiences gained by JAEA and RWMC in previous repository-related studies. According to the results of these discussions, development strategies for each of the technology areas identified above were efficiently formulated by appropriate task allocations. Specific technical subjects requiring further investigation were also identified using this approach, and potential feed-backs from the results of these investigations into the overall research plan and strategy were considered. These specific research and development subjects in the overall strategy defined by this project should be implemented in the future. (author)

  6. US bureau of mines small-scale arc melter tests

    International Nuclear Information System (INIS)

    O'Connor, W.K.; Oden, L.L.; Turner, P.C.; Davis, D.L.

    1993-01-01

    The US Bureau of Mines, in cooperation with the Idaho National Engineering Laboratory (INEL), conducted over 30 hours of melting tests to vitrify simulated low-level radioactive wastes from the INEL. Radioactive Waste Management Complex (RWMC). Five separate waste compositions were investigated, each consisting of noncontaminated soil from the RWMC and surrogate materials used to simulate the actual buried wastes. The RWMC soil and five waste compositions were melted in a 50-lb, single-phase electric arc furnace with a water-cooled shell. These tests were conducted to determine melting parameters in preparation for a large-scale melting campaign to be conducted in the Bureau's 1-metric ton (mt), water-cooled-wall, 3-phase electric arc furnace. Bulk chemical composition was determined for each of the feed materials and for the slag, metal, fume solids, and offgas furnace products, and distributions were calculated for the key elements. The material balance for the furnace operation indicates that from 63 to 84 pct of the feed reported to the slag. Cerium, used as the surrogate for the radionuclides in the wastes, demonstrated an extremely strong affinity for the slag product. Although slag temperatures as low as 1,250 C were recorded when melting the RWMC soil, temperatures in excess of 1,600 C were necessary to achieve the fluidity required for a successful slag tap

  7. Transuranic waste program at EG and G Idaho, Inc. Annual technical report

    International Nuclear Information System (INIS)

    Smith, T.H.; Tolman, C.R.

    1980-12-01

    This document summarizes the objectives and technical achievements of the transuranic (TRU) waste research and development program conducted at EG and G Idaho, Inc., during fiscal year 1980. The TRU waste activities covered in this report include: INEL TRU Waste EIS (Environmental Impact Statement), including preparation of the EIS, Support Studies, and the Public Participation Program; INEL TRU Waste Projects, including System Analysis, Stored Waste projects, and Buried Waste projects; and Waste Management Materials Studies, including Process Control and Durability studies

  8. TRU waste transportation package development

    International Nuclear Information System (INIS)

    Eakes, R.G.; Lamoreaux, G.H.; Romesberg, L.E.; Sutherland, S.H.; Duffey, T.A.

    1980-01-01

    Inventories of the transuranic wastes buried or stored at various US DOE sites are tabulated. The leading conceptual design of Type-B packaging for contact-handled transuranic waste is the Transuranic Package Transporter (TRUPACT), a large metal container comprising inner and outer tubular steel frameworks which are separated by rigid polyurethane foam and sheathed with steel plate. Testing of TRUPACT is reported. The schedule for its development is given. 6 figures

  9. Site characterization program at the radioactive waste management complex of the Idaho National Engineering Laboratory

    International Nuclear Information System (INIS)

    McElroy, D.L.; Rawson, S.A.; Hubbell, J.M.; Minkin, S.C.; Baca, R.G.; Vigil, M.J.; Bonzon, C.J.; Landon, J.L.; Laney, P.T.

    1989-07-01

    The Radioactive Waste Management Complex (RWMC) Site Characterization Program is a continuation of the Subsurface Investigation Program (SIP). The scope of the SIP has broadened in response to the results of past work that identified hazardous as well as radionuclide contaminants in the subsurface environment and in response to the need to meet regulatory requirements. Two deep boreholes were cored at the RWMC during FY-1988. Selected sediment samples were submitted for Appendix IX of 40 CFR Part 264 and radionuclide analyses. Detailed geologic logging of archived core was initiated. Stratigraphic studies of the unsaturated zone were conducted. Studies to determine hydrologic properties of sediments and basalts were conducted. Geochemical studies and analyses were initiated to evaluate contaminant and radionuclide speciation and migration in the Subsurface Disposal Area (SDA) geochemical environment. Analyses of interbed sediments in boreholes D15 and 8801D did not confirm the presence of radionuclide contamination in the 240-ft interbed. Analyses of subsurface air and groundwater samples identified five volatile organic compounds of concern: carbon tetrachloride, trichloroethylene, 1,1,1-trichloroethane, chloroform, and tetrachloroethylene. 33 refs., 5 figs., 2 tabs

  10. Site characterization program at the radioactive waste management complex of the Idaho National Engineering Laboratory

    Energy Technology Data Exchange (ETDEWEB)

    McElroy, D.L.; Rawson, S.A.; Hubbell, J.M.; Minkin, S.C.; Baca, R.G.; Vigil, M.J.; Bonzon, C.J.; Landon, J.L.; Laney, P.T.

    1989-07-01

    The Radioactive Waste Management Complex (RWMC) Site Characterization Program is a continuation of the Subsurface Investigation Program (SIP). The scope of the SIP has broadened in response to the results of past work that identified hazardous as well as radionuclide contaminants in the subsurface environment and in response to the need to meet regulatory requirements. Two deep boreholes were cored at the RWMC during FY-1988. Selected sediment samples were submitted for Appendix IX of 40 CFR Part 264 and radionuclide analyses. Detailed geologic logging of archived core was initiated. Stratigraphic studies of the unsaturated zone were conducted. Studies to determine hydrologic properties of sediments and basalts were conducted. Geochemical studies and analyses were initiated to evaluate contaminant and radionuclide speciation and migration in the Subsurface Disposal Area (SDA) geochemical environment. Analyses of interbed sediments in boreholes D15 and 8801D did not confirm the presence of radionuclide contamination in the 240-ft interbed. Analyses of subsurface air and groundwater samples identified five volatile organic compounds of concern: carbon tetrachloride, trichloroethylene, 1,1,1-trichloroethane, chloroform, and tetrachloroethylene. 33 refs., 5 figs., 2 tabs.

  11. A modeling study of water flow in the vadose zone beneath the Radioactive Waste Management Complex

    International Nuclear Information System (INIS)

    Baca, R.G.; Magnuson, S.O.; Nguyen, H.D.; Martian, P.

    1992-01-01

    A modeling study was conducted for the purpose of gaining insight into the nature of water flow in the vadose zone beneath the Radioactive Waste Management Complex (RWMC). The modeling study focused on three specific hydrologic aspects: (1) relationship between meteorologic conditions and net infiltration, (2) water movement associated with past flooding events, and (3) estimation of water travel-times through the vadose zone. This information is necessary for understanding how contaminants may be transported through the vadose zone. Evaluations of net infiltration at the RWMC were performed by modeling the processes of precipitation, evaporation, infiltration and soil-moisture redistribution. Water flow simulations were performed for two distinct time periods, namely 1955--1964 and 1984--1990. The patterns of infiltration were calculated for both the undisturbed (or natural sediments) and the pit/trench cover materials. Detailed simulations of the 1969 flooding of Pit 10 were performed to estimate the rate and extent of water movement through the vadose zone. Water travel-times through the vadose zone were estimated using a Monte Carlo simulation approach. The simulations accounted for variability of soil and rock hydraulic properties as well as variations in the infiltration rate

  12. Solid waste retrieval. Phase 1, Operational basis

    International Nuclear Information System (INIS)

    Johnson, D.M.

    1994-01-01

    This Document describes the operational requirements, procedures, and options for execution of the retrieval of the waste containers placed in buried storage in Burial Ground 218W-4C, Trench 04 as TRU waste or suspect TRU waste under the activity levels defining this waste in effect at the time of placement. Trench 04 in Burial Ground 218W-4C is totally dedicated to storage of retrievable TRU waste containers or retrievable suspect TRU waste containers and has not been used for any other purpose

  13. Waste processing system for nuclear power plant

    International Nuclear Information System (INIS)

    Higashinakagawa, Emiko; Tezuka, Fuminobu; Maesawa, Yukishige; Irie, Hiromitsu; Daibu, Etsuji.

    1996-01-01

    The present invention concerns a waste processing system of a nuclear power plant, which can reduce the volume of a large amount of plastics without burying them. Among burnable wastes and plastic wastes to be discarded in the power plant located on the sea side, the plastic wastes are heated and converted into oils, and the burnable wastes are burnt using the oils as a fuel. The system is based on the finding that the presence of Na 2 O, K 2 O contained in the wastes catalytically improves the efficiency of thermal decomposition in a heating atmosphere, in the method of heating plastics and converting them into oils. (T.M.)

  14. Solid waste retrieval. Phase 1, Operational basis

    Energy Technology Data Exchange (ETDEWEB)

    Johnson, D.M.

    1994-09-30

    This Document describes the operational requirements, procedures, and options for execution of the retrieval of the waste containers placed in buried storage in Burial Ground 218W-4C, Trench 04 as TRU waste or suspect TRU waste under the activity levels defining this waste in effect at the time of placement. Trench 04 in Burial Ground 218W-4C is totally dedicated to storage of retrievable TRU waste containers or retrievable suspect TRU waste containers and has not been used for any other purpose.

  15. Alternative disposal options for transuranic waste

    International Nuclear Information System (INIS)

    Loomis, G.G.

    1994-01-01

    Three alternative concepts are proposed for the final disposal of stored and retrieved buried transuranic waste. These proposed options answer criticisms of the existing U.S. Department of Energy strategy of directly disposing of stored transuranic waste in deep, geological salt formations at the Waste Isolation Pilot Plant (WIPP) in Carlsbad, New Mexico. The first option involves enhanced stabilization of stored waste by thermal treatment followed by convoy transportation and internment in the existing WIPP facility. This concept could also be extended to retrieved buried waste with proper permitting. The second option involves in-state, in situ internment using an encapsulating lens around the waste. This concept applies only to previously buried transuranic waste. The third option involves sending stored and retrieved waste to the Nevada Test Site and configuring the waste around a thermonuclear device from the U.S. or Russian arsenal in a specially designed underground chamber. The thermonuclear explosion would transmute plutonium and disassociate hazardous materials while entombing the waste in a national sacrifice area

  16. Buried bumber syndrome (internal button buried of the gastrostomy): Unearthing the solution

    International Nuclear Information System (INIS)

    Moreno, Nelson; Otero, William; Gomez, Martin; Bula, Rodrigo; Otero, Elder

    2006-01-01

    The Buried bumper syndrome is a major complication of percutaneous endoscopic gastrostomy and the literature of in of having described of rarely. The physiopathology is the gastric isquemy of the mucous one for an excessive pressure for the ends that fix the gastrostomy. Their clinical manifestations that depend on the depth of migration of the end go from the absence of symptoms, spill of the nutrition enteral being the most frequent, until peritonitis. The diverse described treatment modalities are based on the depth of migration of the end valued endoscopically. The successful use of the ecoendosonography is described for the estimate of the depth of the migration, when you cannot visualize the end internal endoscopically and we propose a handling .algorithm based on this technique

  17. Materials testing for in situ stabilization treatability study of INEEL mixed wastes soils

    International Nuclear Information System (INIS)

    Heiser, J.; Fuhrmann, M.

    1997-09-01

    This report describes the contaminant-specific materials testing phase of the In Situ Stabilization Comprehensive Environment Response, Compensation, and Liability Act (CERCLA) Treatability Study (TS). The purpose of materials testing is to measure the effectiveness of grouting agents to stabilize Idaho National Engineering and Environmental Laboratory (INEEL) Acid Pit soils and select a grout material for use in the Cold Test Demonstration and Acid Pit Stabilization Treatability Study within the Subsurface Disposal Area (SDA) at the Radioactive Waste Management Complex (RWMC). Test results will assist the selecting a grout material for the follow-on demonstrations described in Test Plan for the Cold Test Demonstration and Acid Pit Stabilization Phases of the In Situ Stabilization Treatability Study at the Radioactive Waste Management Complex

  18. Experimental investigation of buried tritium in plant and animal tissues

    International Nuclear Information System (INIS)

    Kim, S. B.; Workman, W. J. G.; Davis, P. A.

    2008-01-01

    Buried exchangeable tritium appears as part of organically bound tritium (OBT) in the traditional experimental determination of OBT. Since buried tritium quickly exchanges with hydrogen atoms in the body following ingestion, assuming that it is part of OBT rather than part of tritiated water (HTO) could result in a significant overestimate of the ingestion dose. This paper documents an experimental investigation into the existence, amount and significance of buried tritium in plant and fish samples. OBT concentrations in the samples were determined in the traditional way and also following denaturing with five chemical solutions that break down large molecules and expose buried tritium to exchange with free hydrogen atoms. A comparison of the OBT concentrations before and after denaturing, together with the concentration of HTO in the supernatant obtained after denaturing, suggests that buried OBT may exist but makes up less than 5% of the OBT concentration in plants and at most 20% of the OBT concentration in fish. The effects of rinse time and rinse water volumes were investigated to optimize the removal of exchangeable OBT from the samples. (authors)

  19. Radioactive waste processing container

    International Nuclear Information System (INIS)

    Ishizaki, Kanjiro; Koyanagi, Naoaki; Sakamoto, Hiroyuki; Uchida, Ikuo.

    1992-01-01

    A radioactive waste processing container used for processing radioactive wastes into solidification products suitable to disposal such as underground burying or ocean discarding is constituted by using cements. As the cements, calcium sulfoaluminate clinker mainly comprising calcium sulfoaluminate compound; 3CaO 3Al 2 O 3 CaSO 4 , Portland cement and aqueous blast furnace slug is used for instance. Calciumhydroxide formed from the Portland cement is consumed for hydration of the calcium sulfoaluminate clinker. According, calcium hydroxide is substantially eliminated in the cement constituent layer of the container. With such a constitution, damages such as crackings and peelings are less caused, to improve durability and safety. (I.N.)

  20. Thermal tests of a transport / Storage cask in buried conditions

    International Nuclear Information System (INIS)

    Yamakawa, H.; Gomi, Y.; Saegusa, T.; Ito, C.

    1998-01-01

    Thermal tests for a hypothetical accident which simulated accidents caused by building collapse in case of an earthquake were conducted using a full-scale dry type transport and storage cask (total heat load: 23 kW). The objectives of these tests were to clarify the heat transfer features of the buried cask under such accidents and the time limit for maintaining the thermal integrity of the cask. Moreover, thermal analyses of the test cask under the buried conditions were carried out on basis of experimental results to establish methodology for the thermal analysis. The characteristics of the test cask are described as well as the test method used. The heat transfer features of the buried cask under such accidents and a time for maintaining the thermal integrity of the cask have been obtained. (O.M.)

  1. Project Execution Plan for the Remote Handled Low-Level Waste Disposal Project

    Energy Technology Data Exchange (ETDEWEB)

    Danny Anderson

    2014-07-01

    As part of ongoing cleanup activities at the Idaho National Laboratory (INL), closure of the Radioactive Waste Management Complex (RWMC) is proceeding under the Comprehensive Environmental Response, Compensation, and Liability Act (42 USC 9601 et seq. 1980). INL-generated radioactive waste has been disposed of at RWMC since 1952. The Subsurface Disposal Area (SDA) at RWMC accepted the bulk of INL’s contact and remote-handled low-level waste (LLW) for disposal. Disposal of contact-handled LLW and remote-handled LLW ion-exchange resins from the Advanced Test Reactor in the open pit of the SDA ceased September 30, 2008. Disposal of remote-handled LLW in concrete disposal vaults at RWMC will continue until the facility is full or until it must be closed in preparation for final remediation of the SDA (approximately at the end of fiscal year FY 2017). The continuing nuclear mission of INL, associated ongoing and planned operations, and Naval spent fuel activities at the Naval Reactors Facility (NRF) require continued capability to appropriately dispose of contact and remote handled LLW. A programmatic analysis of disposal alternatives for contact and remote-handled LLW generated at INL was conducted by the INL contractor in Fiscal Year 2006; subsequent evaluations were completed in Fiscal Year 2007. The result of these analyses was a recommendation to the Department of Energy (DOE) that all contact-handled LLW generated after September 30, 2008, be disposed offsite, and that DOE proceed with a capital project to establish replacement remote-handled LLW disposal capability. An analysis of the alternatives for providing replacement remote-handled LLW disposal capability has been performed to support Critical Decision-1. The highest ranked alternative to provide this required capability has been determined to be the development of a new onsite remote-handled LLW disposal facility to replace the existing remote-handled LLW disposal vaults at the SDA. Several offsite DOE

  2. Method of forming buried oxide layers in silicon

    Science.gov (United States)

    Sadana, Devendra Kumar; Holland, Orin Wayne

    2000-01-01

    A process for forming Silicon-On-Insulator is described incorporating the steps of ion implantation of oxygen into a silicon substrate at elevated temperature, ion implanting oxygen at a temperature below 200.degree. C. at a lower dose to form an amorphous silicon layer, and annealing steps to form a mixture of defective single crystal silicon and polycrystalline silicon or polycrystalline silicon alone and then silicon oxide from the amorphous silicon layer to form a continuous silicon oxide layer below the surface of the silicon substrate to provide an isolated superficial layer of silicon. The invention overcomes the problem of buried isolated islands of silicon oxide forming a discontinuous buried oxide layer.

  3. Determination of Background Uranium Concentration in the Snake River Plain Aquifer under the Idaho National Engineering and Environmental Laboratory's Radioactive Waste Management Complex

    International Nuclear Information System (INIS)

    Molly K. Leecaster; L. Don Koeppen; Gail L. Olson

    2003-01-01

    Uranium occurs naturally in the environment and is also a contaminant that is disposed of at the Radioactive Waste Management Complex (RWMC) at the Idaho National Engineering and Environmental Laboratory. To determine whether uranium concentrations in the Snake River Plain Aquifer, which underlies the laboratory, are elevated as a result of migration of anthropogenic uranium from the Subsurface Disposal Area in the RWMC, uranium background concentrations are necessary. Guideline values are calculated for total uranium, 234U, 235U, and 238U from analytical results from up to five datasets. Three of the datasets include results of samples analyzed using isotope dilution thermal ionization mass spectrometry (ID-TIMS) and two of the datasets include results obtained using alpha spectrometry. All samples included in the statistical testing were collected from aquifer monitoring wells located within 10 miles of the RWMC. Results from ID-TIMS and alpha spectrometry are combined when the data are not statistically different. Guideline values for total uranium were calculated using four of the datasets, while guideline values for 234U were calculated using only the alpha spectrometry results (2 datasets). Data from all five datasets were used to calculate 238U guideline values. No limit is calculated for 235U because the ID-TIMS results are not useful for comparison with routine monitoring data, and the alpha spectrometry results are too close to the detection limit to be deemed accurate or reliable for calculating a 235U guideline value. All guideline values presented represent the upper 95% coverage 95% confidence tolerance limits for background concentration. If a future monitoring result is above this guideline, then the exceedance will be noted in the quarterly monitoring report and assessed with respect to other aquifer information. The guidelines (tolerance limits) for total U, 234U, and 238U are 2.75 pCi/L, 1.92 pCi/L, and 0.90 pCi/L, respectively

  4. Application of PINS and GNAT to the assay of 55-gal containers of radioactive waste

    International Nuclear Information System (INIS)

    Gehrke, R.J.; Aryaeinejad, R.; Watts, K.D.; Staples, D.R.; Akers, D.W.

    1994-03-01

    The Portable Isotropic Neutron Spectroscopy (PINS) and Gamma Neutron Assay Technique (GNAT) assay systems that were developed with funding from the office of Research and Development (NN20), were taken to the Stored Waste Examination Pilot Plant (SWEPP) facility at the Radioactive Waste Management Complex (RWMC) and applied to the assay of surrogate and Rocky Flats Plant waste contained in 55-gal drums. PINS, a portable prompt γ neutron activation analysis technique, was able to identify key elements in both the surrogate and real waste so that three-main waste categories: metal, combustible material, and cemented chlorinated sludge wastes could be identified. GNAT, a γ, neutron assay technique for the identification and quantification of fissioning isotopes, was able to identify 240 Pu in surrogate waste in which nine 1-g nuclear accident dosimeters were inserted. GNAT was also able to identify 24O Pu in real 55-gal waste drums containing 15- and 40-g of plutonium even in the presence of high activity concentrations of 241 Am

  5. Phase 2, Solid waste retrieval strategy

    International Nuclear Information System (INIS)

    Johnson, D.M.

    1994-01-01

    Solid TRU retrieval, Phase 1 is scheduled to commence operation in 1998 at 218W-4C-T01 and complete recovery of the waste containers in 2001. Phase 2 Retrieval will recover the remaining buried TRU waste to be retrieved and provide the preliminary characterization by non-destructive means to allow interim storage until processing for disposal. This document reports on researching the characterization documents to determine the types of wastes to be retrieved and where located, waste configurations, conditions, and required methods for retrieval. Also included are discussions of wastes encompassed by Phase 2 for which there are valid reasons to not retrieve

  6. Phase 2, Solid waste retrieval strategy

    Energy Technology Data Exchange (ETDEWEB)

    Johnson, D.M.

    1994-09-29

    Solid TRU retrieval, Phase 1 is scheduled to commence operation in 1998 at 218W-4C-T01 and complete recovery of the waste containers in 2001. Phase 2 Retrieval will recover the remaining buried TRU waste to be retrieved and provide the preliminary characterization by non-destructive means to allow interim storage until processing for disposal. This document reports on researching the characterization documents to determine the types of wastes to be retrieved and where located, waste configurations, conditions, and required methods for retrieval. Also included are discussions of wastes encompassed by Phase 2 for which there are valid reasons to not retrieve.

  7. UNCOVERING BURIED VOLCANOES: NEW DATA FOR PROBABILISTIC VOLCANIC HAZARD ASSESSMENT AT YUCCA MOUNTAIN

    International Nuclear Information System (INIS)

    F.V. Perry

    2005-01-01

    Basaltic volcanism poses a potential hazard to the proposed Yucca Mountain nuclear waste repository because multiple episodes of basaltic volcanism have occurred in the Yucca Mountain region (YMR) in the past 11 Ma. Intervals between eruptive episodes average about 1 Ma. Three episodes have occurred in the Quaternary at approximately 1.1 Ma (5 volcanoes), 350 ka (2 volcanoes), and 80 ka (1 volcano). Because Yucca Mountain lies within the Basin and Range Province, a significant portion of the pre-Quaternary volcanic history of the YMR may be buried in alluvial-filled basins. An exceptionally high-resolution aeromagnetic survey and subsequent drilling program sponsored by the U.S. Department of Energy (DOE) began in 2004 and is gathering data that will enhance understanding of the temporal and spatial patterns of Pliocene and Miocene volcanism in the region (Figure 1). DOE has convened a ten-member expert panel of earth scientists that will use the information gathered to update probabilistic volcanic hazard estimates originally obtained by expert elicitation in 1996. Yucca Mountain is a series of north-trending ridges of eastward-tilted fault blocks that are bounded by north to northeast-trending normal faults. Topographic basins filled with up to 500 m of alluvium surround it to the east, south and west. In the past several decades, nearly 50 holes have been drilled in these basins, mainly for Yucca Mountain Project Site Characterization and the Nye County Early Warning Drilling Program. Several of these drill holes have penetrated relatively deeply buried (300-400 m) Miocene basalt; a Pliocene basalt dated at 3.8 Ma was encountered at a relatively shallow depth (100 m) in the northern Amargosa Desert (Anomaly B in Figure 1). The current drilling program is the first to specifically target and characterize buried basalt. Based on the new aeromagnetic survey and previous air and ground magnetic surveys (Connor et al. 2000; O'Leary et al. 2002), at least eight drill

  8. Waste container and method for containing waste

    International Nuclear Information System (INIS)

    Ono, Akira; Matsushita, Mitsuhiro; Doi, Makoto; Nakatani, Seiichi.

    1990-01-01

    In a waste container, water-proof membranes and rare earth element layers are formed on the inner surface of a steel plate concrete container in which steel plates are embedded. Further, rear earth element detectors are disposed each from the inner side of the steel plate concrete container by way of a pressure pipe to the outer side of the container. As a method for actually containing wastes, when a plurality of vessels in which wastes are fixed are collectively enhoused to the waste container, cussioning materials are attached to the inner surface of the container and wastes fixing containers are stacked successively in a plurality of rows in a bag made of elastic materials. Subsequently, fixing materials are filled and tightly sealed in the waste container. When the waste container thus constituted is buried underground, even if it should be deformed to cause intrusion of rain water to the inside of the container, the rare earth elements in the container dissolved in the rain water can be detected by the detectors, the containers are exchanged before the rain water intruding to the inner side is leached to the surrounding ground, to previously prevent the leakage of radioactive nuclides. (K.M.)

  9. Ground Penetrating Radar Imaging of Buried Metallic Objects

    DEFF Research Database (Denmark)

    Polat, A. Burak; Meincke, Peter

    2001-01-01

    During the past decade there has been considerable research on ground penetrating radar (GPR) tomography for detecting objects such as pipes, cables, mines and barrels buried under the surface of the Earth. While the earlier researches were all based on the assumption of a homogeneous background...

  10. Detection and characterization of buried lunar craters with GRAIL data

    Science.gov (United States)

    Sood, Rohan; Chappaz, Loic; Melosh, Henry J.; Howell, Kathleen C.; Milbury, Colleen; Blair, David M.; Zuber, Maria T.

    2017-06-01

    We used gravity mapping observations from NASA's Gravity Recovery and Interior Laboratory (GRAIL) to detect, characterize and validate the presence of large impact craters buried beneath the lunar maria. In this paper we focus on two prominent anomalies detected in the GRAIL data using the gravity gradiometry technique. Our detection strategy is applied to both free-air and Bouguer gravity field observations to identify gravitational signatures that are similar to those observed over buried craters. The presence of buried craters is further supported by individual analysis of regional free-air gravity anomalies, Bouguer gravity anomaly maps, and forward modeling. Our best candidate, for which we propose the informal name of Earhart Crater, is approximately 200 km in diameter and forms part of the northwestern rim of Lacus Somniorum, The other candidate, for which we propose the informal name of Ashoka Anomaly, is approximately 160 km in diameter and lies completely buried beneath Mare Tranquillitatis. Other large, still unrecognized, craters undoubtedly underlie other portions of the Moon's vast mare lavas.

  11. Classification System for Individualized Treatment of Adult Buried Penis Syndrome.

    Science.gov (United States)

    Tausch, Timothy J; Tachibana, Isamu; Siegel, Jordan A; Hoxworth, Ronald; Scott, Jeremy M; Morey, Allen F

    2016-09-01

    The authors present their experience with reconstructive strategies for men with various manifestations of adult buried penis syndrome, and propose a comprehensive anatomical classification system and treatment algorithm based on pathologic changes in the penile skin and involvement of neighboring abdominal and/or scrotal components. The authors reviewed all patients who underwent reconstruction of adult buried penis syndrome at their referral center between 2007 and 2015. Patients were stratified by location and severity of involved anatomical components. Procedures performed, demographics, comorbidities, and clinical outcomes were reviewed. Fifty-six patients underwent reconstruction of buried penis at the authors' center from 2007 to 2015. All procedures began with a ventral penile release. If the uncovered penile skin was determined to be viable, a phalloplasty was performed by anchoring penoscrotal skin to the proximal shaft, and the ventral shaft skin defect was closed with scrotal flaps. In more complex patients with circumferential nonviable penile skin, the penile skin was completely excised and replaced with a split-thickness skin graft. Complex patients with severe abdominal lipodystrophy required adjacent tissue transfer. For cases of genital lymphedema, the procedure involved complete excision of the lymphedematous tissue, and primary closure with or without a split-thickness skin graft, also often involving the scrotum. The authors' overall success rate was 88 percent (49 of 56), defined as resolution of symptoms without the need for additional procedures. Successful correction of adult buried penis often necessitates an interdisciplinary, multimodal approach. Therapeutic, IV.

  12. Mutation choice to eliminate buried free cysteines in protein therapeutics.

    Science.gov (United States)

    Xia, Xue; Longo, Liam M; Blaber, Michael

    2015-02-01

    Buried free-cysteine (Cys) residues can contribute to an irreversible unfolding pathway that promotes protein aggregation, increases immunogenic potential, and significantly reduces protein functional half-life. Consequently, mutation of buried free-Cys residues can result in significant improvement in the storage, reconstitution, and pharmacokinetic properties of protein-based therapeutics. Mutational design to eliminate buried free-Cys residues typically follows one of two common heuristics: either substitution by Ser (polar and isosteric), or substitution by Ala or Val (hydrophobic); however, a detailed structural and thermodynamic understanding of Cys mutations is lacking. We report a comprehensive structure and stability study of Ala, Ser, Thr, and Val mutations at each of the three buried free-Cys positions (Cys16, Cys83, and Cys117) in fibroblast growth factor-1. Mutation was almost universally destabilizing, indicating a general optimization for the wild-type Cys, including van der Waals and H-bond interactions. Structural response to Cys mutation characteristically involved changes to maintain, or effectively substitute, local H-bond interactions-by either structural collapse to accommodate the smaller oxygen radius of Ser/Thr, or conversely, expansion to enable inclusion of novel H-bonding solvent. Despite the diverse structural effects, the least destabilizing average substitution at each position was Ala, and not isosteric Ser. © 2014 Wiley Periodicals, Inc. and the American Pharmacists Association.

  13. Burying Nutrition Myths and Activating Choices for our Children's ...

    African Journals Online (AJOL)

    Burying Nutrition Myths and Activating Choices for our Children's Development. Lawrence Haddad. Abstract. (Af. J. of Food, Agriculture, Nutrition and Development: 2003 3(1): 56-59). Full Text: EMAIL FREE FULL TEXT EMAIL FREE FULL TEXT · DOWNLOAD FULL TEXT DOWNLOAD FULL TEXT.

  14. Identification of buried victims in natural disaster with GPR method

    Science.gov (United States)

    Dewi, Rianty Kusuma; Kurniawan, Adityo; Taqwantara, Reyhan Fariz; Iskandar, Farras M.; Naufal, Taufiq Ziyan; Widodo

    2017-07-01

    Indonesian is one of the most seismically active regions in the world and has very complicated plate convergence because there is meeting point of several tectonic plates. The complexity of tectonic features causes a lot of natural disasters such as landslides, tsunamis, earth quakes, volcanoes eruption, etc. Sometimes, the disasters occurs in high populated area and causing thousands to millions of victim been buried under the rumble. Unfortunately, the evacuation still uses the conventional method such using rescue dogs whereas the sensitivity of smell is decrease when the victims buried under the level of the ground. The purpose of this study is to detect buried bodies using GPR method, so it can enhance the effectiveness and the efficiency in looking for the disaster victims. GPR method is used because it can investigate things under the ground. A detailed GPR research has been done in Cikutra Graveyard, Bandung, with corpse buried two week until two years before the research. The radar profiles from this research showed amplitude contras anomaly between the new corpse and the old ones. We obtained the amplitude contras at 1.2-1.4 meters under the surface. This method proved to be effective but still need more attention on undulated surface and non-soil areas.

  15. Protection of Buried Pipe under Repeated Loading by Geocell Reinforcement

    Science.gov (United States)

    Khalaj, Omid; Joz Darabi, N.; Moghaddas Tafreshi, S. N.; Mašek, Bohuslav

    2017-12-01

    With increase in cities’ population and development of urbane life, passing buried pipelines near ground’s surface is inevitable in urban areas, roads, subways and highways. This paper presents the results of three-dimensional full scale model tests on high-density polyethylene (HDPE) pipe with diameter of 250 mm in geocell reinforced soil, subjected to repeated loading to simulate the vehicle loads. The effect of geocell’s pocket size (55*55 mm and 110*110 mm) and embedment depth of buried pipe (1.5 and 2 times pipe diameter) in improving the behaviour of buried pipes was investigated. The geocell’s height of 100 mm was used in all tests. The repeated load of 800 kPa was applied on circular loading plate with diameter of 250 mm. The results show that the pipe displacement, soil surface settlement and transferred pressure on the pipe’s crown has been influenced significantly upon the use of geocells. For example, the vertical diametric strain (VDS) and soil surface settlement (SSS), in a way that using a geocell with pocket size of 110*110 mm reduces by 27% and 43%, respectively, compared with the unreinforced one. Meanwhile, by increasing buried depth of pipe from 1.5D to 2D, the use of geocell of 110*110 mm delivers about 50% reduction in SSS and VDS, compared with the unreinforced soil.

  16. Evaluating the movement of active faults on buried pipelines | Parish ...

    African Journals Online (AJOL)

    During the earthquake, a buried pipeline may be experienced extreme loading that is the result of the relatively large displacement of the Earth along the pipe. Large movements of ground could occur by faulting, liquefaction, lateral spreading, landslides, and slope failures. Since the pipelines are widely spread, and in ...

  17. Examination of faults active motion on buried pipelines | Parish ...

    African Journals Online (AJOL)

    ... lateral spreading, landslides and slope failures. Since the pipelines are widely spread, and in some areas necessarily cross through the areas with faults, therefore, improvement study of pipelines in areas with faults is very important. This article explores faults active motion on buried pipelines. Keywords: water utilities ...

  18. Behaviour of nature and technogenic radioisotopes in buried geochemical barriers

    International Nuclear Information System (INIS)

    Kuznetsov, V.A.; Onoshko, M.P.; Generalova, V.A.

    1998-01-01

    Behaviour of potassium 40, radium 226, thorium 232, strontium 90 and cesium 137 on geochemical barriers connected with buried soils and cut-off meander sediments of the Holocene age of the Sozh river valley are examined. Some sides of the barrier geochemical structure caused by syngeneic and epigenetic processes have been taken into consideration

  19. Home range and local movement of small mammals on the Radioactive Waste Management Complex Idaho National Engineering Laboratory Site

    International Nuclear Information System (INIS)

    Groves, C.R.

    1978-01-01

    In April 1978, a study of local movement of small mammals on the Subsurface Disposal Area (SDA) of the Radioactive Waste Management Complex (RWMC) was undertaken in conjunction with a study of rodent dispersal. Live trapping in May and June revealed a strong potential for the detection of local movement of at least four species of rodents. Information on this movement is important as each species, during burrowing, may transport radioactive waste from the point of interment to the surface. The area over which contamination may be spread, as fecal deposits or as metabolically incorporated elements, is a function of the daily movement of each animal. At least eight factors may effect size and shape of home range. These factors are discussed, techniques employed in the calculation of home range are outlined, and problems associated with live trapping and studying local movement of small mammals are considered

  20. Bearing and Range Estimation Algorithm for Buried Object in Underwater Acoustics

    Directory of Open Access Journals (Sweden)

    Dong Han

    2009-01-01

    (DOA of objects and objects-sensors distances, is used in MUSIC algorithm instead of classical model. The influence of the depth of buried objects is discussed. Finally, the numerical results are given in the case of buried cylindrical shells.

  1. Electrical properties and radiation hardness of SOI systems with multilayer buried dielectric

    International Nuclear Information System (INIS)

    Barchuk, I.P.; Kilchitskaya, V.I.; Lysenko, V.S.

    1997-01-01

    In this work SOI structures with buried SiO 2 -Si 3 N 4 -SiO 2 layers have been fabricated by the ZMR-technique with the aim of improving the total dose radiation hardness of the buried dielectric layer. To optimize the fabrication process, buried layers were investigated by secondary ion mass spectrometry before and after the ZMR process, and the obtained results were compared with electrical measurements. It is shown that optimization of the preparation processes of the initial buried dielectric layers provides ZMR SOI structures with multilayer buried isolation, which are of high quality for both Si film interfaces. Particular attention is paid to the investigation of radiation-induced charge trapping in buried insulators. Buried isolation structures with a nitride layer exhibit significant reduction of radiation-induced positive charge as compared to classical buried SiO 2 layers produced by either the ZMR or the SIMOX technique

  2. Integrated approach to hazardous and radioactive waste remediation

    International Nuclear Information System (INIS)

    Hyde, R.A.; Reece, W.J.

    1994-01-01

    The US Department of Energy Office of Technology Development is supporting the demonstration, and evaluation of a suite of waste retrieval technologies. An integration of leading-edge technologies with commercially available baseline technologies will form a comprehensive system for effective and efficient remediation of buried waste throughout the complex of DOE nuclear facilities. This paper discusses the complexity of systems integration, addressing organizational and engineering aspects of integration as well as the impact of human operators, and the importance of using integrated systems in remediating buried hazardous and radioactive waste

  3. Seismic response of buried pipelines: a state-of-the-art review

    International Nuclear Information System (INIS)

    Datta, T.K.

    1999-01-01

    A state-of-the-art review of the seismic response of buried pipelines is presented. The review includes modeling of soil-pipe system and seismic excitation, methods of response analysis of buried pipelines, seismic behavior of buried pipelines under different parametric variations, seismic stresses at the bends and intersections of network of pipelines. pipe damage in earthquakes and seismic risk analysis of buried pipelines. Based on the review, the future scope of work on the subject is outlined. (orig.)

  4. Current Program for the management of U.S. Department of Energy transuranic waste

    International Nuclear Information System (INIS)

    Harms, T.

    1994-01-01

    The existing inventory of TRU waste can be divided into tow distinct components: (1) retrievably stored TRU waste and (2) buried TRU waste. The distinction between open-quotes storedclose quotes and open-quotes buriedclose quotes TRU waste was established in 1970 when the Atomic Energy Commission (AEC) determined that TRU-contaminated waste, when disposed, should have more effective isolation from the environment than the confinement provided by burial in pits and trenches covered with soil. Buried TRU (and contaminated soils surrounding buried TRU) are the results of disposal operations carried out at DOE sites prior to the 1970 decision. The inventory of buried TRU is 190,600 m 3 . This waste is the responsibility of the Office of Environmental Restoration (EM-40). All TRU waste generated since 1970 has been placed in storage at six DOE sites. This storage was designed with a lifetime expected to be 20 years. The waste is stored in retrievable form for eventual shipment and disposal at a geologic repository. Currently, TRU waste is contained in a variety of packaging, including metal drums and wooden and metal boxes, and stored in earth-mounded berms, concrete culverts, or other facilities. At the end of 1991, there were approximately 64,000 m 3 of retrievably stored TRU waste. With the WIPP facility not becoming operational until the year 2000 or later, the DOE must effectively manage this waste in other manners. The issues regarding the management of TRU wastes is described

  5. Mixed Waste Working Group report

    International Nuclear Information System (INIS)

    1993-01-01

    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

  6. Vadose zone monitoring at the radioactive waste management complex, Idaho National Engineering Laboratory

    International Nuclear Information System (INIS)

    McElroy, D.L.; Hubbell, J.M.

    1989-01-01

    A network of vadose zone instruments was installed in surficial sediments and sedimentary interbeds beneath the Radioactive Waste Management Complex (RWMC) of the Idaho National Engineering Laboratory. The network of instruments monitor moisture movement in a heterogeneous geologic system comprised of sediments which overlie and are intercalated with basalt flows. The general range of matric potentials in the surficial sediments (0 to 9.1 m) was from saturation to -3 bars. The basalt layer beneath the surficial sediments impedes downward water movement. The general range of matric potentials in the 9-, 34- and 73-m interbeds was from -0.3 to 1.7 bars. Preliminary results indicated downward moisture movement through the interbeds. 8 refs., 9 figs., 1 tab

  7. Nuclear Waste Management under Approaching Disaster

    NARCIS (Netherlands)

    Ilg, Patrick; Gabbert, Silke; Weikard, Hans Peter

    2017-01-01

    This article compares different strategies for handling low- and medium-level nuclear waste buried in a retired potassium mine in Germany (Asse II) that faces significant risk of uncontrollable brine intrusion and, hence, long-term groundwater contamination. We survey the policy process that has

  8. Buried Porous Silicon-Germanium Layers in Monocrystalline Silicon Lattices

    Science.gov (United States)

    Fathauer, Robert W. (Inventor); George, Thomas (Inventor); Jones, Eric W. (Inventor)

    1998-01-01

    Monocrystalline semiconductor lattices with a buried porous semiconductor layer having different chemical composition is discussed and monocrystalline semiconductor superlattices with a buried porous semiconductor layers having different chemical composition than that of its monocrystalline semiconductor superlattice are discussed. Lattices of alternating layers of monocrystalline silicon and porous silicon-germanium have been produced. These single crystal lattices have been fabricated by epitaxial growth of Si and Si-Ge layers followed by patterning into mesa structures. The mesa structures are strain etched resulting in porosification of the Si-Ge layers with a minor amount of porosification of the monocrystalline Si layers. Thicker Si-Ge layers produced in a similar manner emitted visible light at room temperature.

  9. Detection of Buried Inhomogeneous Elliptic Cylinders by a Memetic Algorithm

    OpenAIRE

    Caorsi, Salvatore; Massa, Andrea; Pastorino, Matteo; Raffetto, Mirco; Randazzo, Andrea

    2003-01-01

    The application of a global optimization procedure to the detection of buried inhomogeneities is studied in the present paper. The object inhomogeneities are schematized as multilayer infinite dielectric cylinders with elliptic cross sections. An efficient recursive analytical procedure is used for the forward scattering computation. A functional is constructed in which the field is expressed in series solution of Mathieu functions. Starting by the input scattered data, the iterative minimiza...

  10. Descriptive summary of airblast effects for buried cratering detonations

    International Nuclear Information System (INIS)

    Snell, C.M.

    1976-01-01

    Detonation of a buried nuclear or high-explosive charge induces an airblast signal in the air above the explosion site. The waveform of this signal may be complex, involving features created by ground surface motion effects, venting and expansion of gas from the explosive cavity, and energy release through an unstemmed or partly stemmed emplacement hole. The basic physical mechanisms responsible for the airblast pulse and some of the techniques commonly used to predict airblast effects are described

  11. The Thermal Regime Around Buried Submarine High-Voltage Cables

    Science.gov (United States)

    Emeana, C. J.; Dix, J.; Henstock, T.; Gernon, T.; Thompson, C.; Pilgrim, J.

    2015-12-01

    The expansion of offshore renewable energy infrastructure and the desire for "trans-continental shelf" power transmission, all require the use of submarine High Voltage (HV) cables. These cables have maximum operating surface temperatures of up to 70oC and are typically buried at depths of 1-2 m beneath the seabed, within the wide range of substrates found on the continental shelf. However, the thermal properties of near surface shelf sediments are poorly understood and this increases the uncertainty in determining the required cable current ratings, cable reliability and the potential effects on the sedimentary environments. We present temperature measurements from a 2D laboratory experiment, designed to represent a buried, submarine HV cable. We used a large (2.5 m-high) tank, filled with water-saturated ballotini and instrumented with 120 thermocouples, which measured the time-dependent 2D temperature distributions around the heat source. The experiments use a buried heat source to represent a series of realistic cable surface temperatures with the aim for identifying the thermal regimes generated within typical non-cohesive shelf sediments: coarse silt, fine sand and very coarse sand. The steady state heat flow regimes, and normalised and radial temperature distributions were assessed. Our results show that at temperatures up to 60°C above ambient, the thermal regimes are conductive for the coarse silt sediments and convective for the very coarse sand sediments even at 7°C above ambient. However, the heat flow pattern through the fine sand sediment shows a transition from conductive to convective heat flow at a temperature of approximately 20°C above ambient. These findings offer an important new understanding of the thermal regimes associated with submarine HV cables buried in different substrates and has huge impacts on cable ratings as the IEC 60287 standard only considers conductive heat flow as well as other potential near surface impacts.

  12. Investigation of guided waves propagation in pipe buried in sand

    International Nuclear Information System (INIS)

    Leinov, Eli; Cawley, Peter; Lowe, Michael J.S.

    2014-01-01

    The inspection of pipelines by guided wave testing is a well-established method for the detection of corrosion defects in pipelines, and is currently used routinely in a variety of industries, e.g. petrochemical and energy. When the method is applied to pipes buried in soil, test ranges tend to be significantly compromised because of attenuation of the waves caused by energy radiating into the soil. Moreover, the variability of soil conditions dictates different attenuation characteristics, which in-turn results in different, unpredictable, test ranges. We investigate experimentally the propagation and attenuation characteristics of guided waves in pipes buried in fine sand using a well characterized full scale experimental apparatus. The apparatus consists of an 8 inch-diameter, 5.6-meters long steel pipe embedded over 3 meters of its length in a rectangular container filled with fine sand, and an air-bladder for the application of overburden pressure. Longitudinal and torsional guided waves are excited in the pipe and recorded using a transducer ring (Guided Ultrasonics Ltd). Acoustic properties of the sand are measured independently in-situ and used to make model predictions of wave behavior in the buried pipe. We present the methodology and the systematic measurements of the guided waves under a range of conditions, including loose and compacted sand. It is found that the application of overburden pressure modifies the compaction of the sand and increases the attenuation, and that the measurement of the acoustic properties of sand allows model prediction of the attenuation of guided waves in buried pipes with a high level of confidence

  13. Vapor vacuum extraction treatability study at the Idaho National Engineering Laboratory

    International Nuclear Information System (INIS)

    Herd, M.D.; Matthern, G.; Michael, D.L.; Spang, N.; Downs, W.; Weidner, J.; Cleary, P.

    1993-01-01

    During the 1960s and early 1970s, barreled mixed waste containing volatile organic compounds (VOCS) and radioactive waste was buried at the Subsurface Disposal Area (SDA) at the Idaho National Engineering Laboratory (INEL) Radioactive Waste Management Complex (RWMC). Over time, some of the barrels have deteriorated allowing, VOC vapors to be released into the vadose zone. The primary VOC contaminates of concern are CCl 4 and trichloroethylene; however, chloroform, tetrachloroethylene, and 1,1,1-trichloroethane have also been detected. Vapor Vacuum Extraction (VVE) is one alternative being considered for remediation of the RWMC SDA vadose zone. A proposed pilot-scale treatability study (TS) will provide operation and maintenance costs for the design of the potential scale-up of the system

  14. [Congenital buried penis in the child: about a case].

    Science.gov (United States)

    Rami, Mohamed; Bakkaly, Achraf El; Bouljrouf, Jaouad; Lafia, Toualouth; Bouhafs, Mohammed Amine; Belkacem, Rachid

    2017-01-01

    Congenital buried penis in the child is a congenital malformation where the penis appears small in size while all the parts of the organ are normal (the urethra, the erectile tissue and the glans penis). Our study aimed to describe our experience in the surgical treatment of this abnormality. We report the case of a 18-months old infant with bilateral hydrocele initially admitted to the Emergency Department and then referred to our Department. Clinical examination showed buried penis with tight foreskin and a dilation of the preputial reservoir due to urine. Surgical procedure included several steps: Z-shaped incision, pulling back of the foreskin of the penis, release of the adhesions surrounding the corpus cavernosum and ventral penile skin coverage using bladder catheter kept for a week to protect the wound healing. Aesthetic and functional result was satisfactory after 1-year follow-up. Congenital buried penis is a very debated subject in the literature. Our technique was simple and easily reproducible. Voiding difficulties and urinary infection are the main indications of this surgical procedure.

  15. New Technique for the Treatment of Buried Penis in Children.

    Science.gov (United States)

    Liu, Feng; Lin, Tao; He, Dawei; Wei, Guanghui; Liu, Junhong; Liu, Xing; Hua, Yi; Zhang, Deying; Lu, Peng; Wu, Shengde; Li, Xuliang

    2016-02-01

    To present our treatment experience of buried penis, which has no consensus therapeutic technique for all cases of buried penis, by using a new technique for the repair of this condition, in which the approach is through the ventral penile root. We performed a retrospective review of 153 patients (median age: 6.5 years) who underwent repair of a buried penis between March 2005 and March 2013. The technique involves the creation of a wedge-shaped cut of the ventral penile skin, followed by fixation of the subcutaneous penile skin at the base of the degloved penis to the Buck fascia at the 2- and 10-o'clock positions. The ventral outer preputial skin is split down the midline, and the dorsal inner preputial skin is cut with oblique incision. All patients were followed for an average of 12 months after repair. Other than 2 cases (1.3%) of trapped penis with a ring of scar tissue, which required subsequent excision, there were no complications and the cosmetic appearance was satisfactory. The described ventral penile approach is a simple and effective procedure with good cosmetic outcomes and few complications. Copyright © 2016 Elsevier Inc. All rights reserved.

  16. Quantification of Methamphetamine in Mouse Thighbones Buried in Soil.

    Science.gov (United States)

    Nakao, Ken-Ichiro; Tatara, Yuki; Kibayashi, Kazuhiko

    2017-11-01

    Bone samples are used for analysis of drugs in decomposed or skeletonized bodies. Toxicological analyses of buried bones are important for determining the causes and circumstances of death. In this study, methamphetamine and amphetamine concentrations in heart blood, thigh muscles, and thighbones were analyzed using solid-phase extraction with liquid chromatography-tandem mass spectrometry. Methamphetamine concentrations in heart blood, thigh muscle, and thighbone ranged from 0.041 to 0.873 μg/mL, 0.649 to 2.623 μg/g, and 56.543 to 643.371 μg/g, respectively. Thighbone concentrations were significantly higher than those in heart blood or thigh muscles were. Methamphetamine concentrations in buried thighbone (4.010-45.785 μg/g) were significantly lower than those of unburied thighbones were (56.543-643.371 μg/g). Methamphetamine and amphetamine were detected in thighbones buried for 7-180 days. These findings indicate that the methamphetamine concentrations in bone are higher and decrease after burial in soil. © 2017 American Academy of Forensic Sciences.

  17. Tabernaemontana divaricata leaves extract exacerbate burying behavior in mice

    Directory of Open Access Journals (Sweden)

    Raj Chanchal

    2015-06-01

    Full Text Available Objective: Tabernaemontana divaricata (TD from Apocynaceae family offers the traditional folklore medicinal benefits such as an anti-epileptic, anti-mania, brain tonic, and anti-oxidant. The aim of the present study was to evaluate the effect of ethanolic extract of TD leaves on burying behavior in mice. Materials and Methods:Mice were treated with oral administration (p.o. of ethanolic extract of TD (100, 200, and 300 mg/kg. Fluoxetine (FLX, a selective serotonin reuptake inhibitor was used as a reference drug. Obsessive-compulsive behavior was evaluated using marble-burying apparatus. Results:TD at doses of 100, 200, and 300 mg/kg dose-dependently inhibited the obsessive and compulsive behavior. The similar results were obtained from 5, 10, and 20 mg/kg of FLX. TD and FLX did not affect motor activity. Conclusion: The results indicated that TD and FLX produced similar inhibitory effects on marble-burying behavior.

  18. A metallic buried interconnect process for through-wafer interconnection

    International Nuclear Information System (INIS)

    Ji, Chang-Hyeon; Herrault, Florian; Allen, Mark G

    2008-01-01

    In this paper, we present the design, fabrication process and experimental results of electroplated metal interconnects buried at the bottom of deep silicon trenches with vertical sidewalls. A manual spray-coating process along with a unique trench-formation process has been developed for the electroplating of a metal interconnection structure at the bottom surface of the deep trenches. The silicon etch process combines the isotropic dry etch process and conventional Bosch process to fabricate a deep trench with angled top-side edges and vertical sidewalls. The resulting trench structure, in contrast to the trenches fabricated by wet anisotropic etching, enables spray-coated photoresist patterning with good sidewall and top-side edge coverage while maintaining the ability to form a high-density array of deep trenches without excessive widening of the trench opening. A photoresist spray-coating process was developed and optimized for the formation of electroplating mold at the bottom of 300 µm deep trenches having vertical sidewalls. A diluted positive tone photoresist with relatively high solid content and multiple coating with baking between coating steps has been experimentally proven to provide high quality sidewall and edge coverage. To validate the buried interconnect approach, a three-dimensional daisy chain structure having a buried interconnect as the bottom connector and traces on the wafer surface as the top conductor has been designed and fabricated

  19. High-resolution subsurface imaging and neural network recognition: Non-intrusive buried substance location. Final report

    Energy Technology Data Exchange (ETDEWEB)

    Sternberg, B.K.; Poulton, M.M.

    1997-01-26

    A high-frequency, high-resolution electromagnetic (EM) imaging system has been developed for environmental geophysics surveys. Some key features of this system include: (1) rapid surveying to allow dense spatial sampling over a large area, (2) high-accuracy measurements which are used to produce a high-resolution image of the subsurface, (3) measurements which have excellent signal-to-noise ratio over a wide bandwidth (31 kHz to 32 MHz), (4) elimination of electric-field interference at high frequencies, (5) large-scale physical modeling to produce accurate theoretical responses over targets of interest in environmental geophysics surveys, (6) rapid neural network interpretation at the field site, and (7) visualization of complex structures during the survey. Four major experiments were conducted with the system: (1) Data were collected for several targets in our physical modeling facility. (2) The authors tested the system over targets buried in soil. (3) The authors conducted an extensive survey at the Idaho National Engineering Laboratory (INEL) Cold Test Pit (CTP). The location of the buried waste, category of waste, and thickness of the clay cap were successfully mapped. (4) The authors ran surveys over the acid pit at INEL. This was an operational survey over a hot site. The interpreted low-resistivity region correlated closely with the known extent of the acid pit.

  20. High-resolution subsurface imaging and neural network recognition: Non-intrusive buried substance location. Final report

    International Nuclear Information System (INIS)

    Sternberg, B.K.; Poulton, M.M.

    1997-01-01

    A high-frequency, high-resolution electromagnetic (EM) imaging system has been developed for environmental geophysics surveys. Some key features of this system include: (1) rapid surveying to allow dense spatial sampling over a large area, (2) high-accuracy measurements which are used to produce a high-resolution image of the subsurface, (3) measurements which have excellent signal-to-noise ratio over a wide bandwidth (31 kHz to 32 MHz), (4) elimination of electric-field interference at high frequencies, (5) large-scale physical modeling to produce accurate theoretical responses over targets of interest in environmental geophysics surveys, (6) rapid neural network interpretation at the field site, and (7) visualization of complex structures during the survey. Four major experiments were conducted with the system: (1) Data were collected for several targets in our physical modeling facility. (2) The authors tested the system over targets buried in soil. (3) The authors conducted an extensive survey at the Idaho National Engineering Laboratory (INEL) Cold Test Pit (CTP). The location of the buried waste, category of waste, and thickness of the clay cap were successfully mapped. (4) The authors ran surveys over the acid pit at INEL. This was an operational survey over a hot site. The interpreted low-resistivity region correlated closely with the known extent of the acid pit

  1. High-resolution subsurface imaging and neural network recognition: Non-intrusive buried substance location. Final report, January 26, 1997

    International Nuclear Information System (INIS)

    Sternberg, B.K.; Poulton, M.M.

    1998-01-01

    A high-frequency, high-resolution electromagnetic (EIVI) imaging system has been developed for environmental geophysics surveys. Some key features of this system include: (1) rapid surveying to allow dense spatial sampling over a large area, (2) high-accuracy measurements which are used to produce a high-resolution image of the subsurface, (3) measurements which have excellent signal-to-noise ratio over a wide bandwidth (31 kHz to 32 MHZ), (4) elimination of electric-field interference at high frequencies, (5) large-scale physical modeling to produce accurate theoretical responses over targets of interest in environmental geophysics surveys, (6) rapid neural network interpretation at the field site, and (7) visualization of complex structures during the survey. Four major experiments were conducted with the system: (1) Data were collected for several targets in our physical modeling facility. (2) We tested the system over targets buried in soil. (3) We conducted an extensive survey at the Idaho National Engineering Laboratory (INEL) Cold Test Pit (CTP). The location of the buried waste, category of waste, and thickness of the clay cap were successfully mapped. (4) We ran surveys over the acid pit at INEL. This was an operational survey over a hot site. The interpreted low-resistivity region correlated closely with the known extent of the acid pit

  2. Processing vessel for high level radioactive wastes

    International Nuclear Information System (INIS)

    Maekawa, Hiromichi

    1998-01-01

    Upon transferring an overpack having canisters containing high level radioactive wastes sealed therein and burying it into an underground processing hole, an outer shell vessel comprising a steel plate to be fit and contained in the processing hole is formed. A bury-back layer made of dug earth and sand which had been discharged upon forming the processing hole is formed on the inner circumferential wall of the outer shell vessel. A buffer layer having a predetermined thickness is formed on the inner side of the bury-back layer, and the overpack is contained in the hollow portion surrounded by the layer. The opened upper portion of the hollow portion is covered with the buffer layer and the bury-back layer. Since the processing vessel having a shielding performance previously formed on the ground, the state of packing can be observed. In addition, since an operator can directly operates upon transportation and burying of the high level radioactive wastes, remote control is no more necessary. (T.M.)

  3. Strategies for managing rival bacterial communities: Lessons from burying beetles.

    Science.gov (United States)

    Duarte, Ana; Welch, Martin; Swannack, Chris; Wagner, Josef; Kilner, Rebecca M

    2018-03-01

    The role of bacteria in animal development, ecology and evolution is increasingly well understood, yet little is known of how animal behaviour affects bacterial communities. Animals that benefit from defending a key resource from microbial competitors are likely to evolve behaviours to control or manipulate the animal's associated external microbiota. We describe four possible mechanisms by which animals could gain a competitive edge by disrupting a rival bacterial community: "weeding," "seeding," "replanting" and "preserving." By combining detailed behavioural observations with molecular and bioinformatic analyses, we then test which of these mechanisms best explains how burying beetles, Nicrophorus vespilloides, manipulate the bacterial communities on their carcass breeding resource. Burying beetles are a suitable species to study how animals manage external microbiota because reproduction revolves around a small vertebrate carcass. Parents shave a carcass and apply antimicrobial exudates on its surface, shaping it into an edible nest for their offspring. We compared bacterial communities in mice carcasses that were either fresh, prepared by beetles or unprepared but buried underground for the same length of time. We also analysed bacterial communities in the burying beetle's gut, during and after breeding, to understand whether beetles could be "seeding" the carcass with particular microbes. We show that burying beetles do not "preserve" the carcass by reducing bacterial load, as is commonly supposed. Instead, our results suggest they "seed" the carcass with bacterial groups which are part of the Nicrophorus core microbiome. They may also "replant" other bacteria from the carcass gut onto the surface of their carrion nest. Both these processes may lead to the observed increase in bacterial load on the carcass surface in the presence of beetles. Beetles may also "weed" the bacterial community by eliminating some groups of bacteria on the carcass, perhaps through

  4. Long-term management USDOE transuranic waste

    International Nuclear Information System (INIS)

    Bennett, W.S.; Gilbert, K.V.; Lowrey, R.Y.

    1982-01-01

    Activities for permanent disposal of US DOE TRU waste are presently focused on newly generated and stored waste. The buried waste and contaminated soils pose no near term problem. Decisions on any possible actions for these wastes will be deferred until the newly generated and stored wastes are being placed into disposal on a routine basis. Several elements must be in place before such disposal can become routine. These elements consist of: a disposal facility; waste acceptance criteria; waste certification mechanisms; waste processing facilities; and a waste transportation system. Each of these elements has been the subject of considerable activity in the recent past. Progress and plans for each element are summarized. As of January 1981, DOE has 60,500 m 3 of waste classified as Transuranic waste (TRU) in retrievable storage, and projects that additional TRU waste will be generated at an average rate of 4500 m 3 per year for the next 10 years. Over 99% of this waste is contact handled, with the remainder being remote handled, i.e., surface radiation dose levels exceeding 200 mrem/h. An estimated 273,000 m 3 of TRU waste were placed in shallow land burial prior to establishment of the 1970 policy. In addition, large quantities of soil at DOE sites are contaminated with TRU elements due to disposal of liquid wastes and by contact of soil with solid, buried waste whose original containers are now badly degraded. Possibly as much as 10,000,000 m 3 of soil are contaminated above 10 nCi/gm. Less than 1,000,000 m 3 are estimated to be contaminated above 100 nCi/gm

  5. Characteristics of transuranic waste at Department of Energy sites

    International Nuclear Information System (INIS)

    Jensen, R.T.; Wilkinson, F.J. III.

    1983-05-01

    This document reports data and information on TRU waste from all DOE generating and storage sites. The geographical location of the sites is shown graphically. There are four major sections in this document. The first three cover the TRU waste groups known as Newly Generated, Stored, and Buried Wastes. Subsections are included under Newly Generated and Stored on contact-handled and remote-handled waste. These classifications of waste are defined, and the current or expected totals of each are given. Figure 1.3 shows the total amount of Buried and Stored TRU waste. Preparation of this document began in 1981, and most of the data are as of December 31, 1980. In a few cases data were reported to December 31, 1981, and these have been noted. The projections in the Newly Generated section were made, for the most part, at the end of 1981

  6. Laboratory-performance criteria for in situ waste-stabilization materials

    International Nuclear Information System (INIS)

    Shaw, P.; Weidner, J.

    1996-01-01

    The Department of Energy (DOE) Landfill Stabilization Focus Area is investigating a variety of in situ placement methods, grout materials, and characterization techniques for the stabilization of buried low-level transuranic-contaminated waste at Department of Energy sites. In situ stabilization involves underground injection or placement of substances to isolate, treat, or contain buried contaminants. Performance criteria were developed to evaluate various candidate stabilization materials for both long-term stabilization and interim stabilization or retrieval. The criteria are go/no-go, ready, and preliminary. The criterion go/no-go eliminates technologies that are not applicable for in situ treatment of buried waste. The criterion ready indicates that the technology is sufficiently developed and proven to be field demonstrated full-scale. The criterion preliminary indicates the prospective technologies to be potentially applicable to in situ buried waste stabilization, but further development is needed before the technology is ready for field-scale demonstration

  7. TRU [transuranic] waste certification compliance requirements for acceptance of newly generated contact-handled wastes to be shipped to the Waste Isolation Pilot Plant: Revision 2

    International Nuclear Information System (INIS)

    1989-01-01

    Compliance requirements are presented for certifying that unclassified, newly generated (NG), contact-handled (CH) transuranic (TRU) solid wastes from defense programs meet the Waste Isolation Pilot Plant (WIPP) Waste Acceptance Criteria (WAC). Where appropriate, transportation and interim storage requirements are incorporated; however, interim storage sites may have additional requirements consistent with these requirements. All applicable Department of Energy (DOE) orders must continue to be met. The compliance requirements for stored or buried waste are not addressed in this document. The compliance requirements are divided into four sections, primarily determined by the general feature that the requirements address. These sections are General Requirements, Waste Container Requirements, Waste Form Requirements, and Waste Package Requirements. The waste package is the combination of waste container and waste. 10 refs., 1 fig

  8. 1st Quarter Transportation Report FY 2015: Radioactive Waste Shipments to and from the Nevada National Security Site (NNSS)

    Energy Technology Data Exchange (ETDEWEB)

    Gregory, Louis [National Security Technologies, LLC, Las Vegas, NV (United States)

    2015-02-20

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

  9. Separations: The path to waste minimization

    International Nuclear Information System (INIS)

    Bell, J.T.

    1992-01-01

    Waste materials usually are composed of large amounts of innocuous and frequently useful components mixed with lesser amounts of one or more hazardous components. The ultimate path to waste minimization is the separation of the lesser quantities of hazardous components from the innocuous components, and then recycle the useful components. This vision is so simple that everyone would be expected to properly manage waste. Several parameters interfere with this proper waste management, which encourages the open-quotes sweep it under the rugclose quotes or the open-quotes bury it allclose quotes attitudes, both of which delay and complicate proper waste management. The two primary parameters that interfere with proper waste management are: economics drives a process to a product without concerns of waste minimization, and emergency needs for immediate production of a product usually delays proper waste management. A third parameter in recent years is also interfering with proper waste management: quick relief of waste insults to political and public perceptions is promoting the open-quotes bury it allclose quotes attitude. A fourth parameter can promote better waste management for any scenario that suffers either or all of the first three parameters: separations technology can minimize wastes when the application of this technology is not voided by influence of the first three parameters. The US Department of Energy's management of nuclear waste has been seriously affected by the above four parameters. This paper includes several points about how the generation and management of DOE wastes have been, and continue to be, affected by these parameters. Particular separations technologies for minimizing the DOE wastes that must be stored for long periods are highlighted

  10. Storing solid radioactive wastes at the Savannah River Plant

    International Nuclear Information System (INIS)

    Horton, J.H.; Corey, J.C.

    1976-06-01

    The facilities and the operation of solid radioactive waste storage at the Savannah River Plant (SRP) are discussed in the report. The procedures used to segregate and the methods used to store radioactive waste materials are described, and the monitoring results obtained from studies of the movement of radionuclides from buried wastes at SRP are summarized. The solid radioactive waste storage site, centrally located on the 192,000-acre SRP reservation, was established in 1952 to 1953, before any radioactivity was generated onsite. The site is used for storage and burial of solid radioactive waste, for storage of contaminated equipment, and for miscellaneous other operations. The solid radioactive waste storage site is divided into sections for burying waste materials of specified types and radioactivity levels, such as transuranium (TRU) alpha waste, low-level waste (primarily beta-gamma), and high-level waste (primarily beta-gamma). Detailed records are kept of the burial location of each shipment of waste. With the attention currently given to monitoring and controlling migration, the solid wastes can remain safely in their present location for as long as is necessary for a national policy to be established for their eventual disposal. Migration of transuranium, activation product, and fission product nuclides from the buried wastes has been negligible. However, monitoring data indicate that tritium is migrating from the solid waste emplacements. Because of the low movement rate of ground water, the dose-to-man projection is less than 0.02 man-rem for the inventory of tritium in the burial trenches. Limits are placed on the amounts of beta-gamma waste that can be stored so that the site will require minimum surveillance and control. The major portion (approximately 98 percent) of the transuranium alpha radioactivity in the waste is stored in durable containers, which are amenable to recovery for processing and restorage should national policy so dictate

  11. Mathematical model and simulations of radiation fluxes from buried radionuclides

    International Nuclear Information System (INIS)

    Ahmad Saat

    1999-01-01

    A mathematical model and a simple Monte Carlo simulations were developed to predict radiation fluxes from buried radionuclides. The model and simulations were applied to measured (experimental) data. The results of the mathematical model showed good acceptable order of magnitude agreement. A good agreement was also obtained between the simple simulations and the experimental results. Thus, knowing the radionuclide distribution profiles in soil from a core sample, it can be applied to the model or simulations to estimate the radiation fluxes emerging from the soil surface. (author)

  12. High ion temperatures from buried layers irradiated with Vulcan Petawatt

    International Nuclear Information System (INIS)

    Karsch, S.; Schreiber, J.; Willingale, L.; Lancaster, K.; Habara, H.; Nilson, P.; Gopal, A.; Wei, M. S.; Stoeckl, C.; Evans, R.; Clarke, R.; Heathcote, R.; Najmudin, Z.; Krushelnick, K.; Neely, D.; Norreys, P. A.

    2005-01-01

    Deuteron acceleration from CH/CD/CH layer targets irradiated with PW laser pulses has been studied using. Thomson parabola spectrometers and neutron TOF spectroscopy. The measured ion and neutron spectra reveal significant MeV deuteron acceleration from the deeply buried CD layer, which scales with the thickness of the overlying CH layer. While the neutron spectra reveal the scaling of the thermal heating with target thickness, the ion spectra indicate the presence of an efficient nonthermal acceleration mechanism inside. the bulk. Possible explanations will be discussed. (Author)

  13. Response of Buried Vertically Oriented Cylinders to Dynamic Loading,

    Science.gov (United States)

    1980-06-01

    BALSARA • , . / ,, _,-, -. 1i S ,LESPONSE OF BURIED VERTICALLY 9RIENTED CYLINDERS 𔃺 .-TO DINAMIC LOADING_ 9AYLE E. LRTOrwW&-N JIIMY P./BALSARA Nk...1.7, 2,8, and 4.0 inches). The end caps for the cylinders consisted of a steel shell filled with high- strength concrete; however, the end caps were...not designed to be test articles. The average concrete compressive strength of the cylinders on test day was 44.0 MPa (6,380 psi). The three DEOT

  14. Waste Characterization Facility at the Idaho National Engineering Laboratory. Environmental Assessment

    International Nuclear Information System (INIS)

    1995-02-01

    DOE has prepared an Environmental Assessment (EA) on the proposed construction and operation of a Waste Characterization Facility (WCF) at INEL. This facility is needed to examine and characterize containers of transuranic (TRU) waste to certify compliance with transport and disposal criteria; to obtain information on waste constituents to support proper packaging, labeling, and storage; and to support development of treatment and disposal plans for waste that cannot be certified. The proposed WCF would be constructed at the Radioactive Waste Management Complex (RWMC). In accordance with the Council on Environmental Quality (CEQ) requirements in 40 CFR Parts 1500-1508, the EA examined the potential environmental impacts of the proposed WCF and discussed potential alternatives. Based on the analyses in the EA, DOE has determined that the proposed action does not constitute a major Federal action significantly affecting the quality of the human environment within the meaning of the National Environmental Policy Act (NEPA) of 1969, and CEQ regulations at 40 CFR 1508.18 and 1508.27. Therefore, an Environmental Impact Statement is not required, and DOE is issuing this Finding of No Significant Impact

  15. Sexual and Overall Quality of Life Improvements After Surgical Correction of "Buried Penis".

    Science.gov (United States)

    Hughes, Duncan B; Perez, Edgar; Garcia, Ryan M; Aragón, Oriana R; Erdmann, Detlev

    2016-05-01

    "Buried penis" is an increasing burden in our population with many possible etiologies. Although surgical correction of buried penis can be rewarding and successful for the surgeon, the psychological and functional impact of buried penis on the patient is less understood. The study's aim was to evaluate the sexual satisfaction and overall quality of life before and after buried penis surgery in a single-surgeon's patient population using a validated questionnaire (Changes in Sexual Functioning Questionnaire short-form). Using Likert scales generated from the questionnaire and 1-tailed paired t test analysis, we found that there was significantly improved sexual function after correction of a buried penis. Variables individually showed that there was significant improvement with sexual pleasure, urinating, and with genital hygiene postoperatively. There were no significant differences concerning frequency of pain with orgasms. Surgical correction of buried penis significantly improves the functional, sexual, and psychological aspects of patient's lives.

  16. Oxygen dynamics around buried lesser sandeels Ammodytes tobianus (Linnaeus 1785): mode of ventilation and oxygen requirements

    DEFF Research Database (Denmark)

    Behrens, Jane W; Stahl, Henrik J; Steffensen, John F

    2007-01-01

    The oxygen environment around buried sandeels (Ammodytes tobianus) was monitored by planar optodes. The oxygen penetration depth at the sediment interface was only a few mm. Thus fish, typically buried at 1-4 cm depth, were generally in anoxic sediment. However, they induced an advective transport...... down along the body, referred to as ;plume ventilation'. Yet, within approximately 30 min the oxic plume was replenished by oxygen-depleted water from the gills. The potential for cutaneous respiration by the buried fish was thus of no quantitative importance. Calculations derived by three independent...... methods (each with N=3) revealed that the oxygen uptake of sandeel buried for 6-7 h was 40-50% of previous estimates on resting respirometry of non-buried fish, indicating lower O(2) requirements during burial on a diurnal timescale. Buried fish exposed to decreasing oxygen tensions gradually approached...

  17. Transuranic (TRU) Waste Repackaging at the Nevada Test Site

    International Nuclear Information System (INIS)

    Di Sanza, E.F.; Pyles, G.; Ciucci, J.; Arnold, P.

    2009-01-01

    This paper describes the activities required to modify a facility and the process of characterizing, repackaging, and preparing for shipment the Nevada Test Site's (NTS) legacy transuranic (TRU) waste in 58 oversize boxes (OSB). The waste, generated at other U.S. Department of Energy (DOE) sites and shipped to the NTS between 1974 and 1990, requires size-reduction for off-site shipment and disposal. The waste processing approach was tailored to reduce the volume of TRU waste by employing decontamination and non-destructive assay. As a result, the low-level waste (LLW) generated by this process was packaged, with minimal size reduction, in large sea-land containers for disposal at the NTS Area 5 Radioactive Waste Management Complex (RWMC). The remaining TRU waste was repackaged and sent to the Idaho National Laboratory Consolidation Site for additional characterization in preparation for disposal at the Waste Isolation Pilot Plant (WIPP), near Carlsbad, New Mexico. The DOE National Nuclear Security Administration Nevada Site Office and the NTS Management and Operating (M and O) contractor, NSTec, successfully partnered to modify and upgrade an existing facility, the Visual Examination and Repackaging Building (VERB). The VERB modifications, including a new ventilation system and modified containment structure, required an approved Preliminary Documented Safety Analysis prior to project procurement and construction. Upgrade of the VERB from a radiological facility to a Hazard Category 3 Nuclear Facility required new rigor in the design and construction areas and was executed on an aggressive schedule. The facility Documented Safety Analysis required that OSBs be vented prior to introduction into the VERB. Box venting was safely completed after developing and implementing two types of custom venting systems for the heavy gauge box construction. A remotely operated punching process was used on boxes with wall thickness of up to 3.05 mm (0.120 in) to insert aluminum

  18. Note: Laser ablation technique for electrically contacting a buried implant layer in single crystal diamond

    International Nuclear Information System (INIS)

    Ray, M. P.; Baldwin, J. W.; Butler, J. E.; Pate, B. B.; Feygelson, T. I.

    2011-01-01

    The creation of thin, buried, and electrically conducting layers within an otherwise insulating diamond by annealed ion implantation damage is well known. Establishing facile electrical contact to the shallow buried layer has been an unmet challenge. We demonstrate a new method, based on laser micro-machining (laser ablation), to make reliable electrical contact to a buried implant layer in diamond. Comparison is made to focused ion beam milling.

  19. High dose implantations of antimony for buried layer applications

    International Nuclear Information System (INIS)

    Gailliard, J.P.; Dupuy, M.; Garcia, M.; Roussin, J.C.

    1978-01-01

    Electrical and physical properties of high dose implantations of antimony in silicon have been studied for use in buried layer applications. The results have been obtained both on and oriented silicon wafers. Following implantations which lead to amorphization we perform an annealing at 600 0 C for 10 mn in order to recrystallize the layer. The observed electrical properties (μ, R) show that the concentration of electrically active antimony ions is greater than that predicted from the solubility of antimony in silicon. Further annealing (in the range 1050 0 - 1200 0 ) induces: firstly a precipitation of the Sb and secondly a diffusion and dissolution of the precipitates. There is a different evolution of the defects in the and silicon slices. T.E.M. reveals no defects in the wafers after one hour annealing at 1200 0 C, whereas defects and twins remain in wafers. Having obtained the evolution of R with time and temperature it is then determined the implantation and annealing conditions which lead to the low resistivity (R = 10) needed for buried layer applications. Results with very many industrially made devices are discussed

  20. Ground Shock Resistant of Buried Nuclear Power Plant Facility

    International Nuclear Information System (INIS)

    Ornai, D.; Adar, A.; Gal, E.

    2014-01-01

    Nuclear Power Plant (NPP) might be subjected to hostile attacks such as Earth Penetrating Weapons (EPW) that carry explosive charges. Explosions of these weapons near buried NPP facility might cause collapse, breaching, spalling, deflection, shear, rigid body motion (depending upon the foundations), and in-structure shock. The occupants and the equipment in the buried facilities are exposed to the in-structure motions, and if they are greater than their fragility values than occupants might be wounded or killed and the equipment might be damaged, unless protective measures will be applied. NPP critical equipment such as pumps are vital for the normal safe operation since it requires constant water circulation between the nuclear reactor and the cooling system, including in case of an immediate shut down. This paper presents analytical- semi empirical formulation and analysis of the explosion of a penetrating weapon with a warhead of 100kgs TNT (Trinitrotoluene) that creates ground shock effect on underground NPP structure containing equipment, such as a typical pump. If the in-structure spectral shock is greater than the pump fragility values than protective measures are required, otherwise a real danger to the NPP safety might occur

  1. Gamma ray energy spectrum of a buried radioactive source

    Energy Technology Data Exchange (ETDEWEB)

    Massey, N B

    1957-07-01

    Because of current attempts to utilize airborne gamma-ray scintillation spectrometers as a means of detecting and identifying buried radioactive mineral deposits, it has become important to study the effects of multiple scattering on the gamma-ray energy spectrum of a source buried in a semi-infinite medium. A series of ten experiments was made. First a scintillation detector was located in air at a fixed distance above a 250 microcurie cobalt-60 source suspended in a large tank. The level of water was raised from 25 cm below the source to 50 cm above, and the gamma-ray energy spectrum was observed. It was found that the high energy portion of the cobalt-60 spectrum remained identifiable even when the source was submerged more than five half-lengths. Further, the ratio of the counting rate of the total incident gamma radiation to the counting rate of the primary 1.33 MeV radiation was found to be very nearly linearly proportional to the depth of water cover. This leads to an empirical method for determining the depth of burial of a cobalt-60 point source. (author)

  2. Evidence for aeolian origins of heuweltjies from buried gravel layers

    Directory of Open Access Journals (Sweden)

    Michael D. Cramer

    2016-02-01

    Full Text Available Although heuweltjies (19–32 m diameter dominate the surface of much of the southwestern Cape of South Africa, their origins, distribution and age remain controversial. Current hypotheses are that the heuweltjies are (1 constructed by the excavation and mounding habits of burrowing animals; (2 the result of erosion by water of areas between patches protected from fluvial action by denser vegetation or (3 the product of localised aeolian sediment accumulation beneath denser vegetation associated with termitaria. At a site where quartz-containing gravels occur on the soil surface in areas between heuweltjies, these gravels were found to extend as a relatively intact layer of uniform concentration from the inter-mound area into the mound at the same plane as the surrounding soil surface. This buried layer suggests that heuweltjies were either built-up by deposition on a previous soil surface layer or eroded from sediment accumulated above the buried gravel layer. Mounds contain a relatively large proportion of silt consistent with sediment deposition. Mound sediment elemental composition was strongly correlated with that of local shale, indicating a local source of sediment. Pedogenesis was considerably more advanced off- than on-mound. There was no evidence of extensive regional aeolian sediment mantling over the vast area in which the heuweltjies occur. These findings and observations support the aeolian deposition hypothesis of heuweltjie origins combined with a degree of erosion, rather than a termite bioturbation hypothesis or a predominantly erosion-based hypothesis.

  3. Dynamic model of open shell structures buried in poroelastic soils

    Science.gov (United States)

    Bordón, J. D. R.; Aznárez, J. J.; Maeso, O.

    2017-08-01

    This paper is concerned with a three-dimensional time harmonic model of open shell structures buried in poroelastic soils. It combines the dual boundary element method (DBEM) for treating the soil and shell finite elements for modelling the structure, leading to a simple and efficient representation of buried open shell structures. A new fully regularised hypersingular boundary integral equation (HBIE) has been developed to this aim, which is then used to build the pair of dual BIEs necessary to formulate the DBEM for Biot poroelasticity. The new regularised HBIE is validated against a problem with analytical solution. The model is used in a wave diffraction problem in order to show its effectiveness. It offers excellent agreement for length to thickness ratios greater than 10, and relatively coarse meshes. The model is also applied to the calculation of impedances of bucket foundations. It is found that all impedances except the torsional one depend considerably on hydraulic conductivity within the typical frequency range of interest of offshore wind turbines.

  4. Methods to Evaluate Corrosion in Buried Steel Structures: A Review

    Directory of Open Access Journals (Sweden)

    Lorena-de Arriba-Rodriguez

    2018-05-01

    Full Text Available Around the world, there are thousands of metal structures completely or partially buried in the soil. The main concern in their design is corrosion. Corrosion is a mechanism that degrades materials and causes structural failures in infrastructures, which can lead to severe effects on the environment and have direct impact on the population health. In addition, corrosion is extremely complex in the underground environment due to the variability of the local conditions. The problem is that there are many methods to its evaluation but none have been clearly established. In order to ensure the useful life of such structures, engineers usually consider an excess thickness that increases the economic cost of manufacturing and does not satisfy the principles of efficiency in the use of resources. In this paper, an extended revision of the existing methods to evaluate corrosion is carried out to optimize the design of buried steel structures according to their service life. Thus, they are classified into two categories depending on the information they provide: qualitative and quantitative methods. As a result, it is concluded that the most exhaustive methodologies for estimating soil corrosion are quantitative methods fed by non-electrochemical data based on experimental studies that measure the mass loss of structures.

  5. Effect of Pseudomonas fluorescens on Buried Steel Pipeline Corrosion.

    Science.gov (United States)

    Spark, Amy J; Law, David W; Ward, Liam P; Cole, Ivan S; Best, Adam S

    2017-08-01

    Buried steel infrastructure can be a source of iron ions for bacterial species, leading to microbiologically influenced corrosion (MIC). Localized corrosion of pipelines due to MIC is one of the key failure mechanisms of buried steel pipelines. In order to better understand the mechanisms of localized corrosion in soil, semisolid agar has been developed as an analogue for soil. Here, Pseudomonas fluorescens has been introduced to the system to understand how bacteria interact with steel. Through electrochemical testing including open circuit potentials, potentiodynamic scans, anodic potential holds, and electrochemical impedance spectroscopy it has been shown that P. fluorescens increases the rate of corrosion. Time for oxide and biofilms to develop was shown to not impact on the rate of corrosion but did alter the consistency of biofilm present and the viability of P. fluorescens following electrochemical testing. The proposed mechanism for increased corrosion rates of carbon steel involves the interactions of pyoverdine with the steel, preventing the formation of a cohesive passive layer, after initial cell attachment, followed by the formation of a metal concentration gradient on the steel surface.

  6. Ion beam synthesis of buried single crystal erbium silicide

    International Nuclear Information System (INIS)

    Golanski, A.; Feenstra, R.; Galloway, M.D.; Park, J.L.; Pennycook, S.J.; Harmon, H.E.; White, C.W.

    1990-01-01

    High doses (10 16 --10 17 /cm 2 ) of 170 keV Er + were implanted into single-crystal left-angle 111 right-angle Si at implantation temperatures between 350 degree C and 520 degree C. Annealing at 800 degree C in vacuum following the implant, the growth and coalescence of ErSi 2 precipitates leads to a buried single crystalline ErSi 2 layer. This has been studied using Rutherford backscattering/channeling, X-ray diffraction, cross-sectional TEM and resistance versus temperature measurements. Samples implanted at 520 degree C using an Er dose of 7 x 10 16 /cm 2 and thermally annealed were subsequently used as seeds for the mesoepitaxial growth of the buried layer during a second implantation and annealing process. Growth occurs meso-epitaxially along both interfaces through beam induced, defect mediated mobility of Er atoms. The crystalline quality of the ErSi 2 layer strongly depends on the temperature during the second implantation. 12 refs., 4 figs

  7. Process equipment waste and process waste liquid collection systems

    International Nuclear Information System (INIS)

    1990-06-01

    The US DOE has prepared an environmental assessment for construction related to the Process Equipment Waste (PEW) and Process Waste Liquid (PWL) Collection System Tasks at the Idaho Chemical Processing Plant. This report describes and evaluates the environmental impacts of the proposed action (and alternatives). The purpose of the proposed action would be to ensure that the PEW and PWL collection systems, a series of enclosed process hazardous waste, and radioactive waste lines and associated equipment, would be brought into compliance with applicable State and Federal hazardous waste regulations. This would be accomplished primarily by rerouting the lines to stay within the buildings where the lined floors of the cells and corridors would provide secondary containment. Leak detection would be provided via instrumented collection sumps locate din the cells and corridors. Hazardous waste transfer lines that are routed outside buildings will be constructed using pipe-in-pipe techniques with leak detection instrumentation in the interstitial area. The need for the proposed action was identified when a DOE-sponsored Resource Conservation and Recovery Act (RCRA) compliance assessment of the ICPP facilities found that singly-contained waste lines ran buried in the soil under some of the original facilities. These lines carried wastes with a pH of less than 2.0, which were hazardous waste according to the RCRA standards. 20 refs., 7 figs., 1 tab

  8. Stabilization of ancient organic matter in deep buried paleosols

    Science.gov (United States)

    Marin-Spiotta, E.; Chaopricha, N. T.; Mueller, C.; Diefendorf, A. F.; Plante, A. F.; Grandy, S.; Mason, J. A.

    2012-12-01

    Buried soils representing ancient surface horizons can contain large organic carbon reservoirs that may interact with the atmosphere if exposed by erosion, road construction, or strip mining. Paleosols in long-term depositional sites provide a unique opportunity for studying the importance of different mechanisms on the persistence of organic matter (OM) over millennial time-scales. We report on the chemistry and bioavailability of OM stored in the Brady soil, a deeply buried (7 m) paleosol in loess deposits of southwestern Nebraska, USA. The Brady Soil developed 9,000-13,500 years ago during a time of warming and drying. The Brady soil represents a dark brown horizon enriched in C relative to loess immediately above and below. Spanning much of the central Great Plains, this buried soil contains large C stocks due to the thickness of its A horizon (0.5 to 1 m) and wide geographic extent. Our research provides a unique perspective on long-term OM stabilization in deep soils using multiple analytical approaches. Soils were collected from the Brady soil A horizon (at 7 m depth) and modern surface A horizons (0-15 cm) at two sites for comparison. Soils were separated by density fractionation using 1.85 g ml-1 sodium polytungstate into: free particulate organic matter (fPOM) and aggregate-occluded (oPOM) of two size classes (large: >20 μm, and small: separated into sand, silt, and clay size fractions. The distribution and age of C among density and particle-size fractions differed between surface and Brady soils. We isolated the source of the characteristic dark coloring of the Brady soil to the oPOM-small fraction, which also contained 20% of the total organic C pool in the Brady soil. The oPOM-small fraction and the bulk soil in the middle of the Brady A horizon had 14C ages of 10,500-12,400 cal yr BP, within the time that the soil was actively forming at the land surface. Surface soils showed modern ages. Lipid analyses of the Brady soil indicate a predominance of

  9. Response of steel buried pipeline to the three dimensional fault movement

    International Nuclear Information System (INIS)

    Zia Tohidi, R.; Shakib, H.

    2003-01-01

    Fault movement during an earthquake may have severe effect on buried pipelines as a lifeline element. A few studies are carried out on the behaviour of buried pipelines to this kind of damage and disruption. In most of these studies, the fault movements are modeled as two-dimensional. In this study, by modeling the pipe as a beam and the surrounding soil as nonlinear springs, the effect of three dimensional movement of fault on buried pipelines is investigated. Some important parameters such as; fault movement, depth of buried, geometrical characteristics of the pipe, angle of pipe- soil friction, angle of pipe- fault crossing, and the fault slip are considered in this study

  10. Aging management and life assessment of buried commodities in nuclear power plants

    International Nuclear Information System (INIS)

    Park, J. H.; Jung, I. S.; Jo, H. S.; Kim, M. G.; Kim, S. T.; Lee, S. S.

    2000-01-01

    General field survey, inspection and life assessment were performed to establish effective aging management program of buried commodities in nuclear power plant. Basic informations on material characteristics, aging degradation experiences and maintenance history were gathered. Considering their degradation effects on power operation or safety, buried commodities were screened for the aging management priority. Various inspection techniques were applied in field survey and inspection, and their results were incorporated in the life assessment of buried commodities. In the aspect of aging degradation, general status of buried commodities were considered still sound while some revealed local degradation

  11. Total dose hardening of buried insulator in implanted silicon-on-insulator structures

    International Nuclear Information System (INIS)

    Mao, B.Y.; Chen, C.E.; Pollack, G.; Hughes, H.L.; Davis, G.E.

    1987-01-01

    Total dose characteristics of the buried insulator in implanted silicon-on-insulator (SOI) substrates have been studied using MOS transistors. The threshold voltage shift of the parasitic back channel transistor, which is controlled by charge trapping in the buried insulator, is reduced by lowering the oxygen dose as well as by an additional nitrogen implant, without degrading the front channel transistor characteristics. The improvements in the radiation characteristics of the buried insulator are attributed to the decrease in the buried oxide thickness or to the presence of the interfacial oxynitride layer formed by the oxygen and nitrogen implants

  12. Characterization of radioactive-waste drum contents using real-time x-radiography

    International Nuclear Information System (INIS)

    Barna, B.A.; Bishoff, J.R.; Reinhardt, W.W.

    1982-01-01

    Low-level transuranic (TRU) waste is stored in a retrievable manner at the Radioactive Waste Management Complex (RWMC) operated by EG and G Idaho, Inc., for the Department of Energy. The waste, consisting of contaminated rags, paper, plastic, laboratory glassware, tools, scrap metal, wood, electrical components and parts, sludges, etc., is packed in various sized sealed containers, including 55 gallon drums. Waste which can be accurately characterized will be sent to the Waste Isolation Pilot Plant (WIPP) in New Mexico for long term storage if it is certified to meet the WIPP waste acceptance criteria. EG and G Idaho, Inc. is planning to install a real-time x-ray system designed for the automated and semi-automated examination of low-level TRU waste containers including 30, 55, and 83 gallon drums, 4 x 4 x 7 foot plywood boxes, and 4 x 5 x 6 foot metal bins during 1982. This system, designed for production, is capable of examining up to 20,000 waste containers per year using automated container handling, and features real-time x-ray imaging with a 420 kV, 10 ma constant potential source, digital image processing equipment, and video taping facilities (every container examination is required to be taped, for archival documentation). Work planned for the near future involves tests using real-time neutron radiography for waste characterization as a complement to real-time x-ray radiography. Ultimately, the NDE examinations will be combined with automated nondestructive assay (NDA) techniques for complete characterization of a given waste container's contents

  13. Radioactive waste processing field

    International Nuclear Information System (INIS)

    Ito, Minoru.

    1993-01-01

    Storing space for radioactive wastes (storage tunnels) are formed underground of the sea bottom along coast. A plurality of boreholes through which sea water flows are pored vertically in a direction intersecting underground streams of brine in the ground between the tunnels and seaside. Sea water introduction pipes are joined to the upper side walls of the boreholes. The sea water introduction pipes have introduction ports protruded under the sea level of the coastal sea area region. Since sea water flows from the introduction ports to the boreholes passing through the sea water introduction pipes, sea water is always filled in the boreholes. Therefore, brine is sufficiently supplied toward the land by sea water from the boreholes, the underground stream of brine is negligibly small. This can prevent radioactive contamination due to flow of the underground water when radioactive wastes are buried in the underground near coast. (I.N.)

  14. Radioactive waste treatment apparatus

    International Nuclear Information System (INIS)

    Abrams, R.F.; Chellis, J.G.

    1983-01-01

    Radioactive waste treatment apparatus is disclosed in which the waste is burned in a controlled combustion process, the ash residue from the combustion process is removed and buried, the gaseous effluent is treated in a scrubbing solution the pH of which is maintained constant by adding an alkaline compound to the solution while concurrently extracting a portion of the scrubbing solution, called the blowdown stream. The blowdown stream is fed to the incinerator where it is evaporated and the combustibles in the blowdown stream burned and the gaseous residue sent to the scrubbing solution. Gases left after the scrubbing process are treated to remove iodides and are filtered and passed into the atmosphere

  15. A history of solid waste packaging at the Hanford Site

    International Nuclear Information System (INIS)

    Duncan, D.R.; Weyns-Rollosson, D.I.; Pottmeyer, J.A.; Stratton, T.J.

    1995-02-01

    Since the initiation of the defense materials product mission, a total of more than 600,000 m 3 of radioactive solid waste has been stored or disposed at the US Department of Energy's (DOE) Hanford Site, located in southeastern Washington State. As the DOE complex prepares for its increasing role in environmental restoration and waste remediation, the characterization of buried and retrievably stored waste will become increasingly important. Key to this characterization is an understanding of the standards and specifications to which waste was packaged; the regulations that mandated these standards and specifications; the practices used for handling and packaging different waste types; and the changes in these practices with time

  16. The Savannah River Plant low-level waste segregation program

    International Nuclear Information System (INIS)

    Wheeler, V.B.

    1987-01-01

    To extend the life of the Savannah River Plant (SRP) Radioactive Waste Burial Ground, a sitewide program has been implemented to segregate waste that is essentially free of contamination from routine radioactive waste. Much of the low-level waste disposed of as radioactive has no detectable contamination and can be buried in a sanitary landfill. A Landfill Monitoring Facility (LMF) will be constructed at SRP to house the state-of-the-art technology required to provide a final survey on the candidate waste streams that had previously been classified as radioactive. 3 figs

  17. Vitrification of low-level and mixed wastes

    International Nuclear Information System (INIS)

    Johnson, T.R.; Bates, J.K.; Feng, Xiangdong.

    1994-01-01

    The US Department of Energy (DOE) and nuclear utilities have large quantities of low-level and mixed wastes that must be treated to meet repository performance requirements, which are likely to become even more stringent. The DOE is developing cost-effective vitrification methods for producing durable waste forms. However, vitrification processes for high-level wastes are not applicable to commercial low-level wastes containing large quantities of metals and small amounts of fluxes. New vitrified waste formulations are needed that are durable when buried in surface repositories

  18. 3rd Quarter Transportation Report FY 2014: Radioactive Waste Shipments to and from the Nevada National Security Site (NNSS)

    International Nuclear Information System (INIS)

    Gregory, Louis

    2014-01-01

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

  19. Regulatory controls on the hydrogeological characterization of a mixed waste disposal site, Radioactive Waste Management Complex, Idaho National Engineering Laboratory

    International Nuclear Information System (INIS)

    Ruebelmann, K.L.

    1990-01-01

    Following the detection of chlorinated volatile organic compounds in the groundwater beneath the SDA in the summer of 1987, hydrogeological characterization of the Radioactive Waste Management Complex (RWMC), Idaho National Engineering Laboratory (INEL) was required by the Resource Conservation and Recovery Act (RCRA). The waste site, the Subsurface Disposal Area (SDA), is the subject of a RCRA Corrective Action Program. Regulatory requirements for the Corrective Action Program dictate a phased approach to evaluation of the SDA. In the first phase of the program, the SDA is the subject of a RCRA Facility Investigation (RIF), which will obtain information to fully characterize the physical properties of the site, determine the nature and extent of contamination, and identify pathways for migration of contaminants. If the need for corrective measures is identified during the RIF, a Corrective Measures Study (CMS) will be performed as second phase. Information generated during the RIF will be used to aid in the selection and implementation of appropriate corrective measures to correct the release. Following the CMS, the final phase is the implementation of the selected corrective measures. 4 refs., 1 fig

  20. Principles of geological substantiation for toxic waste disposal facilities sites selection

    International Nuclear Information System (INIS)

    Khrushchov, D. P.; Matorin, Eu. M.; Shekhunova, S. B.

    2002-01-01

    Industrial, domestic and military activities result in accumulation of toxic and hazardous waste. Disposal of these waste comprises two main approaches: technological processing (utilization and destruction) and landfill. According to concepts and programs of advanced countries technological solutions are preferable, but in fact over 70 % of waste are buried in storages, prevailingly of near surface type. The target of this paper is to present principles of geological substantiation of sites selection for toxic and hazardous waste isolation facilities location. (author)

  1. Disposal of radioactive waste

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1960-01-15

    The problem of disposal can be tackled in two ways: the waste can be diluted and dispersed so that the radiation to which any single individual would be subjected would be negligible, or it can be concentrated and permanently isolated from man and his immediate environment. A variety of methods for the discharge of radioactive waste into the ground were described at the Monaco conference. They range from letting liquid effluent run into pits or wells at appropriately chosen sites to the permanent storage of high activity material at great depth in geologically suitable strata. Another method discussed consists in the incorporation of high level fission products in glass which is either buried or stored in vaults. Waste disposal into rivers, harbours, outer continental shelves and the open sea as well as air disposal are also discussed. Many of the experts at the Monaco conference were of the view that most of the proposed, or actually applied, methods of waste disposal were compatible with safety requirements. Some experts, felt that certain of these methods might not be harmless. This applied to the possible hazards of disposal in the sea. There seemed to be general agreement, however, that much additional research was needed to devise more effective and economical methods of disposal and to gain a better knowledge of the effects of various types of disposal operations, particularly in view of the increasing amounts of waste material that will be produced as the nuclear energy industry expands

  2. How Burying Biomass Can Contribute to CO2 Stabilization

    Science.gov (United States)

    Cook, B.; Zeng, N.; Zaitchik, B.; Gregg, J.

    2008-12-01

    To mitigate global climate change, a portfolio of strategies will be needed to keep the atmospheric CO2 concentration below a dangerous level. Here a carbon sequestration strategy is proposed in which certain dead or live trees are harvested via collection or selective cutting, then buried in trenches or stowed away in above-ground shelters. The largely anaerobic condition under a sufficiently thick layer of soil will prevent the decomposition of the buried wood. Because a large flux of CO2 is constantly being assimilated into the world's forests via photosynthesis, cutting off its return pathway to the atmosphere forms an effective carbon sink. It is estimated that a sustainable long-term carbon sequestration potential for wood burial is 10 ± 5 GtC y-1, and currently about 65 GtC is on the world's forest floors in the form of coarse woody debris suitable for burial. The potential is largest in tropical forests (4.2 GtC y-1), followed by temperate (3.7 GtC y-1) and boreal forests (2.1 GtC y-1). Burying wood has other benefits including minimizing CO2 source from deforestation, extending the lifetime of reforestation carbon sink, and reducing fire danger. There are possible environmental impacts such as nutrient lock-up which nevertheless appears manageable, but other environmental concerns and factors will likely set a limit so that only part of the full potential can be realized. Based on data from North American logging industry, the cost for wood burial is estimated to be 14/tCO2 (50/tC), lower than the typical cost for power plant CO2 capture with geological storage. The low cost for carbon sequestration with wood burial is possible because the technique uses the natural process of photosynthesis to remove carbon from the atmosphere. The technique is low tech, distributed, safe, and can be stopped at any time, thus an attractive option for large-scale implementation in a world-wide carbon market.

  3. Defense waste transportation: cost and logistics studies

    International Nuclear Information System (INIS)

    Andrews, W.B.; Cole, B.M.; Engel, R.L.; Oylear, J.M.

    1982-08-01

    Transportation of nuclear wastes from defense programs is expected to significantly increase in the 1980s and 1990s as permanent waste disposal facilities come into operation. This report uses models of the defense waste transportation system to quantify potential transportation requirements for treated and untreated contact-handled transuranic (CH-TRU) wastes and high-level defense wastes (HLDW). Alternative waste management strategies in repository siting, waste retrieval and treatment, treatment facility siting, waste packaging and transportation system configurations were examined to determine their effect on transportation cost and hardware requirements. All cost estimates used 1980 costs. No adjustments were made for future changes in these costs relative to inflation. All costs are reported in 1980 dollars. If a single repository is used for defense wastes, transportation costs for CH-TRU waste currently in surface storage and similar wastes expected to be generated by the year 2000 were estimated to be 109 million dollars. Recovery and transport of the larger buried volumes of CH-TRU waste will increase CH-TRU waste transportation costs by a factor of 70. Emphasis of truck transportation and siting of multiple repositories would reduce CH-TRU transportation costs. Transportation of HLDW to repositories for 25 years beginning in 1997 is estimated to cost $229 M in 1980 costs and dollars. HLDW transportation costs could either increase or decrease with the selection of a final canister configuration. HLDW transportation costs are reduced when multiple repositories exist and emphasis is placed on truck transport

  4. Nuclear waste: Department of Energy's Transuranic Waste Disposal Plan needs revision

    International Nuclear Information System (INIS)

    1986-01-01

    Transuranic waste consists of discarded tools, rags, machinery, paper, sheet metal, and glass containing man-made radioactive elements that can be dangerous if inhaled, ingested, or absorbed into the body through an open wound. GAO found that the Defense Waste Management Plan does not provide the Congress with complete inventory and cost data or details on environmental and safety issues related to the permanent disposal of TRU waste; the Plan's $2.8 billion costs are understated by at least $300 million. Further, it does not include costs for disposing of buried waste, contaminated soil, and TRU waste that may not be accepted at the Waste Isolation Pilot Plant. Lastly, the Plan provides no details on the environmental and safety issues related to the permanent disposal of TRU waste, nor does it discuss the types of or timing for environmental analyses needed before WIPP starts operating

  5. Market forces can help lower waste volumes

    International Nuclear Information System (INIS)

    Stavins, R.N.

    1993-01-01

    Market forces can go a long way toward helping communities solve their mounting solid-waste problems. In most communities the increasing costs of solid-waste disposal are invisible to the average homeowner because they are buried in local property tax rates. Even in the few communities that list disposal costs separately on tax bills, individual costs are not related to the volume of waste generated. Fundamental to an effective waste-management strategy is the removal of these distortions by getting the prices right. But even with improved price signals, there is no silver bullet of public policy for solid- and hazardous-waste management. Until the ubiquitous NIMBY (Not In My Backyard) problem is addressed, even the most innovative set of waste management policies will remain, at best, a partial solution

  6. ISOCELL trademark proof-of-concept for retrieval of wastes and contaminated soil

    International Nuclear Information System (INIS)

    Chatwin, T.D.; Krieg, R.K.

    1992-01-01

    ISOCELL TM cryogenic technology is designed to immobilize buried hazardous, radioactive, and mixed waste and contaminated soil by creating a block of frozen waste and soil that can be safely retrieved, stored, transported, and treated with a minimum of dust or aerosol production. A ''proof-of-concept'' test of the ISOCELL process was conducted in clean soil by RKK, Ltd., for the Idaho National Engineering Laboratory (INEL). Results indicate ISOCELL technology successfully froze moist soil into a solid block capable of being lifted and retrieved. Test conditions were compared to characteristics of possible buried waste sites in the INEL

  7. Proceedings of the NEA Workshop on the Management of Non-Nuclear Radioactive Waste

    International Nuclear Information System (INIS)

    Zafiropoulos, Demetre; Dilday, Daniel; Siemann, Michael; Ciambrella, Massimo; Lazo, Edward; Sartori, Enrico; ); Dionisi, Mario; Long, Juliet; Nicholson, David; Chambers, Douglas; Garcia Alves, Joao Henrique; McMahon, Ciara; Bruno, Gerard; Fan, Zhiwen; ); Ripani, Marco; Nielsen, Mette; Solente, Nicolas; Templeton, John; Paratore, Angelo; Feinhals, Joerg; Pandolfi, Dana; Sarchiapone, Lucia; Picentino, Bruno; Simms, Helen; Beer, Hans-Frieder; Deryabin, Sergey; Ulrici, Luisa; Bergamaschi, Carlo; Nottestad, Stacy; Anagnostakis, Marios

    2017-05-01

    All NEA member countries, whether or not they have nuclear power plants, are faced with appropriately managing non-nuclear radioactive waste produced through industrial, research and medical activities. Sources of such waste can include national laboratory and university research activities, used and lost industrial gauges and radiography sources, hospital nuclear medicine activities and in some circumstances, naturally occurring radioactive material (NORM) activities. Although many of these wastes are not long-lived, the shear variety of sources makes it difficult to generically assess their physical (e.g. volume, chemical form, mixed waste) or radiological (e.g. activity, half-life, concentration) characteristics. Additionally, the source-specific nature of these wastes poses questions and challenges to their regulatory and practical management at a national level. This had generated interest from both the radiological protection and radioactive waste management communities, and prompted the Committee on Radiological Protection and Public Health (CRPPH) to organise, in collaboration with the Radioactive Waste Management Committee (RWMC), a workshop tackling some of the key issues of this challenging topic. The key objectives of the NEA Workshop on the Management of Non-Nuclear Radioactive Waste were to address the particularities of managing non-nuclear waste in all its sources and forms and to share and exchange national experiences. Presentations and discussions addressed both technical aspects and national frameworks. Technical aspects included: - the range of non-nuclear waste sources, activities, volumes and other relevant characteristics; - waste storage and repository capacities and life cycles; - safety considerations for mixed wastes management; - human resources and knowledge management; - legal, regulatory and financial assurance, and liability issues. Taking into account the entire non-nuclear waste life-cycle, the workshop covered planning and

  8. Bryophytes of beach forests in Chon Buri Province, Thailand

    Directory of Open Access Journals (Sweden)

    Phiangphak Sukkharak

    2014-10-01

    Full Text Available An investigation of bryophyte diversity of three beach forests including Had Tung Prong, Had Tein Talay, and the beach forest in Thai Island and Sea Natural History Museum in Chon Buri Province, Thailand, was carried out. From 137 enumerated specimens, 16 species (6 mosses, 10 liverworts in 12 genera (5 mosses, 7 liverworts and eight families (5 mosses, 3 liverworts were found. Among those the most common families of mosses are Fissidentaceae (2 species and the most common families of liverwort are Lejeuneaceae (8 species. A comparison of species richness among the three areas revealed that the highest species richness of bryophytes was found in Had Tung Prong. Moreover, of all bryophyte species found, Weissia edentula Mitt. was the most common one.

  9. Buried piping integrity management at fossil power plants

    Energy Technology Data Exchange (ETDEWEB)

    Shulder, Stephen J. [Structural Integrity Associates, Annapolis, MD (United States); Biagiotti, Steve [Structural Integrity Associates, Inc., Centennial, CO (United States)

    2011-07-15

    In the last decade several industries (oil and gas pipelines, nuclear power, and municipal water) have experienced an increase in the frequency and public scrutiny of leaks and failures associated with buried piping and tank assets. In several industries, regulatory pressure has resulted in the mandated need for databases and inspection programs to document and ensure the continued integrity of these assets. Power plants are being extended beyond their design life and the condition of below grade assets is essential toward continued operation. This article shares the latest advances in managing design, operation, process, inspection, and historical data for power plant piping. Applications have also been developed to help with risk prioritization, inspection method selection, managing cathodic protection data for external corrosion control, and a wide variety of other information. This data can be managed in a GIS environment allowing two and three dimensional (2D and 3D) access to the database information. (orig.)

  10. Friction, slip and structural inhomogeneity of the buried interface

    International Nuclear Information System (INIS)

    Dong, Y; Wu, J; Martini, A; Li, Q

    2011-01-01

    An atomistic model of metallic contacts using realistic interatomic potentials is used to study the connection between friction, slip and the structure of the buried interface. Incommensurability induced by misalignment and lattice mismatch is modeled with contact sizes that are large enough to observe superstructures formed by the relative orientations of the surfaces. The periodicity of the superstructures is quantitatively related to inhomogeneous shear stress distributions in the contact area, and a reduced order model is used to clarify the connection between friction and structural inhomogeneity. Finally, the movement of atoms is evaluated before, during and after slip in both aligned and misaligned contacts to understand how the interfacial structure affects the mechanisms of slip and the corresponding frictional behavior

  11. Location of Buried Mineshafts and Adits Using Reconnaissance Geophysical Methods

    Science.gov (United States)

    Culshaw, Martin; Donnelly, Laurance; McCann, David

    Britain has a long history of mining activity, which stretches back some 3000 years to the excavation of flint in East Anglia. The legacy of this long period of activity is the presence of many buried mineshafts and adits, whose location is often unknown precisely and in many cases not even recorded in historical mining records. As has been shown by Donnelly et al (2003) the discovery of a mineshaft in an area of housing development can have a profound effect on property values in its vicinity. Hence, urgent action must be taken to establish at the site investigation stage of a development to determine whether any mineshafts are present at the site so that remedial action can be taken before construction commences. A study of historical information and the drilling may well enable the developer to locate any suspected mineshafts and adits on his site. However, the use of geophysical reconnaissance methods across the whole site may well provide sufficient information to simplify the drilling programme and reduce its cost to a minimum. In this paper a number of rapid reconnaissance geophysical methods are described and evaluated in terms of their success in the location of buried mineshafts and adits. It has shown that a combination of ground conductivity and magnetic surveys provides a most effective approach on open sites in greenfield and brownfield areas. Ground penetrating radar and micro-gravity surveys have proved to be a valuable approach in urban areas where the use of many geophysical methods is prevented by the presence of various types of cultural noise. On a regional scale the infrared thermography method is being increasingly used but care must be taken to overcome certain environmental difficulties. The practical use of all these geophysical methods in the field is illustrated by a number of appropriate case histories.

  12. Buried paleosols of the Upper Paleolithic multilayered site Kostenki-1

    Science.gov (United States)

    Aparin, B. F.; Platonova, N. I.; Sukhacheva, E. Yu.; Dudin, A. E.

    2016-12-01

    The morphology and chemical and physicochemical properties of paleosols buried at the Upper Paleolithic multilayered site Kostenki-1 in Kostenki-Borshchevo district of Voronezh oblast were studied. Four in situ paleosols formed 20-40(45) ka ago were separated in the archaeological excavation. Together with the surface soils, they characterized two different epochs of pedogenesis—the interstadial and interglacial (Holocene) epochs—and three shorter cycles of pedogenesis. The traces of human occupation in the studied hollow in the Late Paleolithic were found in the layers corresponding to the interstadial epoch. The buried paleosols had a simple horizonation: A(W)-C. A shallow thickness of the soil profiles could be due to relatively short periods of pedogenesis and to the shallow embedding by the carbonate geochemical barrier. The degree of the organic matter humification in the paleosols varied from 0.6 to 1.5, which corresponded to the mean duration of the period of biological activity of 60 to 150 days per year characterizing the climatic conditions of the tundra, taiga, forest-steppe, and steppe natural zones. In the excavation Kostenki-1 (2004-2005), soil-sediment sequences composed of five series of lithological layers with soil layers on top of them were found. Their deposition proceeded in two phases—the water phase and the aerial phase—that predetermined the morphology and composition of the soil-sediment sequences. The history of sediment accumulation in the studied hollow consisted of five stages. Similar morphologies and compositions of the soil-sediment sequences corresponding to these stages attest to the cyclic pattern of their development. The stages of sedimentation and soil formation corresponded to cyclic climate fluctuations with changes in the temperature and moisture conditions. A comparative analysis of the morphology and properties of the paleosols and soil-sediment sequences made it possible to characterize the environmental

  13. Searching for the Source of Salt Marsh Buried Mercury.

    Science.gov (United States)

    Brooke, C. G.; Nelson, D. C.; Fleming, E. J.

    2016-12-01

    Salt marshes provide a barrier between upstream mercury contamination and coastal ecosystems. Mercury is sorbed, transported, and deposited in estuarine systems. Once the upstream mercury source has been remediated, the downstream mercury contaminated salt marsh sediments should become "capped" or buried by uncontaminated sediments preventing further ecosystem contamination. Downstream from a remediated mercury mine, an estuarine intertidal marsh in Tomales Bay, CA, USA, scavengers/predators (e.g. Pachygrapsus crassipes, Lined Shore Crab) have leg mercury concentrations as high as 5.5 ppm (dry wt./dry wt.), which increase significantly with crab size, a surrogate for trophic level. These elevated mercury concentrations suggests that "buried" mercury is rereleased into the environment. To locate possible sources of mercury release in Walker Marsh, we sampled a transect across the marsh that included diverse micro-environments (e.g. rhizoshere, stratified sediments, faunal burrows). From each location we determined the sediment structure, sediment color, total sediment mercury, total sediment iron, and microbial composition (n = 28). Where flora or fauna had perturbed the sediment, mercury concentrations were 10% less than undisturbed stratified sediments (1025 ppb vs. 1164 ppb, respectively). High-throughput SSU rRNA gene sequencing and subsequent co-occurrence network analysis genera indicated that in flora- or fauna- perturbed sediments there was an increased likelihood that microbial genera contained mercury mobilizing genes (94% vs 57%; in perturbed vs stratified sediments, respectively). Our observations are consistent with findings by others that in perturbed sites mercury mobility increased. We did however identify a microbial and geochemical profile with increased mercury mobility. For future work we plan to quantify the role these micro-environments have on mercury-efflux from salt marshes.

  14. SEM based overlay measurement between resist and buried patterns

    Science.gov (United States)

    Inoue, Osamu; Okagawa, Yutaka; Hasumi, Kazuhisa; Shao, Chuanyu; Leray, Philippe; Lorusso, Gian; Baudemprez, Bart

    2016-03-01

    With the continuous shrink in pattern size and increased density, overlay control has become one of the most critical issues in semiconductor manufacturing. Recently, SEM based overlay of AEI (After Etch Inspection) wafer has been used for reference and optimization of optical overlay (both Image Based Overlay (IBO) and Diffraction Based Overlay (DBO)). Overlay measurement at AEI stage contributes monitor and forecast the yield after formation by etch and calibrate optical measurement tools. however those overlay value seems difficult directly for feedback to a scanner. Therefore, there is a clear need to have SEM based overlay measurements of ADI (After Develop Inspection) wafers in order to serve as reference for optical overlay and make necessary corrections before wafers go to etch. Furthermore, to make the corrections as accurate as possible, actual device like feature dimensions need to be measured post ADI. This device size measurement is very unique feature of CDSEM , which can be measured with smaller area. This is currently possible only with the CD-SEM. This device size measurement is very unique feature of CD-SEM , which can be measured with smaller area. In this study, we assess SEM based overlay measurement of ADI and AEI wafer by using a sample from an N10 process flow. First, we demonstrate SEM based overlay performance at AEI by using dual damascene process for Via 0 (V0) and metal 1 (M1) layer. We also discuss the overlay measurements between litho-etch-litho stages of a triple patterned M1 layer and double pattern V0. Second, to illustrate the complexities in image acquisition and measurement we will measure overlay between M1B resist and buried M1A-Hard mask trench. Finally, we will show how high accelerating voltage can detect buried pattern information by BSE (Back Scattering Electron). In this paper we discuss the merits of this method versus standard optical metrology based corrections.

  15. Cleanup Verification Package for the 118-B-6, 108-B Solid Waste Burial Ground

    International Nuclear Information System (INIS)

    Proctor, M.L.

    2006-01-01

    This cleanup verification package documents completion of remedial action for the 118-B-6, 108-B Solid Waste Burial Ground. The 118-B-6 site consisted of 2 concrete pipes buried vertically in the ground and capped by a concrete pad with steel lids. The site was used for the disposal of wastes from the 'metal line' of the P-10 Tritium Separation Project.

  16. Design criteria burial containers for non-transuranic solid radioactive waste

    International Nuclear Information System (INIS)

    Hammond, J.E.

    1976-01-01

    The criteria, replace HW-83959 and apply to containers constructed specifically for the containment of beta-gamma radioactively contaminated waste removed from an area controlled by radiation work procedures, transported across an uncontrolled area where there is risk of a radiation release to the environs, and buried in an approved radioactive waste burial ground

  17. The acute and long-term neurotoxic effects of MDMA on marble burying behaviour in mice.

    Science.gov (United States)

    Saadat, Kathryn S; Elliott, J Martin; Colado, M Isabel; Green, A Richard

    2006-03-01

    When mice are exposed to harmless objects such as marbles in their cage they bury them, a behaviour sometimes known as defensive burying. We investigated the effect of an acute dose of MDMA (èecstasy') and other psychoactive drugs on marble burying and also examined the effect of a prior neurotoxic dose of MDMA or p-chloroamphetamine (PCA) on burying. Acute administration of MDMA produced dose-dependent inhibition of marble burying (EC50: 7.6 micro mol/kg). Other drugs that enhance monoamine function also produced dose-dependent inhibition: methamphetamine PCA paroxetine MDMA GBR 12909 methylphenidate. None of these drugs altered locomotor activity at a dose that inhibited burying. A prior neurotoxic dose of MDMA, which decreased striatal dopamine content by 60%, but left striatal 5-HT content unaltered, did not alter spontaneous marble burying 18 or 40 days later. However, a neurotoxic dose of PCA which decreased striatal dopamine by 60% and striatal 5-HT by 70% attenuated marble burying 28 days later. Overall, these data suggest that MDMA, primarily by acutely increasing 5-HT function, acts like several anxiolytic drugs in this behavioural model. Long-term loss of cerebral 5-HT content also produced a similar effect. Since this change was observed only after 28 days, it is probably due to an adaptive response in the brain.

  18. The initiation and linkage of surface fractures above a buried strike ...

    Indian Academy of Sciences (India)

    a buried strike-slip fault: An experimental approach. N Ghosh and A ... conditions viz., (i) heterogeneous simple shear of the cover rocks above a buried strike slip fault. (wrench .... (iii) study of fracture types in the damage zones from Gozo .... was dominant, the results may vary from a true ... For example, as shown in figure 5 ...

  19. Detection of a buried wire with two resistively loaded wire antennas

    NARCIS (Netherlands)

    Vossen, S.H.J.A.; Tijhuis, A.G.; Lepelaars, E.S.A.M.; Zwamborn, A.P.M.

    2002-01-01

    The use of two identical straight thin-wire antennas for the detection of a buried wire is analyzed with the aid of numerical calculations. The buried wire is located below an interface between two homogeneous half-spaces. The detection setup, which is formed by a transmitting and a receiving wire,

  20. Detection of a buried object with pulse-compensated wire antennas

    NARCIS (Netherlands)

    Vossen, S.H.J.A.; Tijhuis, A.G.; Lepelaars, E.S.A.M.; Zwamborn, A.P.M.

    2003-01-01

    For the detection of a buried object we consider two straight thin-wire antennas above an interface between two homogeneous dielectric half spaces. One antenna is a transmitting wire and the other is a receiving wire. Our aim is to use this simple antenna set up for the detection of buried objects

  1. Direct Measurement of the Band Structure of a Buried Two-Dimensional Electron Gas

    DEFF Research Database (Denmark)

    Miwa, Jill; Hofmann, Philip; Simmons, Michelle Y.

    2013-01-01

    We directly measure the band structure of a buried two dimensional electron gas (2DEG) using angle resolved photoemission spectroscopy. The buried 2DEG forms 2 nm beneath the surface of p-type silicon, because of a dense delta-type layer of phosphorus n-type dopants which have been placed there...

  2. Electron spin resonance characterization of trapping centers in Unibond reg-sign buried oxides

    International Nuclear Information System (INIS)

    Conley, J.F. Jr.; Lenahan, P.M.; Wallace, B.D.

    1996-01-01

    Electron spin resonance and capacitance vs. voltage measurements are used to evaluate the radiation response of Unibond buried oxides. When damaged by hole injection, it is found that Unibond reg-sign buried oxides exhibit a rough correspondence between E' centers and positive charge as well as generation of P b centers at the Unibond buried oxide/Si interface. In these respects, Unibond buried oxides qualitatively resemble thermal SiO 2 . However, a hydrogen complexed E' center known as the 74 G doublet is also detected in the Unibond buried oxides. This defect is not detectable in thermal SiO 2 under similar circumstances. Since the presence of 74 G doublet center is generally indicative of very high hydrogen content and since hydrogen is clearly a significant participant in radiation damage, this result suggests a qualitative difference between the radiation response of Unibond and thermal SiO 2 . Unibond results are also compared and contrasted with similar investigations on separation-by-implanted-oxygen (SIMOX) buried oxides. Although the charge trapping response of Unibond buried oxides may be inferior to that of radiation hardened thermal SiO 2 , it appears to be more simple and superior to that of SIMOX buried oxides

  3. Efficient calculation of broadband acoustic scattering from a partially, obliquely buried cylinder

    NARCIS (Netherlands)

    Nijhof, M.J.J.; Espana, A.; Williams, K.

    2013-01-01

    An efficient model for the Target In Environment Response (TIER) of buried/half buried, mine-like objects and UXOs is essential for the development and training of automatic target detection and classification methods and for use in sonar performance prediction models. For instance, to investigate

  4. Numerical Modeling of Mechanical Behavior for Buried Steel Pipelines Crossing Subsidence Strata.

    Directory of Open Access Journals (Sweden)

    J Zhang

    Full Text Available This paper addresses the mechanical behavior of buried steel pipeline crossing subsidence strata. The investigation is based on numerical simulation of the nonlinear response of the pipeline-soil system through finite element method, considering large strain and displacement, inelastic material behavior of buried pipeline and the surrounding soil, as well as contact and friction on the pipeline-soil interface. Effects of key parameters on the mechanical behavior of buried pipeline were investigated, such as strata subsidence, diameter-thickness ratio, buried depth, internal pressure, friction coefficient and soil properties. The results show that the maximum strain appears on the outer transition subsidence section of the pipeline, and its cross section is concave shaped. With the increasing of strata subsidence and diameter-thickness ratio, the out of roundness, longitudinal strain and equivalent plastic strain increase gradually. With the buried depth increasing, the deflection, out of roundness and strain of the pipeline decrease. Internal pressure and friction coefficient have little effect on the deflection of buried pipeline. Out of roundness is reduced and the strain is increased gradually with the increasing of internal pressure. The physical properties of soil have a great influence on the mechanical properties of buried pipeline. The results from the present study can be used for the development of optimization design and preventive maintenance for buried steel pipelines.

  5. Technical Review on Fitness-for-Service for Buried Pipe by ASME Code Case N-806

    International Nuclear Information System (INIS)

    Park, Sang Kyu; Lee, Yo Seop; So, Il Su; Lim, Bu Taek

    2012-01-01

    Fitness-for-Service is a useful technology to determine replacement timing, next inspection timing or in-service when nuclear power plant's buried pipes are damaged. If is possible for buried pipes to be aged by material loss, cracks and occlusion as operating time goes by. Therefore Fitness-for-Service technology for buried pipe is useful for plant industry to perform replacement and repair. Fitness-for-Service for buried pipe is studied in terms of existing code and standard for Fitness-for-Service and a current developing code case. Fitness-for-Service for buried pipe was performed according to Code Case N-806 developed by ASME (American Society of Mechanical Engineers)

  6. Buried topography of Utopia, Mars: Persistence of a giant impact depression

    International Nuclear Information System (INIS)

    McGill, G.E.

    1989-01-01

    Knobs, partially buried craters, ring fractures, and some mesas permit a qualitative determination of the topography buried beneath younger northern plains materials. These features are widely distributed in the Utopia area but are absent in a large, roughly circular region centered at about 48 degree N, 240 degree W. This implies the existence of a circular depression about 3,300 km in diameter buried beneath Utopia Planitia that is here interpreted to represent the central part of a very large impact basin. The presence of buried curved massifs around part of this depression, and a roughly coincident mascon, lend further support. Present topography, areal geology, and paleotopography of buried surfaces all point to the persistence of this major depression for almost the entire history of Mars

  7. A fully coupled finite element model for stress distribution in buried gas pipeline

    International Nuclear Information System (INIS)

    Yahya Sukirman; Zainal Zakaria; Woong Soon Yue

    2001-01-01

    The study of stress-strain relationship is very important in many designs of buried structures over the years. The behavior and mechanism between the interaction of soil and buried structures such as a natural pipeline will mostly contributes to the integrity of the pipeline. This paper presents a fully coupled finite element of consolidation analysis model to study the stress-strain distribution along a buried pipeline before it excess its maximum deformation limit. The behavior of the soil-pipeline system can be modelled by a non-linear elasto-plastic based on Mohr-Coulomb and critical state yield surfaces. The deformation and deflection of the pipeline due to drained and external loading condition will be considered here. Finally the stress-strain distribution of the buried pipeline will be utilised to obtain the maximum deformation limit and the deflection of the buried pipeline. (Author)

  8. Image restoration techniques using Compton backscatter imaging for the detection of buried land mines

    Science.gov (United States)

    Wehlburg, Joseph C.; Keshavmurthy, Shyam P.; Watanabe, Yoichi; Dugan, Edward T.; Jacobs, Alan M.

    1995-06-01

    Earlier landmine imaging systems used two collimated detectors to image objects. These systems had difficulty in distinguishing between surface features and buried features. Using a combination of collimated and uncollimated detectors in a Compton backscatter imaging (CBI) system, allows the identification of surface and buried features. Images created from the collimated detectors contain information about the surface and the buried features, while the uncollimated detectors respond (approximately 80%) to features on the surface. The analysis of surface features are performed first, then these features can be removed and the buried features can be identified. Separation of the surface and buried features permits the use of a globbing algorithm to define regions of interest that can then be quantified [area, Y dimension, X dimension, and center location (xo, yo)]. Mine composition analysis is also possible because of the properties of the four detector system. Distinguishing between a pothole and a mine, that was previously very difficult, can now be easily accomplished.

  9. Operation for Rokkasho Low Level Radioactive Waste Disposal Center

    International Nuclear Information System (INIS)

    Kamizono, Hideki

    2008-01-01

    The Rokkasho Low Level Radioactive Waste (LLW) Disposal Center is located in Oishitai, Rokkasho-mura, Kamikitagun, of Aomori Prefecture. This district is situated in the southern part of Shimohita Peninsula in the northeastern corner of the prefecture, which lies at the northern tip of Honshu, Japan's main island. The Rokkasho LLW Disposal Center deals with only LLW generated by operating of nuclear power plants. The No.1 and No.2 disposal facility are now in operation. The disposal facilities in operation have a total dispose capacity of 80,000m 3 (equivalent to 400,000 drums). Our final business scope is to dispose of radioactive waste corresponding to 600,000 m 3 (equivalent to 3000,000 drums). For No.1 disposal facility, we have been disposing of homogeneous waste, including condensed liquid waste, spent resin, solidified with cement and asphalt, etc. For No.2 disposal facility, we can bury a solid waste solidified with mortar, such as activated metals and plastics, etc. Using an improved construction technology for an artificial barrier, the concrete pits in No.2 disposal facility could be constructed more economical and spacious than that of No.1. Both No.1 and No.2 facility will be able to bury about 200,000 waste packages (drums) each corresponding to 40,000 m 3 . As of March 17, 2008, Approximately 200,00 waste drums summing up No.1 and No.2 disposal facility have been received from Nuclear power plants and buried. (author)

  10. The OTD Robotics Waste Minimization Program

    International Nuclear Information System (INIS)

    Couture, S.A.

    1992-04-01

    The danger to human health and safety posed by exposure to transuranic (TRU) and Pu contaminated materials necessitates remote processing in confined environments. Currently these operations are carried out in gloveboxes and hot-cells by human operators using lead- lined gloves or teleoperated manipulators. Protective clothing worn by operators during gloved operations has contributed significantly to the waste problems currently facing site remediators. The DOE Environmental Restoration and Waste Management (ER/WM) Program is in the process of developing and demonstrating technologies to assist in the remediation of sites that have accumulated wastes generated using these processes over the past five decades. Recognizing that continued use of existing production, recovery and waste treatment systems will compound the remediation problem, DOE has made a commitment to waste minimization. To reduce waste generation during weapons production and waste processing operations, automated processes are being developed and demonstrated for use in future DOE processing facilities as part of OTD's Robotics Technology Development Program. These technologies are currently being applied to pyrochemical processing systems to demonstrate conversion of plutonium oxide to metal. However, these technologies are expected to have applications in a variety of waste processing systems including those used to treat high-level tank wastes, buried wastes requiring remote processing, mixed wastes, and unknown hazardous materials. In addition to reducing the future waste burden of DOE, automated processes are an effective way to comply with existing and anticipated federal, state, and local regulations related to personal health and safety and the health of the environment

  11. Hydrostratigraphy of the Snake River Plain aquifer beneath the Radioactive Waste Management Complex at the Idaho National Engineering Laboratory: A preliminary report

    International Nuclear Information System (INIS)

    Hegmann, M.J.; Wood, S.H.

    1994-01-01

    Geophysical logs for 6 wells which penetrate the Snake River Plain aquifer at the Radioactive Waste Management Complex (RWMC) were analyzed for preliminary information on the hydrostratigraphy. Using stratigraphic correlation of flow groups worked out by Anderson and Lewis (1989), and by Anderson, as well as gamma signatures of flows within these flow groups, correlation of individual flows is attempted. Within these flows, probable permeable zones, suggested by density and caliper logs, are identified, and zones of hydraulic connection are tentatively correlated. In order to understand the response of density and neutron logs in basalt, the geological characteristics are quantified for the 150-ft section of the well C1A core, from depth 550 to 710 ft. 9 refs., 4 figs

  12. In situ vitrification engineering-scale test ES-INEL-5 test plan

    International Nuclear Information System (INIS)

    Stoots, P.R.

    1990-06-01

    In 1952, the Radioactive Waste Management Complex (RWMC) was established at the Idaho National Engineering Laboratory (INEL). RWMC is located on approximately 144 acres in the southwestern corner of the INEL site and was established as a controlled area for the burial of solid low-level wastes generated by INEL operations. In 1954, the 88-acre Subsurface Disposal Area (SDA) of RWMC began accepting solid transuranic-contaminated waste. From 1954 to 1970, transuranic-contaminated waste was accepted from the Rocky Flats Plant (RFP) near Golden, CO, as well as from other US Department of Energy (DOE) locations. In 1987, the Buried Waste Program (BWP) was established by EG ampersand G Idaho, Inc., the prime contractor at INEL. Following the Environmental Restoration guidelines of the Buried Waste Program, the In Situ Vitrification Program is participating in a Remedial Investigation/Feasibility Study (RI/FS) for permanent disposal of INEL waste, in compliance with the Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA). This study was requested and is being funded by the Office of Technology Development of the Idaho Operations Office of DOE (DOE-ID). As part of the RI/FS, an in situ vitrification (ISV) scoping study on the treatability of mixed low-level and mixed transuranic-contaminated waste is being performed to determine applicability of ISV to remediation of waste at SDA. This In Situ Vitrification Engineering-Scale Test ES-INEL-5 Test Plan considers the data needs of engineering, regulatory, health, and safety activities for all sampling and analysis activities in support of engineering scale test ES-INEL-5. 5 refs., 3 figs., 4 tabs

  13. Early screening of nuclear waste retrieval and processing alternatives

    International Nuclear Information System (INIS)

    Whitty, W.J.; Cox, N.D.

    1979-01-01

    The retrieval and processing of the buried transuranic-contaminated waste stored at the Idaho National Engineering Laboratory was studied by two task force teams. A linear additive scoring model was used for the evaluation. The figures of merit for the retrieval systems showed that one of the systems was superior to the others

  14. Radioactive waste disposal

    International Nuclear Information System (INIS)

    Cluchet, J.; Roger, B.

    1975-10-01

    After mentioning the importance of the problem of the disposal of wastes produced in the electro-nuclear industry, a short reminder on a few laws of radioactivity (nature and energy of radiations, half-life) and on some basic dosimetry is given. The conditioning and storage procedures are then indicated for solid wastes. The more active fractions of liquid wastes are incorporated into blocks of glass, whereas the less active are first concentrated by chemical treatments or by evaporation. The concentrates are then embedded into concrete, asphalt or resins. Storage is done according to the nature of each type of wastes: on a hard-surfaced area or inside concrete-lined trenches for the lowest radioactivity, in pits for the others. Transuranium elements with very long half-lives are buried in very deep natural cavities which can shelter them for centuries. From the investigations conducted so far and from the experience already gained, it can be concluded that safe solutions are within our reach [fr

  15. Geological storage of radioactive waste

    International Nuclear Information System (INIS)

    Barthoux, A.

    1983-01-01

    Certain radioactive waste contains substances which present, although they disappear naturally in a progressive manner, a potential risk which can last for very long periods, of over thousands of years. To ensure a safe long-term handling, provision has been made to bury it deep in stable geological structures which will secure its confinement. Radioactive waste is treated and conditioned to make it insoluble and is then encased in matrices which are to immobilize them. The most radioactive waste is thus incorporated in a matrix of glass which will ensure the insulation of the radioactive substances during the first thousands of years. Beyond that time, the safety will be ensured by the properties of the storage site which must be selected from now on. Various hydrogeological configurations have been identified. They must undergo detailed investigations, including even the creation of an underground laboratory. This document also presents examples of underground storage installations which are due to be built [fr

  16. Legal aspects of sub-seabed disposal of radioactive waste

    International Nuclear Information System (INIS)

    Reyners, P.

    1981-10-01

    In connection with methods for disposal of highly radioactive waste, that consisting of burying such waste in the sub-seabed arouses an increasingly marked interest among specialists. Apart from the technical difficulties still to be overcome and current safety assessments, this method gives rise to quite considerable legal and political problems. Their solution will undoubtedly have a bearing on its chances of being implemented. (NEA) [fr

  17. High-Level Waste System Process Interface Description

    International Nuclear Information System (INIS)

    D'Entremont, P.D.

    1999-01-01

    The High-Level Waste System is a set of six different processes interconnected by pipelines. These processes function as one large treatment plant that receives, stores, and treats high-level wastes from various generators at SRS and converts them into forms suitable for final disposal. The three major forms are borosilicate glass, which will be eventually disposed of in a Federal Repository, Saltstone to be buried on site, and treated water effluent that is released to the environment

  18. The puzzle of nuclear wastes. Radioactive threat to your health..

    International Nuclear Information System (INIS)

    2007-01-01

    This document, published by the French association 'Sortir du nucleaire' (Get out of nuclear), gives some information on what is radioactivity, the radioactive materials as a risk for living organisms, nuclear wastes all over France (list and map of the storage sites, power plants and fuel cycle centers), nuclear wastes at every step of the nuclear connection, the insolvable problem of high activity wastes, burying nuclear wastes in order to better forget them, radioactivity as a time bomb for our health, radioactive effluents as an under-estimated risk, artificial radioactivity already responsible for the death of 61 million people in the world, and so on

  19. Buried Object Detection Method Using Optimum Frequency Range in Extremely Shallow Underground

    Science.gov (United States)

    Sugimoto, Tsuneyoshi; Abe, Touma

    2011-07-01

    We propose a new detection method for buried objects using the optimum frequency response range of the corresponding vibration velocity. Flat speakers and a scanning laser Doppler vibrometer (SLDV) are used for noncontact acoustic imaging in the extremely shallow underground. The exploration depth depends on the sound pressure, but it is usually less than 10 cm. Styrofoam, wood (silver fir), and acrylic boards of the same size, different size styrofoam boards, a hollow toy duck, a hollow plastic container, a plastic container filled with sand, a hollow steel can and an unglazed pot are used as buried objects which are buried in sand to about 2 cm depth. The imaging procedure of buried objects using the optimum frequency range is given below. First, the standardized difference from the average vibration velocity is calculated for all scan points. Next, using this result, underground images are made using a constant frequency width to search for the frequency response range of the buried object. After choosing an approximate frequency response range, the difference between the average vibration velocity for all points and that for several points that showed a clear response is calculated for the final confirmation of the optimum frequency range. Using this optimum frequency range, we can obtain the clearest image of the buried object. From the experimental results, we confirmed the effectiveness of our proposed method. In particular, a clear image of the buried object was obtained when the SLDV image was unclear.

  20. Assessing mixed waste treatment technologies

    International Nuclear Information System (INIS)

    Berry, J.B.; Bloom, G.A.; Hart, P.W.

    1994-01-01

    The US Department of Energy (DOE) is responsible for the management and treatment of its mixed low-level wastes (MLLW). As discussed earlier in this conference MLLW are regulated under both the Resource Conservation and Recovery Act and various DOE orders. During the next 5 years, DOE will manage over 1,200,000 m 3 of MLLW and mixed transuranic (MTRU) waste at 50 sites in 22 states (see Table 1). The difference between MLLW and MTRU waste is in the concentration of elements that have a higher atomic weight than uranium. Nearly all of this waste will be located at 13 sites. More than 1400 individual mixed waste streams exist with different chemical and physical matrices containing a wide range of both hazardous and radioactive contaminants. Their containment and packaging vary widely (e.g., drums, bins, boxes, and buried waste). This heterogeneity in both packaging and waste stream constituents makes characterization difficult, which results in costly sampling and analytical procedures and increased risk to workers

  1. Using Downhole Probes to Locate and Characterize Buried Transuranic and Mixed Low Level Waste

    Energy Technology Data Exchange (ETDEWEB)

    Steinman, Donald K; Bramblett, Richard L; Hertzog, Russel C

    2012-06-25

    Borehole logging probes were developed and tested to locate and quantify transuranic elements in subsurface disposal areas and in contaminated sites at USDOE Weapons Complex sites. A new method of measuring very high levels of chlroine in the subsurface was developed using pulsed neutron technology from oilfield applications. The probes were demonstrated at the Hanford site in wells containing plutonium and other contaminants.

  2. Simulations of water and solute movement in the buried waste repository at Vaalputs

    International Nuclear Information System (INIS)

    Hutson, J.L.

    1987-01-01

    A previous series of simulations examined the movement of water through trench cap configurations of several types. The objectives of this series are i) to extent the simulations from the surface to the bottom of the repository, accounting for the placement of drums, ii) to examine the magnitude and direction of water fluxes throughout this depth and iii) to simulate the movement of solutes, using various assumptions regarding solute adsorption. Two models were used. The first was an adaptation of a solute transport model which incorporates the transient water flow model used in previous simulations. This was used primarily to estimate the likely water fluxes in the drum placement region. Since it requires large amounts of computer time this model was used to simulate periods of one or two years only. The second model was a very simple steady state solute transport model which was used to simulate Cs distribution after a 100 year period, using flux data obtained from the transient model simulations. The most important conclusion reached from this series of simulations is that the movement of Cs in the soil under the likely water regime is extremely slow. 'Worst case' situations were simulated. Some of these situations are unlikely in reality but provide a useful indication of the rates of movement of solute under various conditions. For this reason it was assumed that plants were absent in cases when maximum percolation was simulated and present when maximum upward flow was simulated. In no case was a 'wick' (a textural barrier to unsaturated water flow) assumed to be present

  3. New paradigms on how to achieve zero food waste in future cities : Optimizing food use by waste prevention and valorization

    OpenAIRE

    Redlingshofer, Barbara; Guilbert, Stéphane; Fuentes, Claire; Gracieux, Mélanie

    2015-01-01

    Cities currently manage uneaten food and other food system based biowaste quite inefficiently. The organic compound, despite its high nutriment value, is only to a small extent recycled and returned to farm soil and therefore, does not contribute to closing ecological nutrient cycles and to supporting sustainable food production [1]. In the US, over 97% of food waste is estimated to be buried in landfills [2]. Forkes has shown for Toronto that only 4.7% at most of food waste nitrogen (includi...

  4. Statistical survey of the buried waters in the Protein Data Bank.

    Science.gov (United States)

    Carugo, Oliviero

    2016-01-01

    The structures of buried water molecules were studied in an ensemble of high-quality and non-redundant protein crystal structures. Buried water molecules were clustered and classified in lake-like clusters, which are completely isolated from the bulk solvent, and bay-like clusters, which are in contact with the bulk solvent through a surface water molecule. Buried water molecules are extremely common: lake-like clusters are found in 89 % of the protein crystal structures and bay-like clusters in 93 %. Clusters with only one water molecule are much more common than larger clusters. Both cluster types incline to be surrounded by loop residues, and to a minor extent by residues in extended secondary structure. Helical residues on the contrary do not tend to surround clusters of buried water molecules. One buried water molecule is found every 30-50 amino acid residues, depending on the secondary structures that are more abundant in the protein. Both main- and side-chain atoms are in contact with buried waters; they form four hydrogen bonds with the first water and 1-1.5 additional hydrogen bond for each additional water in the cluster. Consequently, buried water molecules appear to be firmly packed and rigid like the protein atoms. In this regard, it is remarkable to observe that prolines often surround water molecules buried in the protein interior. Interestingly, clusters of buried water molecules tend to be just beneath the protein surface. Moreover, water molecules tend to form a one-dimensional wire rather than more compact arrangements. This agrees with recent evidence of the mechanisms of solvent exchange between internal cavities and bulk solvent.

  5. Inventory and sources of transuranic solid waste

    International Nuclear Information System (INIS)

    1978-08-01

    In the past, solid radioactive waste has often been buried in the most accessible and convenient vacant place, without a great deal of thought for the long-term consequences. The transuranium (TRU) elements were very strictly conserved and, at first, solid waste containing separated fission products was not a serious land burial problem. Wartime pressures for production and lack of knowledge or understanding led to siting and operational practices that, in many situations, are unsatisfactory by present day standards. Purpose of this report is to support the development of standards and criteria which will specifically address the problem of TRU contaminated waste generated by Department of Energy (DOE) nuclear programs and commercial application of nuclear technology. This report covers: DOE facilities, commercial disposal sites, commercial nuclear industry, TRU-contaminated waste inventory, and waste projections

  6. Solid waste - the long term strategy

    International Nuclear Information System (INIS)

    Johnson, L.F.

    1990-01-01

    Until deep underground repository sites for low-and intermediate-level radioactive wastes can be identified and prepared by Nirex Limited, these products are being encapsulated into solid concrete form by British Nuclear Fuels Limited (BNFL), and stored in 500- litre drums. Low-level solid waste is dealt with at BNFL's Drigg plant where it is buried in trenches. Recent improvements in rainwater leaching are outlined. Concrete-lined vaults and compactification devices are now operational as well. High-level waste which contains 97% of the radioactivity from irradiated fuel reprocessing, is converted into a vitrified glass product at the new Windscale Vitrification Plant. Together these form BNFL's comprehensive strategy for the treatment, interim storage and disposal of nuclear waste arising from its operations. Progress in the provision of waste management and of disposal facilities has been substantial. U.K

  7. Method for treating waste containing stainless steel

    International Nuclear Information System (INIS)

    Kujawa, S.T.; Battleson, D.M.; Rademacher, E.L. Jr.; Cashell, P.V.; Filius, K.D.; Flannery, P.A.; Whitworth, C.G.

    1999-01-01

    A centrifugal plasma arc furnace is used to vitrify contaminated soils and other waste materials. An assessment of the characteristics of the waste is performed prior to introducing the waste into the furnace. Based on the assessment, a predetermined amount of iron is added to each batch of waste. The waste is melted in an oxidizing atmosphere into a slag. The added iron is oxidized into Fe 3 O 4 . Time of exposure to oxygen is controlled so that the iron does not oxidize into Fe 2 O 3 . Slag in the furnace remains relatively non-viscous and consequently it pours out of the furnace readily. Cooled and solidified slag produced by the furnace is very resistant to groundwater leaching. The slag can be safely buried in the earth without fear of contaminating groundwater. 3 figs

  8. Nuclear waste management: A review of issues

    International Nuclear Information System (INIS)

    Angino, E.E.

    1985-01-01

    The subject of radioactive waste management and burial is a subject that raises strong emotional and political issues and generates sharp technical differences of opinion. The overall problem can be subdivided into the three major categories of (1) credibility and emotionalism, (2) technology, and (3) nuclear waste isolation and containment. An area of concern desperately in need of attention is that of proper public education on all aspects of the high-level radioactive-waste (rad-waste) burial problem. A major problem related to the rad-waste issue is the apparent lack of an official, all-encompassing U.S. policy for nuclear waste management, burial, isolation, and regulation. It is clear from all past technical reports that disposal of rad wastes in an appropriate geologic horizon is the best ultimate solution to the waste problem. After 25 y of dealing with the high-level radioactive waste problem, the difficulty is that no proposed plan has to date been tested properly. It is this indecision and reaction that has contributed in no small way to the public perception of inability to solve the problem. One major change that has occurred in the last few years was the enactment of the Nuclear Waste Policy Act of 1982. This act mandates deadlines, guidelines, and state involvement. It is time that strong differences of opinions be reconciled. One must get on with the difficult job of selecting the best means of isolating and burying these wastes before the task becomes impossible

  9. The Panther Mountain circular structure, a possible buried meteorite crater

    Science.gov (United States)

    Isachsen, Y. W.; Wright, S. F.; Revetta, F. A.; Duneen, R. J.

    Panther Mountain, located near Phoenicia, New York, is part of the Catskill Mountains, which form the eastern end of the Allegheny Plateau in New York. It is a circular mass defined physiographically by an anomalous circular drainage pattern produced by Esopus Creek and its tributary Woodland Creek. The circular valley that rings the mountain is fracture-controlled; where bedrock is exposed, it shows a joint density 5 to 10 times greater than that on either side of the valley. Where obscured by alluvial valley fill, the bedrock's low seismic velocity suggests that this anomalous fracturing is continuous in the bedrock underlying the rim valley. North-south and east-west gravity and magnetic profiles were made across the structure. Terrane-corrected, residual gravity profiles show an 18-mgal negative anomaly, and very steep gradients indicate a near-surface source. Several possible explanations of the gravity data were modeled. We conclude that the Panther Mountain circular structure is probably a buried meteorite crater that formed contemporaneously with marine or fluvial sedimentation during Silurian or Devonian time. An examination of drill core and cuttings in the region is underway to search for ejecta deposits and possible seismic and tsunami effects in the sedimentary section. Success would result in both dating the impact and furnishing a chronostratigraphic marker horizon.

  10. Polyenergy ion beam synthesis of buried oxynitride layer in silicon

    Energy Technology Data Exchange (ETDEWEB)

    Barabanenkov, M.Yu. E-mail: barab@ipmt-hpm.ac.ru; Agafonov, Yu.A.; Mordkovich, V.N.; Pustovit, A.N.; Vyatkin, A.F.; Zinenko, V.I

    2000-11-01

    The efficiency of silicon oxynitride synthesis in silicon crystals implanted with substoichiometric doses of oxygen and nitrogen ions is investigated both experimentally and theoretically. Si crystals are implanted with oxygen and nitrogen ions with doses of 1.5 and 4.5x10{sup 17} cm{sup -2}, respectively, at fixed oxygen ion energy of 150 keV and nitrogen ion energies varied from 80 to 180 keV. The samples annealed at 1200 deg C for 2 h were analysed by secondary ion mass spectroscopy (SIMS). Theoretically, a `diffusion-alternative sinks' model is applied to the annealing stage of ion beam synthesis of a buried layer of a new phase in solids. It is shown that the maximum of the ternary phase production is attained when nitrogen ions are implanted deeper than oxygen ions. An explanation of this fact is given in terms of that (i) the segregation of oxygen and nitrogen species on the surface of oxide nuclei removes the kinetic restriction of nuclei growth, characteristic of oxide growth, at the expense of only oxygen atoms, and (ii) the higher the implantation energy the smoother the shape of ion range distribution in the target, which, in its turn, causes the predominance of the impurity sink over the impurity diffusion.

  11. Polyenergy ion beam synthesis of buried oxynitride layer in silicon

    International Nuclear Information System (INIS)

    Barabanenkov, M.Yu.; Agafonov, Yu.A.; Mordkovich, V.N.; Pustovit, A.N.; Vyatkin, A.F.; Zinenko, V.I.

    2000-01-01

    The efficiency of silicon oxynitride synthesis in silicon crystals implanted with substoichiometric doses of oxygen and nitrogen ions is investigated both experimentally and theoretically. Si crystals are implanted with oxygen and nitrogen ions with doses of 1.5 and 4.5x10 17 cm -2 , respectively, at fixed oxygen ion energy of 150 keV and nitrogen ion energies varied from 80 to 180 keV. The samples annealed at 1200 deg C for 2 h were analysed by secondary ion mass spectroscopy (SIMS). Theoretically, a `diffusion-alternative sinks' model is applied to the annealing stage of ion beam synthesis of a buried layer of a new phase in solids. It is shown that the maximum of the ternary phase production is attained when nitrogen ions are implanted deeper than oxygen ions. An explanation of this fact is given in terms of that (i) the segregation of oxygen and nitrogen species on the surface of oxide nuclei removes the kinetic restriction of nuclei growth, characteristic of oxide growth, at the expense of only oxygen atoms, and (ii) the higher the implantation energy the smoother the shape of ion range distribution in the target, which, in its turn, causes the predominance of the impurity sink over the impurity diffusion

  12. Parental care improves offspring survival and growth in burying beetles

    Science.gov (United States)

    Eggert; Reinking; MULLER

    1998-01-01

    Burying beetles (genus Nicrophorus) provide elaborate parental care to their offspring. Parental beetles defend a small vertebrate carcass, which constitutes the sole food source for the larvae. They also manipulate the carcass in various ways and directly regurgitate pre-digested carrion to the young. The benefits of carcass manipulation and regurgitation have been the subject of a few small-scale studies that have yielded conflicting results. In this study, we investigated the benefits of these behaviours and tested for possible beneficial effects on larval survival rates and final body mass in N. vespilloides. In this species: (1) larval survival and mass were significantly higher in broods receiving parental care throughout larval development on the carcass than in broods developing in the absence of adults; (2) parental presence immediately subsequent to larval hatching greatly improved larval survival rates; (3) continued parental presence for several days further improved larval growth, leading to a greater final mass of individual larvae; (4) larval survival and growth were improved by parental preparation of carcasses and by an excision made in the integument of the carcass surface by the parents that allows the larvae ready access to their food; (5) positive effects of parental feeding on larval survival and growth were not mediated by the transfer of symbionts. Copyright 1998 The Association for the Study of Animal Behaviour.

  13. Parental care buffers against inbreeding depression in burying beetles.

    Science.gov (United States)

    Pilakouta, Natalie; Jamieson, Seonaidh; Moorad, Jacob A; Smiseth, Per T

    2015-06-30

    When relatives mate, their inbred offspring often suffer a reduction in fitness-related traits known as "inbreeding depression." There is mounting evidence that inbreeding depression can be exacerbated by environmental stresses such as starvation, predation, parasitism, and competition. Parental care may play an important role as a buffer against inbreeding depression in the offspring by alleviating these environmental stresses. Here, we examine the effect of parental care on the fitness costs of inbreeding in the burying beetle Nicrophorus vespilloides, an insect with facultative parental care. We used a 2 × 2 factorial design with the following factors: (i) the presence or absence of a caring female parent during larval development and (ii) inbred or outbred offspring. We examined the joint influence of maternal care and inbreeding status on fitness-related offspring traits to test the hypothesis that maternal care improves the performance of inbred offspring more than that of outbred offspring. Indeed, the female's presence led to a higher increase in larval survival in inbred than in outbred broods. Receiving care at the larval stage also increased the lifespan of inbred but not outbred adults, suggesting that the beneficial buffering effects of maternal care can persist long after the offspring have become independent. Our results show that parental care has the potential to moderate the severity of inbreeding depression, which in turn may favor inbreeding tolerance and influence the evolution of mating systems and other inbreeding-avoidance mechanisms.

  14. Multiple-beam LDV system for buried landmine detection

    Science.gov (United States)

    Lal, Amit K.; Zhang, Hansheng; Aranchuk, Vyacheslav; Hurtado, Ernesto; Hess, Cecil F.; Burgett, Richard D.; Sabatier, James M.

    2003-09-01

    This paper discusses the performance and experimental results of a multiple beam laser Doppler vibrometer designed to locate buried landmines with the laser-acoustic technique. The device increases the speed of landmine detection by simultaneously probing 16 positions on the ground over a span of 1 meter, and measuring the ground velocity at each of these positions. Experimental results are presented from controlled laboratory experiments as well as from landmine test lanes at the University of Mississippi. In the mine lanes, the multiple beam system is raised to a height of 2.5 meters with a forklift, with the 16 beams spread over a 1 meter line along the mine lane. A motor system then allows the 16 beams to be translated across the mine lane, enabling the system to scan a 1 x 1 meter area in a much shorter time than with previous scanning techniques. The effects of experimental parameters such as platform motion, angle of incidence, speckle dropout, and system depth-of-field will be presented and discussed.

  15. A corrosion detection system for buried pipeline (II)

    International Nuclear Information System (INIS)

    Choi, Yoon Seok; Shin, Dong Ho; Kim, Sang Hyun; Kim, Jung Gu

    2005-01-01

    In order to develop a new corrosion sensor for detecting and monitoring the corrosion of buried pipeline, the electrochemical property of sensors and the correlation of its output to corrosion rate of steel pipe, were evaluated by electrochemical methods in synthetic groundwater, two soils of varying resistivity (5,000 ohm-cm, 10,000 ohm-cm), and synthetic tap water. In this paper, two types of electrochemical probes were used: galvanic cells containing of pipeline steel-copper and pipeline steel-stainless steel (Type 304). The results of EIS measurement indicated that the sensor current was inversely related to sensor resistance, which was governed by the corrosion behavior of cathode. In galvanic corrosion tests, the galvanic current of Cu-CS probe was higher than that of SS-CS probe. The comparison of the sensor output and corrosion rates revealed that a linear relationship was found between the probe current and the corrosion rates. A good linear quantitative relationship was found between the Cu-CS probe current and the corrosion rate of pipeline steel coupons in the soil resistivity of 5,000 ohm-cm, and synthetic tap water. In the case of the soil resistivity of 10,000 ohm-cm, although the SS-CS probe showed a better linear correlation than that of Cu-CS probe, the Cu-CS probe is more suitable than SS-CS probe, due to the high current output

  16. Visualizing excitations at buried heterojunctions in organic semiconductor blends.

    Science.gov (United States)

    Jakowetz, Andreas C; Böhm, Marcus L; Sadhanala, Aditya; Huettner, Sven; Rao, Akshay; Friend, Richard H

    2017-05-01

    Interfaces play a crucial role in semiconductor devices, but in many device architectures they are nanostructured, disordered and buried away from the surface of the sample. Conventional optical, X-ray and photoelectron probes often fail to provide interface-specific information in such systems. Here we develop an all-optical time-resolved method to probe the local energetic landscape and electronic dynamics at such interfaces, based on the Stark effect caused by electron-hole pairs photo-generated across the interface. Using this method, we found that the electronically active sites at the polymer/fullerene interfaces in model bulk-heterojunction blends fall within the low-energy tail of the absorption spectrum. This suggests that these sites are highly ordered compared with the bulk of the polymer film, leading to large wavefunction delocalization and low site energies. We also detected a 100 fs migration of holes from higher- to lower-energy sites, consistent with these charges moving ballistically into more ordered polymer regions. This ultrafast charge motion may be key to separating electron-hole pairs into free charges against the Coulomb interaction.

  17. Surface wave propagation effects on buried segmented pipelines

    Directory of Open Access Journals (Sweden)

    Peixin Shi

    2015-08-01

    Full Text Available This paper deals with surface wave propagation (WP effects on buried segmented pipelines. Both simplified analytical model and finite element (FE model are developed for estimating the axial joint pullout movement of jointed concrete cylinder pipelines (JCCPs of which the joints have a brittle tensile failure mode under the surface WP effects. The models account for the effects of peak ground velocity (PGV, WP velocity, predominant period of seismic excitation, shear transfer between soil and pipelines, axial stiffness of pipelines, joint characteristics, and cracking strain of concrete mortar. FE simulation of the JCCP interaction with surface waves recorded during the 1985 Michoacan earthquake results in joint pullout movement, which is consistent with the field observations. The models are expanded to estimate the joint axial pullout movement of cast iron (CI pipelines of which the joints have a ductile tensile failure mode. Simplified analytical equation and FE model are developed for estimating the joint pullout movement of CI pipelines. The joint pullout movement of the CI pipelines is mainly affected by the variability of the joint tensile capacity and accumulates at local weak joints in the pipeline.

  18. Computer simulation of explosion crater in dams with different buried depths of explosive

    Science.gov (United States)

    Zhang, Zhichao; Ye, Longzhen

    2018-04-01

    Based on multi-material ALE method, this paper conducted a computer simulation on the explosion crater in dams with different buried depths of explosive using LS-DYNA program. The results turn out that the crater size increases with the increase of buried depth of explosive at first, but closed explosion cavity rather than a visible crater is formed when the buried depth of explosive increases to some extent. The soil in the explosion cavity is taken away by the explosion products and the soil under the explosion cavity is compressed with its density increased. The research can provide some reference for the anti-explosion design of dams in the future.

  19. Distinguishing Buried Objects in Extremely Shallow Underground by Frequency Response Using Scanning Laser Doppler Vibrometer

    Science.gov (United States)

    Touma Abe,; Tsuneyoshi Sugimoto,

    2010-07-01

    A sound wave vibration using a scanning laser Doppler vibrometer are used as a method of exploring and imaging an extremely shallow underground. Flat speakers are used as a vibration source. We propose a method of distinguishing a buried object using a response range of a frequencies corresponding to a vibration velocities. Buried objects (plastic containers, a hollow steel can, an unglazed pot, and a stone) are distinguished using a response range of frequencies. Standardization and brightness imaging are used as methods of discrimination. As a result, it was found that the buried objects show different response ranges of frequencies. From the experimental results, we confirmed the effectiveness of our proposed method.

  20. Ultra thin buried oxide layers formed by low dose Simox process

    Energy Technology Data Exchange (ETDEWEB)

    Aspar, B.; Pudda, C.; Papon, A.M. [CEA Centre d`Etudes de Grenoble, 38 (France). Lab. d`Electronique et d`Instrumentation; Auberton Herve, A.J.; Lamure, J.M. [SOITEC, 38 - Grenoble (France)

    1994-12-31

    Oxygen low dose implantation is studied for two implantation energies. For 190 keV, a continuous buried oxide layer is obtained with a high dislocation density in the top silicon layer due to SiO{sub 2} precipitates. For 120 keV, this silicon layer is free of SiO{sub 2} precipitate and has a low dislocation density. Low density of pin-holes is observed in the buried oxide. The influence of silicon islands in the buried oxide on the breakdown electric fields is discussed. (authors). 6 refs., 5 figs.

  1. Pannus Is the New Prepuce? Penile Cancer in a Buried Phallus

    Directory of Open Access Journals (Sweden)

    Jared Manwaring

    2015-01-01

    Full Text Available Two males presented to our urology department with complaints of bleeding and malodor from buried phallus within a suprapubic fat pad. Although both men had neonatal circumcisions, advanced penile carcinoma was found in both men. Formal penectomies showed high grade, poorly differentiated squamous cell carcinoma invading the corporal bodies and urethra. Buried penis represents a difficulty in early detection of suspicious lesions but may also provide an environment susceptible to poor hygiene and subsequent chronic inflammation. Patients with buried penis may be at a higher risk for development of invasive penile cancer and may benefit from regular and thorough genital exams.

  2. Imaging of buried phosphorus nanostructures in silicon using scanning tunneling microscopy

    Energy Technology Data Exchange (ETDEWEB)

    Oberbeck, Lars [Centre for Quantum Computation and Communication Technology, School of Physics, University of New South Wales, Sydney, New South Wales 2052 (Australia); TOTAL Marketing Services, New Energies, La Défense 10, 92069 Paris La Défense Cedex (France); Reusch, Thilo C. G.; Hallam, Toby; Simmons, Michelle Y., E-mail: n.curson@ucl.ac.uk, E-mail: michelle.simmons@unsw.edu.au [Centre for Quantum Computation and Communication Technology, School of Physics, University of New South Wales, Sydney, New South Wales 2052 (Australia); Schofield, Steven R. [Centre for Quantum Computation and Communication Technology, School of Physics, University of New South Wales, Sydney, New South Wales 2052 (Australia); London Centre for Nanotechnology, UCL, London WC1H 0AH (United Kingdom); Department of Physics and Astronomy, UCL, London WC1E 6BT (United Kingdom); Curson, Neil J., E-mail: n.curson@ucl.ac.uk, E-mail: michelle.simmons@unsw.edu.au [Centre for Quantum Computation and Communication Technology, School of Physics, University of New South Wales, Sydney, New South Wales 2052 (Australia); London Centre for Nanotechnology, UCL, London WC1H 0AH (United Kingdom); Department of Electronic and Electrical Engineering, UCL, London WC1E 7JE (United Kingdom)

    2014-06-23

    We demonstrate the locating and imaging of single phosphorus atoms and phosphorus dopant nanostructures, buried beneath the Si(001) surface using scanning tunneling microscopy. The buried dopant nanostructures have been fabricated in a bottom-up approach using scanning tunneling microscope lithography on Si(001). We find that current imaging tunneling spectroscopy is suited to locate and image buried nanostructures at room temperature and with residual surface roughness present. From these studies, we can place an upper limit on the lateral diffusion during encapsulation with low-temperature Si molecular beam epitaxy.

  3. Ultra thin buried oxide layers formed by low dose Simox process

    International Nuclear Information System (INIS)

    Aspar, B.; Pudda, C.; Papon, A.M.

    1994-01-01

    Oxygen low dose implantation is studied for two implantation energies. For 190 keV, a continuous buried oxide layer is obtained with a high dislocation density in the top silicon layer due to SiO 2 precipitates. For 120 keV, this silicon layer is free of SiO 2 precipitate and has a low dislocation density. Low density of pin-holes is observed in the buried oxide. The influence of silicon islands in the buried oxide on the breakdown electric fields is discussed. (authors). 6 refs., 5 figs

  4. Imaging of buried phosphorus nanostructures in silicon using scanning tunneling microscopy

    International Nuclear Information System (INIS)

    Oberbeck, Lars; Reusch, Thilo C. G.; Hallam, Toby; Simmons, Michelle Y.; Schofield, Steven R.; Curson, Neil J.

    2014-01-01

    We demonstrate the locating and imaging of single phosphorus atoms and phosphorus dopant nanostructures, buried beneath the Si(001) surface using scanning tunneling microscopy. The buried dopant nanostructures have been fabricated in a bottom-up approach using scanning tunneling microscope lithography on Si(001). We find that current imaging tunneling spectroscopy is suited to locate and image buried nanostructures at room temperature and with residual surface roughness present. From these studies, we can place an upper limit on the lateral diffusion during encapsulation with low-temperature Si molecular beam epitaxy.

  5. The Mixed Waste Management Facility closure and expansion at the Savannah River Site

    International Nuclear Information System (INIS)

    Bittner, M.F.; Frye-O'Bryant, R.C.

    1992-01-01

    Process wastes containing radioactive and hazardous constituents have been generated throughout the operational history of the Savannah River Site. Solid wastes containing low level radionuclides were buried in Low Level Radioactive Disposal Facility (LLRWDF). Until 1986, waste containing lead and cadmium was disposed of in the Mixed Waste Management Facility (MWMF) portion of LLRWDF. Between 1986 and 1990, waste containing F-listed hazardous rags were buried. Current Resource Conservation and Recovery Act (RCRA) regulations prohibit the disposal of these hazardous wastes at nonpermitted facilities. This paper describes the closure activities for the MWMF, completed in 1990 and plans proposed for the expansion of this closure to include the LLRWDF suspect solvent rag trenches

  6. Overwintering biology and tests of trap and relocate as a conservation measure for burying beetles.

    Science.gov (United States)

    2015-01-01

    Burying beetles are carrion beetles and utilize dead animal carcasses for feeding : and reproductive efforts. They assist with decomposition, prevent the spread of disease, : and reduce the number of pest species. The largest species of carrion beetl...

  7. Direct measurements of the velocity and thickness of ''explosively'' propagating buried molten layers in amorphous silicon

    International Nuclear Information System (INIS)

    Lowndes, D.H.; Jellison, G.E. Jr.; Pennycook, S.J.; Withrow, S.P.; Mashburn, D.N.

    1986-01-01

    Simultaneous infrared (1152 nm) and visible (633 nm) reflectivity measurements with nanosecond resolution were used to study the initial formation and subsequent motion of pulsed KrF laser-induced ''explosively'' propagating buried molten layers in ion implantation-amorphized silicon. The buried layer velocity decreases with depth below the surface, but increases with KrF laser energy density; a maximum velocity of about 14 m/s was observed, implying an undercooling-velocity relationship of approx. 14 K/(m/s). Z-contrast scanning transmission electron microscopy was used to form a direct chemical image of implanted Cu ions transported by the buried layer and showed that the final buried layer thickness was <15 nm

  8. Radiological hazards of alpha-contaminated waste

    International Nuclear Information System (INIS)

    Rodgers, J.C.

    1982-01-01

    The radiological hazards of alpha-contaminated wastes are discussed in this overview in terms of two components of hazard: radiobiological hazard, and radioecological hazard. Radiobiological hazard refers to human uptake of alpha-emitters by inhalation and ingestion, and the resultant dose to critical organs of the body. Radioecological hazard refers to the processes of release from buried wastes, transport in the environment, and translocation to man through the food chain. Besides detailing the sources and magnitude of hazards, this brief review identifies the uncertainties in their estimation, and implications for the regulatory process

  9. Predicting arsenic concentrations in porewaters of buried uranium mill tailings

    Energy Technology Data Exchange (ETDEWEB)

    Langmuir, D.; Mahoney, J.; MacDonald, A.; Rowson, J.

    1999-10-01

    The proposed JEB Tailings Management Facility (TMF) to be emplaced below the groundwater table in northern Saskatchewan, Canada, will contain uranium mill tailings from McClean Lake, Midwest and Cigar Lake ore bodies, which are high in arsenic (up to 10%) and nickel (up to 5%). A serious concern is the possibility that high arsenic and nickel concentrations may be released from the buried tailings, contaminating adjacent groundwaters and a nearby lake. Laboratory tests and geochemical modeling were performed to examine ways to reduce the arsenic and nickel concentrations in TMF porewaters so as to minimize such contamination from tailings buried for 50 years and longer. The tests were designed to mimic conditions in the mill neutralization circuit (3 hr tests at 25 C), and in the TMF after burial (5--49 day aging tests). The aging tests were run at 50, 25 and 4 C (the temperature in the TMF). In order to optimize the removal of arsenic by adsorption and precipitation, ferric sulfate was added to tailings raffinates having Fe/As ratios of less than 3--5. The acid raffinates were then neutralized by addition of slaked lime to nominal pH values of 7, 8, or 9. Analysis and modeling of the test results showed that with slaked lime addition to acid tailings raffinates, relatively amorphous scorodite (ferric arsenate) precipitates near pH 1, and is the dominant form of arsenate in slake limed tailings solids except those high in Ni and As and low in Fe, in which cabrerite-annabergite (Ni, Mg, Fe(II) arsenate) may also precipitate near pH 5--6. In addition to the arsenate precipitates, smaller amounts of arsenate are also adsorbed onto tailings solids. The aging tests showed that after burial of the tailings, arsenic concentrations may increase with time from the breakdown of the arsenate phases (chiefly scorodite). However, the tests indicate that the rate of change decreases and approaches zero after 72 hrs at 25 C, and may equal zero at all times in the TMF at 4 C

  10. Solving the sulphur situation : research assesses viability of burying sulphur

    International Nuclear Information System (INIS)

    Proce, B.

    2006-01-01

    Oil sands mining companies are looking for ways to manage growing levels of sulphur production from the Athabasca region. Infrastructure is not in place to economically transport the sulphur even though there is a global market for it. Sulphur cannot be stockpiled indefinitely as it can react with air to produce sulphur dioxide. Although above-ground sulphur storage has been regulated for more than 30 years, the underground storage of sulphur is still in a research and development phase. Alberta Sulphur Research Ltd. is currently conducting an ongoing experiment in which 100 tonne test blocks have been buried above and below the water table so that surrounding areas could be monitored over a period of years. A series of tests is being conducted to examine changes in pH in water and sulphate levels. A multi-layered engineering casing to contain the sulphur and prevent seepage is also being investigated. Once stored underground, operators also have to consider how the sulphur will be accessed in the future, as it is subject to government royalties. The storage of sulphur may have economic benefits as the product can be sold when prices are high. Most sulphur produced in Alberta is sold as an export product in the United States for use in products such as fertilizer. Shell Canada penetrated the Chinese market in 2001 and has since become one of Canada's largest sulphur exporters. Shell has also introduced a number of products using sulphur, including fertilizers, enhanced asphalt, and concrete. It was concluded that companies must take action now to mitigate future losses and to utilize current markets in order to remain competitive. 3 figs

  11. Isotope hydrogeochemistry in exploration for buried and blind mineralization

    International Nuclear Information System (INIS)

    Andrew, A.S.; Carr, G.R.; Giblin, A.M.; Whitford, D.J.

    2000-01-01

    Buried and blind deposits, with no direct geological or geochemical manifestation at the surface, are becoming increasingly important targets in Australia. One of the key exploration challenges relates to assessing and ranking targets established from geophysical and other remotely sensed surveys. Sub-surface geology is reflected in the geochemistry of groundwaters (Giblin, 1996) and hydrogeochemical methods provide a particularly powerful technique in areas of poor surface exposure, deep weathering and where transported overburden obscures the underlying geology (Giblin, 1997). In such areas several hundred samples are used to define locally prospective areas although how these relate to a specific mineralization style may be difficult to determine. The question of proximity to an orebody is fundamental to mineral exploration and isotopic (S, Pb, Sr) methods are uniquely capable of contributing to an answer. The isotopic composition of ores and waters that interact with ores carries important information about the elemental source; S and Pb are direct ore indicators allowing straight-forward interpretation of possible ore associations. The isotopic methods also provide unequivocal evidence for mixing. The isotopic compositions of S, Pb and Sr in rocks are unaffected by weathering and in natural waters are unaffected by precipitation, evaporation or dilution. Isotopic methods provide information that is complementary to that obtainable from major and trace element abundances. The application of integrated isotopic studies to conventional hydrogeochemical interpretations was tested in several areas (Fig. 1); Menninnie Dam (Pb, Zn; Eyre Peninsula SA), Abra (Ag, Pb; Bangemall Basin WA), Benambra (Cu, Zn, Pb: Lachlan Fold Belt Vic), Goonumbla (Cu, Au; Lachlan Fold Belt NSW) and Kanmantoo (Cu, Pb, Zn, Au; Kanmantoo Fold Belt SA). These were chosen to include different deposit types, tectonic regimes, climatic and topographic environments and groundwater chemistry

  12. Post-liquefaction soil-structure interaction for buried structures: Sensitivity analysis studies

    International Nuclear Information System (INIS)

    Pires, J.A.; Ang, H.S.; Katayama, I.; Satoh, M.

    1993-01-01

    The post liquefaction behavior of buried conduits is analyzed and sensitivity analysis is conducted to investigate the damage potential of the forces induced in the buried lifelines following seismically induced liquefaction of the surrounding soil. Various lifeline configurations and loading conditions are considered. The loading conditions considered are: buoyancy forces and permanent ground displacements parallel to the lifeline axis. Pertinent parameters for the soil-lifeline interaction following liquefaction are identified. (author)

  13. Exposed versus buried intramedullary implants for pediatric forearm fractures: a comparison of complications.

    Science.gov (United States)

    Kelly, Brian A; Miller, Patricia; Shore, Benjamin J; Waters, Peter M; Bae, Donald S

    2014-12-01

    The purpose of this study was to compare the rate of complications between buried and exposed intramedullary implants after fixation of pediatric forearm fractures. A retrospective comparative cohort study of 339 children treated with intramedullary fixation for displaced forearm fractures between 2004 and 2009 was performed. Implants were left exposed in 128 patients (37.8%) and buried beneath the skin in 208 patients (61.4%); 3 patients had buried and exposed hardware (0.9%). Data on demographics, injury, surgical technique, and complications were analyzed. The buried implant group was older (mean 10.3 vs. 8.5 y; P exposed implant group. The buried group had their implants removed later than the exposed group (median 3.5 vs. 1.2 mo; P exposed implants were successfully removed in the office. Complications were seen in 56 patients (16.5%). There were 16 patients (4.7%) with refracture and 12 patients (3.5%) with infection. The buried and exposed implant groups did not differ significantly with respect to refracture (3.1% vs. 7.0%; P = 0.20), infection (3.5% vs. 2.3%; P = 0.66), or overall complications (14.5% vs. 17.2%; P = 0.87). There was also no difference between groups with respect to loss of reduction, nondelayed or delayed union, loss of motion, hypertrophic granuloma, or tendon rupture. Buried implants were also associated with penetration through the skin (3.9%). Injury to the dominant arm and need for open reduction were significant predictors of complication (OR = 1.01; 95% CI, 1.001-1.012; P = 0.02 and OR = 0.51; 95% CI, 0.264-0.974; P = 0.04, respectively). There were no significant differences seen in number of infections, refractures, or overall complications based on whether implants were left exposed or buried beneath the skin after surgery. Level III, therapeutic.

  14. Seismic fragility analysis of buried steel piping at P, L, and K reactors

    International Nuclear Information System (INIS)

    Wingo, H.E.

    1989-10-01

    Analysis of seismic strength of buried cooling water piping in reactor areas is necessary to evaluate the risk of reactor operation because seismic events could damage these buried pipes and cause loss of coolant accidents. This report documents analysis of the ability of this piping to withstand the combined effects of the propagation of seismic waves, the possibility that the piping may not behave in a completely ductile fashion, and the distortions caused by relative displacements of structures connected to the piping

  15. Geophysical research results of buried relief and distribution groundwater runoff of the Aragats massif

    OpenAIRE

    V.P. Vardanyan; A.H. Hovhannisyan

    2017-01-01

    Based on the synthesis and reinterpretation of long-term data of geophysical studies together with the hydrology - hydrological materials it has been received new data about the buried topography and spatial distribution of groundwater runoff of the Aragats massif. First of all, it requires to determine the structure of its buried relief, which is basically a regional relief aquitard. The underground water sources are considered to be precipitation on the massif (approximately 83% of the tota...

  16. Imaging of Au nanoparticles deeply buried in polymer matrix by various atomic force microscopy techniques

    International Nuclear Information System (INIS)

    Kimura, Kuniko; Kobayashi, Kei; Matsushige, Kazumi; Yamada, Hirofumi

    2013-01-01

    Recently, some papers reported successful imaging of subsurface features using atomic force microscopy (AFM). Some theoretical studies have also been presented, however the imaging mechanisms are not fully understood yet. In the preceeding papers, imaging of deeply buried nanometer-scale features has been successful only if they were buried in a soft matrix. In this paper, subsurface features (Au nanoparticles) buried in a soft polymer matrix were visualized. To elucidate the imaging mechanisms, various AFM techniques; heterodyne force microscopy, ultrasonic atomic force microscopy (UAFM), 2nd-harmonic UAFM and force modulation microscopy (FMM) were employed. The particles buried under 960 nm from the surface were successfully visualized which has never been achieved. The results elucidated that it is important for subsurface imaging to choose a cantilever with a suitable stiffness range for a matrix. In case of using the most suitable cantilever, the nanoparticles were visualized using every technique shown above except for FMM. The experimental results suggest that the subsurface features buried in a soft matrix with a depth of at least 1 µm can affect the local viscoelasticity (mainly viscosity) detected as the variation of the amplitude and phase of the tip oscillation on the surface. This phenomenon presumably makes it possible to visualize such deeply buried nanometer-scale features in a soft matrix. - Highlights: • We visualized subsurface features buried in soft matrix, and investigated its imaging mechanism. • AFM techniques; UAFM, FMM, HFM and 2nd-harmonic UAFM were applied to elucidate the mechanism. • Au nanoparticles buried under 960 nm from surface were visualized, which has never been achieved. • Imaging at contact resonance using a cantilever of suitable stiffness is important. • Subsurface features in a soft matrix affect surface viscoelasticity, which are detected by AFM

  17. Detection of buried land mines using back scattered neutron induced γ-ray analysis

    International Nuclear Information System (INIS)

    Aziz, M.; Megahd, R.

    2003-01-01

    The application of nuclear technique to detection buried land mine is examined. MCNP code was used to design a computer model that calculate the back scattered neutron induced γ rays from buried simulate explosive materials. The characteristic γ rays for each isotopes were used to distinguish materials. The advantage of the nuclear technique was discussed. The results were compared with experimental measurements which show good agreement

  18. Thin films and buried interfaces characterization with X-ray standing waves

    Energy Technology Data Exchange (ETDEWEB)

    Lagomarsino, S [CNR, Rome (Italy). Istituto Elettronica Stato Solido

    1996-09-01

    The X-ray standing wave techniques is a powerful, non destructive method to study interfaces at the atomic level. Its basic features are described here together with the peculiarities of its applications to epitaxial films and buried interfaces. As examples of applications, experiments carried out on Si/silicide interfaces, on GaAs/InAs/GaAs buried interfaces and on Si/Ge superlattices are shown.

  19. Studies of phase formation in CoSi2 buried layers fabricated using ion implantation

    International Nuclear Information System (INIS)

    Galaev, A.A.; Parkhomenko, Yu.N.; Podgornyi, D.A.; Shcherbachev, K.D.

    1998-01-01

    The processes of the formation of cobalt disilicide buried layers in silicon are studied under different conditions of implantation with Co. In particular, the effects of the implantation dose and the postimplantation annealing temperature on the state of the Co-implanted layer are considered. Two types of heteroepitaxial Si/CoSi 2 /Si structures are obtained with the conducting layers of thicknesses 70 and 90 nm buried at the depths 80 and 10 nm, respectively

  20. FOREWORD: Special section on electromagnetic characterization of buried obstacles

    Science.gov (United States)

    Lesselier, Dominique; Chew, Weng Cho

    2004-12-01

    This Inverse Problems special section on electromagnetic characterization of buried obstacles contains a selection of 14 invited papers, involving 41 authors and 19 research groups worldwide. (Though this section consists of invited papers, the standard refereeing procedures of Inverse Problems have been rigorously observed.) We do not claim to have reached all the high-level researchers in the field, but we believe that we have made a fair attempt. As illustrated by the variety of contributions included, the aim of this special section is to address theoretical and practical inversion problems (and the solutions thereof) that arise in the field of electromagnetic characterization of obstacles (artificial or natural) buried on the Earth or in planetary subsoil. Civil and military engineering, archaeological and environmental issues are typically among those within the scope of the investigation. An example is the characterization of a single (or multiple) obstacle(s) located near the interface or at shallow depths via electromagnetic means operating within relevant frequency bands. However, we also welcomed novel and thought-provoking investigations, even though their direct application to the real world, or even to laboratory-controlled settings, may still be far off. Within this general mathematical and applied framework, the submitted papers focused on a combination of theoretical, computational and experimental developments. They either reviewed the most recent advances in a particular area of research or were an original and specialized contribution. Let us now take the opportunity to remind the readers that this special section harks back (in addition to sharing some common contributors) to two special sections already published in the journal which possessed the same flavour of wave-field inversion and its many applications. They were `Electromagnetic imaging and inversion of the Earth's subsurface', which was published in October 2000 (volume 16, issue 5

  1. Comprehensive Review and Case Study on the Management of Buried Penis Syndrome and Related Panniculectomy

    Science.gov (United States)

    Burns, Hadley; Chowdhry, Saeed; Lee, Thomas; Schulz, Steven; Wilhelmi, Bradon J.

    2018-01-01

    Objective: This paper discusses the various surgical techniques and outcomes associated with management of buried penis syndrome. Methods: Presented is the case of a 49-year-old man with morbid obesity, leading to massive panniculus and buried penis. We review our technique for reconstruction of the buried penis and treatment of the overlying large panniculus. Literature search was conducted to review current techniques in correcting buried penis syndrome. Results: The patient underwent a successful panniculectomy with removal of all excess skin and tissue. Thoughtful planning and coordination between plastic surgery and urology were paramount to externalize the penis for an excellent functional and cosmetic result. Conclusions: Management of a buried, hidden penis is complex and difficult. Patients are often obese and have poor hygiene due to the inability to cleanse areas that are entrapped by excessive fat. Following removal of the overhanging panniculus, satisfactory reconstruction of a hidden penis is possible when proper care is taken to adhere the base of the penis to the pubis. Split-thickness skin grafts are often necessary but depend on the viability of the penile skin and whether it is restricting penile length. Complications with wound dehiscence and infection are not uncommon; however, patients generally recover well, are satisfied with results, and are reported to have fully regained urinary and sexual functions following surgical correction of the buried penis. PMID:29467914

  2. Wastes options

    International Nuclear Information System (INIS)

    Maes, M.

    1992-01-01

    After a description of the EEC environmental policy, some wastes families are described: bio-contaminant wastes (municipal and industrial), hospitals wastes, toxic wastes in dispersed quantities, nuclear wastes (radioactive and thermal), plastics compounds wastes, volatiles organic compounds, hydrocarbons and used solvents. Sources, quantities and treatments are given. (A.B.). refs., figs., tabs

  3. Preliminary Evaluation of the Effects of Buried Volcanoes on Estimates of Volcano Probability for the Proposed Repository Site at Yucca Mountain, Nevada

    Science.gov (United States)

    Hill, B. E.; La Femina, P. C.; Stamatakos, J.; Connor, C. B.

    2002-12-01

    Probability models that calculate the likelihood of new volcano formation in the Yucca Mountain (YM) area depend on the timing and location of past volcanic activity. Previous spatio-temporal patterns indicated a 10-4 to 10-3 probability of volcanic disruption of the proposed radioactive waste repository site at YM during the 10,000 year post-closure performance period (Connor et al. 2000, JGR 105:1). A recent aeromagnetic survey (Blakely et al. 2000, USGS OFR 00-188), however, identified up to 20 anomalies in alluvium-filled basins, which have characteristics indicative of buried basalt (O'Leary et al. 2002, USGS OFR 02-020). Independent evaluation of these data, combined with new ground magnetic surveys, shows that these anomalies may represent at least ten additional buried basaltic volcanoes, which have not been included in previous probability calculations. This interpretation, if true, nearly doubles the number of basaltic volcanoes within 30 km [19 mi] of YM. Moreover, the magnetic signature of about half of the recognized basaltic volcanoes in the YM area cannot be readily identified in areas where bedrock also produces large amplitude magnetic anomalies, suggesting that additional volcanoes may be present but undetected in the YM area. In the absence of direct age information, we evaluate the potential effects of alternative age assumptions on spatio-temporal probability models. Interpreted burial depths of >50 m [164 ft] suggest ages >2 Ma, based on sedimentation rates typical for these alluvial basins (Stamatakos et al., 1997, J. Geol. 105). Defining volcanic events as individual points, previous probability models generally used recurrence rates of 2-5 volcanoes/million years (v/Myr). If the identified anomalies are buried volcanoes that are all >5 Ma or uniformly distributed between 2-10 Ma, calculated probabilities of future volcanic disruption at YM change by <30%. However, a uniform age distribution between 2-5 Ma for the presumed buried volcanoes

  4. Waste Sites - Municipal Waste Operations

    Data.gov (United States)

    NSGIC Education | GIS Inventory — A Municipal Waste Operation is a DEP primary facility type related to the Waste Management Municipal Waste Program. The sub-facility types related to Municipal Waste...

  5. Retrieval of buried depleted uranium from the T-1 trench

    International Nuclear Information System (INIS)

    Burmeister, M.; Castaneda, N.; Hull, C.; Barbour, D.; Quapp, W.J.

    1998-01-01

    The Trench 1 remediation project will be conducted this year to retrieve depleted uranium and other associated materials from a trench at Rocky Flats Environmental Technology Site. The excavated materials will be segregated and stabilized for shipment. The depleted uranium will be treated at an offsite facility which utilizes a novel approach for waste minimization and disposal through utilization of a combination of uranium recycling and volume efficient uranium stabilization

  6. Characterization plan for Solid Waste Storage Area 6

    International Nuclear Information System (INIS)

    Boegly, W.J. Jr.; Dreier, R.B.; Huff, D.D.; Kelmers, A.D.; Kocher, D.C.; Lee, S.Y.; O'Donnell, F.R.; Pin, F.G.; Smith, E.D.

    1985-12-01

    Solid Waste Storage Area 6 (SWSA-6) is the only currently operating low-level radioactive waste (LLW) shallow land burial facility at the Oak Ridge National Laboratory. The US Department of Energy (DOE) recently issued DOE Order 5820.2, which provides new policy and guidelines for the management of radioactive wastes. To ensure that SWSA-6 complies with this Order it will be necessary to establish whether sufficient data on the geology, hydrology, soils, and climatology of SWSA-6 exist, and to develop plans to obtain any additional information required. It will also be necessary to establish a source term from the buried waste and provide geochemical information for hydrologic and dosimetric calculations. Where data gaps exist, methodology for obtaining this information must be developed. The purpose of this Plan is to review existing information on SWSA-6 and develop cost estimates and schedules for obtaining any required additional information. Routine operation of SWSA-6 was initiated in 1973, and it is estimated that about 29,100 m 3 (1,000,000 ft 3 ) of LLW containing about 250,000 Ci of radioactivity have been buried through 1984. Since SWSA-6 was sited prior to enactment of current disposal regulations, a detailed site survey of the geologic and hydrologic properties of the site was not performed before wastes were buried. However, during the operation of SWSA-6 some information on site characteristics has been collected

  7. Development of joint regulatory guidance on the management of higher activity radioactive wastes on nuclear licensed sites - 16095

    International Nuclear Information System (INIS)

    Bacon, Mick; Ilett, Doug; Whittall, Andy

    2009-01-01

    In 2006 the UK Government's response (1) to recommendations by its Committee on Radioactive Waste Management (CoRWM) established, in England and Wales, that geological disposal, supported by safe and secure interim storage, is the preferred route for the long-term management of higher-activity radioactive waste (i.e. that which is not suitable for near-surface disposal). It also gave the responsibility for delivering the programme for a deep geological repository to the Nuclear Decommissioning Authority (NDA). The Scottish Government has a policy of long term, near site, near surface safe and secure interim storage. To support the open and transparent approach promised by Government, the Health and Safety Executive (HSE), the Environment Agency and the Scottish Environment Protection Agency (SEPA) are developing joint guidance on the management of higher-activity radioactive waste to explain regulatory objectives in securing safe and secure interim storage and the associated management of radioactive wastes. The guidance comes in two parts: - Guidance on the regulatory process; - Technical guidance modules. The guidance promotes a cradle to grave approach to radioactive waste management and by aligning the regulatory interests of environmental and safety regulators it delivers one of the Government's 'Better Regulation' objectives. This paper describes the process by which the joint guidance was produced with particular emphasis on stakeholder engagement. It describes the key features of the guidance, including the concept of the radioactive waste management case (RWMC). Finally the problems encountered with dissemination and implementation are discussed together with measures taken by the regulators to improve these aspects. (1) : UK Government and the devolved administrations, 'Response to the Report and Recommendations from the Committee on Radioactive Waste Management (CoRWM)', (PB 12303) October 2006. www.defra.gov.uk/environment/radioactivity/waste

  8. DOE states reheat nuclear waste debate

    International Nuclear Information System (INIS)

    Crawford, M.

    1985-01-01

    After decades of struggling with the issue, Congress in late 1982 established a firm plan for burying growing volumes of nuclear reactor wastes. But 2 l/2 years later the waste disposal debate is as hot as ever. Utility companies, environmentalists, federal officials, and state governments are again clashing - this time over the way the program is proceeding. The Nuclear Waste Policy Act calls for the Department of Energy to start accepting wastes in 1998 at the first of two planned repositories. Selection of this first repository site was mandated for early 1987, but program delays at DOE have pushed the decision back to March 1991. Despite this postponement and other schedule slips, the Department still aims to meet Congress's 1998 deadline. But states, Indian tribes, and environmentalists fear the site selection process will be compromised and want the start up date rolled back

  9. Solid waste

    International Nuclear Information System (INIS)

    1995-01-01

    The article drawn up within the framework of 'the assessment of the state of the environment in Lebanon' provides an overview of solid waste management, and assesses future wastes volume and waste disposal issues.In particular it addresses the following concerns: - Long term projections of solid waste arisings (i.e. domestic, industrial, such commercial wastes, vehicle types, construction waste, waste oils, hazardous toxic wastes and finally hospital and clinical wastes) are described. - Appropriate disposal routes, and strategies for reducing volumes for final disposal - Balance between municipal and industrial solid waste generation and disposal/treatment and - environmental impacts (aesthetics, human health, natural environment )of existing dumps, and the potential impact of government plans for construction of solid waste facilities). Possible policies for institutional reform within the waste management sector are proposed. Tables provides estimations of generation rates and distribution of wastes in different regions of Lebanon. Laws related to solid waste management are summarized

  10. Detection and delineation of waste trenches by geophysical methods at Oak Ridge National Laboratory

    International Nuclear Information System (INIS)

    Selfridge, R.J.

    1987-01-01

    Detection and delineation of waste trenches at hazardous waste sites are needed before actual implementation of site corrective measures. In a field study conducted in Solid Waste Storage Area 4 (SWSA4) at Oak Ridge National Laboratory (ORNL), surface geophysical techniques were used to assist in the delineation of waste trenches. A magnetometer/gradiometer survey was used to detect ferrous metals buried at the site. An electromagnetic ground conductivity survey was used to measure the electrical conductivity of the subsurface and aided in supporting the magnetometer/gradiometer results. Results from the two techniques were complimentary and easily integrated into a final interpretation. The reliability, efficiency, and worker safety benefits of these techniques offer a nondestructive surface technique for locating buried waste trenches

  11. Geotechnical reduction of void ratio in low-level radioactive waste burial sites: treatment alternatives

    International Nuclear Information System (INIS)

    Phillips, S.J.; Carlson, R.A.; McGuire, H.E.

    1981-01-01

    A substantial quantity of low-level radioactive and hazardous wastes has been interred in shallow land burial structures throughout the United States. Many of these structures (trenches, pits, and landfills) have proven to be unstable. Some surface feature manifestations such as large cracks, basins, and cave-ins are caused by voids filling and physico-chemical degradation and solubilization of the buried wastes which could result in the release of contamination. The surface features represent a potential for increased contamination transport to the biosphere via water, air, biologic, and direct pathways. Engineering alternatives for the reduction of buried waste and matrix materials voids are identified and discussed. As a guideline, a reduction of the voids within the waste to 80% or more of maximum relative dry density (a measure of in situ voids within the waste) is proposed. The advantages, disadvantages, and costs of each alternative are evaluated. Falling mass and pile driving engineering alternatives were selected for further development

  12. Applicability of a generic monitoring program for radioactive waste burial grounds at Oak Ridge National Laboratory and Idaho National Engineering Laboratory

    International Nuclear Information System (INIS)

    1978-07-01

    Six burial grounds were evaluated at Oak Ridge to determine which would be most suitable for testing the generic monitoring approach, and two were selected. Burial Ground 4 was chosen because it is known to be leaking radioactivity and a monitoring program is desirable to determine the source, pattern and extent of the leakage. Burial Ground 6 was chosen because the most complete radiologic and geologic data is available and modern burial practices have been utilized at this site. At the Idaho National Engineering Laboratory (INEL) only one burial ground exists, the Radioactive Waste Management Complex (RWMC). The data available on the burial grounds are insufficient for an adequate understanding of radionuclide migration patterns and accordingly, inadequate for the design of reliable monitoring programs. It was decided, therefore, that preliminary monitoring programs should be designed in order to obtain additional data for a later implementation of reliable monitoring programs. The monitoring programs designed for ORNL consist primarily of the installation of surface water monitoring stations, the surveillance of trench sump wells, a test boring program to study subsurface geologic conditions, a ground water sampling program and the installation of instrumentation, specifically infiltrometers and evaporation pans, to develop data on site water balances. The program designed for the INEL burial ground includes installation of trench sumps, a ground water monitoring program, test borings to further define subsurface geohydrologic conditions and the installation of instrumentation to develop data on the site water balance. The estimated costs of implementing the recommended programs are about $420,820 for monitoring Burial Grounds 4 and 6 at Oak Ridge and $382,060 for monitoring the RWMC at INEL. 12 figures

  13. Displaced humeral lateral condyle fractures in children: should we bury the pins?

    Science.gov (United States)

    Das De, Soumen; Bae, Donald S; Waters, Peter M

    2012-09-01

    The purpose of this investigation was to determine if leaving Kirschner wires exposed is more cost-effective than burying them subcutaneously after open reduction and internal fixation (ORIF) of humeral lateral condyle fractures. A retrospective cohort study of all lateral condyle fractures treated over a 10-year period at a single institution was performed. Data on surgical technique, fracture healing, and complications were analyzed, as well as treatment costs. A decision analysis model was then constructed to compare the strategies of leaving the pins exposed versus buried. Finally, sensitivity analyses were performed, assessing cost-effectiveness when infection rates and costs of treating deep infections were varied. A total of 235 children with displaced fractures were treated with ORIF using Kirschner wires. Pins were left exposed in 41 cases (17.4%) and buried in 194 cases (82.6%); the age, sex, injury mechanisms, and fracture patterns were similar in both the groups. The median time to removal of implants was shorter with exposed versus buried pins (4 vs. 6 wk, Pfracture union or loss of reduction rates. The rate of superficial infection was higher with exposed pins (9.8% vs. 3.1%), but this was not statistically significant (P=0.076). There were no deep infections with exposed pins, whereas the rate of deep infection was 0.5% with buried pins (P=1.00). Buried pins were associated with additional complications, including symptomatic implants (7.2%); pins protruding through the skin (16%); internal pin migration necessitating additional surgery (1%); and skin necrosis (1%). The decision analysis revealed that leaving pins exposed resulted in an average cost savings of $3442 per patient. This strategy remained cost-effective even when infection rates with exposed pins approached 40%. Leaving the pins exposed after ORIF of lateral condyle fractures is safe and more cost-effective than burying the pins subcutaneously. Retrospective cohort study (level III).

  14. Modelling the buried human body environment in upland climes using three contrasting field sites.

    Science.gov (United States)

    Wilson, Andrew S; Janaway, Robert C; Holland, Andrew D; Dodson, Hilary I; Baran, Eve; Pollard, A Mark; Tobin, Desmond J

    2007-06-14

    Despite an increasing literature on the decomposition of human remains, whether buried or exposed, it is important to recognise the role of specific microenvironments which can either trigger or delay the rate of decomposition. Recent casework in Northern England involving buried and partially buried human remains has demonstrated a need for a more detailed understanding of the effect of contrasting site conditions on cadaver decomposition and on the microenvironment created within the grave itself. Pigs (Sus scrofa) were used as body analogues in three inter-related taphonomy experiments to examine differential decomposition of buried human remains. They were buried at three contrasting field sites (pasture, moorland, and deciduous woodland) within a 15 km radius of the University of Bradford, West Yorkshire, UK. Changes to the buried body and the effect of these changes on hair and associated death-scene textile materials were monitored as was the microenvironment of the grave. At recovery, 6, 12 and 24 months post-burial, the extent of soft tissue decomposition was recorded and samples of fat and soil were collected for gas chromatography mass spectrometry (GCMS) analysis. The results of these studies demonstrated that (1) soil conditions at these three burial sites has a marked effect on the condition of the buried body but even within a single site variation can occur; (2) the process of soft tissue decomposition modifies the localised burial microenvironment in terms of microbiological load, pH, moisture and changes in redox status. These observations have widespread application for the investigation of clandestine burial and time since deposition, and in understanding changes within the burial microenvironment that may impact on biomaterials such as hair and other associated death scene materials.

  15. Summary: special waste form lysimeters - arid program

    International Nuclear Information System (INIS)

    Skaggs, R.L.; Walter, M.B.

    1987-01-01

    The purpose of the Special Waste Form Lysimeters - Arid Program is to determine the performance of solidified commercial low-level waste forms using a field-scale lysimeter facility constructed for measuring the release and migration of radionuclides from the waste forms. The performance of these waste forms, as measured by radionuclide concentrations in lysimeter effluent, will be compared to that predicted by laboratory characterization of the waste forms. Waste forms being tested include nuclear power reactor waste streams that have been solidified in cement, Dow polymer, and bitumen. To conduct the field leaching experiments a lysimeter facility was built to measure leachate under actual environmental conditions. Field-scale samples of waste were buried in lysimeters equipped to measure water balance components, effluent radionuclide concentrations, and to a limited extent, radionuclide concentrations in lysimeter soil samples. The waste forms are being characterized by standard laboratory leach tests to obtain estimates of radionuclide release. These estimates will be compared to leach rates observed in the field. Adsorption studies are being conducted to determine the amount of contaminant available for transport after the release. Theoretical solubility calculations will also be performed to investigate whether common solid phases could be controlling radionuclide release. 4 references, 8 figures, 1 table

  16. Hazardous chemical and radioactive wastes at Hanford

    International Nuclear Information System (INIS)

    Keller, J.F.; Stewart, T.L.

    1991-07-01

    The Hanford Site was established in 1944 to produce plutonium for defense. During the past four decades, a number of reactors, processing facilities, and waste management facilities have been built at Hanford for plutonium production. Generally, Hanford's 100 Area was dedicated to reactor operation; the 200 Area to fuel reprocessing, plutonium recovery, and waste management; and the 300 Area to fuel fabrication and research and development. Wastes generated from these operations included highly radioactive liquid wastes, which were discharged to single- and double-shell tanks; solid wastes, including both transuranic (TRU) and low-level wastes, which were buried or discharged to caissons; and waste water containing low- to intermediate-level radioactivity, which was discharged to the soil column via near-surface liquid disposal units such as cribs, ponds, and retention basins. Virtually all of the wastes contained hazardous chemical as well as radioactive constituents. This paper will focus on the hazardous chemical components of the radioactive mixed waste generated by plutonium production at Hanford. The processes, chemicals used, methods of disposition, fate in the environment, and actions being taken to clean up this legacy are described by location

  17. Hazardous chemical and radioactive wastes at Hanford

    International Nuclear Information System (INIS)

    Keller, J.F.; Stewart, T.L.

    1993-01-01

    The Hanford Site was established in 1944 to produce plutonium for defense. During the past four decades, a number of reactors, processing facilities, and waste management facilities were built at Hanford for plutonium production. Generally, Hanford's 100 Area was dedicated to reactor operation; the 200 Areas to fuel reprocessing, plutonium recovery, and waste management; and the 300 Area to fuel fabrication and research and development. Wastes generated from these operations included highly radioactive liquid wastes, which were discharged to single- and double-shell tanks; solid wastes, including both transuranic and low-level wastes, which were buried or discharged to caissons; and waste water containing low- to intermediate-level radioactivity, which was discharged to the soil column via near-surface liquid disposal units such as cribs, ponds, and retention basins. Virtually all of the wastes contained hazardous chemicals as well as radioactive constituents. This paper focuses on the hazardous chemical components of the radioactive mixed waste generated by plutonium production at Hanford. The processes, chemicals used, methods of disposition, fate in the environment, and actions being taken to clean up this legacy are described by location

  18. Waste management - sewage - special wastes

    International Nuclear Information System (INIS)

    1987-01-01

    The 27 papers represent a cross-section of the subject waste management. Particular attention is paid to the following themes: waste avoidance, waste product utilization, household wastes, dumping technology, sewage sludge treatments, special wastes, seepage from hazardous waste dumps, radioactive wastes, hospital wastes, purification of flue gas from waste combustion plants, flue gas purification and heavy metals, as well as combined sewage sludge and waste product utilization. The examples given relate to plants in Germany and other European countries. 12 papers have been separately recorded in the data base. (DG) [de

  19. In-situ stabilization of TRU/mixed waste project at the INEEL

    International Nuclear Information System (INIS)

    Milian, L.W.; Heiser, J.H.; Adams, J.W.; Rutenkroeger, S.P.

    1997-08-01

    Throughout the DOE complex, buried waste poses a threat to the environment by means of contaminant transport. Many of the sites contain buried waste that is untreated, prior to disposal, or insufficiently treated, by today's standards. One option to remedy these disposal problems is to stabilize the waste in situ. This project was in support of the Transuranic/Mixed Buried Waste - Arid Soils product line of the Landfill Focus Area, which is managed currently by the Idaho National Engineering Laboratory (BNL) provided the analytical laboratory and technical support for the various stabilization activities that will be performed as part of the In Situ Stabilization of TRU/Mixed Waste project at the INEL. More specifically, BNL was involved in laboratory testing that included the evaluation of several grouting materials and their compatibility, interaction, and long-term durability/performance, following the encapsulation of various waste materials. The four grouting materials chosen by INEL were: TECT 1, a two component, high density cementious grout, WAXFIX, a two component, molten wax product, Carbray 100, a two component elastomeric epoxy, and phosphate cement, a two component ceramic. A simulated waste stream comprised of sodium nitrate, Canola oil, and INEL soil was used in this study. Seven performance and durability tests were conducted on grout/waste specimens: compressive strength, wet-dry cycling, thermal analysis, base immersion, solvent immersion, hydraulic conductivity, and accelerated leach testing

  20. Plasma/arc melter review for vitrification of mixed wastes: Results

    Energy Technology Data Exchange (ETDEWEB)

    Eddy, T.L.; Soelberg, N.R.; Raivo, B.D. [MeltTran, Inc., Idaho Falls, ID (United States)

    1995-12-31

    In October of 1994, the Idaho Waste Treatment Program (IWTP) sponsored a workshop to review the results of a plasma/arc melter system preliminary design for treating mixed waste. Attention focused on (1) the melter design, (2) the offgas system design, and (3) the overall system design. The inclusion of feed preparation and handling systems, as well as monitoring and control systems, were considered premature until decisions regarding the melter and offgas treatment were resolved. The evaluation was based on the constraints of the transuranic-contaminated mixed waste in the Radioactive Waste Management Complex (RWMC) at the Idaho National Engineering Laboratory (INEL). Major factors are the retention of the transuranics in the basaltic slag, maintenance in a radioactive environment, reliability of components to prevent any major problems, upsets, or safety concerns, and the collection, elimination, or reduction of hazardous materials for appropriate stabilization. Several modifications were recommended by the group at large, discussed by the subcommittees, and accepted as the preferred options by the design team. Though all questions were not answered, the preferred systems for mixed waste treatment were the arc melters with graphite electrode systems with appropriate cooling which reduced maintenance and the possibility of eruptions that have occurred with plasma torches. Arc melters can also result in the minimum footprint and shielding. The preferred offgas systems were the wet/dry systems, that essentially eliminate the formation of carcinogenic compounds so they do not have to be destroyed down stream. This system also puts all of the particulate matter into one stream, instead of two.