WorldWideScience

Sample records for surface impoundments waste

  1. Wind erosion of waste impoundments in arid climates and mitigation of dust pollution.

    Science.gov (United States)

    Blight, G E

    2008-12-01

    Wind can erode and disperse fine-grained material from an impoundment of mining, industrial or municipal waste that stands above the level of its surroundings. Such dust dispersion can be a serious nuisance as well as a health hazard to inhabitants and animals in nearby settlements. It can also degrade crops, making them less marketable, and pollute soil, surface water and ground water. Wind can seasonally erode waste impoundments in all types of climate, but the erosion intensifies and persists for more of each year as regional aridity increases. As clouds of dust are often observed billowing across the top surfaces of waste impoundments in dry windy weather, there is a common misconception that dust arises from erosion of the top surface of an impoundment, resulting in much effort and money being misspent on top treatments when in fact the sloped sides of the impoundments are the true source of blown dust. This paper offers a brief review of general waste impoundment wind erosion issues and then focuses in more detail on the mechanics of how wind erodes surfaces of waste impoundments. Recommendations are offered for mitigating the effects of wind-eroded dust.

  2. 30 CFR 816.84 - Coal mine waste: Impounding structures.

    Science.gov (United States)

    2010-07-01

    ... control, the probable maximum precipitation of a 6-hour precipitation event, or greater event as specified.... Runoff from areas above the disposal facility or runoff from surface of the facility that may cause...-hour design precipitation event. (e) Impounding structures constructed of or impounding coal mine waste...

  3. Closure certification report: TA-35 TSL-125 surface impoundment

    International Nuclear Information System (INIS)

    1991-01-01

    This report summarizes the actions that were taken to clean close the TA-35 TSL-125 surface impoundment Building 125 is used for developing electron guns and related laser assemblies/equipment for a Laser Technology Research Program at the Laboratory. There is no permanent outfall from the surface impoundment; however, the impoundment accidentally overtopped on December 3, 1986, spilling an unknown volume of insulating oil and water into Ten Site Canyon. Sandbags were installed around the surface impoundment on June 25, 1988, to provide additional freeboard in the impoundment and reduce the risk of overtopping during a precipitation event. On July 1, 1988, the impoundment again overtopped releasing an unknown volume of insulating oil and water. Actions taken include removal of waste from the surface impoundment and its associated structures, decontamination of the floor trough and piping inside Building 125, grouting of the piping connecting the floor drain/trough system to the impoundment, decontamination, removal, and disposal of the impoundment liner and sandbags lining the top of the impoundment, and removal and disposal of contaminated soil underlying the impoundment area. Procedures followed to verify that clean closure objectives have been met are also documented in this report. Initial verification was performed through an extensive soil sampling and analysis program

  4. 30 CFR 817.84 - Coal mine waste: Impounding structures.

    Science.gov (United States)

    2010-07-01

    ... 30 Mineral Resources 3 2010-07-01 2010-07-01 false Coal mine waste: Impounding structures. 817.84... ACTIVITIES § 817.84 Coal mine waste: Impounding structures. New and existing impounding structures constructed of coal mine waste or intended to impound coal mine waste shall meet the requirements of § 817.81...

  5. Distribution of aquifers, liquid-waste impoundments, and municipal water-supply sources, Massachusetts

    Science.gov (United States)

    Delaney, David F.; Maevsky, Anthony

    1980-01-01

    Impoundments of liquid waste are potential sources of ground-water contamination in Massachusetts. The map report, at a scale of 1 inch equals 4 miles, shows the idstribution of aquifers and the locations of municipal water-supply sources and known liquid-waste impoundments. Ground water, an important source of municipal water supply, is produced from shallow sand and gravel aquifers that are generally unconfined, less than 200 feet thick, and yield less than 2,000 gallons per minute to individual wells. These aquifers commonly occupy lowlands and stream valleys and are most extensive in eastern Massachusetts. Surface impoundments of liquid waste are commonly located over these aquifers. These impoundments may leak and allow waste to infiltrate underlying aquifers and alter their water quality. (USGS)

  6. Coal combustion waste management at landfills and surface impoundments 1994-2004.

    Energy Technology Data Exchange (ETDEWEB)

    Elcock, D.; Ranek, N. L.; Environmental Science Division

    2006-09-08

    On May 22, 2000, as required by Congress in its 1980 Amendments to the Resource Conservation and Recovery Act (RCRA), the U.S. Environmental Protection Agency (EPA) issued a Regulatory Determination on Wastes from the Combustion of Fossil Fuels. On the basis of information contained in its 1999 Report to Congress: Wastes from the Combustion of Fossil Fuels, the EPA concluded that coal combustion wastes (CCWs), also known as coal combustion by-products (CCBs), did not warrant regulation under Subtitle C of RCRA, and it retained the existing hazardous waste exemption for these materials under RCRA Section 3001(b)(3)(C). However, the EPA also determined that national regulations under Subtitle D of RCRA were warranted for CCWs that are disposed of in landfills or surface impoundments. The EPA made this determination in part on the basis of its findings that 'present disposal practices are such that, in 1995, these wastes were being managed in 40 percent to 70 percent of landfills and surface impoundments without reasonable controls in place, particularly in the area of groundwater monitoring; and while there have been substantive improvements in state regulatory programs, we have also identified gaps in State oversight' (EPA 2000). The 1999 Report to Congress (RTC), however, may not have reflected the changes in CCW disposal practices that occurred since the cutoff date (1995) of its database and subsequent developments. The U.S. Department of Energy (DOE) and the EPA discussed this issue and decided to conduct a joint DOE/EPA study to collect new information on the recent CCW management practices by the power industry. It was agreed that such information would provide a perspective on the chronological adoption of control measures in CCW units based on State regulations. A team of experts from the EPA, industry, and DOE (with support from Argonne National Laboratory) was established to develop a mutually acceptable approach for collecting and analyzing data

  7. Groundwater monitoring at three Oak Ridge National Laboratory inactive waste impoundments: results after one year

    Energy Technology Data Exchange (ETDEWEB)

    Francis, C. W.; Stansfield, R. G.

    1986-10-01

    To determine if the migration of potential contaminants from three inactive waste impoundments at Oak Ridge National Laboratory poses a threat to groundwater quality, at least one upgradient groundwater monitoring well and threee downgradient monitoring wells were installed at each impoundment in early 1985. These three unlined impoundments, formerly used to collect and, in some instances, treat wastewater are: the 3513 impoundment; the Old Hydrofracture Facility (OHF) impoundment; and the Homogeneous Reactor Experimnt No. 2 impoundment. Groundwater samples were collected quarterly for one year. Analyses were conducted for the groundwater protection parameters promulgated by the Resource Conservation and Recovery Act. The groundwater samples were also analyzed for polychlorinated biphenyls, copper, nickel, zinc, /sup 90/Sr, /sup 137/Cs, and tritium. The contaminants found most often to affect groundwater quality at all three waste impoundments were radionuclides. For example, mean concentrations of gross beta and gross alpha activity exceeded drinking water limits at all three sites. The gross beta limit was exceeded at the 3513 and OHF impoundments by either /sup 90/Sr or tritium levels. At the 3513 impoundment, there was substantial evidence that the downgradient groundwater has been contaminated by chromium and lead and possibly by halogenated organic compounds. At the OHF impoundment, the mean level of tritium measured in the upgradient well (about 91,000 Bq/L as compared with 80,000 Bq/L in the downgradient wells) indicated that the groundwater quality has been affected by the radioactive wastes buried in the low-level radioactive waste burial ground solid waste storage area-5 upgradient of the impoundment. Testing for groundwater contamination, disclosed statistically significant contamination at all three sites.

  8. Groundwater monitoring at three Oak Ridge National Laboratory inactive waste impoundments: results after one year

    International Nuclear Information System (INIS)

    Francis, C.W.; Stansfield, R.G.

    1986-10-01

    To determine if the migration of potential contaminants from three inactive waste impoundments at Oak Ridge National Laboratory poses a threat to groundwater quality, at least one upgradient groundwater monitoring well and threee downgradient monitoring wells were installed at each impoundment in early 1985. These three unlined impoundments, formerly used to collect and, in some instances, treat wastewater are: the 3513 impoundment; the Old Hydrofracture Facility (OHF) impoundment; and the Homogeneous Reactor Experimnt No. 2 impoundment. Groundwater samples were collected quarterly for one year. Analyses were conducted for the groundwater protection parameters promulgated by the Resource Conservation and Recovery Act. The groundwater samples were also analyzed for polychlorinated biphenyls, copper, nickel, zinc, 90 Sr, 137 Cs, and tritium. The contaminants found most often to affect groundwater quality at all three waste impoundments were radionuclides. For example, mean concentrations of gross beta and gross alpha activity exceeded drinking water limits at all three sites. The gross beta limit was exceeded at the 3513 and OHF impoundments by either 90 Sr or tritium levels. At the 3513 impoundment, there was substantial evidence that the downgradient groundwater has been contaminated by chromium and lead and possibly by halogenated organic compounds. At the OHF impoundment, the mean level of tritium measured in the upgradient well (about 91,000 Bq/L as compared with 80,000 Bq/L in the downgradient wells) indicated that the groundwater quality has been affected by the radioactive wastes buried in the low-level radioactive waste burial ground solid waste storage area-5 upgradient of the impoundment. Testing for groundwater contamination, disclosed statistically significant contamination at all three sites

  9. Closure certification report: TA-35 TSL-125 surface impoundment

    International Nuclear Information System (INIS)

    1991-01-01

    This closure report documents closure activities for the TA-35 TSL-125 surface impoundment and associated structures at Los Alamos National Laboratory (the Laboratory). Prior to formal approval of the closure plan, the decision was made to proceed with closure activities to prevent any further releases from the site following informal discussions with New Mexico Environment Department (NMED) personnel. The closure plan is a revision of the previously submitted draft dated July 1988. Clean closure of the TSL-125 site was accomplished through: Removal and proper disposal of all wastes contained within the surface impoundment system; Decontamination and/or removal and proper disposal of the surface impoundment, its associated structures, and contaminated soil underlying the impoundment area; Sampling and analysis of soil to determine the presence and concentrations of any hazardous constituents remaining in the soil at the TSL-125 site; and Demonstration through a risk assessment that any constituents remaining in the soil at the TSL-125 site pose no threat to human health and the environment. All remaining soil concentrations of hazardous constituents were below health-based action levels. Analytical results indicated that benzidine, n-nitrosodimethylamine, and n-nitrosodi-n-propylamine were not detected at or above their limits of quantitation and beryllium was not present at or above its laboratory detection limit. However, the limits of quantitation and detection for these constituents were greater than their calculated health-based action levels. To demonstrate that these constituents were not present, historical data was researched and it was determined that the constituents were not utilized at the Building 125 site. 4 refs., 8 figs., 1 tab

  10. Probabilistic risk assessment for the Sandia National Laboratories Technical Area V Liquid Waste Disposal System surface impoundments

    International Nuclear Information System (INIS)

    Dawson, L.A.; Eidson, A.F.

    1996-01-01

    A probabilistic risk assessment was completed for a former radioactive waste disposal site. The site, two unlined surface impoundment, was designed as part of the Liquid Waste Disposal System (LWDS) to receive radioactive effluent from nuclear reactors in Technical Area-V (TA-V) at Sandia National Laboratories/New Mexico (SNL/NM). First, a statistical comparison of site sampling results to natural background, using EPA methods, and a spatial distribution analysis were performed. Risk assessment was conducted with SNL/NM's Probabilistic Risk Evaluation and Characterization Investigation System model. The risk assessment indicated that contamination from several constituents might have been high enough to require remediation. However, further analysis based on expected site closure activities and recent EPA guidance indicated that No Further Action was acceptable

  11. Gully potential in soil-covered uranium waste impoundments

    International Nuclear Information System (INIS)

    Abt, S.R.; Hogan, S.A.; Johnson, T.L.

    1994-01-01

    Soil covers are routinely considered a design alternative to stabilize uranium waste impoundments. Gully intrusion into the cover is one of the greatest potential threats to the long-term stability of an impoundment. An investigation was conducted to estimate the maximum depth of gully intrusion, the approximate top width of the gully at the point of maximum incision, and the approximate location of the maximum intrusion. A large-scale laboratory study was conducted on seven embankments in which approximately 200 years of rainfall was simulated and the resulting gullies were documented. In addition, 11 gullies occurring in actual reclaimed impoundments were documented. An analysis of the laboratory and field data sets was performed in which the maximum depth of gully incision, top width of the gully, and location of the maximum gully incision were related to the pile height, tributary volume of runoff, and soil composition. These relations provide the designers with a means for assessing the cover design to meet the long-term stability of the waste

  12. Using Helicopter Electromagnetic Surveys to Identify Potential Hazards at Mine Waste Impoundments

    Energy Technology Data Exchange (ETDEWEB)

    Hammack, R.W.

    2008-01-01

    In July 2003, helicopter electromagnetic surveys were conducted at 14 coal waste impoundments in southern West Virginia. The purpose of the surveys was to detect conditions that could lead to impoundment failure either by structural failure of the embankment or by the flooding of adjacent or underlying mine works. Specifically, the surveys attempted to: 1) identify saturated zones within the mine waste, 2) delineate filtrate flow paths through the embankment or into adjacent strata and receiving streams, and 3) identify flooded mine workings underlying or adjacent to the waste impoundment. Data from the helicopter surveys were processed to generate conductivity/depth images. Conductivity/depth images were then spatially linked to georeferenced air photos or topographic maps for interpretation. Conductivity/depth images were found to provide a snapshot of the hydrologic conditions that exist within the impoundment. This information can be used to predict potential areas of failure within the embankment because of its ability to image the phreatic zone. Also, the electromagnetic survey can identify areas of unconsolidated slurry in the decant basin and beneath the embankment. Although shallow, flooded mineworks beneath the impoundment were identified by this survey, it cannot be assumed that electromagnetic surveys can detect all underlying mines. A preliminary evaluation of the data implies that helicopter electromagnetic surveys can provide a better understanding of the phreatic zone than the piezometer arrays that are typically used.

  13. Characterization plan for the waste holding basin (3513 impoundment)

    International Nuclear Information System (INIS)

    Stansfield, R.G.; Francis, C.W.

    1986-09-01

    US Department of Energy (DOE) facilities are required to comply fully with all federal and state regulations. In response to this requirement, the Oak Ridge National Laboratory (ORNL) has established the remedial action program, to provide comprehensive management of areas where past research, development, and waste management activities have been conducted and have resulted in residual contamination of facilities or the environment. One of the objectives of this program is to define the extent of contamination at these sites. The intent is to document the known environmental characteristics of the sites and identify the additional actions, such as sampling, analytical measurements, and modeling, necessary to confirm contamination and the possible migration of contaminants from the sites. One of these sites is the waste holding basin (3513 impoundment). The 3513 impoundment is an unlined waste settling basin constructed in 1944 for collection of ORNL wastewater before its discharge into White Oak Creek. Operation of the facility ceased in 1976 when a new process waste treatment plant came into operation. Considerable site-specific environmental information has been developed over the years relative to the type and quantities of radionuclides and hazardous substances contained in the pond water and sediment. The concentrations and patterns of distribution for many of the radionuclides in the aquatic biota as well as for the terrestrial plants growing on the berm of the impoundment have been determined by DOE ecological studies. Recently, some data were collected that evaluate the extent of contaminant movement to the groundwater. Results from these studies are summarized in this report. Also included in this report is an outline of additional tasks needed to obtain the necessary information to model the transport and dose pathways of hazardous substances from the site

  14. Results of the radiological and chemical characterization of surface impoundments 3539 and 3540 at Oak Ridge National Laboratory, Oak Ridge, Tennessee

    International Nuclear Information System (INIS)

    Murray, M.E.; Rose, D.A.; Brown, K.S.; Winton, W.; Dean, R.A.; Coe, R.H. III

    1998-03-01

    A radiological and chemical characterization survey of impoundments 3539 and 3540 at the Oak Ridge National Laboratory (ORNL) was conducted during December 1997. Impoundments 3539 and 3540 are located in the Surface Impoundments Operable Unit (SIOU) of Waste Area Group 1. The investigation was performed by the Measurement Applications and Development Group of the Life Sciences Division of ORNL at the request of the Department of Energy (DOE) Office of Environmental Restoration. Sampling was conducted in order to quantify the presence of polychlorinated biphenyls (PCBs), Resource Conservation and Recovery Act (RCRA) constituents, and other contaminants of interest in support of the Comprehensive Environmental Response, Compensation and Liability Act (CERCLA) remediation for the SIOU> The survey included collection of sediment/clay samples, quality control blank water samples and equipment rinsate samples for chemical and radiological analysis. Results show the samples contain traces of various organic, inorganic, and radioactive materials. Of particular interest are PCB values which demonstrate the impoundments are not regulated under the Toxic Substances Control Act

  15. Microbial communities in flowback water impoundments from hydraulic fracturing for recovery of shale gas

    Energy Technology Data Exchange (ETDEWEB)

    Mohan, Arvind Murali; Hartsock, Angela; Hammack, Richard W; Vidic, Radisav D; Gregory, Kelvin B

    2013-12-01

    Hydraulic fracturing for natural gas extraction from shale produces waste brine known as flowback that is impounded at the surface prior to reuse and/or disposal. During impoundment, microbial activity can alter the fate of metals including radionuclides, give rise to odorous compounds, and result in biocorrosion that complicates water and waste management and increases production costs. Here, we describe the microbial ecology at multiple depths of three flowback impoundments from the Marcellus shale that were managed differently. 16S rRNA gene clone libraries revealed that bacterial communities in the untreated and biocide-amended impoundments were depth dependent, diverse, and most similar to species within the taxa [gamma]-proteobacteria, [alpha]-proteobacteria, δ-proteobacteria, Clostridia, Synergistetes, Thermotogae, Spirochetes, and Bacteroidetes. The bacterial community in the pretreated and aerated impoundment was uniform with depth, less diverse, and most similar to known iodide-oxidizing bacteria in the [alpha]-proteobacteria. Archaea were identified only in the untreated and biocide-amended impoundments and were affiliated to the Methanomicrobia class. This is the first study of microbial communities in flowback water impoundments from hydraulic fracturing. The findings expand our knowledge of microbial diversity of an emergent and unexplored environment and may guide the management of flowback impoundments.

  16. Transport and dispersion of pollutants in surface impoundments: a finite difference model

    Energy Technology Data Exchange (ETDEWEB)

    Yeh, G.T.

    1980-07-01

    A surface impoundment model by finite-difference (SIMFD) has been developed. SIMFD computes the flow rate, velocity field, and the concentration distribution of pollutants in surface impoundments with any number of islands located within the region of interest. Theoretical derivations and numerical algorithm are described in detail. Instructions for the application of SIMFD and listings of the FORTRAN IV source program are provided. Two sample problems are given to illustrate the application and validity of the model.

  17. 40 CFR 268.4 - Treatment surface impoundment exemption.

    Science.gov (United States)

    2010-07-01

    ... residues may not be placed in any other surface impoundment for subsequent management. (iv) Recordkeeping... exemption. 268.4 Section 268.4 Protection of Environment ENVIRONMENTAL PROTECTION AGENCY (CONTINUED) SOLID...), the residues from treatment are analyzed, as specified in § 268.7 or § 268.32, to determine if they...

  18. Low-level radioactive waste disposal in the USA - Use of mill tailings impoundments as a new policy option

    International Nuclear Information System (INIS)

    Farrell, C.W.

    2006-01-01

    Disposal of low-level radioactive waste (LLW) in the United States is facing severe and immediate capacity limitations. Seemingly intractable regulatory and jurisdictional conflicts make establishment of new LLW disposal sites effectively impossible. Uranium mill tailings impoundments constructed at conventional uranium open-cast and underground mines could offer approximately 40 to 80+ million tons of disposal capacity for low activity radioactive waste. Such impoundments would provide an enhanced, high level of environmental and health and safety protection for the direct disposal of depleted uranium, special nuclear material, technologically-enhanced, naturally-occurring radioactive material (TENORM) and mixed waste. Many waste streams, such as TENORM and decommissioning rubble, will be high-volume, low activity materials and ideally suited for disposal in such structures. Materials in a given decay chain with a total activity from all radionuclides present of ∼820 Bq/g (2.22 x 10 -08 Ci/g) with no single radionuclide present in an activity greater than ∼104 Bq/g (2,800 pCi/g) should be acceptable for disposal. Materials of this type could be accepted without any site-specific dose modelling, so long as the total activity of the tailings impoundment not exceed its design capacity (generally 82 x 10 07 Bq/metric tonne) (0.020 Ci/short ton) and the cover design requirements to limit radon releases are satisfied. This paper provides background on US LLW disposal regulations, examines LLW disposal options under active consideration by the US Environmental Protection Agency and Department of Energy, develops generic waste acceptance criteria and identifies policy needs for federal and state governments to facilitate use of uranium mill tailings impoundments for LLW disposal. (author)

  19. Microbial communities in flowback water impoundments from hydraulic fracturing for recovery of shale gas.

    Science.gov (United States)

    Murali Mohan, Arvind; Hartsock, Angela; Hammack, Richard W; Vidic, Radisav D; Gregory, Kelvin B

    2013-12-01

    Hydraulic fracturing for natural gas extraction from shale produces waste brine known as flowback that is impounded at the surface prior to reuse and/or disposal. During impoundment, microbial activity can alter the fate of metals including radionuclides, give rise to odorous compounds, and result in biocorrosion that complicates water and waste management and increases production costs. Here, we describe the microbial ecology at multiple depths of three flowback impoundments from the Marcellus shale that were managed differently. 16S rRNA gene clone libraries revealed that bacterial communities in the untreated and biocide-amended impoundments were depth dependent, diverse, and most similar to species within the taxa γ-proteobacteria, α-proteobacteria, δ-proteobacteria, Clostridia, Synergistetes, Thermotogae, Spirochetes, and Bacteroidetes. The bacterial community in the pretreated and aerated impoundment was uniform with depth, less diverse, and most similar to known iodide-oxidizing bacteria in the α-proteobacteria. Archaea were identified only in the untreated and biocide-amended impoundments and were affiliated to the Methanomicrobia class. This is the first study of microbial communities in flowback water impoundments from hydraulic fracturing. The findings expand our knowledge of microbial diversity of an emergent and unexplored environment and may guide the management of flowback impoundments. © 2013 Federation of European Microbiological Societies. Published by John Wiley & Sons Ltd. All rights reserved.

  20. Evaluating the effect of vehicle impoundment policy on illegal construction and demolition waste dumping: Israel as a case study.

    Science.gov (United States)

    Seror, Nissim; Hareli, Shlomo; Portnov, Boris A

    2014-08-01

    Construction and demolition (C&D) waste dumped alongside roads and in open areas is a major source of soil and underground water pollution. Since 2006, Israeli ministry for environmental protection enacted a policy of vehicle impoundment (VI) according to which track drivers caught while dumping C&D waste illegally have their vehicles impounded. The present study attempted to determine whether the VI policy was effective in increasing the waste hauling to authorized landfill sites, thus limiting the number of illegal unloads of C&D waste at unauthorized landfill sites and in open areas. During the study, changes in the ratio between the monthly amount of C&D waste brought to authorized landfills sites and the estimated total amount of C&D waste generated in different administrative districts of Israel were examined, before and after the enactment of the 2006 VI policy. Short questionnaires were also distributed among local track drivers in order to determine the degree of awareness about the policy in question and estimate its deterrence effects. According to the study's results, in the district of Haifa, in which the VI policy was stringently enacted, the ratio between C&D waste, dumped in authorized landfill sites, and the total amount of generated C&D waste, increased, on the average, from 20% in January 2004 to 35% in October 2009, with the effect attributed to the number of vehicle impoundments being highly statistically significant (t=2.324; p0.1). The analysis of the questionnaires, distributed among the local truck drivers further indicated that the changes observed in the district of Haifa are not coincident and appeared to be linked to the VI policy's enactment. In particular, 62% of the truck drivers, participated in the survey, were aware of the policy and 47% of them personally knew a driver whose vehicle was impounded. Furthermore, the drivers estimated the relative risk of being caught for unloading C&D waste in unauthorized sites, on the average, as

  1. Transport and dispersion of pollutants in surface impoundments: a finite element model

    International Nuclear Information System (INIS)

    Yeh, G.T.

    1980-07-01

    A surface impoundment model in finite element (SIMFE) is presented to enable the simulation of flow circulations and pollutant transport and dispersion in natural or artificial lakes, reservoirs or ponds with any number of islands. This surface impoundment model consists of two sub-models: hydrodynamic and pollutant transport models. Both submodels are simulated by the finite element method. While the hydrodynamic model is solved by the standard Galerkin finite element scheme, the pollutant transport model can be solved by any of the twelve optional finite element schemes built in the program. Theoretical approximations and the numerical algorithm of SIMFE are described. Detail instruction of the application are given and listing of FORTRAN IV source program are provided. Two sample problems are given. One is for an idealized system with a known solution to show the accuracy and partial validation of the models. The other is applied to Prairie Island for a set of hypothetical input data, typifying a class of problems to which SIMFE may be applied

  2. Transport and dispersion of pollutants in surface impoundments: a finite element model

    Energy Technology Data Exchange (ETDEWEB)

    Yeh, G.T.

    1980-07-01

    A surface impoundment model in finite element (SIMFE) is presented to enable the simulation of flow circulations and pollutant transport and dispersion in natural or artificial lakes, reservoirs or ponds with any number of islands. This surface impoundment model consists of two sub-models: hydrodynamic and pollutant transport models. Both submodels are simulated by the finite element method. While the hydrodynamic model is solved by the standard Galerkin finite element scheme, the pollutant transport model can be solved by any of the twelve optional finite element schemes built in the program. Theoretical approximations and the numerical algorithm of SIMFE are described. Detail instruction of the application are given and listing of FORTRAN IV source program are provided. Two sample problems are given. One is for an idealized system with a known solution to show the accuracy and partial validation of the models. The other is applied to Prairie Island for a set of hypothetical input data, typifying a class of problems to which SIMFE may be applied.

  3. Hydrologic effects of impoundments in Sherburne National Wildlife Refuge, Minnesota

    Science.gov (United States)

    Brown, R.G.

    1984-01-01

    The hydrologic effects of proposed impoundments in Sherburne National Wildlife Refuge were found to be insignificant with respect to both ground- and surface-water flow patterns and water quality. Monitoring of water levels in 23 observation wells and of discharge in the St. Francis River during 1980 and 1981 has shown that ground water in the surf icial aquifer responds quickly to areal recharge and subsequently discharges to the St. Francis River. The impoundment of surface water in the refuge was not found to affect water levels in the refuge significantly. The impoundments may affect ground-water-flow systems beneath and adjacent to the impoundments. Quality of ground and surface water was found to be similar except ground water contained higher concentrations of dissolved nitrite plus nitrate nitrogen than surface water. Phytoplankton removed dissolved nitrite plus nitrate nitrogen from surface water. The effects of impoundments on water quality are expected to be minor.

  4. 40 CFR 264.231 - Special requirements for hazardous wastes FO20, FO21, FO22, FO23, FO26, and FO27.

    Science.gov (United States)

    2010-07-01

    ... HAZARDOUS WASTE TREATMENT, STORAGE, AND DISPOSAL FACILITIES Surface Impoundments § 264.231 Special requirements for hazardous wastes FO20, FO21, FO22, FO23, FO26, and FO27. (a) Hazardous Wastes FO20, FO21, FO22... surface impoundments managing hazardous wastes FO20, FO21, FO22, FO23, FO26, and FO27 in order to reduce...

  5. Technical work plan for Surface Impoundments Operable Unit engineering support studies

    International Nuclear Information System (INIS)

    1995-11-01

    This document provides a comprehensive work plan which, when utilized as a data collection guide for field activities, will provide the necessary information required to complete a report on geotechnical properties of the sediments contained in the Surface Impoundments Operable Unit at Oak Ridge National Laboratory in Oak Ridge, Tennessee. Detailed guidance is provided for the following activities: collection of samples from the impoundments; compressive strength testing of the raw sediments; compressive strength testing of the structurally modified (lime and cement additives) sediments; testing for sediment physical properties and settling rates; testing for sediment dewatering characteristics; testing for radiation activity during the field work; testing for polymer additions that may enhance settling. The work plan additionally provides guidance and examples for the preparation of documents necessary to establish readiness for safe and satisfactory performance of the field activities. An outline for the format requested for a report of these data is also provided

  6. Technical work plan for Surface Impoundments Operable Unit engineering support studies

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1995-11-01

    This document provides a comprehensive work plan which, when utilized as a data collection guide for field activities, will provide the necessary information required to complete a report on geotechnical properties of the sediments contained in the Surface Impoundments Operable Unit at Oak Ridge National Laboratory in Oak Ridge, Tennessee. Detailed guidance is provided for the following activities: collection of samples from the impoundments; compressive strength testing of the raw sediments; compressive strength testing of the structurally modified (lime and cement additives) sediments; testing for sediment physical properties and settling rates; testing for sediment dewatering characteristics; testing for radiation activity during the field work; testing for polymer additions that may enhance settling. The work plan additionally provides guidance and examples for the preparation of documents necessary to establish readiness for safe and satisfactory performance of the field activities. An outline for the format requested for a report of these data is also provided.

  7. Responsiveness summary for the engineering evaluation/cost analysis for the proposed management of contaminated water impounded at the Weldon Spring Chemical Plant Area

    International Nuclear Information System (INIS)

    Maxey, M.L.; MacDonell, M.M.; Peterson, J.M.

    1991-01-01

    The US Department of Energy (DOE) issued the Engineering Evaluation/Cost Analysis for the Proposed Management of Contaminated Water Impounded at the Weldon Spring Chemical Plant Area in July 1990. The engineering evaluation/cost analysis (EE/CA) examines various alternatives for the proposed action to manage contaminated surface water impounded at the chemical plant area. The primary objective is to minimize potential migration of contaminants from surface impoundments to the local environment. The EE/CA addresses water currently impounded in four waste raffinate pits and two small ponds and water that will be impounded in the future as a result of upcoming response actions. Radioactive and chemical contaminants are migrating from the currently impounded water to underlying on-site groundwater via seepage and to off-site surface water via runoff. The treatment process and facilities that will be provided for management of currently impounded water can subsequently be used to manage other contaminated water in the future. Based on the evaluation of various alternatives in the EE/CA, DOE determined that the best approach for managing surface water impounded at the chemical plant area would be to remove contaminants from the water and release the treatment water to the Missouri River via a natural drainage channel. To establish requirements for releasing this treated water, DOE applied for a modification to its existing discharge permit from the Missouri Department of Natural Resources (DNR) under the National Pollutant Discharge Elimination System (NPDES) program. The EE/CA provided a major source of technical input to the application for modifying the permit. This responsiveness summary has been prepared to address the major issues identified in oral and written comments on the proposed action. 1 tab

  8. Design and construction of an impoundment for precious metal mill tailings

    International Nuclear Information System (INIS)

    Moldt, S.F.; Miller, R.G.; Johnson, K.

    1985-01-01

    An engineering study and design of impoundments for the disposal of mill tailings is presented. The site is located in central Nevada, and the mill will incorporate conventional flotation followed by a carbon-in-pulp cyanide process for extraction of gold from ore. Mill process waste will be generated as flotation tailings and cyanide residue. Permeable site soils and environmental considerations required the prevention of infiltration of cyanide residue leachate into the subgrade. Geochemical modeling of flotation tailings indicated the potential for high concentration of iron and nickel to be present in the flotation tailings leachate. On-site soils were optimized for use in construction of the separate flotation tailings and cyanide residue impoundments. Embankments were constructed on compacted on-site sandy gravels. The cyanide residue impoundment was designed using a four-layer liner, utilizing all on-site soils and chemical soil additives. The liner consists of a leachate collection system over a low-permeability layer, which in turn is underlain by a leak detection drainage blanket and a low permeability subliner. The geochemical modeling performed in the analysis indicated that placement of a thin layer of oxidized surface soils, high in soluble sulfates, on the bottom of the flotation tailings impoundment would be sufficient to react with tailings leachate and cause precipitation of ferric oxide and the associated removal of nickel, permitting flotation tailings leachate to dilute acceptably with natural groundwater

  9. An experimental approach to determining subsurface leakage from a surface impoundment using a radioisotope tracer

    International Nuclear Information System (INIS)

    Ashwood, T.L.; Story, J.D.; Larsen, I.L.; Schultz, F.J.

    1987-01-01

    Bromine-82, a 35.3-h half-life radionuclide, was used as a tracer to determine the paths and rates of leakage from an unlined, 1,000,000-gal (3,785,000 L), surface impoundment at the Oak Ridge National Laboratory. Since the impoundment is underlain and surrounded by storm sewer and sanitary sewer lines (most of them predating the impoundment), known and suspected leak sites in storm drain catch basins and sanitary sewer manholes were sampled periodically and analyzed for 82 Br. A series of four ground water monitoring wells - three downgradient and one upgradient from the impoundment - were also sampled for 82 Br. Although the catch basin and manhole samples picked up 82 Br in leakage from the impoundment less than 5 h after application of the tracer, the monitoring well samples did not contain detectable levels of the radionuclide. It was concluded that the monitoring wells were sampling groundwater moving through the formation, whereas the storm drains and manholes were sampling water leading rapidly through secondary porosity and along preferred pathways. The decline in tracer concentration as a function of time was used to determine the residence time of water in the pond and hence the flow rate through the pond. This flow rate, when compared with the known outflow rate, indicated that the leakage flow was small. Hence, the main value of the test was to identify rapid leakage pathways. The experiment demonstrates the need for sampling subsurface drain systems as part of an integrated monitoring system for leak detection. The effectiveness of 82 Br as a tracer for rapid leaks was also shown

  10. Pre- and post-impoundment nitrogen in the lower Missouri River

    Science.gov (United States)

    Blevins, Dale W.; Wilkison, Donald H.; Niesen, Shelley L.

    2013-01-01

    Large water-sample sets collected from 1899 through 1902, 1907, and in the early 1950s allow comparisons of pre-impoundment and post-impoundment (1969 through 2008) nitrogen concentrations in the lower Missouri River. Although urban wastes were not large enough to detectably increase annual loads of total nitrogen at the beginning of the 20th century, carcass waste, stock-yard manure, and untreated human wastes measurably increased ammonia and organic-nitrogen concentrations during low flows. Average total-nitrogen concentrations in both periods were about 2.5 mg/l, but much of the particulate-organic nitrogen, which was the dominant form of nitrogen around 1900, has been replaced by nitrate. This change in speciation was caused by the nearly 80% decrease in suspended-sediment concentrations that occurred after impoundment, modern agriculture, drainage of riparian wetlands, and sewage treatment. Nevertheless, bioavailable nitrogen has not been low enough to limit primary production in the Missouri River since the beginning of the 20th century. Nitrate concentrations have increased more rapidly from 2000 through 2008 (5 to 12% per year), thus increasing bioavailable nitrogen delivered to the Mississippi River and affecting Gulf Coast hypoxia. The increase in nitrate concentrations with distance downstream is much greater during the post-impoundment period. If strategies to decrease total-nitrogen loads focus on particulate N, substantial decreases will be difficult because particulate nitrogen is now only 23% of total nitrogen in the Missouri River. A strategy aimed at decreasing particulates also could further exacerbate land loss along the Gulf of Mexico, which has been sediment starved since Missouri River impoundment. In contrast, strategies or benchmarks aimed at decreasing nitrate loads could substantially decrease nitrogen loadings because nitrates now constitute over half of the Missouri's nitrogen input to the Mississippi. Ongoing restoration and creation

  11. Post-remediation action radiological report for Surface Impoundments C (3539) and D (3540) at the Oak Ridge National Laboratory, Oak Ridge, Tennessee

    International Nuclear Information System (INIS)

    1998-12-01

    During August and September 1998, Bechtel Jacobs Company LLC performed a remedial action within Impoundments 3539 and 3540 (Impoundments C and D, respectively) in accordance with the Comprehensive Environmental Response, Compensation, and Liability Act Record of Decision (ROD) for the Surface Impoundments Operable Unit. The remedial action included removal of sediments and 0.1 ft of subimpoundment soil. A post-remedial action radiological survey was conducted to provide data to support the Bethel Valley ROD. Data was obtained from (1) a walkover survey for residual gamma radiation on the base of the impoundments, (2) smear surveys for transferable contamination on remaining riprap, and (3) representative sampling of subimpoundment soils. Walkover surveys identified no locations outside the impoundments with gamma exposure levels greater than three times background levels. Smear surveys detected no removable contamination above release limits as specified in 10 CFR 835, Appendix D. Subimpoundment soil samples quantified low levels of residual contamination

  12. Mine Waste Disposal and Managements

    Energy Technology Data Exchange (ETDEWEB)

    Cheong, Young-Wook; Min, Jeong-Sik; Kwon, Kwang-Soo [Korea Institute of Geology Mining and Materials, Taejon (KR)] (and others)

    1999-12-01

    This research project deals with: Analysis and characterization of mine waste piles or tailings impoundment abandoned in mining areas; Survey of mining environmental pollution from mine waste impounds; Modelling of pollutants in groundwater around tailings impoundment; Demonstration of acid rock drainage from coal mine waste rock piles and experiment of seeding on waste rock surface; Development of a liner using tailings. Most of mine wastes are deposited on natural ground without artificial liners and capping for preventing contamination of groundwater around mine waste piles or containments. In case of some mine waste piles or containments, pollutants have been released to the environment, and several constituents in drainage exceed the limit of discharge from landfill site. Metals found in drainage exist in exchangeable fraction in waste rock and tailings. This means that if when it rains to mine waste containments, mine wastes can be pollutant to the environment by release of acidity and metals. As a result of simulation for hydraulic potentials and groundwater flow paths within the tailings, the simulated travel paths correlated well with the observed contaminant distribution. The plum disperse, both longitudinal and transverse dimensions, with time. Therefore liner system is a very important component in tailings containment system. As experimental results of liner development using tailings, tailings mixed with some portion of resin or cement may be used for liner because tailings with some additives have a very low hydraulic conductivity. (author). 39 refs.

  13. 40 CFR 264.230 - Special requirements for incompatible wastes.

    Science.gov (United States)

    2010-07-01

    ... DISPOSAL FACILITIES Surface Impoundments § 264.230 Special requirements for incompatible wastes... 40 Protection of Environment 25 2010-07-01 2010-07-01 false Special requirements for incompatible wastes. 264.230 Section 264.230 Protection of Environment ENVIRONMENTAL PROTECTION AGENCY (CONTINUED...

  14. Methodologies for evaluating long-term stabilization designs of uranium mill tailings impoundments

    International Nuclear Information System (INIS)

    Nelson, J.D.; Abt, S.R.; Volpe, R.L.; Van Zye, D.; Hinkle, N.E.; Staub, W.P.

    1986-06-01

    Uranium mill tailings impoundments require long-term (200 to 1000 years) stabilization. This report reviews currently available methodologies for evaluating factors that can have a significant influence on tailings stabilization and develops methodologies in technical areas where none presently exist. Mill operators can use these methodologies to assist with (1) the selection of sites for mill tailings impoundments, (2) the design of stable impoundments, and (3) the development of reclamation plans for existing impoundments. These methodologies would also be useful for regulatory agency evaluations of proposals in permit or license applications. Methodologies were reviewed or developed in the following technical areas: (1) prediction of the Probable Maximum Precipitation (PMP) and an accompanying Probable Maximum Flood (PMF); (2) prediction of the stability of local and regional fluvial systems; (3) design of impoundment surfaces resistant to gully erosion; (4) evaluation of the potential for surface sheet erosion; (5) design of riprap for protecting embankments from channel flood flow and overland flow; (6) selection of riprap with appropriate durability for its intended use; and (7) evaluation of oversizing required for marginal quality riprap

  15. Characterization and assessment of potential environmental risk of tailings stored in seven impoundments in the Aries river basin, Western Romania

    Science.gov (United States)

    2013-01-01

    Background The objective of this study was to examine the potential environmental risk of tailings resulted after precious and base metal ores processing, stored in seven impoundments located in the Aries river basin, Romania. The tailings were characterized by mineralogical and elemental composition, contamination indices, acid rock drainage generation potential and water leachability of hazardous/priority hazardous metals and ions. Multivariate statistical methods were used for data interpretation. Results Tailings were found to be highly contaminated with several hazardous/priority hazardous metals (As, Cu, Cd, Pb), and pose potential contamination risk for soil, sediments, surface and groundwater. Two out of the seven studied impoundments does not satisfy the criteria required for inert wastes, shows acid rock drainage potential and thus can contaminate the surface and groundwater. Three impoundments were found to be highly contaminated with As, Pb and Cd, two with As and other two with Cu. The tailings impoundments were grouped based on the enrichment factor, geoaccumulation index, contamination factor and contamination degree of 7 hazardous/priority hazardous metals (As, Cd, Cr, Cu, Ni, Pb, Zn) considered typical for the studied tailings. Principal component analysis showed that 47% of the elemental variability was attributable to alkaline silicate rocks, 31% to acidic S-containing minerals, 12% to carbonate minerals and 5% to biogenic elements. Leachability of metals and ions was ascribed in proportion of 61% to silicates, 11% to acidic minerals and 6% to the organic matter. A variability of 18% was attributed to leachability of biogenic elements (Na, K, Cl-, NO3-) with no potential environmental risk. Pattern recognition by agglomerative hierarchical clustering emphasized the grouping of impoundments in agreement with their contamination degree and acid rock drainage generation potential. Conclusions Tailings stored in the studied impoundments were found to

  16. Characterization and assessment of potential environmental risk of tailings stored in seven impoundments in the Aries river basin, Western Romania

    Directory of Open Access Journals (Sweden)

    Levei Erika

    2013-01-01

    Full Text Available Abstract Background The objective of this study was to examine the potential environmental risk of tailings resulted after precious and base metal ores processing, stored in seven impoundments located in the Aries river basin, Romania. The tailings were characterized by mineralogical and elemental composition, contamination indices, acid rock drainage generation potential and water leachability of hazardous/priority hazardous metals and ions. Multivariate statistical methods were used for data interpretation. Results Tailings were found to be highly contaminated with several hazardous/priority hazardous metals (As, Cu, Cd, Pb, and pose potential contamination risk for soil, sediments, surface and groundwater. Two out of the seven studied impoundments does not satisfy the criteria required for inert wastes, shows acid rock drainage potential and thus can contaminate the surface and groundwater. Three impoundments were found to be highly contaminated with As, Pb and Cd, two with As and other two with Cu. The tailings impoundments were grouped based on the enrichment factor, geoaccumulation index, contamination factor and contamination degree of 7 hazardous/priority hazardous metals (As, Cd, Cr, Cu, Ni, Pb, Zn considered typical for the studied tailings. Principal component analysis showed that 47% of the elemental variability was attributable to alkaline silicate rocks, 31% to acidic S-containing minerals, 12% to carbonate minerals and 5% to biogenic elements. Leachability of metals and ions was ascribed in proportion of 61% to silicates, 11% to acidic minerals and 6% to the organic matter. A variability of 18% was attributed to leachability of biogenic elements (Na, K, Cl-, NO3- with no potential environmental risk. Pattern recognition by agglomerative hierarchical clustering emphasized the grouping of impoundments in agreement with their contamination degree and acid rock drainage generation potential. Conclusions Tailings stored in the studied

  17. UAV Remote Sensing Surveillance of a Mine Tailings Impoundment in Sub-Arctic Conditions

    Directory of Open Access Journals (Sweden)

    Anssi Rauhala

    2017-12-01

    Full Text Available Mining typically involves extensive areas where environmental monitoring is spatially sporadic. New remote sensing techniques and platforms such as Structure from Motion (SfM and unmanned aerial vehicles (UAVs may offer one solution for more comprehensive and spatially continuous measurements. We conducted UAV campaigns in three consecutive summers (2015–2017 at a sub-Arctic mining site where production was temporarily suspended. The aim was to monitor a 0.5 km2 tailings impoundment and measure potential subsidence of tailings. SfM photogrammetry was used to produce yearly topographical models of the tailings surface, which allowed the amount of surface displacement between years to be tracked. Ground checkpoints surveyed in stable areas of the impoundment were utilized in assessing the vertical accuracy of the models. Observed surface displacements were linked to a combination of erosion, tailings settlement, and possible compaction of the peat layer underlying the tailings. The accuracy obtained indicated that UAV-assisted monitoring of tailings impoundments is sufficiently accurate for supporting impoundment management operations and for tracking surface displacements in the decimeter range.

  18. Liners and Leak Detection Systems for Hazardous Waste Land Disposal Units - Federal Register Notice, January 29, 1992

    Science.gov (United States)

    The EPA is amending its current regulations under the Resource Conservation and Recovery Act (RCRA) concerning liner and leachate collection and removal systems for hazardous waste surface impoundments, landfills, and waste piles.

  19. Erosion protection of uranium tailings impoundments

    International Nuclear Information System (INIS)

    Walters, W.H.; Skaggs, R.L.; Foley, M.G.; Beedlow, P.A.

    1986-09-01

    Pacific Northwest Laboratory (PNL) prepared this report to assist in the design and review of erosion protection works for decommissioned uranium tailings impoundments. The major causes of erosion over the long-term decommissioning period are from rainfall-runoff (overland flow) and stream channel flooding. The method of protection recommended for the impoundment side slopes and site drainage channels is rock riprap. Combinations of vegetation and rock mulch are recommended for the top surface. The design methods were developed from currently available procedures supplemented by field, laboratory, and mathematical model studies performed by PNL. Guidelines for the placement of riprap, inspection, and maintenance are presented. Other subjects discussed are rock selection and testing, slope stability, and overland erosion modeling

  20. Evaluation of Co and Cr mobility in soil profiles collected in a scrapyard of impounded vehicles

    International Nuclear Information System (INIS)

    Lange, Camila N.; Figueiredo, Ana Maria G.; Enzweiler, Jacinta

    2015-01-01

    The number of motor vehicles in urban environments has increased dramatically in the past years. As a result, so has the number of impounded and end-of-life vehicles. Car wastes can have a very high metal content, which can cause important environmental impacts to the soil where these vehicles are kept. Most Brazilian vehicle impound scrapyards are currently operating at their maximum capacity and soils may have become contaminated by past or current vehicle handling practices. Most of these areas do not present an impermeable surface. The level of soil contamination with heavy metals depends on the type of soil, climate and management practices. Metals, such as Co and Cr, that are present in many auto-parts, may be considered potentially toxic elements in these areas. The aim of this study was to evaluate Co and Cr levels and behavior in soil profiles located in a scrapyard of impounded vehicles of Ribeirao Pires-SP city. For this purpose, samples from distinct horizons of three soil profiles were collected. Element concentrations were determined by Instrumental Neutron Activation Analysis (INAA). Soil parameters such as pH, organic matter content and clay, silt and sand percentage were also determined. The obtained data were statistically analyzed in order to establish correlations between elemental concentrations and the impounded vehicles scrapyard soil. Soil acidity showed to be the most remarkable property for Cr and Co mobility through soil profile. (author)

  1. Evaluation of Co and Cr mobility in soil profiles collected in a scrapyard of impounded vehicles

    Energy Technology Data Exchange (ETDEWEB)

    Lange, Camila N.; Figueiredo, Ana Maria G., E-mail: clange@usp.br, E-mail: anamaria@ipen.br [Instituto de Pesquisas Energeticas e Nucleares (IPEN/CNEN-SP), Sao Paulo, SP (Brazil); Enzweiler, Jacinta, E-mail: jacinta@ige.unicamp.br [Universidade Estadual de Campinas (UNICAMP), Campinas, SP (Brazil). Instituto de Geociencias

    2015-07-01

    The number of motor vehicles in urban environments has increased dramatically in the past years. As a result, so has the number of impounded and end-of-life vehicles. Car wastes can have a very high metal content, which can cause important environmental impacts to the soil where these vehicles are kept. Most Brazilian vehicle impound scrapyards are currently operating at their maximum capacity and soils may have become contaminated by past or current vehicle handling practices. Most of these areas do not present an impermeable surface. The level of soil contamination with heavy metals depends on the type of soil, climate and management practices. Metals, such as Co and Cr, that are present in many auto-parts, may be considered potentially toxic elements in these areas. The aim of this study was to evaluate Co and Cr levels and behavior in soil profiles located in a scrapyard of impounded vehicles of Ribeirao Pires-SP city. For this purpose, samples from distinct horizons of three soil profiles were collected. Element concentrations were determined by Instrumental Neutron Activation Analysis (INAA). Soil parameters such as pH, organic matter content and clay, silt and sand percentage were also determined. The obtained data were statistically analyzed in order to establish correlations between elemental concentrations and the impounded vehicles scrapyard soil. Soil acidity showed to be the most remarkable property for Cr and Co mobility through soil profile. (author)

  2. Radioactive safety analysis and assessment of waste rock pile site in uranium tailings

    International Nuclear Information System (INIS)

    Liu Changrong; Liu Zehua; Wang Zhiyong; Zhou Xinghuo

    2007-01-01

    Based on theoretical calculation and in-situ test results, distribution and emissions of radioactive nuclides of uranium tailings impoundment and waste rock pile sites are analyzed in this paper. It is pointed out that 222 Rn is the main nuclide of uranium tailings impoundment and waste rock pile site. Also 222 Rn is the main source term of public dose. 222 Rn concentrations in the atmospheric environment around and individual dose to Rn gradually decrease with increasing distances to uranium tailings impoundment and waste rock pile site. Based on in-situ tests on five uranium tailings impoundment and waste rock pile sites, a decisive method and safety protection distance are presented, which can be used to guide the validation and design of radioactive safety protection in uranium tailings impoundment and waste rock pile sites. (authors)

  3. 77 FR 36447 - Hazardous Waste Management System; Identification and Listing of Hazardous Waste

    Science.gov (United States)

    2012-06-19

    ... underflow water is an aqueous solution which seeps through the treatment zone (soils) of the North Landfarm... Trichloroethylene ND 5.00E-01 2,4,6-Trichlorophenol....... ND 2.00E+00 Vinyl chloride ND 1.56E-01 Zinc 6.05E-02 3... groundwater contamination resulting from disposal of the petitioned waste in a surface impoundment, and that a...

  4. 30 CFR 816.49 - Impoundments.

    Science.gov (United States)

    2010-07-01

    ..., prudent, engineering practices and any design criteria established by the regulatory authority. The... surrounding landowners for agricultural, industrial, recreational, or domestic uses. (6) The impoundment will... safely removed in accordance with current, prudent, engineering practices. Such an impoundment shall be...

  5. 50 CFR 28.42 - Impounding of domestic animals.

    Science.gov (United States)

    2010-10-01

    ... 50 Wildlife and Fisheries 6 2010-10-01 2010-10-01 false Impounding of domestic animals. 28.42... VIOLATIONS OF PARTS 25, 26, AND 27 Impoundment Procedures § 28.42 Impounding of domestic animals. (a) Any animal trespassing on the lands of any national wildlife refuge may be impounded and disposed of in...

  6. Wildlife and the coal waste policy debate: proposed rules for coal waste disposal ignore lessons from 45 years of wildlife poisoning

    Science.gov (United States)

    A. Dennis Lemly; Joseph P. Skorupa

    2012-01-01

    This analysis examines wildlife poisoning from coal combustion waste (CCW) in the context of EPA's proposed policy that would allow continued use of surface impoundments as a disposal method. Data from 21 confirmed damage sites were evaluated, ranging from locations where historic poisoning has led to corrective actions that have greatly improved environmental...

  7. Design, permitting, and construction issues associated with closure of the Panna Maria uranium tailings impoundment

    International Nuclear Information System (INIS)

    Strachan, C.L.; Raabe, K.L.

    1997-01-01

    In 1992, Panna Maria Uranium Operations (PMUO) initiated licensing and engineering activities for closure of the Panna Maria mill and 150-acre tailings impoundment located in southeast Texas. Closure of the tailings impoundment is permitted by license amendment through the Texas Natural Resources Conservation Commission (TNRCC), and based on closure criteria outlined in Texas regulations. The closure plan for the Panna Maria tailings impoundment was submitted for Texas regulatory agency review in April 1993, with details of the closure plan modified in 1994, 1995, and 1996. The closure plan included a multi-layered cover over the regraded tailings surface which was designed for long-term isolation of tailings, reduction of radon emanation to regulated levels, and reduction of infiltration to TNRCC-accepted levels. The cover and embankment slope surfaces and surrounding areas were designed to provide acceptable erosional stability as compared to runoff velocities from the Probable Maximum Precipitation event. Cover materials were selected from on-site materials and evaluated for suitability based on permeability, radon attenuation, and soil dispersivity characteristics. Off-site materials were used when necessary. The cover over the tailings has a maximum slope of 0.5 percent, and the regraded embankment slopes outside the perimeter of the impoundment have a maximum slope of 20 percent. All reclaimed slopes are covered with topsoil and revegetated. A riprap-lined channel is to be used to convey runoff from within the perimeter of the reclaimed impoundment to the north of the impoundment

  8. The Role of Small Impoundments on Flow Alteration Within River Networks

    Science.gov (United States)

    Brogan, C. O.; Keys, T.; Scott, D.; Burgholzer, R.; Kleiner, J.

    2017-12-01

    Numerous water quality and quantity models have been established to illustrate the ecologic and hydrologic effects of large reservoirs. Smaller, unregulated ponds are often assumed to have a negligible impact on watershed flow regimes even though they overwhelmingly outnumber larger waterbodies. Individually, these small impoundments impart merely a fraction of the flow alteration larger reservoirs do; however, a network of ponds may act cumulatively to alter the flow regime. Many models have attempted to study smaller impoundments but rely on selectively available rating curves or bathymetry surveys. This study created a generalized process to model impoundments of varying size across a 58 square mile watershed exclusively using satellite imagery and publicly available information as inputs. With information drawn from public Army Corps of Engineers databases and LiDAR surveys, it was found that impoundment surface and drainage area served as useful explanatory variables, capable of predicting both pond bathymetry and outlet structure area across the 37 waterbodies modeled within the study area. Working within a flow routing model with inputs from the Chesapeake Bay HSPF model and verified with USGS gauge data, flow simulations were conducted with increasing number of impoundments to quantify how small ponds affect the overall flow regime. As the total impounded volume increased, simulations showed a notable reduction in both low and peak flows. Medium-sized floods increased as the network of ponds and reservoirs stabilized the catchment's streamflow. The results of this study illustrate the importance of including ponded waters into river corridor models to improve downstream management of both water quantity and quality.

  9. 36 CFR 262.11 - Impounding of dogs.

    Science.gov (United States)

    2010-07-01

    ... 36 Parks, Forests, and Public Property 2 2010-07-01 2010-07-01 false Impounding of dogs. 262.11... ENFORCEMENT SUPPORT ACTIVITIES Impoundments and Removals § 262.11 Impounding of dogs. Any dog found running at large in a part of the National Forest System, which has been closed to dogs running at large, may be...

  10. 49 CFR 193.2181 - Impoundment capacity: LNG storage tanks.

    Science.gov (United States)

    2010-10-01

    ... LIQUEFIED NATURAL GAS FACILITIES: FEDERAL SAFETY STANDARDS Design Impoundment Design and Capacity § 193.2181 Impoundment capacity: LNG storage tanks. Each impounding system serving an LNG storage tank must have a... 49 Transportation 3 2010-10-01 2010-10-01 false Impoundment capacity: LNG storage tanks. 193.2181...

  11. Protection of uranium tailings impoundments against overland erosion

    International Nuclear Information System (INIS)

    Walters, W.H.; Skaggs, R.L.

    1986-01-01

    This study investigates the problems involved in designing protection methods to prevent erosion of a uranium tailings impoundment cover from rainfall and runoff (overland flow) processes. The study addresses the side slopes and top surface as separate elements. The side slopes are more subject to gully erosion and require absolute protection such as that provided by rock riprap. The flatter top surface needs much less protection (vegetation/rock combinations) but some estimate of erosion rates are needed to compare alternatives. A literature review indicated that, currently, procedures are not available for the design of rock riprap to prevent gully erosion. Therefore, rock protection on the side slope will have to be based upon engineering judgment determined by the particular site conditions. The Manning-kinetic equations (velocity and depth of runoff) were investigated as a possible aid to the design of gully erosion protection. Guidelines are suggested for the use of rock riprap to prevent gully erosion. Three mathematical models were used to compute erosion rates for the top surface of a hypothetical tailings impoundment. The results recommend that one or possibly both of the regression models could be used to evaluate preliminary protection designs for the top surface. A physical process simulation model should be used for the final design. 30 refs., 13 figs., 16 tabs

  12. Coal waste management practices in the USA:an overview

    Institute of Scientific and Technical Information of China (English)

    Yoginder P. Chugh; Paul T. Behum

    2014-01-01

    This paper provides an overview of coal waste management practices with two case studies and an estimate of management cost in 2010 US dollars. Processing of as-mined coal typically results in considerable amount of coarse and fine coal processing wastes because of in-seam and out-of-seam dilution mining. Processing plant clean coal recovery values run typically 50%–80%. Trace metals and sulfur may be present in waste materials that may result in leachate water with corrosive charac-teristics. Water discharges may require special measures such as liner and collection systems, and treatment to neutralize acid drainage and/or water quality for trace elements. The potential for variations in coal waste production and quality depends upon mining or processing, plus the long-term methods of waste placement. The changes in waste generation rates and engineering properties of the coal waste during the life of the facility must be considered. Safe, economical and environmentally acceptable management of coal waste involves consideration of geology, soil and rock mechanics, hydrology, hydraulics, geochemistry, soil science, agronomy and environmental sciences. These support all aspects of the regulatory environment including the design and construction of earth and rock embankments and dams, as well as a wide variety of waste disposal structures. Development of impoundments is critical and require considerations of typical water-impounding dams and additional requirements of coal waste disposal impoundments. The primary purpose of a coal waste disposal facility is to dispose of unusable waste materials from mining. However, at some sites coal waste impoundments serve to provide water storage capacity for processing and flood attenuation.

  13. Design, placement, and sampling of groundwater monitoring wells for the management of hazardous waste disposal facilities

    International Nuclear Information System (INIS)

    Tsai, S.Y.

    1988-01-01

    Groundwater monitoring is an important technical requirement in managing hazardous waste disposal facilities. The purpose of monitoring is to assess whether and how a disposal facility is affecting the underlying groundwater system. This paper focuses on the regulatory and technical aspects of the design, placement, and sampling of groundwater monitoring wells for hazardous waste disposal facilities. Such facilities include surface impoundments, landfills, waste piles, and land treatment facilities. 8 refs., 4 figs

  14. Effects of rock riprap design parameters on flood protection costs for uranium tailings impoundments

    International Nuclear Information System (INIS)

    Ecker, R.M.

    1984-07-01

    The Pacific Northwest Laboratory (PNL) is studying the problem of long-term protection of earthen covers on decommissioned uranium tailings impoundments. The major erosive forces acting on these covers will be river flooding and overland flow from rainfall-runoff. For impoundments adjacent to rivers, overbank flooding presents the greater potential for significant erosion. To protect the earthen covers against flood erosion, rock riprap armoring will be placed over the cover surface. Because of the large size rock usually required for riprap, the quarrying, transport, and placement of the rock could be a significant part of the decommissioning cost. This report examines the sensitivity of riprap protection costs to certain design parameters at tailings impoundments. The parameters include flood discharge, riprap materials, impoundment side slopes, and an added safety factor. Two decommissioned tailings impoundments are used as case studies for the evaluation. These are the Grand Junction, Colorado, impoundment located adjacent to the Colorado River and the Slickrock, Colorado, impoundment located adjacent to the Dolores River. The evaluation considers only the cost of riprap protection against flood erosion. The study results show that embankment side slope and rock specific gravity can have optimum values or ranges at a specific site. For both case study sites the optimum side slope is about 5H:1V. Of the rock sources considered at Grand Junction, the optimum specific gravity would be about 2.50; however, an optimum rock specific gravity for the Slickrock site could not be determined. Other results indicate that the arbitrary safety factor usually added in riprap design can lead to large increases in protection costs. 22 references, 19 figures, 15 tables

  15. Rehabilitation of uranium tailings impoundments

    International Nuclear Information System (INIS)

    Crawley, A.H.

    1983-01-01

    Under Australian environmental controls relating to the management of uranium tailings, it is no longer acceptable practice to search for a rehabilitation strategy at the end of production when the generation of tailings has ceased. The uranium projects currently in production and those being proposed are tightly regulated by the authorities. The waste management plans must consider site specific factors and must include selection of appropriate disposal sites and design for long term containment. The final encapsulation in engineered facilities must take into account the probable routes to the environment of the tailings. Rehabilitation shoud be undertaken by the mining and milling operators to standards approved by appropriate authorities. Appropriate administrative arrangements are required, by way of technical committees and financial bonds to ensure that agreed standards of rehabilitation may be achieved. Past and present experience with the rehabilitation of uranium tailings impoundments in Australia is discussed

  16. Application of carbon isotopes to detect seepage out of coalbed natural gas produced water impoundments

    International Nuclear Information System (INIS)

    Sharma, Shikha; Baggett, Joshua K.

    2011-01-01

    Highlights: → Coalbed natural gas extraction results in large amount of produced water. → Risk of deterioration of ambient water quality. → Carbon isotope natural tracer for detecting seepage from produced water impoundments. - Abstract: Coalbed natural gas (CBNG) production from coal bed aquifers requires large volumes of produced water to be pumped from the subsurface. The produced water ranges from high quality that meets state and federal drinking water standards to low quality due to increased salinity and/or sodicity. The Powder River Basin of northeastern Wyoming is a major coalbed natural gas producing region, where water quality generally decreases moving from the southeastern portion of the basin towards the center. Most produced water in Wyoming is disposed into impoundments and other surface drainages, where it may infiltrate into shallow groundwater. Groundwater degradation caused by infiltration of CBNG produced water holding impoundments into arid, soluble salt-rich soils is an issue of immense importance because groundwater is a major source for stock water, irrigation, and drinking water for many small communities in these areas. This study examines the potential of using stable C isotope signatures of dissolved inorganic C (δ 13 C DIC ) to track the fate of CBNG produced water after it is discharged into the impoundments. Other geochemical proxies like the major cations and major anions were used in conjunction with field water quality measurements to understand the geochemical differences between CBNG produced waters and ambient waters in the study area. Samples were collected from the CBNG discharge outfalls, produced water holding impoundments, and monitoring wells from different parts of the Powder River Basin and analyzed for δ 13 C DIC . The CBNG produced waters from outfalls and impoundments have positive δ 13 C DIC values that fall within the range of +12 per mille to +22 per mille, distinct from the ambient regional surface and

  17. Results of the measurement survey of elevation and environmental media in surface impoundments 3513 (B) and 3524 (A) at Oak Ridge National Laboratory, Oak Ridge, Tennessee

    International Nuclear Information System (INIS)

    Murray, M.E.; Rose, D.A.; Brown, K.S.; Coe, R.H.C. III; Lawrence, J.D.; Winton, W.

    1998-07-01

    A measurement survey of the elevation and environmental media in impoundments 3513 (B) and 3524 (A) at the Oak Ridge National Laboratory (ORNL) was conducted during April 1998. The investigation was performed by the Measurement Applications and Development Group of the Life Sciences Division of ORNL at the request of Bechtel Jacobs Company. Measurement activities were conducted at selected locations in order to determine the depth and appearance of the sediment and describe the clay underlying the impoundments prior to remediation. The survey was a follow-up to a previous elevation survey. The survey included the following: collection of sediment/clay cores from selected locations in each impoundment; measurement and documentation of the elevation at the water surface, at the top of sediment, at the top of clay, and at the bottom of each core; visual inspection of each core by a soil scientist to confirm the presence of clay and not material such as fly ash and soda lime compacted over the last 50 years; measurement and documentation of the background beta-gamma radiation level at the time and location of collection of each core, the highest beta-gamma level along the sediment portion of each core, and the highest beta-gamma level along the clay portion of each core; measurement and documentation of the length of the clay and of the sediment portion of each core; photographic documentation of each core; and replacement of each core in the impoundment

  18. Hazardous-waste landfill research, US EPA (United States Environmental Protection Agency) program

    Energy Technology Data Exchange (ETDEWEB)

    Schomaker, N.B.

    1988-08-01

    The Land Pollution Control Division (LPCD), Hazardous Waste Engineering Research Lab. (HWERL), U.S. Environmental Protection Agency, in Cincinnati, Ohio, has responsibility for research in solid- and hazardous-waste management with respect to land disposal of wastes. To fulfill the responsibility, the LPCD is developing concepts and is documenting the environmental effects of various waste-disposal practices; and is collecting data necessary to support implementation of disposal guidelines mandated by the Hazardous and Solid Waste Amendments of 1984 (HSWA). This paper presents an overview of the land-disposal research associated with the LPCD hazardous waste program plan and will report the current status of work in the following categorical areas: Hazardous-waste facilities - landfills and surface impoundments; Non-Hazardous waste facilities; and Technology transfer.

  19. Effects of seasonal drawdowns on fish assemblages in sections of an impounded river-canal system in upstate New York

    Science.gov (United States)

    George, Scott D.; Baldigo, Barry P.; Wells, Scott M

    2016-01-01

    The Mohawk River and New York State Barge Canal run together as a series of permanent and temporary impoundments for most of the distance between Rome and Albany, New York. The downstream or lower section is composed of two permanent impoundments, the middle section of a series of temporary (seasonal) impoundments, and the upper section of a series of permanent impoundments. In the middle section, movable dams are lifted from the water during winter and the wetted surface area decreases by 36–56%. We used boat electrofishing during spring 2014 and 2015 to compare the relative abundance of fish populations and the composition of fish assemblages between the permanently and seasonally impounded sections of the Barge Canal and to infer the effects of the two flow management practices. A total of 3,264 individuals from 38 species were captured, and total catch per unit effort (CPUE) ranged from 46.0 to 134.7 fish/h at sites in the seasonally impounded section, compared with 140.0–342.0 fish/h in the permanent lower section and 89.0–282.0 fish/h in the permanent upper section. The amount of drawdown explained 55% of the variation in total CPUE and was a highly significant predictor variable. Mean total CPUE in the seasonally impounded section was significantly lower (by about 50%) than that in either permanently impounded section, and the assemblage composition differed significantly between sections. The relative abundance of many lentic species was markedly lower in the seasonally impounded section, while the relative abundance of several native cyprinids and the percentage of individuals belonging to species that are native to the watershed was greater in this section. Overall, these findings suggest that winter dam removal in impounded rivers may reduce the abundance of fish but may also create more natural riverine conditions that favor some native species.

  20. Dewatering tailings impoundments : interior drains

    International Nuclear Information System (INIS)

    Charlie, W.A.; Doehring, D.O.; Durnford, D.S.

    1984-01-01

    For the design of a new uranium tailings impoundment in the western United States, it was proposed that an interior drainage system be considered to economically and reliably minimize potential short- and long-term environmental impacts. The objectives were to decrease the effective hydraulic head on the clay liner, to dewater and stabilize the tailings, and to increase the amount of water recycled to the mill. In addition, desaturation of the impoundment would induce capillary pressure (negative porewater pressure), further reducing the potential movement of dissolved pollutants. This paper presents saturated and unsaturated seepage principles and reviews the concept, criteria and design of the various interior drainage systems considered

  1. Uranium mill tailings: nuclear waste and natural laboratory for geochemical and radioecological investigations

    Science.gov (United States)

    Landa, Edward R.

    2004-01-01

    Uranium mill tailings (UMT) are a high volume, low specific activity radioactive waste typically disposed in surface impoundments. This review focuses on research on UMT and related earth materials during the past decade relevant to the assessment of: (1) mineral hosts of radionuclides; (2) the use of soil analogs in predicting long-term fate of radionuclides; (3) microbial and diagenetic processes that may alter radionuclide mobility in the surficial environment; (4) waste-management technologies to limit radionuclide migration; and (5) the impact of UMT on biota.

  2. Distribution and migration of pesticide residues in mosquito control impoundments St. Lucie County, Florida, USA

    Science.gov (United States)

    Parkinson, R. W.; Wang, T. C.; White, J. R.; David, J. R.; Hoffman, M. E.

    1993-09-01

    This project was designed to: (1) document the distribution and migration of organochlorine pesticide residues within marsh substrates of 18 St. Lucie County mosquito control impoundments located along the Indian River Lagoon estuary, and (2) evaluate the impact of water management techniques on residue mobility. Our results indicate that detectible concentrations of organochlorine compounds, applied between the late 1940s and early 1950s, are present in 16 of the 18 St. Lucie County mosquito control impoundments. These compounds are primarily restricted to the surficial, organic-rich wetland sediment, which, based upon geotechnical analysis, was exposed to the atmosphere at a time when the impoundments were subjected to pesticide treatment. Contaminated sediments are present below the surficial, organic-rich layer, suggesting that some vertical migration of pesticides has occurred. It is unlikely that leaching associated with the downward percolation of impounded water was responsible for this migration as pesticide residues were never detected within the in situ pore waters. An alternative explanation is that biological processes (e.g., rooting, burrowing) facilitated the downward flux of organochlorine compounds into sediment horizons not subjected to direct treatment. Eighty-eight surface water samples obtained from two impoundments subjected to contrasting water management techniques were analyzed for pesticide content. None of the surficial water samples collected in association with these impoundments contained detectible concentrations of organochlorine compounds. These samples were unfiltered and contained as much as 25 mg/1 of particulate organic matter. This suggests that the currently preferred management technique (RIM), which is designed to maintain water quality, limit mosquito production, and provide for ecological continuity, does not hydraulically mobilize pesticide residues into the Indian River Lagoon estuary.

  3. Influence of lake surface area and total phosphorus on annual bluegill growth in small impoundments of central Georgia

    Science.gov (United States)

    Jennings, Cecil A.; Sundmark, Aaron P.

    2017-01-01

    The relationships between environmental variables and the growth rates of fishes are important and rapidly expanding topics in fisheries ecology. We used an informationtheoretic approach to evaluate the influence of lake surface area and total phosphorus on the age-specific growth rates of Lepomis macrochirus (Bluegill) in 6 small impoundments in central Georgia. We used model averaging to create composite models and determine the relative importance of the variables within each model. Results indicated that surface area was the most important factor in the models predicting growth of Bluegills aged 1–4 years; total phosphorus was also an important predictor for the same age-classes. These results suggest that managers can use water quality and lake morphometry variables to create predictive models specific to their waterbody or region to help develop lake-specific management plans that select for and optimize local-level habitat factors for enhancing Bluegill growth.

  4. Economic Floating Waste Detectionfor Surface Cleaning Robots

    Directory of Open Access Journals (Sweden)

    Sumroengrit Jakkrit

    2017-01-01

    Full Text Available Removing waste out of water surface is a routine task and can be operated by using autonomous surface cleaning robots. This paper presents amethodoflaser-based floating waste detection for surface robot guidance when waste positions are unknown beforehand. Basing on concept of refraction and reflection of laser ray, the proposed laser-based technique is proven to be applicable on floating waste detection. The economic waste detector is constructed and mounted on the robot. Five DOF equations of motion are formulated for calculation of waste position incorporating distance measured by the laser and also the robot motion caused by external wind force as well as water surface tension. Experiments were conducted on a pond with calm water and results show that the presented economic waste detection successfully identify and locate position of plastic bottles floating on water surface within the range of 5 meters.

  5. 25 CFR 700.727 - Impoundment and disposal of unauthorized livestock.

    Science.gov (United States)

    2010-04-01

    ... 25 Indians 2 2010-04-01 2010-04-01 false Impoundment and disposal of unauthorized livestock. 700... RELOCATION PROCEDURES New Lands Grazing § 700.727 Impoundment and disposal of unauthorized livestock. Unauthorized livestock within any range unit of the New Lands which are not removed therefrom within the...

  6. 25 CFR 168.16 - Impoundment and disposal of unauthorized livestock.

    Science.gov (United States)

    2010-04-01

    ... 25 Indians 1 2010-04-01 2010-04-01 false Impoundment and disposal of unauthorized livestock. 168... REGULATIONS FOR THE HOPI PARTITIONED LANDS AREA § 168.16 Impoundment and disposal of unauthorized livestock. Unauthorized livestock within any range unit of the Hopi Partitioned Lands which are not removed therefrom...

  7. 78 FR 46940 - Hazardous and Solid Waste Management System: Identification and Listing of Special Wastes...

    Science.gov (United States)

    2013-08-02

    ...The U.S. Environmental Protection Agency (EPA or the Agency) invites comment on additional information obtained in conjunction with the proposed rule: Hazardous and Solid Waste Management System: Identification and Listing of Special Wastes; Disposal of Coal Combustion Residuals From Electric Utilities that was published in the Federal Register on June 21, 2010. This information is categorized as: additional data to supplement the Regulatory Impact Analysis and risk assessment, information on large scale fill, and data on the surface impoundment structural integrity assessments. EPA is also seeking comment on two issues associated with the requirements for coal combustion residual management units. The Agency is not reopening any other aspect of the proposal or underlying support documents, and will consider comments on any issues other than those raised in the NODA to be late comments and not part of the rulemaking record.

  8. Run-of-River Impoundments Can Remain Unfilled While Transporting Gravel Bedload: Numerical Modeling Results

    Science.gov (United States)

    Pearson, A.; Pizzuto, J. E.

    2015-12-01

    Previous work at run-of-river (ROR) dams in northern Delaware has shown that bedload supplied to ROR impoundments can be transported over the dam when impoundments remain unfilled. Transport is facilitated by high levels of sand in the impoundment that lowers the critical shear stresses for particle entrainment, and an inversely sloping sediment ramp connecting the impoundment bed (where the water depth is typically equal to the dam height) with the top of the dam (Pearson and Pizzuto, in press). We demonstrate with one-dimensional bed material transport modeling that bed material can move through impoundments and that equilibrium transport (i.e., a balance between supply to and export from the impoundment, with a constant bed elevation) is possible even when the bed elevation is below the top of the dam. Based on our field work and previous HEC-RAS modeling, we assess bed material transport capacity at the base of the sediment ramp (and ignore detailed processes carrying sediment up and ramp and over the dam). The hydraulics at the base of the ramp are computed using a weir equation, providing estimates of water depth, velocity, and friction, based on the discharge and sediment grain size distribution of the impoundment. Bedload transport rates are computed using the Wilcock-Crowe equation, and changes in the impoundment's bed elevation are determined by sediment continuity. Our results indicate that impoundments pass the gravel supplied from upstream with deep pools when gravel supply rate is low, gravel grain sizes are relatively small, sand supply is high, and discharge is high. Conversely, impoundments will tend to fill their pools when gravel supply rate is high, gravel grain sizes are relatively large, sand supply is low, and discharge is low. The rate of bedload supplied to an impoundment is the primary control on how fast equilibrium transport is reached, with discharge having almost no influence on the timing of equilibrium.

  9. Sources and management of hazardous waste in Papua New Guinea

    Energy Technology Data Exchange (ETDEWEB)

    Singh, K. [Univ. of Papua New Guinea (Papua New Guinea)

    1996-12-31

    Papua New Guinea (PNG) has considerable mineral wealth, especially in gold and copper. Large-scale mining takes place, and these activities are the source of most of PNG`s hazardous waste. Most people live in small farming communities throughout the region. Those living adjacent to mining areas have experienced some negative impacts from river ecosystem damage and erosion of their lands. Industry is centered mainly in urban areas and Generates waste composed of various products. Agricultural products, pesticide residues, and chemicals used for preserving timber and other forestry products also produce hazardous waste. Most municipal waste comes from domestic and commercial premises; it consists mainly of combustibles, noncombustibles, and other wastes. Hospitals generate pathogenic organisms, radioactive materials, and chemical and pharmaceutical laboratory waste. Little is known about the actual treatment of waste before disposal in PNG. Traditional low-cost waste disposal methods are usually practiced, such as use of landfills; storage in surface impoundments; and disposal in public sewers, rivers, and the sea. Indiscriminate burning of domestic waste in backyards is also commonly practiced in urban and rural areas. 10 refs., 4 tabs.

  10. Evaluation of Major Dike-Impounded Ground-Water Reservoirs, Island of Oahu

    Science.gov (United States)

    Takasaki, Kiyoshi J.; Mink, John Francis

    1985-01-01

    Ground-water reservoirs impounded by volcanic dikes receive a substantial part of the total recharge to ground water on the island of Oahu because they generally underlie the rainiest areas. These reservoirs accumulate the infiltration from rainfall, store it temporarily, and steadily leak it to abutting basal reservoirs or to streams cutting into them. The dike reservoirs have high hydraulic heads and are mostly isolated from saline water. The most important and productive of the dike-impounded reservoirs are in an area of about 135 square miles in the main fissure zone of the Koolau volcano where the top of the dike-impounded water reaches an altitude of at least 1,000 feet. Water is impounded and stored both above and below sea level. The water stored above sea level in the 135 square mile area has been roughly estimated at 560 billion gallons. In comparison, the water stored above sea level in reservoirs underlying a dike-intruded area of about 53 square miles in the Waianae Range has been roughly estimated at 100 billion gallons. Storage below sea level is indeterminable, owing to uncertainties about the ability of the rock to store water as dike density increases and porosity decreases. Tunnels, by breaching dike controls, have reduced the water stored above sea level by at least 50 billion gallons in the Koolau Range and by 5 1/2 billion gallons in the Waianae Range, only a small part of the total water stored. Total leakage from storage in the Koolau Range has been estimated at about 280 Mgal/d (million gallons per day). This estimated leakage from the dike-impounded reservoirs makes up a significant part of the ground-water yield of the Koolau Range, which has been estimated to range from 450 to 580 Mgal/d. The largest unused surface leakage is in the Kaneohe, Kahana, and Punaluu areas, and the largest unused underflow occurs in the Waialee, Hauula-Laie, Punaluu, and Kahana areas. The unused underflow leakage is small in areas near and east of Waialae, but

  11. 30 CFR 817.49 - Impoundments.

    Science.gov (United States)

    2010-07-01

    ... runoff from the design precipitation event when it is demonstrated by the operator and certified by a... constructed to safely pass the applicable design precipitation event specified in paragraph (a)(9)(ii) of this... this section, the required design precipitation event for an impoundment meeting the spillway...

  12. French Modular Impoundment: Final Cost and Performance Evaluation

    Energy Technology Data Exchange (ETDEWEB)

    Drown, Peter [French Development Enterprises, LLC, North Billerica, MA (United States); French, Bill [French Development Enterprises, LLC, North Billerica, MA (United States)

    2017-05-17

    This report comprises the Final Cost and Performance Report for the Department of Energy Award # EE0007244, the French Modular Impoundment (aka the “French Dam”.) The French Dam is a system of applying precast modular construction to water control structures. The “French Dam” is a term used to cover the construction means/methods used to construct or rehabilitate dams, diversion structures, powerhouses, and other hydraulic structures which impound water and are covered under FDE’s existing IP (Patents # US8414223B2; US9103084B2.)

  13. Incineration of hazardous waste: A critical review update

    International Nuclear Information System (INIS)

    Dempsey, C.R.; Oppelt, E.T.

    1993-01-01

    Over the last 15 years, concern over improper disposal practices of the past has manifested itself in the passage of a series of federal and state-level hazardous waste cleanup and control statutes of unprecedented scope. The more traditional and lowest-cost methods of direct landfilling, storage in surface impoundments and deep-well injection are being replaced in large measure by waste minimization at the source of generation, waste reuse, physical/chemical/biological treatment, incineration and chemical stabilization/solidification methods. Of all of the 'permanent' treatment technologies, properly designed incineration systems are capable of the highest overall degree of destruction and control for the broadest range of hazardous waste streams. Substantial design and operation experience exists in this area and a wide variety of commercial systems are available. Consequently, significant growth is anticipated in the use of incineration and other thermal destruction methods. The objective of this review is to examine the current state of knowledge regarding hazardous waste incineration in an effort to put these technological and environmental issues into perspective

  14. Predictive geochemical modeling of contaminant concentrations in laboratory columns and in plumes migrating from uranium mill tailings waste impoundments

    International Nuclear Information System (INIS)

    Peterson, S.R.; Martin, W.J.; Serne, R.J.

    1986-04-01

    A computer-based conceptual chemical model was applied to predict contaminant concentrations in plumes migrating from a uranium mill tailings waste impoundment. The solids chosen for inclusion in the conceptual model were selected based on reviews of the literature, on ion speciation/solubility calculations performed on the column effluent solutions and on mineralogical characterization of the contacted and uncontacted sediments. The mechanism of adsorption included in the conceptual chemical model was chosen based on results from semiselective extraction experiments and from mineralogical characterization procedures performed on the sediments. This conceptual chemical model was further developed and partially validated in laboratory experiments where assorted acidic uranium mill tailings solutions percolated through various sediments. This document contains the results of a partial field and laboratory validation (i.e., test of coherence) of this chemical model. Macro constituents (e.g., Ca, SO 4 , Al, Fe, and Mn) of the tailings solution were predicted closely by considering their concentrations to be controlled by the precipitation/dissolution of solid phases. Trace elements, however, were generally predicted to be undersaturated with respect to plausible solid phase controls. The concentration of several of the trace elements were closely predicted by considering their concentrations to be controlled by adsorption onto the amorphous iron oxyhydroxides that precipitated

  15. Sedimentation in Lake Onalaska, Navigation Pool 7, upper Mississippi River, since impoundment

    Science.gov (United States)

    Korschgen, C.E.; Jackson, G.A.; Muessig, L.F.; Southworth, D.C.

    1987-01-01

    Sediment accumulation was evaluated in Lake Onalaska, a 2800-ha backwater impoundment on the Upper Mississippi River. Computer programs were used to process fathometric charts and generate an extensive data set on water depth for the lake. Comparison of 1983 survey data with pre-impoundment (before 1937) data showed that Lake Onalaska had lost less than 10 percent of its original mean depth in the 46 years since impoundment. Previous estimates of sedimentation rates based on Cesium-137 sediment core analysis appear to have been too high. (DBO)

  16. The Authority of the President to Impound Funds Appropriated by Congress.

    Science.gov (United States)

    Adams, James R.

    During fiscal year 1973, President Nixon ordered the impoundment of about 18 billion dollars in Federal funds for domestic programs. A large portion of that amount was used to slash federal funding for education programs. The entire impoundment controversy revolves around the doctrine of separation of powers. Insofar as the President has refused…

  17. Presentations from the 1992 Coal Mining Impoundment Informational Meeting

    Energy Technology Data Exchange (ETDEWEB)

    1993-12-31

    On May 20 and 21, 1992, the MSHA Coal Mining Impoundment Informational Meeting was held at the National Mine Health and Safety Academy in Beckley, West Virginia. Fifteen presentations were given on key issues involved in the design and construction of dams associated with coal mining. The attendees were told that to improve the consistency among the plan reviewers, engineers from the Denver and Pittsburgh Technical Support Centers meet twice annually to discuss specific technical issues. It was soon discovered that the topics being discussed needed to be shared with anyone involved with coal waste dam design, construction, or inspection. The only way to accomplish that goal was through the issuance of Procedure Instruction Letters. The Letters present a consensus of engineering philosophy that could change over time. They do not present policy or carry the force of law. Currently, thirteen position papers have been disseminated and more will follow as the need arises. The individual paper were not even entered into the database.

  18. Handling 78,000 drums of mixed-waste sludge

    International Nuclear Information System (INIS)

    Berry, J.B.; Harrington, E.S.; Mattus, A.J.

    1991-01-01

    The Oak Ridge Gaseous Diffusion Plant (now known as the Oak Ridge K-25 Site) closed two mixed-waste surface impoundments by removing the sludge and contaminated pond-bottom clay and attempting to process it into durable, nonleachable, concrete monoliths. Interim, controlled, above-ground storage included delisting the stabilized sludge from hazardous to nonhazardous and disposing of the delisted monoliths as Class 1 radioactive waste. Because of schedule constraints and process design and control deficiencies, ∼46,000 drums of material in various stages of solidification and ∼32,000 barrels of unprocessed sludge are stored. The abandoned treatment facility still contains ∼16,000 gal of raw sludge. Such storage of mixed waste does not comply with the Resource Conservation and Recovery Act (RCRA) guidelines. This paper describes actions that are under way to bring the storage of ∼78,000 drums of mixed waste into compliance with RCRA. Remediation of this problem by treatment to meet regulatory requirements is the focus of the discussion. 3 refs., 2 figs., 4 tabs

  19. Assessment of sediments in the riverine impoundments of national wildlife refuges in the Souris River Basin, North Dakota

    Science.gov (United States)

    Tangen, Brian A.; Laubhan, Murray K.; Gleason, Robert A.

    2014-01-01

    Accelerated sedimentation of reservoirs and riverine impoundments is a major concern throughout the United States. Sediments not only fill impoundments and reduce their effective life span, but they can reduce water quality by increasing turbidity and introducing harmful chemical constituents such as heavy metals, toxic elements, and nutrients. U.S. Fish and Wildlife Service national wildlife refuges in the north-central part of the United States have documented high amounts of sediment accretion in some wetlands that could negatively affect important aquatic habitats for migratory birds and other wetland-dependent wildlife. Therefore, information pertaining to sediment accumulation in refuge impoundments potentially is important to guide conservation planning, including future management actions of individual impoundments. Lands comprising Des Lacs, Upper Souris, and J. Clark Salyer National Wildlife Refuges, collectively known as the Souris River Basin refuges, encompass reaches of the Des Lacs and Souris Rivers of northwestern North Dakota. The riverine impoundments of the Souris River Basin refuges are vulnerable to sedimentation because of the construction of in-stream dams that interrupt and slow river flows and because of post-European settlement land-use changes that have increased the potential for soil erosion and transport to rivers. Information regarding sediments does not exist for these refuges, and U.S. Fish and Wildlife Service personnel have expressed interest in assessing refuge impoundments to support refuge management decisions. Sediment cores and surface sediment samples were collected from impoundments within Des Lacs, Upper Souris, and J. Clark Salyer National Wildlife Refuges during 2004–05. Cores were used to estimate sediment accretion rates using radioisotope (cesium-137 [137Cs], lead-210 [210Pb]) dating techniques. Sediment cores and surface samples were analyzed for a suite of elements and agrichemicals, respectively. Examination of

  20. The hydrogeochemistry of four inactive tailings impoundments: Perspectives on tailings pore-water evolution

    International Nuclear Information System (INIS)

    Blowes, D.W.; Cherry, J.A.; Reardon, E.J.

    1987-01-01

    Extensive hydrogeochemical investigations are currently underway at three inactive tailings impoundments in Canada. These programs include detailed measurements of pore-water and gas-phase geochemistry through the vadose zone and the groundwater zone. An extensive piezometer network has been installed at each location to monitor the groundwater flow regime. All of the impoundments studied have been inactive for 15 to 25 years, sufficient time for extensive tailings pore-water evolution. The study areas include a very high-sulfide impoundment, a low-sulfide, high-carbonate impoundment, a low-sulfide, very low-carbonate impoundment, and a moderately high-sulfide impoundment. The pore water at each of the sites has evolved in a distinctly different and characteristic manner, representing broad styles of tailings pore-water evolution. At the high sulfide impoundment the oxidation of sulfide minerals has resulted in low pH, high redox potential conditions, with Fe 2+ concentrations in excess of 60,000 mg/L. At a depth of about 40 cm a 10 cm thick layer of ferrous and calcium sulfate minerals has precipitated. This hardpan layer limits the downward movement of O 2 and infiltrating pore waters. As a result, the pore water chemistry, both above and below the hardpan layer, has remained relatively unchanged over the past 10 years. The low-sulfide, high-carbonate tailings are sufficiently well buffered that no low pH conditions are present. The high pH conditions limit the concentrations of the metals released by sulfide mineral oxidation to levels that are two or three orders of magnitude less than is observed at the high-sulfide site. Pore waters at the low-sulfide, low-carbonate site were sampled by other researchers from the University of Waterloo

  1. Handling 78,000 drums of mixed-waste sludge

    International Nuclear Information System (INIS)

    Berry, J.B.; Gilliam, T.M.; Harrington, E.S.; Youngblood, E.L.; Baer, M.B.

    1991-01-01

    The Oak Ridge Gaseous Diffusion Plant (now know as the Oak Ridge K-25 Site) prepared two mixed-waste surface impoundments for closure by removing the sludge and contaminated pond-bottom clay and attempting to process it into durable, nonleachable, concrete monoliths. Interim, controlled, above-ground storage of the stabilized waste was planned until final disposition. The strategy for disposal included delisting the stabilized pond sludge from hazardous to nonhazardous and disposing of the delisted monoliths as radioactive waste. Because of schedule constraints and process design and control deficiencies, ∼46,000 drums of material in various stages of solidification and ∼32,000 drums of unprocessed sludge are presently being stored. In addition, the abandoned treatment facility still contains ∼16,000 gal of raw sludge. Such conditions do not comply with the requirements set forth by the Resource Conservation and Recovery Act (RCRA) for the storage of listed waste. Various steps are being taken to bring the storage of ∼78,000 drums of mixed waste into compliance with RCRA. This paper (1) reviews the current situation, (2) discusses the plan for remediation of regulatory noncompliances, including decanting liquid from stabilized waste and dewatering untreated waste, and (3) provides an assessment of alternative raw-waste treatment processes. 1 ref., 6 figs., 2 tabs

  2. 32 CFR 634.51 - Procedures for impoundment.

    Science.gov (United States)

    2010-07-01

    ... complete DD Form 2506 (Vehicle Impoundment Report) as a record of the actions taken. (i) An inventory... not be inventoried. Such articles should be opened only if necessary to identify the owner of the...

  3. Reclamation plans at uranium mill tailings sites

    International Nuclear Information System (INIS)

    Abt, S.R.; Nelson, J.D.

    1990-01-01

    Long-term stability of waste impoundments is of concern because of the long time periods over which various types of waste may remain active. Over the past decade much technology has been developed specifically for reclamation of uranium mill tailings impoundments. Aspects of this technology will be discussed here and is presented as also being directly applicable to reclamation of industrial waste impoundments in general. The paper discusses Title I and Title II sites which represent two different generations in uranium tailings impoundment construction. The comparison between the two represent differences in philosophies as well as in impoundment type. Reclamation of uranium mill tailings impoundments in the U.S. is controlled by Federal legislation, which has set forth the regulatory framework for reclamation plan approval. Title I requirements govern government owned inactive sites and Title II requirements govern active tailings impoundments or those operated by private industries. While the Title I and Title II designation may result in a slightly different regulatory process, reclamation of uranium tailings sites has the same. Differences between Title I and Title II reclamation plans to achieve surface stability relate primarily to the embankment and surface covers. The differences in the cover designs result from site-specific conditions, rather than from differences in engineering approaches or the regulatory process. This paper discusses the site-specific conditions that affect the selection of cover designs, and provides a comparative example to illustrate the effect of this condition

  4. Hazardous waste landfill research

    Energy Technology Data Exchange (ETDEWEB)

    Schomaker, N.B.

    1983-05-01

    The hazardous waste land disposal research program is collecting data necessary to support implementation of disposal guidelines mandated by the 'Resource Conservation and Recovery Act of 1976' (RCRA) PL 94-580. This program relating to the categorical area of landfills, surface impoundments, and underground mines encompasses state-of-the-art documents, laboratory analysis, economic assessment, bench and pilot studies, and full scale field verification studies. Over the next five years the research will be reported as Technical Resource Documents in support of the Permit Writers Guidance Manuals. These manuals will be used to provide guidance for conducting the review and evaluation of land disposal permit applications. This paper will present an overview of this program and will report the current status of work in the various categorical areas.

  5. Cumulative impoundment evaporation in water resource management within the mid-Atlantic: A case study in Virginia

    Science.gov (United States)

    Scott, D.; Burgholzer, R.; Kleiner, J.; Brogan, C. O.; Julson, C.; Withers, E.

    2017-12-01

    Across the eastern United States, successful management of water resources to satisfy the competing demands for human consumption, industry, agriculture, and ecosystems requires both water quality and water quantity considerations. Over the last 2 decades, low streamflows during dry summers have increased scrutiny on water supply withdrawals. Within Virginia, a statewide hydrologic model provides quantitative assessments on impacts from proposed water withdrawals to downstream river flow. Currently, evaporative losses are only accounted for from the large reservoirs. In this study, we sought to provide a baseline estimate for the cumulative evaporation from impoundments across all of the major river basins in Virginia. Virginia provides an ideal case study for the competing water demands in the mid-Atlantic region given the unique tracking of water withdrawals throughout the river corridor. In the over 73,000 Virginia impoundments, the cumulative annual impoundment evaporation was 706 MGD, or 49% of the permitted water withdrawal. The largest reservoirs (>100 acres) represented over 400 MGD, and 136 MGD for the smaller impoundments (water loss (evaporation + demand), with some areas where impoundment evaporation was greater than human water demand. Seasonally, our results suggest that cumulative impoundment evaporation in some watersheds greatly impacts streamflow during low flow periods. Our results demonstrate that future water supply planning will require not only understanding evaporation within large reservoirs, but also the thousands of small impoundments across the landscape.

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1982-08-01

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

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

    International Nuclear Information System (INIS)

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

    1982-08-01

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

  8. Developments in the management of radioactive waste from the mining and milling of radioactive ores

    International Nuclear Information System (INIS)

    Crawley, H.

    1990-01-01

    The philosophy of a waste management system is discussed. The origins of the various wastes from the mining and milling processes are outlined and the development of a waste management program described. The technical aspects of a waste management plan, namely water management systems, waste rock and ore stockpile management, tailings impoundment and decommissioning and rehabilitation are discussed in detail. 12 refs., 4 tabs, 15 figs

  9. Quality assurance program for environmental assessment of Savannah River Plant waste sites: Environmental information document

    International Nuclear Information System (INIS)

    Looney, B.B.; King, C.M.; Stephenson, D.E.

    1987-03-01

    Forty-eight locations were identified that received a variety of radioactive and nonradioactive constituents during the past 35 years including surface impoundments and shallow land burial facilities. Detailed environmental assessments of existing waste disposal areas, as well as new waste disposal techniques and disposition of tritiated water, were completed to air in an evaluation of the low level, mixed and hazardous waste management activities. These assessments result in estimation of risk, or residual risk, posed by each disposal area to various receptors as a function of waste management alternative. For example, at existing waste sites, the closure actions evaluated were waste removal and closure, no waste removal and closure, and no action; several pathways/receptors were considered, including groundwater to river, groundwater to well, atmospheric transport, occupational exposure, direct exposure, and contamination followed by ingestion of crops and meat. Modeling of chemical transport in a variety of media was an integral part of the assessment process. The quality of the models used and the application of these models were assured by an explicit quality assurance program

  10. Effect of ship locking on sediment oxygen uptake in impounded rivers

    DEFF Research Database (Denmark)

    Lorke, A.; McGinnis, D. F.; Maeck, A.

    2012-01-01

    In the majority of large river systems, flow is regulated and/or otherwise affected by operational and management activities, such as ship locking. The effect of lock operation on sediment-water oxygen fluxes was studied within a 12.9 km long impoundment at the Saar River (Germany) using eddy....... Additional means by which the oxygen budget of the impoundment is affected by lock-induced flow variations are discussed. Citation: Lorke, A., D. F. McGinnis, A. Maeck, and H. Fischer (2012), Effect of ship locking on sediment oxygen uptake in impounded rivers, Water Resour. Res., 48, W12514, doi: 10....... These wave-induced flow variations cause variations in sediment-water oxygen fluxes. While the mean flux during time periods without lock operation was 0.5 +/- 0.1 g m(-2) d(-1), it increased by about a factor of 2 to 1.0 +/- 0.5 g m(-2) d(-1) within time periods with ship locking. Following the daily...

  11. Closure plan for the M-Area settling basin and vicinity at the Savannah River Plant

    International Nuclear Information System (INIS)

    Colven, W.P.; Pickett, J.B.

    1985-07-01

    The areas addressed in this closure plan include a process sewer line, surface impoundment (settling basin), overflow ditch, seepage area, and a Carolina Bay known as Lost Lake. Since it is proposed that the basin and vicinity be closed with the hazardous wastes placed and stabilized in the basin, it will be closed pursuant to regulations for closing a hazardous waste landfill. No free liquids will remain in the impoundment after closure is completed

  12. Coal combustion waste management study

    International Nuclear Information System (INIS)

    1993-02-01

    Coal-fired generation accounted for almost 55 percent of the production of electricity in the United States in 1990. Coal combustion generates high volumes of ash and flue gas desulfurization (FGD) wastes, estimated at almost 90 million tons. The amount of ash and flue gas desulfurization wastes generated by coal-fired power plants is expected to increase as a result of future demand growth, and as more plants comply with Title IV of the 1990 Clean Air Act Amendments. Nationwide, on average, over 30 percent of coal combustion wastes is currently recycled for use in various applications; the remaining percentage is ultimately disposed in waste management units. There are a significant number of on-site and off-site waste management units that are utilized by the electric utility industry to store or dispose of coal combustion waste. Table ES-1 summarizes the number of disposal units and estimates of waste contained at these unites by disposal unit operating status (i.e, operating or retired). Further, ICF Resources estimates that up to 120 new or replacement units may need to be constructed to service existing and new coal capacity by the year 2000. The two primary types of waste management units used by the industry are landfills and surface impoundments. Utility wastes have been exempted by Congress from RCRA Subtitle C hazardous waste regulation since 1980. As a result of this exemption, coal combustion wastes are currently being regulated under Subtitle D of RCRA. As provided under Subtitle D, wastes not classified as hazardous under Subtitle C are subject to State regulation. At the same time Congress developed this exemption, also known as the ''Bevill Exclusion,'' it directed EPA to prepare a report on coal combustion wastes and make recommendations on how they should be managed

  13. Simulated effects of impoundment of lake seminole on ground-water flow in the upper Floridan Aquifer in southwestern Georgia and adjacent parts of Alabama and Florida

    Science.gov (United States)

    Jones, L. Elliott; Torak, Lynn J.

    2004-01-01

    Hydrologic implications of the impoundment of Lake Seminole in southwest Georgia and its effect on components of the surface- and ground-water flow systems of the lower Apalachicola?Chattahoochee?Flint (ACF) River Basin were investigated using a ground-water model. Comparison of simulation results of postimpoundment drought conditions (October 1986) with results of hypothetical preimpoundment conditions (a similar drought prior to 1955) provides a qualitative measure of the changes in hydraulic head and ground-water flow to and from streams and Lake Seminole, and across State lines caused by the impoundment. Based on the simulation results, the impoundment of Lake Seminole changed ground-water flow directions within about 20?30 miles of the lake, reducing the amount of ground water flowing from Florida to Georgia southeast of the lake. Ground-water storage was increased by the impoundment, as indicated by a simulated increase of as much as 26 feet in the water level in the Upper Floridan aquifer. The impoundment of Lake Seminole caused changes to simulated components of the ground-water budget, including reduced discharge from the Upper Floridan aquifer to streams (315 million gallons per day); reduced recharge from or increased discharge to regional ground-water flow at external model boundaries (totaling 183 million gallons per day); and reduced recharge from or increased discharge to the undifferentiated overburden (totaling 129 million gallons per day).

  14. 40 CFR 63.961 - Definitions.

    Science.gov (United States)

    2010-07-01

    ... system used to convey regulated-material to a waste management unit or to discharge or disposal. The term...-material to a downstream waste management unit. Sewer lines include pipes, grates, and trenches. Waste... regulated-material. Examples of waste management units include: wastewater tanks, surface impoundments...

  15. Investigation, assessment and remediation of the water pathway in the surroundings of the Culmitzsch A tailings impoundment

    International Nuclear Information System (INIS)

    Schulze, G.; Paul, M.; Priester, J.; Schoepfer, C.

    1998-01-01

    Several large tailings impoundments in Saxony and Thuringia are the result of the extensive uranium mining and milling in Eastern Germany after World War II. The Culmitzsch tailings pond in Eastern Thuringia was constructed within a former uranium open pit mine and is located within the Culmitzsch trench fault. The tailings impoundment includes two ponds (Culmitzsch A and B) which are separated by an internal dam with an impervious core. The Culmitzsch A pond covers an area of 158 ha, the maximum tailings thickness is 70 m. Between this pond (elevation of up to 340 m above sea-level) and the Lerchenbach creek (265.. 280 m above sea-level) a steep gradient exists. So the valley of the Lerchenbach is the general discharge area for the seepage of the pond which is a result of dewatering by gravity and consolidation. The seepage water migrates through the southern dam of the impoundment and through permeable layers which are in contact with the tailings. About 400 groundwater wells were installed within three aquifers in order to clarify the flow direction and the degree of contamination of the groundwater as well as to investigate the geohydraulic properties of the rocks in the surroundings of the pond. Based on the results of this investigation programme a three-dimensional hydrogeological model was built up which reflects the general relationships between the pond and its geological setting as well as the water balance of the whole system. Presently a catchment system exists which gathers all surface waters with significant uranium and salt concentrations. Moreover dewatering wells on the beach zone of the pond and catchment wells in the downstream area of the impoundment have been installed. Before being released to the receiving streams seepage and freewater are treated in a two-step water treatment plant in order to decrease their uranium, radium and arsenic contents. (orig.) [de

  16. An Object-Based Machine Learning Classification Procedure for Mapping Impoundments in Brazil's Amazon-Cerrado Agricultural Frontier

    Science.gov (United States)

    Solvik, K.; Macedo, M.; Graesser, J.; Lathuilliere, M. J.

    2017-12-01

    Large-scale agriculture and cattle ranching in Brazil has driving the creation of tens of thousands of small stream impoundments to provide water for crops and livestock. These impoundments are a source of methane emissions and have significant impacts on stream temperature, connectivity, and water use over a large region. Due to their large numbers and small size, they are difficult to map using conventional methods. Here, we present a two-stage object-based supervised classification methodology for identifying man-made impoundments in Brazil. First, in Google Earth Engine pixels are classified as water or non-water using satellite data and HydroSHEDS products as predictors. Second, using Python's scikit-learn and scikit-image modules the water objects are classified as man-made or natural based on a variety of shape and spectral properties. Both classifications are performed by a random forest classifier. Training data is acquired by visually identifying impoundments and natural water bodies using high resolution satellite imagery from Google Earth.This methodology was applied to the state of Mato Grosso using a cloud-free mosaic of Sentinel 1 (10m resolution) radar and Sentinel 2 (10-20m) multispectral data acquired during the 2016 dry season. Independent test accuracy was estimated at 95% for the first stage and 93% for the second. We identified 54,294 man-made impoundments in Mato Grosso in 2016. The methodology is generalizable to other high resolution satellite data and has been tested on Landsat 5 and 8 imagery. Applying the same approach to Landsat 8 images (30 m), we identified 35,707 impoundments in the 2015 dry season. The difference in number is likely because the coarser-scale imagery fails to detect small (work will apply this approach to satellite time series for the entire Amazon-Cerrado frontier, allowing us to track changes in the number, size, and distribution of man-made impoundments. Automated impoundment mapping over large areas may help with

  17. Review of environmental surveillance data around low-level waste disposal areas at Oak Ridge National Laboratory

    International Nuclear Information System (INIS)

    Oakes, T.W.; Shank, K.E.

    1979-01-01

    White Oak Creek and Melton Branch tributary surface streams flow through the Oak Ridge National Laboratory (ORNL) reservation and receive treated low-level radioactive liquid waste which originates from various Laboratory operations. The streams receive additional low-level liquid waste generated by seepage of radioactive materials from solid-waste burial grounds, hydrofracture sites, and intermediate-level liquid-waste sites. Over the years, various liquid-waste treatment and disposal processes have been employed at ORNL; some of these processes have included: settling basins, impoundment, storage tanks, evaporation, ground disposal in trenches and pits, and hydrofracture. Burial of solid radioactive waste was initiated in the early 1940's, and there are six burial grounds at ORNL with two currently in use. Monitoring at White Oak Dam, the last liquid control point for the Laboratory, was started in the late 1940's and is continuing. Presently, a network of five environmental monitoring stations is in operation to monitor the radionuclide content of surface waters in the White Oak watershed. In this paper, the solid waste burial grounds will be described in detail, and the environmental data tabulated over the past 29 years will be presented. The various monitoring systems used during the years will also be reviewed. The liquid effluent discharge trends at ORNL from the radioactive waste operations will be discussed

  18. Diet and trophic structure of the fish fauna in a subtropical ecosystem: impoundment effects

    Directory of Open Access Journals (Sweden)

    Rosilene Luciana Delariva

    Full Text Available This study examined the diet and trophic structure of the fish fauna, over temporal and spatial scales, as affected by the impoundment of the Iguaçu River in the region of Salto Caxias, Paraná State, Brazil. Sampling was conducted before (March 1997 - February 1998 and after the impoundment (March 1999 - February 2000, at four sampling sites. The stomach contents were analyzed by the volumetric method. The species could be organized in 10 trophic guilds: algivores, carcinophages, detritivores, herbivores, aquatic insectivores, terrestrial insectivores, invertivores, omnivores, piscivores, and planktivores; the first and last guilds were represented only in the post-impoundment period. Similarity patterns and feeding changes were summarized by a non-metric Multi-dimensional Scaling (nMDS analysis and statistically tested by a Permutational multivariate analysis of variance (PERMANOVA. Most species showed feeding changes, except for the piscivores and detritivores. These changes were related to the temporal factor (impoundment phases, such as reduced intake of benthic organisms and allochthonous food, which were usually replaced by resources from the reservoir itself (algae, microcrustaceans, and fish, simplifying the food spectrum of the fish fauna. A different indicator of food resources (IndVal corroborated these changes in the feeding of the species. The proportions of the trophic guilds evaluated based on the catch per unit of effort (CPUE and tested by ANOSIM were significantly different before and after the impoundment. Herbivores and piscivores were the guilds that contributed (SIMPER to these differences, especially the high increase in biomass of the piscivore guild after the impoundment. Variations in the abundance of trophic guilds were more directly related to changes in the feeding habits of the fish fauna than to increases in the number and biomass of the species that constitute these guilds.

  19. The geo-environmental design of a coal refuse impoundment in Illinois

    International Nuclear Information System (INIS)

    Ripp, B.J.

    1997-01-01

    The coal refuse impoundment discussed was one of the first permitted under new regulatory standards within the State of Illinois. The new standards go beyond the geotechnial stability of the structure and must address the groundwater quality of the area and the impact of the impoundment on the groundwater system. The geotechnial design of the coal refuse impoundment dam and associated structures had its own particular challenges such as: 1) the construction of the structure over mined workings; 2) the close proximity of seismically active fault zones; and 3) the embankment configuration being controlled by the material balance of the mine refuse. The implementation of the groundwater protection plan included: 1) incorporating the groundwater quality standards and sampling protocols of several state agencies while the standards were being drafted; 2) sampling of the potential sources of groundwater impact; 3) establishing background levels; and 4) establishing the groundwater class. An initial groundwater transport model was developed and used as the basis for recommending a groundwater monitoring design in place of constructing a soil or synthetic liner. 15 refs., 2 figs., 3 tabs

  20. The impact of uncontrolled waste disposal on surface water quality ...

    African Journals Online (AJOL)

    The main threat to the surface water quality in Addis Ababa is environmental pollution derived from domestic and industrial activities. Due to the inadequacy of controlled waste management strategies and waste treatment plants, people are forced to discharge wastes both on open surface and within water bodies.

  1. Effects of impoundment and regulation upon the stomach contents of fish at Cow Green, Upper Teesdale

    Energy Technology Data Exchange (ETDEWEB)

    Crisp, D.T.; Mann, R.H.K.; McCormack, J.C.

    1978-04-01

    The stomach contents of 1003 brown trout, 1551 bullheads and 800 minnows taken from the reservoir basin and below the dam, before and after impoundment of the river Tees, were examined. Their composition reflected observations by other workers on river and reservoir benthos, except for the increase in numbers of Hydra and Nais below the dam, and Mollusca, Hirudinea and oligochaetes in the reservoir. Trout below the dam ate more Ephemeroptera nymphs and Chironomidae larvae but fewer terrestrial casualties after river regulation, whereas bullheads ate more Mollusca but fewer Plecoptera nymphs. In both species Baetidae nymphs increased in numerical importance relative to Ecdyonuridae. Trout, but not bullheads, took zooplankton discharged from the reservoir. Before impoundment, trout within the reservoir basin ate chiefly benthic organisms and terrestrial casualties. Inundated terrestrial material, mainly earthworms, formed the bulk of their food for at least three years after impoundment, whilst from the second year onwards Chironomidae and, in some years, Gammarus became increasingly important. Zooplankton was taken by all sizes of reservoir trout. Bullheads within the reservoir basin ate chiefly river benthos before impoundment, with Ephemeroptera and Plecoptera nymphs predominant in older fish, and aquatic Diptera and Coleoptera also important in the fry. After impoundment, Chironomidae and Gammarus were the main items taken by older bullheads, and Chironomidae and micro-crustacea by the fry. Among all sizes of minnow, Chironomidae, micro-crustacea and detritus increased in numerical importance after impoundment.

  2. Stochastic Modelling of the Hydraulic Anisotropy of Ash Impoundment Sediment

    Science.gov (United States)

    Slávik, Ivan

    2017-12-01

    In the case reported here the impoundments of a 400 MW coal heated power plant with an annual production of about 1.5 million tons of fuel ash are of the cross-valley type, operated by the simple and cheap „upstream method”. The aim of the research was to determine overall and local values of the permeability in horizontal as well as in vertical direction and the anisotropy of the thin-layered sedimented ash. The coal ashes are hydraulically transported through pipelines in form of a slurry and periodically floated on the beach of the impoundment. The ashes are deposited in the form of a thin-layered sediment, with random alternation of layers with a coarser or finer granularity. The ash impoundment sediment is anthropogenic sediment with horizontally laminated texture. Therefore, the sediment is anisotropic from the viewpoint of water seepage. The knowledge of the permeability and the seepage anisotropy of the sediment is a basic requirement for the design of an appropriate dewatering system. The seepage anisotropy of the ash sediment has been checked by means of stochastic modelling, based on the correlation between the effective grain diameter and the coefficient of permeability of the ash: the effective grain diameter and the thickness of individual layers have been proposed to be random events.

  3. Synthesis long life storage studies surface storage of vitrified wastes

    International Nuclear Information System (INIS)

    Beziat, A.; Breton, E.; Ranc, G.; Gaillard, J.P.; Lagrave, H.; Hollender, F.; Jourdain, F.; Piault, E.; Garnier, J.; Lamare, V.; Duret, B.; Helie, M.; Ferry, C.; Mijuin, D.; Gagnier, E.

    2004-01-01

    This document is realized in the framework of the axis 3 of the law of 1991 on the radioactive wastes management. It justifies the choices concerning long time surface storage installation of vitrified wastes, called high activity wastes. The long time of the installation would reach 300 years at the maximum. These wastes represent 1 % at the maximum, of radioactive wastes in France but 95 % of the whole radioactivity. Three main objectives were followed: provide a permanent containment of radionuclides; give the possibility of wastes containers retrieval at all the time; minimize the maintenance and the control. The results allow to conclude that the long time surface storage of high activity wastes is feasible. (A.L.B.)

  4. Research on near-surface disposal of very low level radioactive waste

    International Nuclear Information System (INIS)

    Wang Shaowei; Yue Huiguo; Hou Jie; Chen Haiying; Zuo Rui; Wang Jinsheng

    2012-01-01

    Radioactive waste disposal is one of the most sensitive environmental problems to control and solve. As the arriving of decommissioning of early period nuclear facilities in China, large amounts of very low level radioactive waste will be produced inevitably. The domestic and abroad definitions about very low level radioactive waste and its disposal were introduced, and then siting principles of near-surface disposal of very low level radioactive waste were discussed. The near- surface disposal siting methods of very low level radioactive waste were analyzed from natural and geographical conditions assessment, geological conditions analysis, hydrogeological conditions analysis, geological hazard assessment and radioactive background investigation; the near-surface disposal sites'natural barriers of very low level radioactive waste were analyzed from the crustal structure and physico-chemical characteristics, the dynamics characteristics of groundwater, the radionuclide adsorption characteristics of natural barriers and so on; the near-surface disposal sites' engineered barriers of very low level radioactive waste were analyzed from the repository design, the repository barrier materials selection and so on. Finally, the improving direction of very low level radioactive waste disposal was proposed. (authors)

  5. Inspection and verification of waste packages for near surface disposal

    International Nuclear Information System (INIS)

    2000-01-01

    Extensive experience has been gained with various disposal options for low and intermediate level waste at or near surface disposal facilities. Near surface disposal is based on proven and well demonstrated technologies. To ensure the safety of near surface disposal facilities when available technologies are applied, it is necessary to control and assure the quality of the repository system's performance, which includes waste packages, engineered features and natural barriers, as well as siting, design, construction, operation, closure and institutional controls. Recognizing the importance of repository performance, the IAEA is producing a set of technical publications on quality assurance and quality control (QA/QC) for waste disposal to provide Member States with technical guidance and current information. These publications cover issues on the application of QA/QC programmes to waste disposal, long term record management, and specific QA/QC aspects of waste packaging, repository design and R and D. Waste package QA/QC is especially important because the package is the primary barrier to radionuclide release from a disposal facility. Waste packaging also involves interface issues between the waste generator and the disposal facility operator. Waste should be packaged by generators to meet waste acceptance requirements set for a repository or disposal system. However, it is essential that the disposal facility operator ensure that waste packages conform with disposal facility acceptance requirements. Demonstration of conformance with disposal facility acceptance requirements can be achieved through the systematic inspection and verification of waste packages at both the waste generator's site and at the disposal facility, based on a waste package QA/QC programme established by the waste generator and approved by the disposal operator. However, strategies, approaches and the scope of inspection and verification will be somewhat different from country to country

  6. The impact of impoundment on the rotifer communities in two tropical floodplain environments: interannual pulse variations

    Directory of Open Access Journals (Sweden)

    CC. Bonecker

    Full Text Available Hydrological pulses are the main factor regulating the structure of biological communities in floodplains. Reservoirs above this ecosystem change the environment's dynamics and the community's biodiversity. This study evaluated the structure and stability of the rotifer community in response to changes in hydrological pulses after the Porto Primavera impoundment in the Upper Paraná River floodplain. The community was studied in a river and in a floodplain lake downstream of the dam over a four-year period before and after the impoundment. A decrease in species richness and abundance was observed soon after the impoundment, followed by an increase in these attributes and in specific diversity when the hydrometric level of the Paraná River rose and, consequently, increased the connectivity between the floodplain environments. Conochilus coenobasis, Filinia longiseta, Keratella cochlearis, Lecane proiecta and Polyarthra dolichoptera persisted throughout the study and contributed to community stability (the maintenance of rank in species abundance over time, which was high in the floodplain lake, mainly after the impoundment. Reductions in the frequency, intensity and amplitude of potamophase pulses after the impoundment led to the decrease in species richness and the increases in abundance, community stability, and species diversity, which determine community resilience.

  7. Water-quality study of Tulpehocken Creek, Berks County, Pennsylvania, prior to impoundment of Blue Marsh Lake

    Science.gov (United States)

    Barker, James L.

    1977-01-01

    Blue Marsh Lake is planned as a multipurpose impoundment to be constructed on Tulpehocken Creek near Bernville, Berks County, Pennsylvania. Prior to construction, samples of water, bed material, and soil were collected throughout the impoundment site to determine concentrations of nutrients, insecticides, trace metals, suspended sediment, and bacteria. Analyses of water suggest the Tulpehocken Creek basin to be a highly fertile environment. Nitrogen and phosphorus concentrations near the proposed dam site had median values of 4.5 and 0.13 mg/L, respectively. Suspended sediment discharges average between 100 and 200 tons (90.7 to 181.4 metric tons) per day during normal flows but may exceed 10,000 tons (9,070 metric tons) per day during storm runoff. Highest yields were measured during winter and early spring. Concentrations range from 3 mg/L to more than 500 mg/L. Bed material samples contain trace quantities of aldrin, DDT, DDD, DDE, dieldrin, and chlordane. Polychlorinated biphyenyls (PCB's) ranged from 10 to 100 μg/kg. Soils at the impoundment site are of average fertility. However, the silt loam texture is ideal for attachment and growth of aquatic plants. Bacteria populations indicative of recent fecal contamination are prevalent in the major inflows to the proposed lake. Fecal Coliform exceeded the standards recommended by the Federal Water Pollution Administration Committee on Water Quality Criteria for public water supply in 29 percent of the monthly samples, and exceeded the recommended public bathing waters standard in 83 percent of the samples collected from June to September. Arsenic from an industrial waste was found in the water, suspended sediment, and bed material of Tulpehocken Creek in concentrations of 0 to 30 μg/l, 2 to 879 μg/l, and 1 to 79 μg/g, respectively. It represents a potential environmental hazard; however, the measured concentrations are less than that known to be harmful to man, fish, or wildlife, according to published water

  8. KS 20322007 Near-Surface Disposal Radioactive Waste - Code Of Practice

    International Nuclear Information System (INIS)

    Omondi, C.

    2017-01-01

    To provide a basis for the near-surface disposal of solid radioactive waste to ensures that there is no unacceptable risk to humans, other biota or the environment. Near-Surface Disposal is the disposal of radioactive waste in below or above the natural ground surface, within app. 30 m. The code deals with management aspects associated with radioactive waste disposal only, and is not intended to cover issues related to the production and use of radionuclides. The objective of waste disposal is to isolate radioactive waste in order to ensure that there is no unacceptable health risk to humans and no long-term unacceptable effect to the environment. Radiation protection annual effective dose for exposure of members of the public should not exceed 1 mSv/year and occupational exposure of 20 mSv/year

  9. Profiling of Sediment Microbial Community in Dongting Lake before and after Impoundment of the Three Gorges Dam

    Directory of Open Access Journals (Sweden)

    Wei Huang

    2016-06-01

    Full Text Available The sediment microbial community in downstream-linked lakes can be affected by the operation of large-scale water conservancy projects. The present study determined Illumina reads (16S rRNA gene amplicons to analyze and compare the bacterial communities from sediments in Dongting Lake (China before and after impoundment of the Three Gorges Dam (TGD, the largest hydroelectric project in the world. Bacterial communities in sediment samples in Dongting Lake before impoundment of the TGD (the high water period had a higher diversity than after impoundment of the TGD (the low water period. The most abundant phylum in the sediment samples was Proteobacteria (36.4%–51.5%, and this result was due to the significant abundance of Betaproteobacteria and Deltaproteobacteria in the sediment samples before impoundment of the TGD and the abundance of Gammaproteobacteria in the sediment samples after impoundment of the TGD. In addition, bacterial sequences of the sediment samples are also affiliated with Acidobacteria (11.0% on average, Chloroflexi (10.9% on average, Bacteroidetes (6.7% on average, and Nitrospirae (5.1% on average. Variations in the composition of the bacterial community within some sediment samples from the river estuary into Dongting Lake were related to the pH values. The bacterial community in the samples from the three lake districts of Dongting Lake before and after impoundment of the TGD was linked to the nutrient concentration.

  10. Surface analysis: its uses and abuses in waste form evaluation

    International Nuclear Information System (INIS)

    McVay, G.L.; Pederson, L.R.

    1981-01-01

    Surface and near-surface analytical techniques are significant aids in understanding waste form-aqueous solution interactions. They can be beneficially employed to evaluate reaction layers on waste forms, to assess surface treatments prior to and after leaching, and to identify interactions with waste forms. Surface analyses are best used in conjunction with other types of analyses, such as solution analyses, in order to obtain a better overall understanding of reaction processes. In spite of all the benefits to be gained by using surface analyses, misinterpretations can result if care is not taken to properly obtain and analyze the data. In particular, the density variations through a reaction layer must be accounted for in both sputtering and data analysis techniques

  11. Moist Soil Management of Wetland Impoundments for Plants and Invertebrates

    Data.gov (United States)

    Department of the Interior — In year’s past an impoundment was drained (a drawdown) when floating-leaved plants covered more than 50% of the water area. Drawdowns encourage beneficial moist soil...

  12. Recent advances in yeast cell-surface display technologies for waste biorefineries.

    Science.gov (United States)

    Liu, Zhuo; Ho, Shih-Hsin; Hasunuma, Tomohisa; Chang, Jo-Shu; Ren, Nan-Qi; Kondo, Akihiko

    2016-09-01

    Waste biorefinery aims to maximize the output of value-added products from various artificial/agricultural wastes by using integrated bioprocesses. To make waste biorefinery economically feasible, it is thus necessary to develop a low-cost, environment-friendly technique to perform simultaneous biodegradation and bioconversion of waste materials. Cell-surface display engineering is a novel, cost-effective technique that can auto-immobilize proteins on the cell exterior of microorganisms, and has been applied for use with waste biofinery. Through tethering different enzymes (e.g., cellulase, lipase, and protease) or metal-binding peptides on cell surfaces, various yeast strains can effectively produce biofuels and biochemicals from sugar/protein-rich waste materials, catalyze waste oils into biodiesels, or retrieve heavy metals from wastewater. This review critically summarizes recent applications of yeast cell-surface display on various types of waste biorefineries, highlighting its potential and future challenges with regard to commercializing this technology. Copyright © 2016 Elsevier Ltd. All rights reserved.

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

    International Nuclear Information System (INIS)

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

    1982-01-01

    The age of nuclear waste - the length of time between its removal from the reactor cores and its emplacement in a repository - is a significant factor in determining the thermal loading of a repository. The surface cooling period as well as the density and sequence of waste emplacement affects both the near-field repository structure and the far-field geologic environment. To investigate these issues, a comprehensive review was made of the available literature pertaining to thermal effects and thermal properties of mined geologic repositories. This included a careful evaluation of the effects of different surface cooling periods of the wastes, which is important for understanding the optimal thermal loading of a repository. The results led to a clearer understanding of the importance of surface cooling in evaluating the overall thermal effects of a radioactive waste repository. The principal findings from these investigations are summarized in this paper

  14. 40 CFR 421.11 - Specialized definitions.

    Science.gov (United States)

    2010-07-01

    ... pond water surface area for the purpose of calculating the volume of waste water shall mean the area within the impoundment for rainfall and the actual water surface area for evaporation. [39 FR 12825, Apr...

  15. Engineering evaluation/cost analysis for the proposed management of contaminated water impounded at the Weldon Spring chemical plant area

    International Nuclear Information System (INIS)

    MacDonell, M.M.; Maxey, M.L.; Peterson, J.M.; Joya, I.E.

    1990-07-01

    This engineering evaluation/cost analysis (EE/CA) report has been prepared to support the proposed removal action for managing contaminated surface waters impounded at the chemical plant area of the Weldon Spring site, located near Weldon Spring, Missouri. The US Department of Energy is responsible for cleanup activities at the site under its Surplus Facilities Management Program (SFMP). The major goals of SFMP are to eliminate potential hazards to human health and the environment that are associated with contamination at SFMP sites and to make surplus real property available for other uses, to the extent possible. The objectives of this EE/CA report are to identify the cleanup as a removal action, document the selection of a response that will mitigate the potential release of radioactive or chemical contaminants from the impounded waters into the nearby environment, and address environmental impacts associated with the proposed action. 41 refs., 8 figs., 8 tabs

  16. Analysis of spatial distribution and inventory of radioactivity within the uranium mill tailings impoundment

    Directory of Open Access Journals (Sweden)

    D. O. Bugai

    2015-10-01

    Full Text Available Results are presented of the characterization of radioactivity inventory of Zapadnoe uranium mill tailings impoundment situated at Pridneprovsky Chemical Plant (PChP; Dneprodzerzhinsk, Ukraine. Analyses of radioactivity data set based on analytical studies of core material from 15 characterization boreholes allowed significantly refining waste volume and radioactivity inventory estimates. Geostatistical analyses using variogram function have established that radioactivity distribution in Zapadnoe tailings is characterized by regular spatial correlation patterns. Ordinary kriging method was applied to assess distribution of radioactivity in 3D. Results of statistical analyses suggest significant redistribution of uranium in the dissolved form in the residues (presumably due to water infiltration process. The developed structural model for radioactivity distribution is used for further risk assessment analyses. Derived radioactivity correlation scales can be used for optimization of sample collection when characterizing the PChP Site and similar contaminated sites elsewhere.

  17. 40 CFR 264.221 - Design and operating requirements.

    Science.gov (United States)

    2010-07-01

    ..., and other equipment; and human error. (h) A surface impoundment must have dikes that are designed... (CONTINUED) STANDARDS FOR OWNERS AND OPERATORS OF HAZARDOUS WASTE TREATMENT, STORAGE, AND DISPOSAL FACILITIES... external hydrogeologic forces), physical contact with the waste or leachate to which they are exposed...

  18. 40 CFR 144.3 - Definitions.

    Science.gov (United States)

    2010-07-01

    ... operations, and sinks or washing machines where food and beverage serving dishes, glasses, and utensils are.... Hazardous waste management facility (“HWM facility”) means all contiguous land, and structures, other... landfills, surface impoundments, or combination of them). HWM facility means “Hazardous Waste Management...

  19. The use of artificial impoundments by two amphibian species in the Delaware Water Gap National Recreation Area

    Science.gov (United States)

    Julian, J.T.; Snyder, C.D.; Young, J.A.

    2006-01-01

    We compared breeding activity of Ambystoma maculatum (Spotted Salamander) and Rana sylvatica (Wood Frog) in artificial impoundments to patterns in natural wetlands over a three-year period in the Delaware Water Gap National Recreation Area. Rana sylvatica were 5.6 times more likely to use natural bodies of water for breeding than artificial impoundments, while A. maculatum were 2.7 times more likely to use natural bodies of water. Both species were approximately 9 times more likely to breed in fishless bodies of water than in waters with predatory fish. Ambystoma maculatum were 6 times more likely to breed in wetlands with more stable seasonal hydroperiods, while R. sylvatica were only 2 times more likely to do so. We conclude that the high likelihood of fish presence in impoundments was the primary explanation for why both species were less likely to use impoundments than natural wetlands, while the tendency of A. maculatum to avoid natural wetlands with shorter hydroperiods explained why differences in use between pond types was more pronounced for R. sylvatica.

  20. The Impact of Impoundment on Mercury Bioaccumulation in Fish Downstream from a Newly Constructed Reservoir, Wujiang River, Southwest China.

    Science.gov (United States)

    Li, Sixin; Zhou, Lianfeng; Chang, Jianbo; Yang, Zhi; Hu, Juxiang; Hongjun, Wang

    2017-11-01

    Mercury concentrations in fish were investigated downstream from a newly impounded subtropical reservoir in August 2008. After 6-7 months of reservoir impoundment, mean mercury concentration in fish from downstream is significantly increased by 1.9 times. Not only carnivorous fish but also benthic fish had significantly higher total mercury concentrations than others. No significant correlation was found between total mercury concentrations and body length or weight of 13 fish species. Compared with the pre-impoundment, total mercury in fish from downstream is significantly increased by reservoir impoundment, but the increased rate is lower than those in subarctic and temperate areas. Fish samples surpassed the Chinese hygienic standard for tolerances of mercury in foods increased by 4.3%. More attention should be given to fish mercury levels from downstream sites to prevent possible adverse effects on the health of local people.

  1. Screening Assessment of Radionuclide Migration in Groundwater from the “Dneprovskoe” Tailings Impoundment (Dneprodzerzhynsk City) and Evaluation of Remedial Options

    Energy Technology Data Exchange (ETDEWEB)

    Skalskyi, O.; Bugai, D. [Institute of Geological Sciences, National Academy of Sciences of Ukraine (Ukraine); Ryazantsev, V. [State Nuclear Regularity Committee of Ukraine, Kiev (Ukraine)

    2014-05-15

    The paper presents results of mathematical modeling of the hydrogeological conditions at the “Dneprovskoe” (“D”) tailings impoundment –object of the former industrial association of “Pridneprovsky Chemical Plant”, which contains uranium ore processing wastes. This radioactively polluted site is located in a densely populated region (at the outskirts of Dneprodzerginsk City) near the major watercourse of the Ukraine — Dnieper River.The mathematical modeling utilized Visual Modflow (for groundwater flow) and Ecolego (Facilia AB, Sweden) radioecology modeling software (for radionuclide transport).Modeling results indicate the possibility of essential radioactive contamination in future of the phreatic aquifer in alluvial deposits between the “D” tailings and the Dnieper River (mainly due to migration of uranium). Therefore long-term management strategies should preclude water usage from the aquifer in the zone of the in-fluence of the “D” tailings. Filtration discharge of uranium to the Dnepr River does not represent a significant risk due to large dilution by surface waters. The important modeling conclusion is that besides the uranium ore processing wastes inside the tailings, the major source of radionuclide migration to groundwater is represented by contaminated geological deposits below the tailings. This last source was formed due to leakage of wastewaters during the operational period of the “D” tailings (1954–1968). Therefore an exemption and re-disposal of wastes from the “D” tailings to a more safe storage location (proposed by some remedial plans) will not provide significant benefit from the viewpoint of minimizing of radionuclide transport to the groundwater and Dnieper River (especially in short-and medium-term perspective). The rational remedial strategy for the “D” tailings is conservation of tailing wastes in-situ by means of specially designed “zero flux” soil screen, which would minimize infiltration of

  2. Waste water treatment in surface mines

    Energy Technology Data Exchange (ETDEWEB)

    Navasardyants, M A; Esipov, V Z; Ryzhkov, Yu A

    1981-01-01

    This paper evaluates problems associated with waste water from coal surface mines of the Kemerovougol' association in the Kuzbass. Waste water treatment in the Kuzbass is of major importance as the region is supplied with water from only one river, the Tom river. Water influx to Kemerovougol' surface mines in a year amounts to 136 million m/sup 3/. The water is used during technological processes, for fire fighting, and spraying to prevent dusting; the rest, about 82.1 million m/sup 3/, is discharged into surface waters. Of this amount, 25.1 million m/sup 3/ is heavily polluted water, 46.6 million m3 are polluted but within limits, and 10.4 million m/sup 3/ are characterized as relatively clean. Waste water is polluted with: suspended matters, oils and oil products, nitrates, nitrides and chlorides. Suspended matter content sometimes reaches 4,000 and 5,000 mg/l, and oil product content in water amounts to 2.17 mg/l. Water treatment in surface mines is two-staged: sumps and sedimentation tanks are used. Water with suspended matter content of 50 to 100 mg/l in winter and summer, and 200 to 250 mg/l in spring and autumn is reduced in sumps to 25 to 30 mg/l in summer and winter and to 40 to 50 mg/l in autumn and spring. During the first stage water treatment efficiency ranges from 50 to 80%. During the second stage water is collected in sedimentation tanks. It is noted that so-called secondary pollution is one of the causes of the relatively high level of suspended matter in discharged water. Water discharged from sedimentation tanks carries clay and loam particles from the bottom and walls of water tanks and channels.

  3. Retrievable surface storage: interim storage of solidified high-level waste

    International Nuclear Information System (INIS)

    LaRiviere, J.R.; Nelson, D.C.

    1976-01-01

    Studies have been conducted on retrievable-surface-storage concepts for the interim storage of solidified high-level wastes. These studies have been reviewed by the Panel on Engineered Storage, convened by the Committee on Radioactive Waste Management of the National Research Council-National Academy of Sciences. The Panel has concluded that ''retrievable surface storage is an acceptable interim stage in a comprehensive system for managing high-level radioactive wastes.'' The scaled storage cask concept, which was recommended by the Panel on Engineered Storage, consists of placing a canister of waste inside a carbon-steel cask, which in turn is placed inside a thick concrete cylinder. The waste is cooled by natural convection air flow through an annulus between the cask and the inner wall of the concrete cylinder. The complete assembly is placed above ground in an outdoor storage area

  4. Acidity of Lakes and Impoundments in North-Central Minnesota

    Science.gov (United States)

    Elon S. Verry

    1981-01-01

    Measurements of lake and impoundment pH for several years, intensive sampling within years, and pH-calcium plots verify normal pH levels and do not show evidence of changes due to acid precipitation. These data in comparison with general lake data narrow the northern Lake States area in which rain or snow may cause lake acidification.

  5. Site characterization design and techniques used at the Southern Shipbuilding Corporation site

    International Nuclear Information System (INIS)

    Mueller, J.P.; Geraghty, C.A.; Moore, G.W.; Mullins, J.R.

    1995-01-01

    The Southern Shipbuilding Corporation (SSC) site is an inactive barge/ship manufacturing and repair facility situated on approximately 54 acres in Slidell, St. Tammany Parish, Louisiana. Two unlined surface impoundments (North and South impoundments) are situated on the northwest portion of the site and are surrounded on three sides by Bayou Bonfouca. These impoundments are the sources of carcinogenic polynuclear aromatic hydrocarbon (CPAH) contamination at the site. Inadequate containment has resulted in the release of impoundment wastes into the bayou. To evaluate potential response alternatives for the site, an Engineering Evaluation/Cost Analysis (EE/CA) field investigation was conducted from July through October 1994. A two phase sampling approach was used in combination with innovative and traditional sampling techniques, field screening technologies, and exploitation of the visual characteristics of the waste to determine the extent of waste migration with limited off-site laboratory confirmation. A skid-mounted mobile drilling unit, secured to a specialized sampling platform designed for multiple applications, was used for collection of sediment cores from the bayou as well as tarry sludge cores from the impoundments. Field screening of core samples was accomplished on site using an organic vapor analyzer and a total petroleum hydrocarbon (TPH) field analyzer. Pollutants of concern include metals, cyanide, dioxin, and organic compounds. This paper presents details on the sampling design and characterization techniques used to accomplish the EE/CA field investigation

  6. Geomorphological assessment of sites and impoundments for the long term containment of uranium mill tailings in the Alligator Rivers Region

    International Nuclear Information System (INIS)

    East, T.J.

    1985-01-01

    Current and future research into the geomorphological processes likely to affect the long term containment of uranium mill tailings in the Alligator Rivers Region is directed at three main areas: identification of geomorphic hazards at proposed impoundment sites; determination of erosion rates on impoundment slopes; and prediction of patterns of fluvial dispersal of released tailings. Each necessitates consideration of present and future geomorphic processes. Process rates during the next few thousand years might be predictable by extrapolation of contemporary and past (i.e. Holocene) climates, sea-levels and depositional environments, evidence for which is preserved in the sedimentary record. In current projects, the Late Quarternary stratigraphy of Magela Creek are examined to provide data for modelling of present and future sedimentological processes. Site stability evaluation entails recognition of present and future geomorphic hazards at impoundment sites, and includes fluvial and hillslope erosion, extreme flood events and mass movements. The life of a tailings impoundment is further determined by the intensity of erosional processes acting upon its slopes and their cover materials. A knowledge of present and future erosion rates will allow the optimisation of slope characteristics and materials in the impoundment design

  7. Coal waste slurries as a fuel for integrated gasification combined cycle plants

    Directory of Open Access Journals (Sweden)

    Lutynski Marcin A.

    2016-01-01

    Full Text Available The article summarizes recent development in integrated gasification combined cycle technology and lists existing and planned IGCC plants. A brief outlook on the IGCC gasification technology is given with focus on entrained-flow gasifiers where the low-quality coal waste slurry fuel can be used. Desired properties of coal and ash for entrained-flow gasifiers are listed. The coal waste slurries, which were deposited at impoundments in Upper Silesian Coal Basin, were considered as a direct feed for such gasifiers. The average ash content, moisture content and lower heating value were analysed and presented as an average values. Entrained-flow commercial gasifiers can be considered as suitable for the coal slurry feed, however the ash content of coal slurries deposited in impoundments is too high for the direct use as the feed for the gasifiers. The moisture content of slurries calculated on as received basis meets the requirements of entrained-flow slurry feed gasifiers. The content of fines is relatively high which allow to use the slurries in entrained-flow gasifiers.

  8. Surface layer effects on waste glass corrosion

    International Nuclear Information System (INIS)

    Feng, X.

    1993-01-01

    Water contact subjects waste glass to chemical attack that results in the formation of surface alteration layers. Two principal hypotheses have been advanced concerning the effect of surface alteration layers on continued glass corrosion: (1) they act as a mass transport barrier and (2) they influence the chemical affinity of the glass reaction. In general, transport barrier effects have been found to be less important than affinity effects in the corrosion of most high-level nuclear waste glasses. However, they can be important under some circumstances, for example, in a very alkaline solution, in leachants containing Mg ions, or under conditions where the matrix dissolution rate is very low. The latter suggests that physical barrier effect may affect the long-term glass dissolution rate. Surface layers influence glass reaction affinity through the effects of the altered glass and secondary phases on the solution chemistry. The reaction affinity may be controlled by various precipitates and crystalline phases, amorphous silica phases, gel layer, or all the components of the glass. The surface alteration layers influence radionuclide release mainly through colloid formation, crystalline phase incorporation, and gel layer retention. This paper reviews current understanding and uncertainties

  9. Effects of increased summer flooding on nitrogen dynamics in impounded mangroves

    NARCIS (Netherlands)

    Verhoeven, Jos T A; Laanbroek, Hendrikus J; Rains, Mark C; Whigham, Dennis F

    2014-01-01

    Mangroves are important for coastal protection, carbon sequestration and habitat provision for plants and animals in the tropics and subtropics. Mangroves are threatened by habitat destruction and sea level rise, but management activities such as impounding for mosquito control can also have

  10. Rock riprap design methods and their applicability to long-term protection of uranium mill tailings impoundments

    International Nuclear Information System (INIS)

    Walters, W.H.

    1982-08-01

    This report reviews the more accepted or recommended riprap design methods currently used to design rock riprap protection against soil erosion by flowing water. The basic theories used to develop the various methods are presented. The Riprap Design with Safety Factors Method is identified as the logical choice for uranium mill tailings impoundments. This method is compared to the other methods and its applicability to the protection requirements of tailings impoundments is discussed. Other design problems are identified and investigative studies recommended

  11. Effect of weir impoundments on methane dynamics in a river

    Czech Academy of Sciences Publication Activity Database

    Bednařík, A.; Blaser, M.; Matoušů, Anna; Hekera, P.; Rulík, M.

    2017-01-01

    Roč. 584, April (2017), s. 164-174 ISSN 0048-9697 R&D Projects: GA ČR(CZ) GA13-00243S Institutional support: RVO:60077344 Keywords : methane production * methane emission * methane ebullition * river impoundment * river sediment Subject RIV: DA - Hydrology ; Limnology OBOR OECD: Marine biology, freshwater biology, limnology Impact factor: 4.900, year: 2016

  12. Reestablishment of woody plants on mine spoils and management of mine water impoundments: an overview of Forest Service research on the northern High Plain

    Energy Technology Data Exchange (ETDEWEB)

    Bjugstad, A J

    1977-01-01

    The function of the research unit at Rapid city, S. Dakota, is to provide guidelines for the reestablisment of shrubs and trees on land characteristic of the High Plains, and for the mitigation of possible detrimental effects of surface mining on ground water and surface water. One possible problem posed by surface mining concerns the formation of land drainage patterns that could result in post-mining formations of large salt playas. Surface mining could affect shallow ground water aquifers up to /sup 1///sub 4/ mile from the mine site. Research is being conducted on the reclamation of mine spoils and on the rehabilitation and management of impounded mine water.

  13. Design surface covers: an approach to long-term waste site stabilization

    International Nuclear Information System (INIS)

    Beedlow, P.A.; Cadwell, L.L.; McShane, M.C.

    1983-02-01

    The wide range of existing environmental conditions, potential contaminants and available cover materials at waste disposal sites necessitates site-specific designing of surface covers for effective long-term erosion resistance. This paper presents a systematic approach to designing surface covers for hazardous waste repositories that can be tailored to conditions at any site. The approach consists of three phases: (1) an assessment, during which the degree of required surface protection (erosion potential) is determined; (2) a preliminary design that integrates surface cover design with the need to minimize transport of contaminants; and (3) a final design, where the cost and effectiveness of the surface cover are determined. 1 figure

  14. Hazardous waste landfill research: U. S. E. P. A. (United States Environmental Protection Agency) Program

    Energy Technology Data Exchange (ETDEWEB)

    Schomaker, N.B.

    1984-06-01

    The hazardous waste land disposal research program is collecting data necessary to support implementation of disposal guidelines mandated by the 'Resource Conservation and Recovery Act of 1976' (RCRA) PL 94-580. This program relating to the categorical areas of landfills, surface impoundments, and underground mines encompasses state-of-the-art documents, laboratory analysis, economic assessment, bench and pilot studies, and full-scale field verification studies. Over the next five years the research will be reported as Technical Resource Documents in support of the RCRA Guidance Documents. These documents will be used to provide guidance for conducting the review and evaluation of land disposal permit applications. This paper will present an overview of this program and will report the current status of the work.

  15. The fish community of a small impoundment in upstate New York

    Science.gov (United States)

    McCoy, C. Mead; Madenjian, Charles P.; Adams, Jean V.; Harman, Willard N.

    2001-01-01

    Moe Pond is a dimictic impoundment with surface area of 15.6 ha, a mean depth of 1.8 m, and an unexploited fish community of only two species: brown bullhead (Ameiurus nebulosus) and golden shiner (Notemigonus crysoleucas). The age-1 and older brown bullhead population was estimated to be 4,057 individuals, based on the Schnabel capture-recapture method of population estimation. Density and biomass were respectively estimated at 260 individuals/ha and 13 kg/ha. Annual survival rate of age-2 through age-5 brown bullheads was estimated at 48%. The golden shiner length-frequency distribution was unimodal with modal length of 80 mm and maximum total length of 115 m. The golden shiner population estimate was 7,154 individuals, based on seven beach seine haul replicate samples; the density and biomass were 686 shiners/ha and 5 kg/ha, respectively. This study provides an information baseline that may be useful in understanding food web interactions and whole-pond nutrient flux.

  16. Effect of solid waste landfill on underground and surface water ...

    African Journals Online (AJOL)

    Effect of solid waste landfill on underground and surface water quality at ring road, Ibadan, Nigeria. ... parameters showed increased concentrations over those from control sites. ... Keywords: Landfill, groundwater, surface-water, pollution.

  17. Modelling of contaminant migration in acidic groundwater plumes at uranium tailings impoundments: ADNEUT3

    International Nuclear Information System (INIS)

    Cherry, J.A.; Morin, K.A.; Dubrovsky, N.M.

    1984-06-01

    This report describes the creation and application of ADNEUT3, the latest addition to the ADNEUT (Acid-Drainage NEUTralization) family of computer programs for simulating acid-drainage transport and neutralization. The creation of ADNEUT3 involved the expansion of ADNEUT1 to allow variable input conditions such as changing input solution with time, variable initial amounts of minerals through the simulated streamtube, variable velocities through the streamtube, and variable solubilities for relevant minerals dependent on aqueous chemical composition. Concepts for simulating acid-drainage neutralization are reviewed and ADNEUT3 is then applied to a field-study site of acidic contaminant migration from the Nordic Main uranium-tailings impoundment near Elliot Lake, Ontario. A sensitivity study is first implemented to calibrate ADNEUT3 to the results of the 1979 to 1983 field studies. Then ADNEUT3 is used to define probable past conditions at the site which are not reliably known. In particular, ADNEUT3 is used to help identify: 1) the approximate year when acidic seepage began leaving the tailings impoundment (1966-1967), 2) the past chemical composition of the seepage (somewhat more acidic for a short period of time), and 3) the location of the source area within the tailings for the acidic seepage (near the impoundment dam, close to the field site). Finally, ADNEUT3 is used to predict future contaminant migration. Results indicate that hundreds of years are required under present conditions for the most acidic water with associated high levels of contaminants to migrate about 100 m from the tailings impoundment. The cause of this slow movement is the significant neutralization capacity of the aquifer. If acid production within the tailings decreases in the future, migration rates of contaminants will also decrease

  18. Low-waste electrochemical decontamination of stainless-steel surface

    International Nuclear Information System (INIS)

    Babain, V.A.; Smirnov, I.V.; Shadrin, A.Yu.; Firsin, N.G.; Zakharchuk, G.A.; Pavlov, A.B.; Shilov, V.V.

    2002-01-01

    An electrochemical decontamination method using a formic acid-based recycling electrolyte was proposed to remove firmly fixed contaminants from stainless-steel surfaces. The following provisions make for minimisation of the amounts of waste: (i) use of specially designed electrodes with vacuum removal of spent electrolyte; (ii) inter-cycle removal of radionuclides from the electrolyte by using an inorganic sorbent; (iii) periodic regeneration of the spent electrolyte. the dissolved metals (Fe, Cr, Ni) being transformed into acidic phosphates; (iv) solidification of residues arising from the regeneration of the electrolyte and spent sorbent into iron-phosphate ceramics. The technology and equipment developed were used for decontamination of a plutonium glove-box. The level of surface contamination was reduced 100-fold in two decontamination cycles. The depth of metal skimming was 1.5 μ for the ceiling and walls and 4.5 μ for the table top. Each square meter of stainless-steel surface provides about 100 g of solid radioactive waste in the form of iron-phosphate ceramic blocks

  19. Mine waste disposal and managements

    Energy Technology Data Exchange (ETDEWEB)

    Cheong, Young Wook; Min, Jeong Sik; Kwon, Kwang Soo; Kim, Ok Hwan; Kim, In Kee; Song, Won Kyong; Lee, Hyun Joo [Korea Institute of Geology Mining and Materials, Taejon (Korea)

    1998-12-01

    Acid Rock Drainage (ARD) is the product formed by the atmospheric oxidation of the relatively common pyrite and pyrrhotite. Waste rock dumps and tailings containing sulfide mineral have been reported at toxic materials producing ARD. Mining in sulphide bearing rock is one of activity which may lead to generation and release of ARD. ARD has had some major detrimental affects on mining areas. The purpose of this study was carried out to develop disposal method for preventing contamination of water and soil environment by waste rocks dump and tailings, which could discharge the acid drainage with high level of metals. Scope of this study was as following: environmental impacts by mine wastes, geochemical characteristics such as metal speciation, acid potential and paste pH of mine wastes, interpretation of occurrence of ARD underneath tailings impoundment, analysis of slope stability of tailings dam etc. The following procedures were used as part of ARD evaluation and prediction to determine the nature and quantities of soluble constituents that may be washed from mine wastes under natural precipitation: analysis of water and mine wastes, Acid-Base accounting, sequential extraction technique and measurement of lime requirement etc. In addition, computer modelling was applied for interpretation of slope stability od tailings dam. (author). 44 refs., 33 tabs., 86 figs.

  20. Reestablishing the Dominance of Biogeochemical Pathways for Reducing Downstream Nutrient Losses from Aged Impounded Features

    Science.gov (United States)

    Shukla, S.; Shukla, A.

    2017-12-01

    Water and phosphorus (P) dynamics and loss pathways at two stormwater impoundments (SIs) were analyzed using measured fluxes between 2008 and 2011. These SIs are a decade old. Analyses of water and P budgets along with the discernment of various P pools and characterization of the intermediary processes revealed that soil adsorption and plant uptake are secondary to volume reduction apropos of P treatment. At one site, extreme wet conditions in a year combined with soil P saturation resulted in it being a P source rather than a sink. The impoundment (SI-1) discharged 12% more P than incoming due to soil P desorption, a consequence of dilution of incoming stormwater with large water input from an extreme tropical rain event. The second impoundment (SI-2) was a consistent sink of P; 55% and 95% of the incoming total P was retained in the two years, mainly as a result of 49% and 84% volume retention, respectively. Analysis of plant available aluminum, iron, and phosphorus showed the surface soil to be P saturated and at risk of releasing P to a limit of environmental concern. These results when seen in light of more frequent extreme precipitation events under the changed climate scenario call for alternatives to revive the role of biogeochemical processes in P treatment because volume reduction may not always be the viable option, especially for wet conditions. Aboveground biomass harvesting and removal was evaluated to transform the SIs from a frequent P source to sink and maintain the long-term sink functions of the SIs. Use of harvested biomass as a source of nutrients (N and P) and carbon to agricultural soil can result in beneficial use of biomass and offset the cost of harvesting. Other avenues such as altering the hydrology of the SIs by compartmentalizing the system and increasing the storage were also explored for short-term benefits. Results provided a combination of hydraulic and biochemical options for achieving long-term water and nutrient retentions in

  1. Derivation of activity limits for the disposal of radioactive waste in near surface disposal facilities

    International Nuclear Information System (INIS)

    2003-12-01

    Radioactive waste must be managed safely, consistent with internationally agreed safety standards. The disposal method chosen for the waste should be commensurate with the hazard and longevity of the waste. Near surface disposal is an option used by many countries for the disposal of radioactive waste containing mainly short lived radionuclides and low concentrations of long lived radionuclides. The term 'near surface disposal' encompasses a wide range of design options, including disposal in engineered structures at or just below ground level, disposal in simple earthen trenches a few metres deep, disposal in engineered concrete vaults, and disposal in rock caverns several tens of metres below the surface. The use of a near surface disposal option requires design and operational measures to provide for the protection of human health and the environment, both during operation of the disposal facility and following its closure. To ensure the safety of both workers and the public (both in the short term and the long term), the operator is required to design a comprehensive waste management system for the safe operation and closure of a near surface disposal facility. Part of such a system is to establish criteria for accepting waste for disposal at the facility. The purpose of the criteria is to limit the consequences of events which could lead to radiation exposures and in addition, to prevent or limit hazards, which could arise from non-radiological causes. Waste acceptance criteria include limits on radionuclide content concentration in waste materials, and radionuclide amounts in packages and in the repository as a whole. They also include limits on quantity of free liquids, requirements for exclusion of chelating agents and pyrophoric materials, and specifications of the characteristics of the waste containers. Largely as a result of problems encountered at some disposal facilities operated in the past, in 1985 the IAEA published guidance on generic acceptance

  2. Decommissioning high-level waste surface facilities

    International Nuclear Information System (INIS)

    1978-04-01

    The protective storage, entombment and dismantlement options of decommissioning a High-Level Waste Surface Facility (HLWSF) was investigated. A reference conceptual design for the facility was developed based on the designs of similar facilities. State-of-the-art decommissioning technologies were identified. Program plans and cost estimates for decommissioning the reference conceptual designs were developed. Good engineering design concepts were on the basis of this work identified

  3. [Influence of 175-m-impoundment in Three Gorges Reservoir area on the food web energy sources of main commercial fishes in backwater area of xiaojiang River].

    Science.gov (United States)

    Li, Bin; Wang, Zhi-Jian; Yue, Xing-Jian; Wang, Yong-Ming; Jin, Li; Zhang, Yao-Guang

    2013-06-01

    The impoundment in the Three Gorges Reservoir Area (TGRA) was first reached 175 m in 2010. To approach the influence of this impoundment on the food web energy sources of fishes in the tributaries of TRGA, an analysis was made on the food web energy sources of seven economically important fishes (Carassius auratus, Cyprinus carpio, Silurus asotus, Culter mongolicus mongolicus, Mystus macropterus, Pelteobagrus vachelli, and Pelteobagrus nitidus) in the backwater area of Xiaojiang River by using stable isotope method in combining with IsoSource Model. The results showed that before this impoundment (July 2010), microalgae were the main energy sources for the seven species. After this impoundment (December 2010), the contribution ratio of the microalgae decreased somewhat, while the relative contribution of terrestrial C4 plants had an obvious increase. Especially for crucian carp (C. auratus) and catfish (S. asotus), the contribution rate of the C4 plants reached 38-54% and 32-50%, respectively. After the impoundment, at least 30% of the energy resources of these two fishes were come from terrestrial C4 plants, suggesting that the impoundment in TGRA increased the contribution rate of exogenous terrestrial C4 plants as the energy sources of fishes.

  4. Dose assessment of remedial action for uranium tailing impoundment of a nuclear factory

    International Nuclear Information System (INIS)

    Li Xutong; Ma Ruwei; Guo Zede

    2000-01-01

    A large uranium tailing impoundment in China will be closure and remedial action have been planned. The remedial action will include shaping and covering the dam and beach in order to prevent the impoundment from damage and restrict spread of tailing sands and emission of radon. The author presents the analysis and estimation of the exposure to workers for remedial action and to public after the remedial action. To estimate the exposure to workers, the pathway of inhalation of radon, tailing sands in suspension and external γ exposure were taken into consideration. The exposure scenario is considered as probably maximum exposure to the workers who work on the tailing pile without any protection measures, the dose is 6.0 mSv/a. Two situation for the exposure to public after remedial action were considered: normal and abnormal condition. For the normal condition, inhalation of radon emitted from impoundment is only the pathway to public for the exposure, and individual dose for critical group of public is 0.053 mSv/a, collective dose for population within 80 km is 1.0 man·Sv/a. For the abnormal conditions, four scenarios were considered, i.e. dwelling on tailing pile, farming on tailing pile, living in a house built by contaminated materials and some temporal activities on the pile. The scenarios of dwellings is living in a house on the pile and drinking contaminated water. The maximum individual dose is 27 mSv/a

  5. Processing method and processing device for liquid waste containing surface active agent and radioactive material

    International Nuclear Information System (INIS)

    Nishi, Takashi; Matsuda, Masami; Baba, Tsutomu; Yoshikawa, Ryozo; Yukita, Atsushi.

    1998-01-01

    Washing liquid wastes containing surface active agents and radioactive materials are sent to a deaerating vessel. Ozone is blown into the deaerating vessel. The washing liquid wastes dissolved with ozone are introduced to a UV ray irradiation vessel. UV rays are irradiated to the washing liquid wastes, and hydroxy radicals generated by photodecomposition of dissolved ozone oxidatively decompose surface active agents contained in the washing liquid wastes. The washing liquid wastes discharged from the UV ray irradiation vessel are sent to an activated carbon mixing vessel and mixed with powdery activated carbon. The surface active agents not decomposed in the UV ray irradiation vessel are adsorbed to the activated carbon. Then, the activated carbon and washing liquid wastes are separated by an activated carbon separating/drying device. Radioactive materials (iron oxide and the like) contained in the washing liquid wastes are mostly granular, and they are separated and removed from the washing liquid wastes in the activated carbon separating/drying device. (I.N.)

  6. Pre-treatment of bituminized NPP wastes for disposal in near-surface repository

    Energy Technology Data Exchange (ETDEWEB)

    Vieira, Vanessa Mota; Tello, Clédola Cássia Oliveira de, E-mail: vanessamotavieira@gmail.com, E-mail: tellocc@cdtn.br [Centro de Desenvolvimento da Tecnologia Nuclear (CDTN/CNEN-MG), Belo Horizonte, MG (Brazil)

    2017-07-01

    The implementation of the national repository is an important technical requirement, and a legal requirement for the entry into operation of the nuclear power plant Angra 3. The Brazilian repository is being planned to be a near-surface one. In Brazil the low and intermediate level radioactive wastes are immobilized using cement and bitumen for Angra 1 and Angra 2 NPP, respectively. The main problems due to the disposal of bituminized wastes in repositories are swelling of the waste products and their degradation in the long term. To accommodate the swelling of the bituminized wastes, the drums are filled up to 70 - 90% of their volume, which reduces the structural the repository stability and the disposal availability. Countries, which use bitumen in the solidification of NPP's radioactive waste and have near-surface repositories, need to immobilize this bituminized waste within other drums containing cement pastes or mortars to disposal them. This study aims to find solutions for the storage in surface repository of bituminized radioactive waste products, making them compatible with the acceptance criteria of cemented waste products. It was also performed a modeling with the results obtained in the leaching test using the ALT program and defined the transport model of the cesium leachate element and it was verified that in the early times the leaching was governed by the diffusion model and later by the partition model. The results obtained in this study can be used in the evaluation of performance of repositories. (author)

  7. Pre-treatment of bituminized NPP wastes for disposal in near-surface repository

    International Nuclear Information System (INIS)

    Vieira, Vanessa Mota; Tello, Clédola Cássia Oliveira de

    2017-01-01

    The implementation of the national repository is an important technical requirement, and a legal requirement for the entry into operation of the nuclear power plant Angra 3. The Brazilian repository is being planned to be a near-surface one. In Brazil the low and intermediate level radioactive wastes are immobilized using cement and bitumen for Angra 1 and Angra 2 NPP, respectively. The main problems due to the disposal of bituminized wastes in repositories are swelling of the waste products and their degradation in the long term. To accommodate the swelling of the bituminized wastes, the drums are filled up to 70 - 90% of their volume, which reduces the structural the repository stability and the disposal availability. Countries, which use bitumen in the solidification of NPP's radioactive waste and have near-surface repositories, need to immobilize this bituminized waste within other drums containing cement pastes or mortars to disposal them. This study aims to find solutions for the storage in surface repository of bituminized radioactive waste products, making them compatible with the acceptance criteria of cemented waste products. It was also performed a modeling with the results obtained in the leaching test using the ALT program and defined the transport model of the cesium leachate element and it was verified that in the early times the leaching was governed by the diffusion model and later by the partition model. The results obtained in this study can be used in the evaluation of performance of repositories. (author)

  8. Restoration of Tidal Flow to Impounded Salt Marsh Exerts Mixed Effect on Leaf Litter Decomposition

    Science.gov (United States)

    Henry, B. A.; Schade, J. D.; Foreman, K.

    2015-12-01

    Salt marsh impoundments (e.g. roads, levees) disconnect marshes from ocean tides, which impairs ecosystem services and often promotes invasive species. Numerous restoration projects now focus on removing impoundments. Leaf litter decomposition is a central process in salt marsh carbon and nutrient cycles, and this study investigated the extent to which marsh restoration alters litter decomposition rates. We considered three environmental factors that can potentially change during restoration: salinity, tidal regime, and dominant plant species. A one-month field experiment (Cape Cod, MA) measured decay of litter bags in impounded, restored, and natural marshes under ambient conditions. A two-week lab experiment measured litter decay in controlled incubations under experimental treatments for salinity (1ppt and 30 ppt), tidal regime (inundated and 12 hr wet-dry cycles), and plant species (native Spartina alterniflora and invasive Phragmites australis). S. alterniflora decomposed faster in situ than P. australis (14±1.0% mass loss versus 0.74±0.69%). Corroborating this difference in decomposition, S. alterniflora supported greater microbial respiration during lab incubation, measured as CO2 flux from leaf litter and biological oxygen demand of water containing leached organic matter (OM). However, nutrient analysis of plant tissue and leached OM show P. australis released more nitrogen than S. alterniflora. Low salinity treatments in both lab and field experiments decayed more rapidly than high salinity treatments, suggesting that salinity inhibited microbial activity. Manipulation of inundation regime did not affect decomposition. These findings suggest the reintroduction of tidal flow to an impounded salt marsh can have mixed effects; recolonization by the native cordgrass could supply labile OM to sediment and slow carbon sequestration, while an increase in salinity might inhibit decomposition and accelerate sequestration.

  9. Environmental assessment for the Radioactive and Mixed Waste Management Facility: Sandia National Laboratories/New Mexico

    International Nuclear Information System (INIS)

    1993-06-01

    The Department of Energy (DOE) has prepared an environmental assessment (EA) (DOE/EA-0466) under the National Environmental Policy Act (NEPA) of 1969 for the proposed completion of construction and subsequent operation of a central Radioactive and Mixed Waste Management Facility (RMWMF), in the southeastern portion of Technical Area III at Sandia National Laboratory, Albuquerque (SNLA). The RMWMF is designed to receive, store, characterize, conduct limited bench-scale treatment of, repackage, and certify low-level waste (LLW) and mixed waste (MW) (as necessary) for shipment to an offsite disposal or treatment facility. The RMWMF was partially constructed in 1989. Due to changing regulatory requirements, planned facility upgrades would be undertaken as part of the proposed action. These upgrades would include paving of road surfaces and work areas, installation of pumping equipment and lines for surface impoundment, and design and construction of air locks and truck decontamination and water treatment systems. The proposed action also includes an adjacent corrosive and reactive metals storage area, and associated roads and paving. LLW and MW generated at SNLA would be transported from the technical areas to the RMWMF in containers approved by the Department of Transportation. The RMWMF would not handle nonradioactive hazardous waste. Based on the analysis in the EA, the proposed completion of construction and operation of the RMWMF does not constitute a major Federal action significantly affecting the quality of the human environment within the meaning of NEPA. Therefore, preparation of an environmental impact statement for the proposed action is not required

  10. Near-surface storage facilities for vitrified high-level wastes

    International Nuclear Information System (INIS)

    Kondrat'ev, A.N.; Kulichenko, V.V.; Kryukov, I.I.; Krylova, N.V.; Paramoshkin, V.I.; Strakhov, M.V.

    1980-01-01

    Concurrently with the development of methods for solidifying liquid radioactive wastes, reliable and safe methods for the storage and disposal of solidified wastes are being devised in the USSR and other countries. One of the main factors affecting the choice of storage conditions for solidified wastes originating from the vitrification of high-level liquid wastes from fuel reprocessing plants is the problem of removing the heat produced by radioactive decay. In order to prevent the temperature of solidified wastes from exceeding the maximum permissible level for the material concerned, it is necessary to limit either the capacity of waste containers or the specific heat release of the wastes themselves. In order that disposal of high-level wastes in geological formations should be reliable and economic, solidified wastes undergo interim storage in near-surface storage facilities with engineered cooling systems. The paper demonstrates the relative influences of specific heat release, of the maximum permissible storage temperature for vitrified wastes and of the methods chosen for cooling wastes in order for the dimensions of waste containers to be reduced to the extent required. The effect of concentrating wastes to a given level in the vitrification process on the cost of storage in different types of storage facility is also examined. Calculations were performed for the amount of vitrified wastes produced by a reprocessing plant with a capacity of five tonnes of uranium per 24 hours. Fuel elements from reactors of the water-cooled, water-moderated type are sent for reprocessing after having been held for about two years. The dimensions of the storage facility are calculated on the assumption that it will take five years to fill

  11. Sharptooth catfish shows its metal: a case study of metal contamination at two impoundments in the Olifants River, Limpopo river system, South Africa.

    Science.gov (United States)

    Jooste, Antoinette; Marr, Sean M; Addo-Bediako, Abraham; Luus-Powell, Wilmien J

    2015-02-01

    Clarias gariepinus is increasing in importance as a global aquaculture species with a 100 fold increase in production over the past decade but this species still remains one of the most important wild harvested freshwater food fish throughout rural Africa. However, this species has been shown to accumulate metals from contaminated inland waters. In this paper, the metal concentrations in muscle tissue of C. gariepinus from two main-stem impoundments in the Olifants River, Limpopo Basin, were measured and a desktop risk assessment based on the US-EPA methodology completed to evaluate whether long-term consumption of C. gariepinus from these impoundments may pose a health risk to rural communities. Our results show that metals are accumulating in the muscle tissue of C. gariepinus and have appeared to have increased in the last two decades. Risk assessment generated Hazard quotients (HQ) greater than 1 indicate that long term consumption of fish from these impoundments may cause adverse health impacts. We found that lead (HQ=9), antimony (HQ=14), cobalt (HQ=2) and chromium (HQ=1) at one impoundment and lead (HQ=2) at the other impoundment were above acceptable levels for weekly consumption of 150 g C. gariepinus muscle tissue. Copyright © 2014 Elsevier Inc. All rights reserved.

  12. The management system for the disposal of radioactive waste. Safety guide

    International Nuclear Information System (INIS)

    2008-01-01

    The objective of this Safety Guide is to provide recommendations on developing and implementing management systems for all phases of facilities for the disposal of radioactive waste and related activities. It covers the management systems for managing the different stages of waste disposal facilities, such as siting, design and construction, operation (i.e. the activities, which can extend over several decades, involving receipt of the waste product in its final packaging (if it is to be disposed of in packaged form), waste emplacement in the waste disposal facility, backfilling and sealing, and any subsequent period prior to closure), closure and the period of institutional control (i.e. either active control - monitoring, surveillance and remediation; or passive control - restricted land use). The management systems apply to various types of disposal facility for different categories of radioactive waste, such as: near surface (for low level waste), geological (for low, intermediate and/or high level waste), boreholes (for sealed sources), surface impoundment (for mining and milling waste) and landfill (for very low level waste). It also covers management systems for related processes and activities, such as extended monitoring and surveillance during the period of active institutional control in the post-closure phase, safety and performance assessments and development of the safety case for the waste disposal facility and regulatory authorization (e.g. licensing). This Safety Guide is intended to be used by organizations that are directly involved in, or that regulate, the facilities and activities described in paras 1.15 and 1.16, and by the suppliers of nuclear safety related products that are required to meet some or all of the requirements established in IAEA Safety Standards Series No. GS-R-3 'The Management System for Facilities and Activities'. It will also be useful to legislators and to members of the public and other parties interested in the nuclear

  13. Impact of Water Recovery from Wastes on the Lunar Surface Mission Water Balance

    Science.gov (United States)

    Fisher, John W.; Hogan, John Andrew; Wignarajah, Kanapathipi; Pace, Gregory S.

    2010-01-01

    Future extended lunar surface missions will require extensive recovery of resources to reduce mission costs and enable self-sufficiency. Water is of particular importance due to its potential use for human consumption and hygiene, general cleaning, clothes washing, radiation shielding, cooling for extravehicular activity suits, and oxygen and hydrogen production. Various water sources are inherently present or are generated in lunar surface missions, and subject to recovery. They include: initial water stores, water contained in food, human and other solid wastes, wastewaters and associated brines, ISRU water, and scavenging from residual propellant in landers. This paper presents the results of an analysis of the contribution of water recovery from life support wastes on the overall water balance for lunar surface missions. Water in human wastes, metabolic activity and survival needs are well characterized and dependable figures are available. A detailed life support waste model was developed that summarizes the composition of life support wastes and their water content. Waste processing technologies were reviewed for their potential to recover that water. The recoverable water in waste is a significant contribution to the overall water balance. The value of this contribution is discussed in the context of the other major sources and loses of water. Combined with other analyses these results provide guidance for research and technology development and down-selection.

  14. 76 FR 9376 - Proposed Extension of Existing Information Collection;

    Science.gov (United States)

    2011-02-17

    ... Extension of Existing Information Collection; Refuse Piles and Impoundment Structures, Recordkeeping and... surface installations. More specifically, these sections address refuse piles (30 CFR 77.215), and... combination of materials; and refuse piles are deposits of coal mine waste (other than overburden or spoil...

  15. Geomorphological assessment of sites and impoundments for the long term containment of uranium mill tailings in the Alligator Rivers Region

    International Nuclear Information System (INIS)

    East, T.J.

    1986-01-01

    This paper presents a program of current and future research into those geomorphological processes likely to affect the long term containment of uranium mill tailings in the Alligator Rivers Region of the Northern Territory. Research is directed at three main areas: identification of geomorphic hazards at proposed impoundment sites; determination of erosion rates on impoundment slopes; and prediction of patterns of fluvial dispersal of released tailings. Each necessitates consideration of present and future geomorphic processes

  16. Liner used in tailings ponds

    International Nuclear Information System (INIS)

    Dinchak, W.G.

    1984-01-01

    A composite liner has been developed for use in hazardous waste impoundments and in tailings ponds where uranium is involved. The liner offers a high degree of reliability against seepage, is durable, and provides a firm working surface. The advantages of the liner are discussed

  17. Alternatives for the disposal of NORM [naturally occurring radioactive materials] wastes in Texas

    International Nuclear Information System (INIS)

    Nielson, K.K.; Rogers, V.C.; Pollard, C.G.

    1989-01-01

    Some of the Texas wastes containing naturally occurring radioactive materials (NORM) have been disposed of in a uranium mill tailings impoundment. There is currently no operating disposal facility in Texas to accept these wastes. As a result, some wastes containing extremely small amounts of radioactivity are sent to elaborate disposal sites at extremely high costs. The Texas Low-Level Radioactive Waste Disposal Authority has sponsored a study to investigate lower cost, alternative disposal methods for certain wastes containing small quantities of NORM. This paper presents the results of a multipathway safety analysis of various scenarios for disposing of wastes containing limited quantities of NORM in Texas. The wastes include pipe scales and sludges from oil and gas production, residues from rare-earth mineral processing, and water treatment resins, but exclude large-volume, diffuse wastes (coal fly ash, phosphogypsum). The purpose of the safety analysis is to define concentration and quantity limits for the key nuclides of NORM that will avoid dangerous radiation exposures under different waste disposal scenarios

  18. contaminant migration in a sand aquifer near an inactive uranium tailings impoundment, Elliot Lake, Ontario

    International Nuclear Information System (INIS)

    Morin, K.A.; Cherry, J.A.

    1982-01-01

    An investigation of the movement of contaminated groundwater from inactive uranium tailings through a sand aquifer is being conducted at the Nordic Main tailings impoundment near Elliot Lake, Ontario. During 1979 and 1980, multilevel bundle-type piezometers were installed at several locations around the edge of the tailings impoundment. Chemical analysis of water samples from the bundle piezometers indicate that a major contaminant plume extends outward through a sand aquifer from the southeastern part of the Nordic Main impoundment dam. In the vincinity of the contaminant plume, the sand aquifer varies in thickness from about 9 to 15 m. The plume has two distinct segments, referred to as the inner core and the outer zone. The inner core, which has a pH of 4.3-5.0 and extends about 15 m from the foot of the tailings dam, contains several grams per litre of iron and sulfate, and tens of pCi/L of 226 Ra and 210 Pb. Water levels in piezometers within the inner core show that groundwater is moving horizontally, away from the tailings impoundment, with a velocity of up to several hundred metres per year. The outer zone, which extends a few hundred metres downgradient from the dam, is characterized by hundreds to thousands of milligrams per litre of iron and sulfate, less than 15pCi/L of 226 Ra, and a pH greater than 5.7. Comparison of 1979 and 1980 data shows that the front of the inner core is advancing a few metres per year, which is less than a few percent of the groundwater velocity. This retardation of movement of the inner core is caused by neutralization of the acidic water as a result of dissolution of calcium carbonate in the sand. With the rise in pH, precipitation of iron carbonate and possibly some iron hydroxide occurs and the contaminants of main concern such as 226 Ra, 210 Pb, and uranium are removed from solution by adsorption or coprecipitation

  19. Treatment and utilization of waste waters of surface mines in Ukraine

    Energy Technology Data Exchange (ETDEWEB)

    Khmel' , N S

    1981-01-01

    Waste water of brown coal surface mines in the Dnieper basin is characterized. The water's pH value is 7, alkalinity ranges from 5.1 to 5.9 mg equivalent/1, it has no odor, a low mineralization level ranging from 1000 to 1100 mg/l. Concentration of mechanical impurities (suspended matter) ranges from 90 to 900 mg/l, and its maximum level can reach 5000 mg/l. An improved design of tanks in which waste water from surface mines is treated, and mechanical impurities settle, is proposed. Conventional design of a water sedimentation tank consists of a long ditch in which suspended matter settles, and a rectangular water reservoir at its end. In the improved version the long ditch is enlarged in some places to create additional tanks and to reduce velocity of flowing waste water. This improvement increases the amount of suspended matter which settles in the ditch and in its enlarged zones. When water reaches the rectangular sedimentation tank at the end of the system its suspended matter content is reduced to 40-45 mg/l. Formulae used to calculate dimensions of water treatment system, gradient of the ditch and size of sedimentation tank are presented. Methods of discharging treated waste water to surface water, rivers and stagnant waters, are evaluated. (In Russian)

  20. Near-surface facilities for disposal radioactive waste from non-nuclear application

    International Nuclear Information System (INIS)

    Barinov, A.

    2000-01-01

    The design features of the near-surface facilities of 'Radon', an estimation of the possible emergency situations, and the scenarios of their progress are given. The possible safety enhancing during operation of near-surface facilities, so called 'Historical facilities', and newly developed ones are described. The Moscow SIA 'Radon' experience in use of mobile module plants for liquid radioactive waste purification and principal technological scheme of the plant are presented. Upgrading of the technological scheme for treatment and conditioning of radioactive waste for new-developed facilities is shown. The main activities related to management of spent ionizing sources are mentioned

  1. Extended characterization of M-Area settling basin and vicinity. Technical data summary. Revision

    Energy Technology Data Exchange (ETDEWEB)

    Pickett, J B

    1985-10-01

    The Savannah River Plant M-Area settling basin, an unlined surface impoundment, has received process effluents from the M-Area fuel and target fabrication facilities since 1958. The waste effluents have contained metal degreasing agents (chlorinated hydrocarbons), acids, caustics, and heavy metals. Data analyses are provided.

  2. Installation Restoration Program. Phase 2. Confirmation McClellan AFB, California. Volume 1

    Science.gov (United States)

    1983-06-01

    testing in accordance with ASTH C 828-78 and in conformance with CAL/ OSHA safety orders and ES Industrial Sewer Entry Procedures. Indi- viduals entering...Liquid Palm Cil Wastes," Proceedings: Asia Acuatech, Singapore, Malaysia , March 1980 (Coauthors R. White and C. Ponniah). "Surface Impoundment of

  3. 40 CFR 445.1 - General applicability.

    Science.gov (United States)

    2010-07-01

    ... discharges from land application or land treatment units, surface impoundments, underground injection wells, waste piles, salt dome formations, salt bed formations, underground mines or caves as these terms are... ground water or wastewater from recovery pumping wells. (e) This part does not apply to discharges of...

  4. Use of special oedometer tests for the remediation of large uranium mill tailings impoundments at Wismut, Germany

    International Nuclear Information System (INIS)

    Barnekow, U.; Paul, M.

    2002-01-01

    The paper presents the use of recently developed special oedometer tests for designing the remediation of large uranium tailings ponds at WISMUT, Germany. Uranium ore mining and milling in eastern Germany by the former Soviet-German WISMUT company lasted from 1946 to 1990. Wastes from the hydrometallurgical uranium extraction processes were discharged into large tailings impoundments covering a total area of 5.5 km 2 and containing about 150 x 10 6 m 3 of uranium mill tailings. Tailings pond remediation is ongoing by in-place decommissioning with dewatering by technical means. Geotechnical properties and the most suitable so-called non-linear finite strain consolidation behaviour of fine uranium mill tailings are described. Decommissioning techniques comprise, among others, interim covering of under consolidated fine tailings, contouring of tailings surfaces and final covering. Contouring, in particular, has a huge potential for optimization in terms of cost reduction. For contouring total settlement portions, the spatial distribution of differential settlement portions and the time-dependent settlement rates, especially of the cohesive fine uranium mill tailings are of critical importance. A new special oedometer KD 314 S has been developed to generate all the input data needed to derive the fundamental geotechnical relationships of void ratio vs. effective stress and of permeability coefficient vs. void ratio for consolidation calculations. Since December 1999 the new special oedometer KD 314 S has been working successfully on fine uranium mill tailings from both acid and from soda alkaline milling. Results coincide with non-linear finite strain consolidation theory. The geotechnical functions derived were used as input parameters for consolidation modelling. An example of the consolidation modelling on Helmsdorf tailings pond is presented. (author)

  5. Arsenic mobility from anthropogenic impoundment sediments - Consequences of contamination to biota, water and sediments, Posa, Eastern Slovakia

    Energy Technology Data Exchange (ETDEWEB)

    Hiller, E.; Jurkovic, L.; Kordik, J.; Slaninka, I.; Jankular, M.; Majzlan, J.; Gottlicher, J.; Steininger, R. [Geological Survey of Slovak Republic, Bratislava (Slovakia). Dept. of Environmental Geochemistry

    2009-11-15

    An impoundment located near the village of Posa, Slovakia, is a significant source of contamination with As originating from the deposited coal fly-ash. Waters penetrating the impoundment are enriched in As and other potentially toxic elements. As a consequence of the contamination, the Kyjov Brook and the Ondava River have been extensively polluted. The mobility and solid-state partitioning of As in the impoundment material and stream sediments were investigated using column leaching and batch extraction tests, and a five-step sequential extraction procedure. Moreover, to investigate the bioavailability of As, two native plant species (Typha latifolia, or cattail, and Phragmites australis, or common reed) growing at the site were collected and analyzed. The As concentrations in representative sediment and water samples ranged from 36.3 to 3210 mg/kg and from 4.05 to 613 {mu} g/L, respectively, both being many times above the background levels. Although a part of As was present in a readily soluble form (6.6%), the majority of As was mainly associated with Fe and Mn oxides (37%) and residual phases (51%). Combined results of the column leaching, batch extraction, and sequential extraction tests, as well as mineralogical analysis, indicated that As mobilisation potential from the sediments is likely controlled by Fe, Al and Mn oxides, and by pH. There was no influence of various anions (PO{sub 4}{sup 3-}, SO{sub 4}{sup 2-}, NO{sup 3-}, Cl{sup -} and HCO{sub 3}{sup -}) on As mobility when present in aqueous solution at concentrations analogous to those in the water of the Kyjov Brook. Plants growing in the impoundment had As concentrations 10-100 times greater than did the same plants growing in a relatively non-polluted area.

  6. Hypersalinity reduces the risk of cyanide toxicosis to insectivorous bats interacting with wastewater impoundments at gold mines.

    Science.gov (United States)

    Griffiths, Stephen R; Donato, David B; Lumsden, Linda F; Coulson, Graeme

    2014-01-01

    Wildlife and livestock that ingest bioavailable cyanide compounds in gold mining tailings dams are known to experience cyanide toxicosis. Elevated levels of salinity in open impoundments have been shown to prevent wildlife cyanide toxicosis by reducing drinking and foraging. This finding appears to be consistent for diurnal wildlife interacting with open impoundments, however the risks to nocturnal wildlife of cyanide exposure are unknown. We investigated the activity of insectivorous bats in the airspace above both fresh (potable to wildlife) and saline water bodies at two gold mines in the goldfields of Western Australian. During this study, cyanide-bearing solutions stored in open impoundments at both mine sites were hypersaline (range=57,000-295,000 mg/L total dissolved solids (TDS)), well above known physiological tolerance of any terrestrial vertebrate. Bats used the airspace above each water body monitored, but were more active at fresh than saline water bodies. In addition, considerably more terminal echolocation buzz calls were recorded in the airspace above fresh than saline water bodies at both mine sites. However, it was not possible to determine whether these buzz calls corresponded to foraging or drinking bouts. No drinking bouts were observed in 33 h of thermal video footage recorded at one hypersaline tailings dam, suggesting that this water is not used for drinking. There is no information on salinity tolerances of bats, but it could be assumed that bats would not tolerate salinity in drinking water at concentrations greater than those documented as toxic for saline-adapted terrestrial wildlife. Therefore, when managing wastewater impoundments at gold mines to avoid wildlife mortalities, adopting a precautionary principle, bats are unlikely to drink solutions at salinity levels ≥50,000 mg/L TDS. © 2013 Published by Elsevier Inc.

  7. Evaluation of improved chemical waste disposal and recovery methods for N reactor fuel fabrication operations: 1984 annual report

    International Nuclear Information System (INIS)

    Stewart, T.L.; Hartley, J.N.

    1984-12-01

    Pacific Northwest Laboratory personnel identified and evaluated alternative methods for recovery, recycle, and disposal of waste acids produced during N Reactor fuel operations. This work was conducted under a program sponsored by UNC Nuclear Industries, Inc.; the program goals were to reduce the volume of liquid waste by rejuvenating and recycling acid solutions and to generate a residual waste low in nitrates, fluorides, and metals. Disposal methods under consideration included nitric acid reclamation, grout encapsulation of final residual waste, nitrogen fertilizer production, biodenitrifaction, chemical or thermal destruction of NO 3 , and short-term impoundment of liquid NO 3 /SO 4 wastes. Preliminary testing indicated that the most feasible and practicable of these alternatives were (1) nitric acid reclamation followed by grouting of residual waste and (2) nitrogen fertilizer production. This report summarizes the investigations, findings, and recommendations for the 1984 fiscal year

  8. Surface sealing systems for dumps and old waste sites. Oberflaechenabdichtungssysteme fuer Deponien und Altlasten

    Energy Technology Data Exchange (ETDEWEB)

    Egloffstein, T [ed.; ICP Ingenieurgesellschaft Prof. Czurda und Partner mbH, Karlsruhe (Germany); Burkhardt, G [ed.; ICP Ingenieurgesellschaft Prof. Czurda und Partner mbH, Karlsruhe (Germany)

    1994-01-01

    The primary task of surface lining is to prevent rainwater from seeping into the wastes deposited below the surface. Its function is therefore to seal the surface. Above the sealing layer there is a drainage system; if large amount of gas are generated (domestic wastes) the gas is channeled through a gas drainage layer. The top layer of the system serves as recultivation horizon for plants. The functions of the liner are: - sealing against precipitating water; - channeling off gas or - seepage water; - plant site. (orig./EF)

  9. Site characterization summary report for Waste Area Grouping 10 Wells at the Old Hydrofracture Facility, Oak Ridge National Laboratory, Oak Ridge, Tennessee

    International Nuclear Information System (INIS)

    1995-03-01

    The Oak Ridge National Laboratory (ORNL) in Oak Ridge, Tennessee, is operated for the Department of Energy (DOE) by Martin Marietta Energy Systems (Energy Systems). As part of its DOE mission, ORNL has pioneered waste disposal technologies throughout the years of site operations since World War II. In the late 1950s, efforts were made to develop a permanent disposal alternative to the surface impoundments at ORNL at the request of the National Academy of Sciences. One such technology, the hydrofracture process, involved forming fractures in an underlying geologic host formation (a low-permeability shale) at depths of up to 1000 ft and subsequently injecting a grout slurry containing low-level liquid waste, cement, and other additives at an injection pressure of about 2000 psi. The objective of the effort was to develop a grout slurry that could be injected as a liquid but would solidify after injection, thereby immobilizing the radioisotopes contained in the low-level liquid waste. The scope of this site characterization was the access, sampling, logging, and evaluation of observation wells near the Old Hydrofracture Facility (OHF) in preparation for plugging, recompletion, or other final disposition of the wells

  10. Scoping survey of perceived concerns, issues, and problems for near-surface disposal of FUSRAP waste

    International Nuclear Information System (INIS)

    Robinson, J.E.; Gilbert, T.L.

    1982-12-01

    This report is a scoping summary of concerns, issues, and perceived problems for near-surface disposal of radioactive waste, based on a survey of the current literature. Near-surface disposal means land burial in or within 15 to 20 m of the earth's surface. It includes shallow land burial (burial in trenches, typically about 6 m deep with a 2-m cap and cover) and some intermediate-depth land burial (e.g., trenches and cap similar to shallow land burial, but placed below 10 to 15 m of clean soil). Proposed solutions to anticipated problems also are discussed. The purpose of the report is to provide a better basis for identifying and evaluating the environmental impacts and related factors that must be analyzed and compared in assessing candidate near-surface disposal sites for FUSRAP waste. FUSRAP wastes are of diverse types, and their classification for regulatory purposes is not yet fixed. Most of it may be characterized as low-activity bulk solid waste, and is similar to mill tailings, but with somewhat lower average specific activity. It may also qualify as Class A segregated waste under the proposed 10 CFR 61 rules, but the parent radionuclides of concern in FUSRAP (primarily U-238 and Th-232) have longer half-lives than do the radionuclides of concern in most low-level waste. Most of the references reviewed deal with low-level waste or mill tailings, since there is as yet very little literature in the public domain on FUSRAP per se

  11. Pollution distribution of heavy metals in surface soil at an informal electronic-waste recycling site.

    Science.gov (United States)

    Fujimori, Takashi; Takigami, Hidetaka

    2014-02-01

    We studied distribution of heavy metals [lead (Pb), copper (Cu) and zinc (Zn)] in surface soil at an electronic-waste (e-waste) recycling workshop near Metro Manila in the Philippines to evaluate the pollution size (spot size, small area or the entire workshop), as well as to assess heavy metal transport into the surrounding soil environment. On-site length-of-stride-scale (~70 cm) measurements were performed at each surface soil point using field-portable X-ray fluorescence (FP-XRF). The surface soil at the e-waste recycling workshop was polluted with Cu, Zn and Pb, which were distributed discretely in surface soil. The site was divided into five areas based on the distance from an entrance gate (y-axis) of the e-waste recycling workshop. The three heavy metals showed similar concentration gradients in the y-axis direction. Zn, Pb and Cu concentrations were estimated to decrease to half of their maximum concentrations at ~3, 7 and 7 m from the pollution spot, respectively, inside the informal e-waste recycling workshop. Distance from an entrance may play an important role in heavy metal transport at the soil surface. Using on-site FP-XRF, we evaluated the metal ratio to characterise pollution features of the solid surface. Variability analysis of heavy metals revealed vanishing surficial autocorrelation over metre ranges. Also, the possibility of concentration prediction at unmeasured points using geostatistical kriging was evaluated, and heavy metals had a relative "small" pollution scales and remained inside the original workshop compared with toxic organohalogen compounds. Thus, exposure to heavy metals may directly influence the health of e-waste workers at the original site rather than the surrounding habitat and environmental media.

  12. Impacts of Freshwater Impoundment in the West Loch of Pearl Harbor

    Science.gov (United States)

    1993-05-01

    absence of applicable non-point standards, the "Yellow Book" criteria for freshwater aquatic life or domestic water supply could be applied to evaluate the...Waimalu, Waipahu, Wahiawa, and Ewa water use districts and contains the largest groundwater body on Oahu, supplying more than 50 percent of the island’s...irrigation; desalt existing brackish water supplies, and; 3 create a freshwater impoundment in West Loch. 6I I I The Board of Water Supply (BWS) and

  13. Eutrophication levels of some South African impoundments. IV. Vaal Dam

    CSIR Research Space (South Africa)

    Steyn, DJ

    1976-04-01

    Full Text Available inere;iae(l the \\G P In? between 7,1- and I 1,2 mg/r? lbr t?verv nile pet? t?t?ttt v/v) added_Nitrogen and phosphorus wert? the important algal growth?limiting ntltrients in the impoundment. Plant nntt-ients adsorbed onto clay particles could ht... stream_source_info Steyn2_1976.pdf.txt stream_content_type text/plain stream_size 20870 Content-Encoding ISO-8859-1 stream_name Steyn2_1976.pdf.txt Content-Type text/plain; charset=ISO-8859-1 Za~3n Abstract The Vital...

  14. Relationships among catch, angler catisfaction, and fish assemblage characteristics of an urban small impoundment fishery

    Science.gov (United States)

    Ivasauskas, Tomas J.; Xiong, Wilson N.; Engman, Augustin C.; Fischer, Jesse R.; Kwak, Thomas J.; Rundle, Kirk R.

    2017-01-01

    Urban fisheries provide unique angling opportunities for people from traditionally underrepresented demographics. Lake Raleigh is a 38-ha impoundment located on the North Carolina State University campus in Raleigh. Like many urban fisheries, little is known about angler use and satisfaction or how angling catch rate is related to fish availability in Lake Raleigh. We characterized the recreational fishery and fish assemblage with concurrent creel and boat electrofishing surveys over the course of one year. In total, 245 anglers were interviewed on 68 survey days. On average, anglers spent 1.7 h fishing per trip and caught 0.385 fish h –1. A large proportion of anglers (43.9%) targeted multiple species, whereas 36.5% targeted largemouth bass (Micropterus salmoides), 10.0% targeted panfish (i.e., sunfishes [Lepomis spp.] and crappies [Pomoxis spp.]), and 9.6% targeted catfish (Ameiurus spp. and Ictalurus spp.). Most anglers (69.4%) were satisfied with their experience, and overall satisfaction was unrelated to catch rate. Pulsed-DC boat electrofishing was conducted on 25 dates, and 617 fish were sampled. Angler catch rate was unrelated to electrofishing catch rate, implying that anglers' catch rate was independent of fish density or availability. Our results demonstrate that even minimally managed urban fisheries can provide high angler satisfaction, with limited dedication of management resources. Relationships Among Catch, Angler Satisfaction, and Fish Assemblage Characteristics of an Urban Small Impoundment Fishery (PDF Download Available). Available from: https://www.researchgate.net/publication/316636550_Relationships_Among_Catch_Angler_Satisfaction_and_Fish_Assemblage_Characteristics_of_an_Urban_Small_Impoundment_Fishery [accessed Aug 11, 2017].

  15. 40 CFR 265.1081 - Definitions.

    Science.gov (United States)

    2010-07-01

    ... captured vapors through a closed-vent system to a control device. External floating roof means a pontoon... move with fluctuations in the level of the material managed in the unit. Floating membrane cover means... hazardous waste being managed in a surface impoundment. Floating roof means a cover consisting of a double...

  16. Application of a modified electrochemical system for surface decontamination of radioactive metal waste

    International Nuclear Information System (INIS)

    Lee, J.H.; Lim, Y.K.; Yang, H.Y.; Shin, S.W.; Song, M.J.

    2003-01-01

    Conventional and modified electrolytic decontamination experiments were performed in a solution of sodium sulfate for the decontamination of carbon steel as the simulated metal wastes which are generated in large amounts from nuclear power plants. The effect of reaction time, current density and concentration of electrolytes in the modified electrolytic decontamination system were examined to remove the surface contamination of the simulated radioactive metal wastes. As for the results of this research, the modified electrochemical decontamination process can decontaminate more effectively than the conventional decontamination process by applying different anode material which causes higher induced electro-motive forces. When 0.5 M sodium sulfate, 0.4 A/cm 2 current density and 30 minutes reaction time were applied in the modified process, a 16 μm thickness change that is expected to remove most surface contamination in radioactive metal wastes was achieved on carbon steel which is the main material of radioactive metal waste in nuclear power plants. The decontamination efficiency of metal waste showed similar results with the small and large lab-scale modified electrochemical system. The application of this modified electrolytic decontamination system is expected to play a considerable role for decontamination of radioactive metal waste in nuclear power plants in the near future. (author)

  17. 40 CFR Appendix Vii to Part 268 - LDR Effective Dates of Surface Disposed Prohibited Hazardous Wastes

    Science.gov (United States)

    2010-07-01

    ... 40 Protection of Environment 26 2010-07-01 2010-07-01 false LDR Effective Dates of Surface Disposed Prohibited Hazardous Wastes VII Appendix VII to Part 268 Protection of Environment ENVIRONMENTAL... VII to Part 268—LDR Effective Dates of Surface Disposed Prohibited Hazardous Wastes Table 1—Effective...

  18. WasteChem Corporation's Volume Reduction and Solidification (VRS) system for low-level radwaste treatment: Final report

    International Nuclear Information System (INIS)

    1988-01-01

    Since 1965, low and medium level radwastes from nuclear power stations, reprocessing plants and nuclear research centers have been stabilized using the Volume Reduction and Solidification (VRS) system. The VRS system uses an extruder/evaporator to evaporate the liquids from waste influents, while simultaneously incorporating the remaining radioactive solids in an asphalt binder. In the period 1965 to 1986 a minimum of 700,000 cubic feet of wastes have been processed with the VRS system. This report provides current operating data from various systems including the volume reduction factors achieved, and the progress of start-ups in the US. The report also provides previously unpublished experience with mixed wastes including uranium raffinate and nitrate-bearing sludges from surface impoundments. VRS systems in the US are currently operating at the Palisades and Hope Creek nuclear stations. These systems produce a variety of waste types including boric acid, bead resin, sodium sulfate and powdered resins. There are three start-ups of VRS systems scheduled in the US in 1987. These systems are at Fermi 2, Seabrook, and Nine Mile Point 2. Overseas, the startup of new systems continues with three VRS process lines coming on-line at the LaHague Reprocessing Center in France in 1986 and a start-up scheduled for 1987 at the Laguna Verde plant in Mexico. The US systems are operating continuously and with little required maintenance. Data on maintenance and the operator exposure are provided in this report. 6 refs., 11 figs., 13 tabs

  19. Evaluation of factors related to increased zooplankton biomass and altered species composition following impoundment of a Newfoundland reservoir

    International Nuclear Information System (INIS)

    Campbell, C.E.; Knoechel, R.; Copeman, D.

    1998-01-01

    An 11-year study of the zooplankton community in Cat Arm Hydroelectric Reservoir in Newfoundland was conducted to assess long-term zooplankton community dynamics in a subarctic system. Zooplankton biomass and species compositions were monitored from 1983 to 1993. The monitoring program documented the trophic evolution of the Cat Arm system as it changed from a shallow lake with short water retention time to a deep reservoir with a much lower flushing rate. Zooplankton biomass increased approximately 19-fold in the oligotrophic hydroelectric reservoir following impoundment in 1984, relative to biomass in the preexisting lake. During the first three years of impoundment, there were no increases in either phytoplankton biomass or primary productivity. Natality of the dominant cladoceran (Daphnia catawba) did not increase. Summer water retention time increased from pre-impoundment levels of 4 days in 1983 to 338 days in 1993. The study showed that zooplankton biomass was greatly correlated with water retention time, and showed no major correlation with phytoplankton biomass, primary productivity, nutrient concentrations, pH, colour, or epilimnetic temperature. It was concluded that changes in the zooplankton community in the hydroelectric reservoir were a result of decreases in losses due to washout. 41 refs., 2 tabs., 6 figs

  20. A long-term comparison of carbon sequestration rates in impounded and naturally tidal freshwater marshes along the lower Waccamaw River, South Carolina

    Science.gov (United States)

    Drexler, Judith Z.; Krauss, Ken W.; Sasser, M. Craig; Fuller, Christopher C.; Swarzenski, Christopher M.; Powell, Amber; Swanson, Kathleen M.; Orlando, James L.

    2013-01-01

    Carbon storage was compared between impounded and naturally tidal freshwater marshes along the Lower Waccamaw River in South Carolina, USA. Soil cores were collected in (1) naturally tidal, (2) moist soil (impounded, seasonally drained since ~1970), and (3) deeply flooded “treatments” (impounded, flooded to ~90 cm since ~2002). Cores were analyzed for % organic carbon, % total carbon, bulk density, and 210Pb and 137Cs for dating purposes. Carbon sequestration rates ranged from 25 to 200 g C m−2 yr−1 (moist soil), 80–435 g C m−2 yr−1 (naturally tidal), and 100–250 g C m−2 yr−1 (deeply flooded). The moist soil and naturally tidal treatments were compared over a period of 40 years. The naturally tidal treatment had significantly higher carbon storage (mean = 219 g C m−2 yr−1 vs. mean = 91 g C m−2 yr−1) and four times the vertical accretion rate (mean = 0.84 cm yr−1 vs. mean = 0.21 cm yr−1) of the moist soil treatment. The results strongly suggest that the long drainage period in moist soil management limits carbon storage over time. Managers across the National Wildlife Refuge system have an opportunity to increase carbon storage by minimizing drainage in impoundments as much as practicable.

  1. Weathering behavior of mine tailings and waste rock: A surface investigation

    International Nuclear Information System (INIS)

    Domvile, S.J.; Li, M.G.; Sollner, D.D.; Nesbitt, W.

    1994-01-01

    A study focusing on the ion movement in the near surface of sulfide minerals was conducted to better understand the weathering mechanisms of mine waste materials. Tailings and waste rock samples from Canadian mines were subjected to controlled weathering studies using various chemical leachants. Leachates were analyzed for various parameters, and petrographic analyses were conducted on the solid residues. Laboratory oxidation studies of pure pyrrhotite and arsenopyrite were carried out using the surface techniques X-ray photoelectron spectroscopy (XPS) and auger electron spectroscopy (AES). The data derived from the weathering study and the surface techniques were correlated to determine mechanisms of oxidation. Several results were observed during the project: ferric iron constitutes one third of the iron present in pyrrhotite, sulfide oxidation is initiated when rock is blasted, sulfide sulfur is oxidized to di- and poly-sulfides prior to forming sulfates, and significantly more sulfate is produced upon exposure to aqueous environments than to air alone

  2. Environmental Geophysical Study for the Landfill Waste Disposal at Tenth of Ramadan City

    International Nuclear Information System (INIS)

    El-Hemamy, S.T.

    2006-01-01

    Tenth of Ramadan city is the onset of new industrial, reconstruction cities. It includes different kinds of industries (Heavy, medium and light industry). waste releases from these industries have different types (solid, liquid and gas). many industrial facilities produce hazardous waste such as toxic materials, heavy metals. therefore, there are three impoundments; each one lined by a clay layer to retain all hazards ions of the liquid waste, by time, liquid waste released increases with growth of industrial activities. for this reason there is a release of hazards ions appear in the aquifer. therefore, construction of disposal unit for those factories is mandatory. to fulfill this target the geologic and hydrogeologic conditions in the tenth of Ramadan area have been studied, to delineate the extension of the main aquifers and the effect of the subsurface structure of the area by using shallow seismic refraction and geoelectrical resistivity methods and aid of data of new drilled wells

  3. Hydrogeological aspects of radioactive waste disposal into surface formations

    International Nuclear Information System (INIS)

    Dlouhy, Z.

    1980-01-01

    Safe disposal is discussed of radioactive wastes in geological surface formations and basic criteria are shown of the radiological protection of population from possible effects of radioactive materials diffused in the environment. Main principles are listed governing the selection of suitable localities with respect to possible interactions of the locality and the storage site with the environment. (author)

  4. Autogenous Tumbling Media Assessment to Clean Weathered Surfaces of Waste-Rock Particles from a Basalt Quarry

    Directory of Open Access Journals (Sweden)

    Baran Tufan

    2015-06-01

    Full Text Available In this study, the optimum feed composition in autogenous tumbling of basalt waste-rock particles to clean their weathered surface was determined. The weathered surfaces of basalt are generally cut out consequent to extraction of basalt columns in quarry operations. The inefficiently cut out portions of basalt cause formation of huge quarry waste dumps causing visual pollution on roadsides. Mixtures of different particle size fractions of basalt waste-rock particles were experimented to achieve the optimum feed material composition. The minimum loss of commercially available basalt particles and maximum clear surface was intended. The results were compared with respect to weight loss (% and reflectance values of used and generated samples.

  5. Evaluation of behaviors of earth and rockfill dams during construction and initial impounding using instrumentation data and numerical modeling

    Directory of Open Access Journals (Sweden)

    Mohammad Rashidi

    2017-08-01

    Full Text Available In this study, the behavior of Gavoshan dam was evaluated during construction and the first impounding. A two-dimensional (2D numerical analysis was conducted based on a finite difference method on the largest cross-section of the dam using the results of instrument measurements and back analysis. These evaluations will be completed in the case that back analysis is carried out in order to control the degree of the accuracy and the level of confidence of the measured behavior since each of the measurements could be controlled by comparing it to the result obtained from the numerical model. Following that, by comparing the results of the numerical analysis with the measured values, it is indicated that there is a proper consistency between these two values. Moreover, it was observed that the dam performance was suitable regarding the induced pore water pressure, the pore water pressure ratio ru, settlement, induced stresses, arching degree, and hydraulic fracturing probability during the construction and initial impounding periods. The results demonstrated that the maximum settlement of the core was 238 cm at the end of construction. In the following 6 years after construction (initial impounding and exploitation period, the accumulative settlement of the dam was 270 cm. It is clear that 88% of the total settlement of the dam took place during dam construction. The reason is that the clay core was smashed in the wet side, i.e. the optimum moisture content. Whereas the average curving ratio was 0.64 during dam construction; at the end of the initial impounding, the maximum amount of curving ratio in the upstream was 0.81, and the minimum (critical amount in the downstream was 0.52. It was also concluded that this dam is safe in comparison with the behaviors of other similar dams in the world.

  6. A Two-Phase Cooling Loop for Fission Surface Power Waste Heat Transport, Phase I

    Data.gov (United States)

    National Aeronautics and Space Administration — Current lunar-based Fission Surface Power (FSP) Systems that will support sustained surface outposts consist of a nuclear reactor with power converters, whose waste...

  7. Waste-surface mapping of the Fernald K-65 silos using a structured light measurement system

    International Nuclear Information System (INIS)

    Burks, B.L.; DePiero, F.W.; Dinkins, M.A.; Rowe, J.C.; Selleck, C.B.; Jacoboski, D.L.

    1992-10-01

    A remotely operated surface-mapping measurement system was developed by the Robotics ampersand Process Systems Division at Oak Ridge National Laboratory for use in the K-65 waste-storage silos at Fernald, Ohio. The mapping system used three infrared line-generating laser diodes as illumination sources and three high-resolution, low-lux, calibrated, black-and-white, charge-coupled-device video cameras as receivers. These components were combined to form structured light source range and direction sensors with six different possible emitter-receiver pairs. A technology demonstration and predeployment tests were performed at Fernald using the empty Silo 4 into which was placed rectangular objects of known dimensions. These objects were scanned by the structured light sources to demonstrate functionality and verify that the system was giving sufficiently accurate range data in three dimensions. The structured light sources were deployed in Silos 1 and 2 to scan the waste surfaces. The resulting data were merged to create three-dimensional maps of those surfaces. A bentonite clay cap was placed over the waste surfaces and surface maps were obtained. The change in surface height before and after bentonite addition was utilized as a measure of clay cap thickness

  8. Occurrence of steroid hormones and antibiotics in shallow groundwater impacted by livestock waste control facilities

    Science.gov (United States)

    Bartelt-Hunt, Shannon; Snow, Daniel D.; Damon-Powell, Teyona; Miesbach, David

    2011-04-01

    Wastewater impoundments at concentrated animal feeding operations (CAFOs) represent a potential source of veterinary pharmaceuticals and steroid hormone contamination to shallow groundwater. This study investigates the occurrence of seventeen veterinary pharmaceuticals and thirteen steroid hormones and hormone metabolites in lagoons and adjacent groundwater at operating swine and beef cattle facilities. These sites were chosen because subsurface geology and previous monitoring of nitrate, ammonia and chloride levels in shallow ground water strongly indicated direct infiltration, and as such represent worst cases for ground water contamination by waste water. Pharmaceutical compounds detected in samples obtained from cattle facilities include sulfamerazine; sulfamethazine; erythromycin; monensin; tiamulin; and sulfathiazole. Lincomycin; ractopamine; sulfamethazine; sulfathiazole; erythromycin; tiamulin and sulfadimethoxine were detected in wastewater samples obtained from swine facilities. Steroid hormones were detected less frequently than veterinary pharmaceuticals in this study. Estrone, testosterone, 4-androstenedione, and androsterone were detected in wastewater impoundments at concentrations ranging from 30 to 3600 ng/L, while only estrone and testosterone were detected in groundwater samples at concentrations up to 390 ng/L. The co-occurrence of veterinary pharmaceutical and steroid hormone contamination in groundwater at these locations and the correlation between pharmaceutical occurrence in lagoon wastewater and hydraulically downgradient groundwater indicates that groundwater underlying some livestock wastewater impoundments is susceptible to contamination by veterinary pharmaceuticals and steroid hormones originating in wastewater lagoons.

  9. Occurrence of steroid hormones and antibiotics in shallow groundwater impacted by livestock waste control facilities.

    Science.gov (United States)

    Bartelt-Hunt, Shannon; Snow, Daniel D; Damon-Powell, Teyona; Miesbach, David

    2011-04-25

    Wastewater impoundments at concentrated animal feeding operations (CAFOs) represent a potential source of veterinary pharmaceuticals and steroid hormone contamination to shallow groundwater. This study investigates the occurrence of seventeen veterinary pharmaceuticals and thirteen steroid hormones and hormone metabolites in lagoons and adjacent groundwater at operating swine and beef cattle facilities. These sites were chosen because subsurface geology and previous monitoring of nitrate, ammonia and chloride levels in shallow ground water strongly indicated direct infiltration, and as such represent worst cases for ground water contamination by waste water. Pharmaceutical compounds detected in samples obtained from cattle facilities include sulfamerazine; sulfamethazine; erythromycin; monensin; tiamulin; and sulfathiazole. Lincomycin; ractopamine; sulfamethazine; sulfathiazole; erythromycin; tiamulin and sulfadimethoxine were detected in wastewater samples obtained from swine facilities. Steroid hormones were detected less frequently than veterinary pharmaceuticals in this study. Estrone, testosterone, 4-androstenedione, and androsterone were detected in wastewater impoundments at concentrations ranging from 30 to 3600ng/L, while only estrone and testosterone were detected in groundwater samples at concentrations up to 390ng/L. The co-occurrence of veterinary pharmaceutical and steroid hormone contamination in groundwater at these locations and the correlation between pharmaceutical occurrence in lagoon wastewater and hydraulically downgradient groundwater indicates that groundwater underlying some livestock wastewater impoundments is susceptible to contamination by veterinary pharmaceuticals and steroid hormones originating in wastewater lagoons. Copyright © 2010 Elsevier B.V. All rights reserved.

  10. Implications of long-term surface or near-surface storage of intermediate and low-level wastes in the UK

    International Nuclear Information System (INIS)

    Murray, N.; Vande Putte, D.; Ware, R.J.

    1986-02-01

    Various options for 200 year-long storage of all Low- and Intermediate-Level wastes generated to the year 2030 are considered. On-site storage and centralised storage have been examined and compared. The feasibility of storing some of the wastes in underground facilities that are convertible to repositories has been demonstrated, but it is shown that centralised, surface storage of wastes would be more economical. There appears to be little merit in storing Intermediate Level wastes in separate facilities that could be converted to repositories. Storage is shown to be more expensive than direct disposal, except if future costs are discounted by more than about 10%. With carefully designed stores and remote handling, the collective dose to operators could be limited to about 20-40 man Sv over the whole period of storage. (author)

  11. An overview of technical requirements on durable concrete production for near surface disposal facilities for radioactive wastes

    International Nuclear Information System (INIS)

    Tolentino, Evandro; Tello, Cledola Cassia Oliveira de

    2013-01-01

    Radioactive waste can be generated by a wide range of activities varying from activities in hospitals to nuclear power plants, to mines and mineral processing facilities. General public have devoted nowadays considerable attention to the subject of radioactive waste management due to heightened awareness of environmental protection. The preferred strategy for the management of all radioactive waste is to contain it and to isolate it from the accessible biosphere. The Federal Government of Brazil has announced the construction for the year of 2014 and operation for the year of 2016 of a near surface disposal facility for low and intermediate level radioactive waste. The objective of this paper is to provide an overview of technical requirements related to production of durable concrete to be used in near surface disposal facilities for radioactive waste concrete structures. These requirements have been considered by researchers dealing with ongoing designing effort of the Brazilian near surface disposal facility. (author)

  12. 2101-M pond closure plan. Volume 1, Revision 2

    Energy Technology Data Exchange (ETDEWEB)

    Izatt, R. D.; Lerch, R. E.

    1993-06-01

    This document describes activities for the closure of a surface impoundment (2101-M Pond) at the Hanford Site. The 2101-H Pond was initially constructed in 1953 to serve as a drainage collection area for the 2101-H Building. (Until the Basalt Waste Isolation Project (BWIP) Laboratory was constructed in the 2101-M Building in 1979--1981, the only source contributing discharge to the pond was condensate water from the 2101-H Building heating, ventilation, and air conditioning (HVAC) system. The drains for the BWIP Laboratory rooms were plumbed into a 4-in., cast-iron, low-pressure drain pipe that carries waste water from the HVAC system to the pond. During the active life of the BWIP Laboratory, solutions of dissolved barium in groundwater samples were discharged to the 2101-M Pond via the laboratory drains. As a result of the discharges, a Part A permit application was initially submitted to the Washington State Department of Ecology (Ecology) in August 1986 which designates the 2101-M Pond as a surface impoundment.

  13. 2101-M pond closure plan

    International Nuclear Information System (INIS)

    1993-06-01

    This document describes activities for the closure of a surface impoundment (2101-M Pond) at the Hanford Site. The 2101-H Pond was initially constructed in 1953 to serve as a drainage collection area for the 2101-H Building. (Until the Basalt Waste Isolation Project (BWIP) Laboratory was constructed in the 2101-M Building in 1979--1981, the only source contributing discharge to the pond was condensate water from the 2101-H Building heating, ventilation, and air conditioning (HVAC) system. The drains for the BWIP Laboratory rooms were plumbed into a 4-in., cast-iron, low-pressure drain pipe that carries waste water from the HVAC system to the pond. During the active life of the BWIP Laboratory, solutions of dissolved barium in groundwater samples were discharged to the 2101-M Pond via the laboratory drains. As a result of the discharges, a Part A permit application was initially submitted to the Washington State Department of Ecology (Ecology) in August 1986 which designates the 2101-M Pond as a surface impoundment

  14. [Effects of Three Gorges Reservoir impoundment on the wetland ecosystem service value of Dongting Lake, South-central China].

    Science.gov (United States)

    Li, Jing-Bao; Dai, Yong; Yin, Ri-Xin; Yang, Yan; Li, Yu-dan; Wang, Ke-ying

    2013-03-01

    Based on the field investigation and measurement, and by using the monetary method, this paper estimated the wetland ecosystem service value of Dongting Lake before and after the impoundment of Three Gorges Reservoir (in 1996 and 2010, respectively). After the impoundment, the total ecosystem service value increased from 156.69x10(8) yuan in 1996 to 177.11x10(8) yuan in 2010. The main services value in 1996 was in the order of flood storage and regulation > water storage and supply > air regulation > scientific research and education, while that in 2010 was leisure tourism > shipping transportation > air regulation > water storage and supply. In the total service value of the wetland ecosystem, the direct value associated with water decreased from 110. 85x10(8) in 1996 to 27.47x10(8) in 2010, with a decrement of 75.2%. Though the proportion of the direct value in the production and supply of material products had somewhat increase, the indirect value in ecological environment regulation and maintenance and in culture and society still maintained at about 80% of the total value. In addition to climate factors, the impoundment of Three Gorges Reservoir and the reduction of water and sediment from Yangtze River to the Lake were the crucial reasons leading to the changes of the wetland ecosystem service value of Dongting Lake.

  15. Modulation of Extreme Flood Levels by Impoundment Significantly Offset by Floodplain Loss Downstream of the Three Gorges Dam

    Science.gov (United States)

    Mei, Xuefei; Dai, Zhijun; Darby, Stephen E.; Gao, Shu; Wang, Jie; Jiang, Weiguo

    2018-04-01

    River flooding—the world's most significant natural hazard—is likely to increase under anthropogenic climate change. Most large rivers have been regulated by damming, but the extent to which these impoundments can mitigate extreme flooding remains uncertain. Here the catastrophic 2016 flood on the Changjiang River is first analyzed to assess the effects of both the Changjiang's reservoir cascade and the Three Gorges Dam (TGD), the world's largest hydraulic engineering project on downstream flood discharge and water levels. We show that the Changjiang's reservoir cascade impounded over 30.0 × 103 m3/s of flow at the peak of the flood on 25 July 2016, preventing the occurrence of what would otherwise have been the second largest flood ever recorded in the reach downstream of the TGD. Half of this flood water storage was retained by the TGD alone, meaning that impoundment by the TGD reduced peak water levels at the Datong hydrometric station (on 25 July) by 1.47 m, compared to pre-TGD conditions. However, downstream morphological changes, in particular, extensive erosion of the natural floodplain, offset this reduction in water level by 0.22 m, so that the full beneficial impact of floodwater retention by the TGD was not fully realized. Our results highlight how morphological adjustments downstream of large dams may inhibit their full potential to mitigate extreme flood risk.

  16. Geometrical and hydrogeological impact on the behaviour of deep-seated rock slides during reservoir impoundment

    Science.gov (United States)

    Lechner, Heidrun; Zangerl, Christian

    2015-04-01

    Given that there are still uncertainties regarding the deformation and failure mechanisms of deep-seated rock slides this study concentrates on key factors that influence the behaviour of rock slides in the surrounding of reservoirs. The focus is placed on the slope geometry, hydrogeology and kinematics. Based on numerous generic rock slide models the impacts of the (i) rock slide geometry, (ii) reservoir impoundment and level fluctuations, (iii) seepage and buoyancy forces and (iv) hydraulic conductivity of the rock slide mass and the basal shear zone are examined using limit equilibrium approaches. The geometry of many deep-seated rock slides in metamorphic rocks is often influenced by geological structures, e.g. fault zones, joints, foliation, bedding planes and others. With downslope displacement the rock slide undergoes a change in shape. Several observed rock slides in an advanced stage show a convex, bulge-like topography at the foot of the slope and a concave topography in the middle to upper part. Especially, the situation of the slope toe plays an important role for stability. A potentially critical situation can result from a partially submerged flat slope toe because the uplift due to water pressure destabilizes the rock slide. Furthermore, it is essential if the basal shear zone daylights at the foot of the slope or encounters alluvial or glacial deposits at the bottom of the valley, the latter having a buttressing effect. In this study generic rock slide models with a shear zone outcropping at the slope toe are established and systematically analysed using limit equilibrium calculations. Two different kinematic types are modelled: (i) a translational or planar and (ii) a rotational movement behaviour. Questions concerning the impact of buoyancy and pore pressure forces that develop during first time impoundment are of key interest. Given that an adverse effect on the rock slide stability is expected due to reservoir impoundment the extent of

  17. Tailings treatment techniques for uranium mill waste: a review of existing information

    International Nuclear Information System (INIS)

    Sherwood, D.R.; Serne, R.J.

    1983-07-01

    Of primary concern at uranium mill sites in the United States is the potential of ground-water contamination from mill wastes that are disposed in tailings impoundments. Although many systems have been used to control seepage from tailings impoundments, most of these systems are limited in their ability to handle an excess of tailings solution. Three general amelioration methods were identified: neutralization, fixation and specific constituent removal. During neutralization, a reagent is added to the tailings solution to neutralize the acidity and raise the pH to reduce the solubility of various pH sensitive contaminants. Fixation processes add materials such as lime, cement or asphalt to the waste to produce a physically stable composition that resists leaching of hazardous constituents. Specific constituent removal encompasses varying techniques, such as alternate ore leaching processes, effluent treatment with sorption, or ion exchange agents or selected precipitation that reduce specific constituent concentrations in tailings solution. Neutralization processes appear to be best suited for treating uranium mill tailings because they can, at a reasonable cost, limit the solution concentration of many contaminants. The effectiveness of the process depends on the reagent used as well as the waste being treated. Of the six reagents studied (lime, limestone, caustic soda, soda ash, combined limestone/lime and combined alumina/lime/soda), a combined treatment of limestone and lime seems best, especially for tailings containing ferric iron as the limestone economically buffers the solution acidity while the lime takes the pH to 8.0, an optimum level for heavy metal removal. For those tailings containing ferrous iron, lime alone works best. The costs for the lime/limestone or lime processes range from $0.20 to $1.00 per 1000 gal of treated water, excluding capital equipment costs

  18. Cyanobacteria and cyanotoxins are present in drinking water impoundments and groundwater wells in desert environments.

    Science.gov (United States)

    Chatziefthimiou, Aspassia D; Metcalf, James S; Glover, W Broc; Banack, Sandra A; Dargham, Soha R; Richer, Renee A

    2016-05-01

    Desert environments and drylands experience a drastic scarcity of water resources. To alleviate dependence on freshwater for drinking water needs, countries have invested in infrastructure development of desalination plants. Collectively, the countries of the Arabian Gulf produce 45% of the world's desalinated water, which is stored in dams, mega-reservoirs and secondary house water tanks to secure drinking water beyond daily needs. Improper storage practices of drinking water in impoundments concomitant with increased temperatures and light penetration may promote the growth of cyanobacteria and accumulation of cyanotoxins. To shed light on this previously unexplored research area in desert environments, we examined drinking and irrigation water of urban and rural environments to determine whether cyanobacteria and cyanotoxins are present, and what are the storage and transportation practices as well as the environmental parameters that best predict their presence. Cyanobacteria were present in 80% of the urban and 33% of the rural water impoundments. Neurotoxins BMAA, DAB and anatoxin-a(S) were not detected in any of the water samples, although they have been found to accumulate in the desert soils, which suggests a bioaccumulation potential if they are leached into the aquifer. A toxic BMAA isomer, AEG, was found in 91.7% of rural but none of the urban water samples and correlated with water-truck transportation, light exposure and chloride ions. The hepatotoxic cyanotoxin microcystin-LR was present in the majority of all sampled impoundments, surpassing the WHO provisional guideline of 1 μg/l in 30% of the urban water tanks. Finally, we discuss possible management strategies to improve storage and transportation practices in order to minimize exposure to cyanobacteria and cyanotoxins, and actions to promote sustainable use of limited water resources. Copyright © 2016 Elsevier Ltd. All rights reserved.

  19. Study of aquatic macroinvertebrate communities exposed to buckeye reclamation landfill drainage wastes

    International Nuclear Information System (INIS)

    Klemm, D.J.; Thoeny, W.T.; McCarthy, H.W.

    1995-01-01

    The Buckeye Reclamation Landfill (BRL), a Superfund site, incorporates approximately 50 acres of a 658 acre tract of land. The BRL consists of past underground mining voids, including some surface-mined lands, and mine refuse piles from processed bituminous coal. The area was subsequently used as a nonhazardous public and municipal solid waste landfill, and industrial sludge and liquid wastes were also deposited in an impoundment in the northern section of the landfill. The entire landfill area was completely covered with soil and revegetated in the late 1980's and early 1990's. The BRL produces acidic and highly mineralized drainage causing a widespread problem of serious mine drainage pollution in the watershed. A study was undertaken to assess the exposure of pollutants to the macroinvertebrate assemblages and to determine the extent of pollution of the BRL watershed. Samples were collected from ten sites in 1995. Nine systematic and spatial transect samples were taken at each collection site for macroinverbrates with a 595 microm mesh, modified kick net from riffle/run and glide/pool habitats of streams above and below the BRL watershed. All macroinverbrates were identified to the lowest taxonomic level possible. The levels for total Zn ranged from 22--604 microg/L; pH ranged from 4.4 to 8.1. The data distinguished the exposed sites receiving landfill leachates and sedimentation runoff from the less impacted sites

  20. Characterization of transient groundwater flow through a high arch dam foundation during reservoir impounding

    Directory of Open Access Journals (Sweden)

    Yifeng Chen

    2016-08-01

    Full Text Available Even though a large number of large-scale arch dams with height larger than 200 m have been built in the world, the transient groundwater flow behaviors and the seepage control effects in the dam foundations under difficult geological conditions are rarely reported. This paper presents a case study on the transient groundwater flow behaviors in the rock foundation of Jinping I double-curvature arch dam, the world's highest dam of this type to date that has been completed. Taking into account the geological settings at the site, an inverse modeling technique utilizing the time series measurements of both hydraulic head and discharge was adopted to back-calculate the permeability of the foundation rocks, which effectively improves the uniqueness and reliability of the inverse modeling results. The transient seepage flow in the dam foundation during the reservoir impounding was then modeled with a parabolic variational inequality (PVI method. The distribution of pore water pressure, the amount of leakage, and the performance of the seepage control system in the dam foundation during the entire impounding process were finally illustrated with the numerical results.

  1. National Enforcement Initiative: Preventing Animal Waste from Contaminating Surface and Ground Water

    Science.gov (United States)

    This page describes EPA's goal in preventing animal waste from contaminating surface and ground Water. It is an EPA National Enforcement Initiative. Both enforcement cases, and a map of enforcement actions are provided.

  2. Derivation of Waste Acceptance Criteria for Low and Intermediate Level Waste in Surface Disposal Facility

    International Nuclear Information System (INIS)

    Gagner, L.; Voinis, S.

    2000-01-01

    In France, low- and intermediate-level radioactive wastes are disposed in a near-surface facility, at Centre de l'Aube disposal facility. This facility, which was commissioned in 1992, has a disposal capacity of one million cubic meters, and will be operated up to about 2050. It took over the job from Centre de la Manche, which was commissioned in 1969 and shut down in 1994, after having received about 520,000 cubic meters of wastes. The Centre de l'Aube disposal facility is designed to receive a many types of waste produced by nuclear power plants, reprocessing, decommissioning, as well as by the industry, hospitals and armed forces. The limitation of radioactive transfer to man and the limitation of personnel exposure in all situations considered plausible require limiting the total activity of the waste disposed in the facility as well as the activity of each package. The paper presents how ANDRA has derived the activity-related acceptance criteria, based on the safety analysis. In the French methodology, activity is considered as end-point for deriving the concentration limits per package, whereas it is the starting point for deriving the total activity limits. For the concentration limits (called here LMA) the approach consists of five steps: the determination of radionuclides important for safety with regards to operational and long-term safety, the use of relevant safety scenarios as a tool to derive quantitative limits, the setting of dose constraint per situation associated with scenarios, the setting of contribution factor per radionuclide, and the calculation of concentration activity limits. An exhaustive survey has been performed and has shown that the totality of waste packages which should be delivered by waste generators are acceptable in terms of activity limits in the Centre de l'Aube. Examples of concentration activity limits derived from this methodology are presented. Furthermore those limits have been accepted by the French regulatory body and

  3. Vertical Drop of the Naval SNF Long Waste Package On Unyielding Surface

    International Nuclear Information System (INIS)

    S. Mastilovic

    2006-01-01

    The purpose of this calculation is to determine the structural response of a Naval SNF (Spent Nuclear Fuel) Long Waste Package (WP) subjected to 2 m-vertical drop on unyielding surface (US). The scope of this document is limited to reporting the calculation results in terms of maximum stress intensities. This calculation is associated with the waste package design; calculation is performed by the Waste Package Design group. AP-3.12Q, Revision 0, ICN 0, Calculations, is used to perform the calculation and develop the document. The finite element calculation is performed by using the commercially available ANSYS Version (V) 5.4 finite element code. The result of this calculation is provided in terms of maximum stress intensities

  4. Consideration of Criteria for a Conceptual Near Surface Radioactive Waste disposal Facility in Kenya

    Energy Technology Data Exchange (ETDEWEB)

    Nderitu, Stanley Werugia; Kim, Changlak [KEPCO International Nuclear Graduate School, Ulsan (Korea, Republic of)

    2014-05-15

    The purpose of the criteria is to limit the consequences of events which could lead to radiation exposures. This study will present an approach for establishing radiological waste acceptance criteria using a safety assessment methodology and illustrate some of its application in establishing limits on the total activity and the activity concentrations of radioactive waste to be disposed in a conceptual near surface disposal facility in Kenya. The approach will make use of accepted methods and computational schemes currently used in assessing the safety of near surface disposal facilities. The study will mainly focus on post-closure periods. The study will employ some specific inadvertent human intrusion scenarios in the development of example concentration ranges for the disposal of near-surface wastes. The overall goal of the example calculations is to illustrate the application of the scenarios in a performance assessment to assure that people in the future cannot receive a dose greater than an established limit. The specific performance assessments will use modified scenarios and data to establish acceptable disposal concentrations for specific disposal sites and conditions. Safety and environmental impacts assessments is required in the post-closure phase to support particular decisions in development, operation, and closure of a near surface repository.

  5. Organochlorine pesticide levels in Clarias gariepinus from polluted freshwater impoundments in South Africa and associated human health risks

    CSIR Research Space (South Africa)

    Barnhoorn, IEJ

    2014-02-01

    Full Text Available There are increasing concerns regarding the safe human consumption of fish from polluted, freshwater impoundments. The aim of this study was to analyse the muscle tissue of the sharptooth catfish Clarias gariepinus for selected organo-chlorine...

  6. Heavy metal contamination of surface soil in electronic waste dismantling area: site investigation and source-apportionment analysis.

    Science.gov (United States)

    Jinhui Li; Huabo Duan; Pixing Shi

    2011-07-01

    The dismantling and disposal of electronic waste (e-waste) in developing countries is causing increasing concern because of its impacts on the environment and risks to human health. Heavy-metal concentrations in the surface soils of Guiyu (Guangdong Province, China) were monitored to determine the status of heavy-metal contamination on e-waste dismantling area with a more than 20 years history. Two metalloids and nine metals were selected for investigation. This paper also attempts to compare the data among a variety of e-waste dismantling areas, after reviewing a number of heavy-metal contamination-related studies in such areas in China over the past decade. In addition, source apportionment of heavy metal in the surface soil of these areas has been analysed. Both the MSW open-burning sites probably contained invaluable e-waste and abandoned sites formerly involved in informal recycling activities are the new sources of soil-based environmental pollution in Guiyu. Although printed circuit board waste is thought to be the main source of heavy-metal emissions during e-waste processing, requirement is necessary to soundly manage the plastic separated from e-waste, which mostly contains heavy metals and other toxic substances.

  7. Conversion of a tailing impoundment to a freshwater reservoir, the Eagle Park Reservoir project, Climax Mine, Colorado

    Energy Technology Data Exchange (ETDEWEB)

    Romig, B.R.; Cupp, J.L.; Ford, R.C.

    1999-07-01

    The Climax Molybdenum Mine, located near Leadville, Colorado, is the site of a lengthy mining history spanning more than 80 years. In the 1960's, extraction of molybdenum from oxide ore located adjacent to the massive molybdenite sulfide deposit resulted in the construction of an earthen core dam to impound fine-grained oxide tailing in the Eagle River Valley. Through recognized value of water storage and reclamation opportunities, a tailing removal project was initiated in 1993 to convert the impoundment facilities to a post-mining beneficial land use of developed water resources. An evaluation of the effect residual materials and lake dynamics would have on in-stream water quality was performed. Eagle Park Reservoir stands as a model for future reclamation efforts that involve water delivery to highly sensitive receiving waters. This paper provides a case study on project development, the evolution of water quality assessment, and the regulatory framework that contributed to this project's success.

  8. French surface disposal experience. The disposal of large waste

    International Nuclear Information System (INIS)

    Dutzer, Michel; Lecoq, Pascal; Duret, Franck; Mandoki, Robert

    2006-01-01

    More than 90 percent of the volume of radioactive waste that are generated in France can be managed in surface disposal facilities. Two facilities are presently operated by ANDRA: the Centre de l'Aube disposal facility that is dedicated to low and intermediate short lived waste and the Morvilliers facility for very low level waste. The Centre de l'Aube facility was designed at the end of the years 1980 to replace the Centre de la Manche facility that ended operation in 1994. In order to achieve as low external exposure as possible for workers it was decided to use remote handling systems as much as possible. Therefore it was necessary to standardize the types of waste containers. But taking into account the fact that these waste were conditioned in existing facilities, it was not possible to change a major part of existing packages. As a consequence, 6 mobile roofs were constructed to handle 12 different types of waste packages in the disposal vaults. The scope of Centre de l'Aube was mainly to dispose operational waste. However some packages, as 5 or 10 m 3 metallic boxes, could be used for larger waste generated by decommissioning activities. The corresponding flow was supposed to be small. After the first years of operations, it appeared interesting to develop special procedures to dispose specific large waste in order to avoid external exposure costly cutting works in the generating facilities. A 40 m 3 box and a large remote handling device were disposed in vaults that were currently used for other types of packages. Such a technique could not be used for the disposal of vessel heads that were replaced in 55 pressurised water power reactors. The duration of disposal and conditioning operation was not compatible with the flow of standard packages that were delivered in the vaults. Therefore a specific type of vault was designed, including handling and conditioning equipment. The first pressure vessel head was delivered on the 29 of July 2004, 6 heads have been

  9. A generic model of contaminant migration from uranium tailings impoundments

    International Nuclear Information System (INIS)

    Shepherd, T.A.; Brown, S.E.

    1982-01-01

    This paper presents an analytical hydrogeochemical model based upon acid consumption-neutralization front movement. The development of contaminant plumes is discussed and distinct zones within these plumes are identified and characterized. The most important process influencing the rate and extent of contaminant migration at acid-leach uranium tailings impoundments is the neutralization of seepage water by soils along ground water flow paths. The chemical characteristics of the ground water is determined in order to identify and characterize zones within migrating plumes of tailings-derived water. It is concluded that the characterization of specific zones is useful in the interpretation of existing conditions, in the evaluation of future migration, and in the determination of appropriate models for the specific situation

  10. Synthesis of long live storage studies surface storage of MA-VL wastes

    International Nuclear Information System (INIS)

    Hollender, F.; Jourdain, F.; Piault, E.; Blanchet, Y.; Avakian, G.; Goger, F.; Caillaud, J.; Devictor, N.; Bary, B.; Moitier, C.; Breton, E.; Ranc, G.; Gaillard, J.P.; Lagrave, H.

    2004-01-01

    This document is realized in the framework of the axis 3 of the law of 1991 on the radioactive wastes management. It presents a long time surface storage installation of medium activity long life wastes. The long time of the installation would reach 300 years at the maximum. The feasibility is demonstrated and the design choices are presented and justified. The specific points of the long time storage installation, which are different from a classical industrial storage installation, are also discussed. (A.L.B.)

  11. Durability of simulated waste glass: effects of pressure and formation of surface layers

    International Nuclear Information System (INIS)

    Wicks, G.G.; Mosley, W.C.; Whitkop, P.G.; Saturday, K.A.

    1981-01-01

    The leaching behavior of simulated Savannah River Plant (SRP) waste glass was studied at elevated pressures and anticipated storage temperatures. An integrated approach, which combined leachate solution analyses with both bulk and surface studies, was used to study the corrosion process. Compositions of leachates were evaluated by colorimetry and atomic absorption. Used in the bulk and surface analyses were optical microscopy, scanning electron microscopy, x-ray energy spectroscopy, wide-angle x-ray, diffraction, electron microprobe analysis, infrared reflectance spectroscopy, electron spectroscopy for chemical analysis, and Auger electron spectroscopy. Results from this study show that there is no significant adverse effect of pressure, up to 1500 psi and 90 0 C, on the chemical durability of simulated SPR waste glass leached for one month in deionized water. In addition, the leached glass surface layer was characterized by an adsorbed film rich in minor constituents from the glass. This film remained on the glass surface even after leaching in relatively alkaline solutions at elevated pressures at 90 0 C for one month. The sample surface area to volume of leachant ratios (SA/V) was 10:1 cm -1 and 1:10 cm -1 . The corrosion mechanisms and surface and subsurface layers produced will be discussed along with the potential importance of these results to repository storage

  12. Maximum surface level and temperature histories for Hanford waste tanks

    International Nuclear Information System (INIS)

    Flanagan, B.D.; Ha, N.D.; Huisingh, J.S.

    1994-01-01

    Radioactive defense waste resulting from the chemical processing of spent nuclear fuel has been accumulating at the Hanford Site since 1944. This waste is stored in underground waste-storage tanks. The Hanford Site Tank Farm Facilities Interim Safety Basis (ISB) provides a ready reference to the safety envelope for applicable tank farm facilities and installations. During preparation of the ISB, tank structural integrity concerns were identified as a key element in defining the safety envelope. These concerns, along with several deficiencies in the technical bases associated with the structural integrity issues and the corresponding operational limits/controls specified for conduct of normal tank farm operations are documented in the ISB. Consequently, a plan was initiated to upgrade the safety envelope technical bases by conducting Accelerated Safety Analyses-Phase 1 (ASA-Phase 1) sensitivity studies and additional structural evaluations. The purpose of this report is to facilitate the ASA-Phase 1 studies and future analyses of the single-shell tanks (SSTs) and double-shell tanks (DSTs) by compiling a quantitative summary of some of the past operating conditions the tanks have experienced during their existence. This report documents the available summaries of recorded maximum surface levels and maximum waste temperatures and references other sources for more specific data

  13. Dynamics of dissolved organic matter in riverine sediments affected by weir impoundments: Production, benthic flux, and environmental implications.

    Science.gov (United States)

    Chen, Meilian; Kim, Sung-Han; Jung, Heon-Jae; Hyun, Jung-Ho; Choi, Jung Hyun; Lee, Hyo-Jin; Huh, In-Ae; Hur, Jin

    2017-09-15

    In order to understand the characteristics and dynamics of dissolved organic matter (DOM) in the sediment of rivers affected by impoundments, we examined the vertical profiles and the benthic fluxes of DOM in four different core sediments located at upstream sites of weirs in major rivers of South Korea. In three out of four sites, exponential accumulation of dissolved organic carbon (DOC) with depth was observed with the signature of seasonal variability. Except for the site displaying a below-detection limit of Fe(II), the general accumulation trends of DOC with depth was concurrent with the increases of Fe(II) and NH 4 + and the decrease of PO 4 3- , signifying a close linkage of the DOM dynamics with anaerobic respiration via iron reduction, an important early diagenesis pathway. The estimated benthic fluxes from the cores revealed that the sediments likely serve as DOC, chromophoric DOM (CDOM), and fluorescent DOM (FDOM) sources to the overlying water. The benthic effluxes based on DOC were comparable to the ranges previously reported in lake and coastal areas, and those of CDOM and FDOM showed even higher levels. These findings imply that impoundment-affected river systems would change the DOM composition of the overlying water, ultimately influencing the subsequent water treatment processes such as disinfection byproducts production and membrane fouling. A simple mass balance model indicated that the impoundment-affected river sediments may operate as a net carbon sink in the environments due to a greater extent of sedimentation compared to the estimated benthic efflux and sediment biological respiration. Copyright © 2017 Elsevier Ltd. All rights reserved.

  14. Direct Measurement of Surface Dissolution Rates in Potential Nuclear Waste Forms: The Example of Pyrochlore.

    Science.gov (United States)

    Fischer, Cornelius; Finkeldei, Sarah; Brandt, Felix; Bosbach, Dirk; Luttge, Andreas

    2015-08-19

    The long-term stability of ceramic materials that are considered as potential nuclear waste forms is governed by heterogeneous surface reactivity. Thus, instead of a mean rate, the identification of one or more dominant contributors to the overall dissolution rate is the key to predict the stability of waste forms quantitatively. Direct surface measurements by vertical scanning interferometry (VSI) and their analysis via material flux maps and resulting dissolution rate spectra provide data about dominant rate contributors and their variability over time. Using pyrochlore (Nd2Zr2O7) pellet dissolution under acidic conditions as an example, we demonstrate the identification and quantification of dissolution rate contributors, based on VSI data and rate spectrum analysis. Heterogeneous surface alteration of pyrochlore varies by a factor of about 5 and additional material loss by chemo-mechanical grain pull-out within the uppermost grain layer. We identified four different rate contributors that are responsible for the observed dissolution rate range of single grains. Our new concept offers the opportunity to increase our mechanistic understanding and to predict quantitatively the alteration of ceramic waste forms.

  15. Safety assessment of near surface radioactive waste disposal facilities: Model intercomparison using simple hypothetical data (Test Case 1). First report of NSARS. Part of the co-ordinated research programme on the safety assessment of near surface radioactive waste disposal facilities (NSARS)

    International Nuclear Information System (INIS)

    1995-11-01

    In many countries near surface disposal is the preferred option for the comparatively large volumes of low and intermediate level wastes which arise during nuclear power plant operations, nuclear fuel reprocessing and also for the wastes arising from radionuclide applications in hospitals and research establishments. Near surface disposal is also widely practised in the case of hazardous wastes from chemical industries. It is obviously necessary to show that waste disposal methods are safe and that both man and the environment will be adequately protected. Following a previous related Co-ordinated Research Programme (CRP) on ''Migration and Biological Transfer of Radionuclides from Shallow Land Burial'' during 1985 to 1989 (IAEA-TECDOC-579, Vienna, 1990), the issue of reliability of safety assessments was identified as an important topic for further support and development. A new CRP was formulated with the acronym NSARS (Near Surface Radioactive Waste Disposal Safety Assessment Reliability Study). This technical document is the first report of from the CRP and contains the intercomparison of results of the first test exercise (Test Case 1) on modelling of potential radiation exposures as a result of near surface disposal. Test Case 1 is based on entirely hypothetical data and includes consideration of exposures due to leaching and as a result of human intrusion into the site. Refs, figs and tabs

  16. Safety assessment of near surface radioactive waste disposal facilities: Model intercomparison using simple hypothetical data (Test Case 1). First report of NSARS. Part of the co-ordinated research programme on the safety assessment of near surface radioactive waste disposal facilities (NSARS)

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1995-11-01

    In many countries near surface disposal is the preferred option for the comparatively large volumes of low and intermediate level wastes which arise during nuclear power plant operations, nuclear fuel reprocessing and also for the wastes arising from radionuclide applications in hospitals and research establishments. Near surface disposal is also widely practised in the case of hazardous wastes from chemical industries. It is obviously necessary to show that waste disposal methods are safe and that both man and the environment will be adequately protected. Following a previous related Co-ordinated Research Programme (CRP) on ``Migration and Biological Transfer of Radionuclides from Shallow Land Burial`` during 1985 to 1989 (IAEA-TECDOC-579, Vienna, 1990), the issue of reliability of safety assessments was identified as an important topic for further support and development. A new CRP was formulated with the acronym NSARS (Near Surface Radioactive Waste Disposal Safety Assessment Reliability Study). This technical document is the first report of from the CRP and contains the intercomparison of results of the first test exercise (Test Case 1) on modelling of potential radiation exposures as a result of near surface disposal. Test Case 1 is based on entirely hypothetical data and includes consideration of exposures due to leaching and as a result of human intrusion into the site. Refs, figs and tabs.

  17. Multiple containment for LSA [low specific activity] and SCO [surface contaminated objects] wastes

    International Nuclear Information System (INIS)

    Burgess, M.H.

    1993-09-01

    Radioactive wastes are generally transported in the form of Low Specific Activity (LSA) materials or Surface Contaminated Objects (SCO). This report proposes that a method of acknowledging the beneficial effects of multiple containment for such wastes should be written into the 1996 Edition of the IAEA Transport Regulations. Experience used to assess risks from on-site movements of radioactive material in the UK can be applied to develop safety arguments justifying the alleviation of off-site transport risks. (UK)

  18. Spatial variations in water composition at a northern Canadian lake impacted by mine drainage

    International Nuclear Information System (INIS)

    Moncur, M.C.; Ptacek, C.J.; Blowes, D.W.; Jambor, J.L.

    2006-01-01

    Release of acid drainage from mine-waste disposal areas is a problem of international scale. Contaminated surface water, derived from mine wastes, originates both as direct surface runoff and, indirectly, as subsurface groundwater flow. At Camp Lake, a small Canadian Shield lake that is in northern Manitoba and is ice-covered 6 months of the year, direct and indirect release of drainage from an adjacent sulfide-rich tailings impoundment has severely affected the quality of the lake water. Concentrations of the products from sulfide oxidation are extremely high in the pore waters of the tailings impoundment. Groundwater and surface water derived from the impoundment discharge into a semi-isolated shallow bay in Camp Lake. The incorporation of this aqueous effluent has altered the composition of the lake water, which in turn has modified the physical limnology of the lake. Geochemical profiles of the water column indicate that, despite its shallow depth (6 m), the bay is stratified throughout the year. The greatest accumulation of dissolved metals and SO 4 is in the lower portion of the water column, with concentrations up to 8500 mg L -1 Fe, 20,000 mg L -1 SO 4 , 30 mg L -1 Zn, 100 mg L -1 Al, and elevated concentrations of Cu, Cd, Pb and Ni. Meromictic conditions and very high solute concentrations are limited to the bay. Outside the bay, solute concentrations are lower and some stratification of the water column exists. Identification of locations and composition of groundwater discharge relative to lake bathymetry is a fundamental aspect of understanding chemical evolution and physical stability of mine-impacted lakes

  19. Operable Unit 3-13, Group 3, Other Surface Soils Remediation Sets 4-6 (Phase II) Waste Management Plan

    International Nuclear Information System (INIS)

    G. L. Schwendiman

    2006-01-01

    This Waste Management Plan describes waste management and waste minimization activities for Group 3, Other Surface Soils Remediation Sets 4-6 (Phase II) at the Idaho Nuclear Technology and Engineering Center located within the Idaho National Laboratory. The waste management activities described in this plan support the selected response action presented in the Final Record of Decision for Idaho Nuclear Technology and Engineering Center, Operable Unit 3-13. This plan identifies the waste streams that will be generated during implementation of the remedial action and presents plans for waste minimization, waste management strategies, and waste disposition

  20. Treatment of oily wastes by agglomeration techniques to produce an auxiliary carbonaceous fuel with low SO2 emissions

    International Nuclear Information System (INIS)

    Majid, A.; Capes, C.E.; Sparks, B.D.

    1992-01-01

    Oily sludges and organic wastes are produced by a number of industries, particularly those related to the recovery of processing of petroleum. Traditional sludge disposal methods, involving concentration by impoundment followed by land filling or land farming, are meeting with increasingly stringent regulations. Further treatment of the wastes and reduction of volume and recycle are being encouraged and legislated. Such treatment may range from separation of constituents into higher value products, such as the separation of oil or other organic components from mineral (ash forming) impurities and water, to stabilization of impurities to prevent leaching or to reduce emissions during combustion. This paper reports on liquid phase agglomeration (LPA) which has the potential to play a major role in oily waste treatment processes. It can be adapted to separate finely divided solids or liquids from immiscible liquid suspensions or emulsions

  1. Evaluation of bubbler/diaphragm techniques to measure surface level in the waste storage tanks

    International Nuclear Information System (INIS)

    Peters, T.J.; Hickman, B.J.; Colson, J.B.

    1993-10-01

    This report describes the results of tests conducted at the Pacific Northwest Laboratory (PNL) to determine if a bubbler technique can be used to determine the surface level in the waste tanks. Two techniques were evaluated. The first technique is a standard bubbler system in which a tube is placed below the surface of the liquid to be measured and air pressure inside a tube is increased until bubbles begin to become emitted from the tube. The air pressure then is a function of the pressure at the bottom of the tube. The second technique involves a system similar to the standard bubbler technique, but instead of bubbles being released into the material to be gauged, air pressure is increased against a diaphragm until enough pressure is applied to overcome the pressure of the liquid at the given depth, at which time the air then flows in a return loop back to a vent. The advantage of the diaphragm system is that it is a sealed system; thus no air is released into the waste tank materials, and it is not possible for the waste tank materials to get into the air flow. Based on the results of the tests conducted in this program, it appears that the bubbler and diaphragm systems that were tested could not be used for accurate measurements of the level in the waste tanks. Both exhibited deposits of simulated waste tank material at the end of the devices which affected the ability of the gauge to accurately determine changes in the surface level even though the measured value of the level was inaccurate. Further investigations into the cause of this inaccuracy may be warranted. Alternate diaphragm materials may improve the performance of this gauge

  2. Waste Volume Reduction Using Surface Characterization and Decontamination By Laser Ablation

    International Nuclear Information System (INIS)

    Pellin, Michael J.; Savina, Michael R.; Reed, Claude B.; Zhiyue, Xu; Yong, Wang

    2000-01-01

    The U.S. Department of Energy's nuclear complex, a nation-wide system of facilities for research and production of nuclear materials and weapons, contains large amounts of radioactively contaminated concrete[1]. This material must be disposed of prior to the decommissioning of the various sites. Often the radioactive contaminants in concrete occupy only the surface and near-surface (∼3-6 mm deep) regions of the material. Since many of the structures such as walls and floors are 30 cm or more thick, it makes environmental and economic sense to try to remove and store only the thin contaminated layer rather than to treat the entire structure as waste. Current mechanical removal methods, known as scabbling, are slow and labor intensive, suffer from dust control problems, and expose workers to radiation fields. Improved removal methods are thus in demand[2-5]. Prior to decontamination, the surface must be characterized to determine the types and amounts of contaminants present i n order to decide on an appropriate cleaning strategy. Contamination occurs via exposure to air and water-borne radionuclides and by neutron activation. The radionuclides of greatest concern are (in order of abundance) [1]: 137Cs and 134Cs, 238U, 60Co, and 90Sr, followed by 3H, radioactive iodine, and a variety of Eu isotopes and transuranics. A system capable of on- line analysis is valuable since operators can determine the type of contaminants in real time and make more efficient use of costly sampling and characterization techniques. Likewise, the removed waste itself must be analyzed to insure that proper storage and monitoring techniques are used. The chemical speciation of radionuclides in concrete is largely unknown. Concrete is a complex material comprising many distinct chemical and physical phases on a variety of size scales[6-8]. Most studies of radionuclides in cements and concrete are for the most part restricted to phenomenological treatments of diffusion of ion s, particularly

  3. Considerations in the development of near surface repositories for radioactive waste

    International Nuclear Information System (INIS)

    2003-01-01

    The report presents an integrated, stepwise approach for the development (includes pre-operational, operational and post-closure phases) of near surface disposal facilities for low and intermediate level radioactive waste. It has been developed in light of the considerable experience that has accumulated on the development of such disposal systems and is consistent with the current international requirements, principles, standards and guidance for the disposal of radioactive waste. It is considered that the systematic application of the various steps of the approach can contribute to the successful development of a repository programme. The approach is designed to be generic, integrating the various technical and nontechnical factors, and flexible enough to be suitable for use in the various Member States, ranging from countries that have nuclear power plants to countries that have small inventories of radioactive waste from nuclear applications. It is anticipated that this report will be particularly useful and of direct relevance to Member States that are currently developing, or have plans to develop, disposal facilities for low and intermediate level radioactive waste in the near future. The report is intended to respond to the disposal needs of the various Member States, ranging from countries with nuclear power plants to countries having small inventories of radioactive waste from nuclear applications. It was developed with the help of consultants and through an Advisory Group Meeting held in November 2001

  4. Recovery of the Three-Gorges Reservoir Impoundment Signal from ICESat altimetry and GRACE

    Science.gov (United States)

    Carabajal, C. C.; Boy, J.; Luthcke, S. B.; Harding, D. J.; Rowlands, D. D.; Lemoine, F. G.

    2006-12-01

    The Three Gorges Dam along the Yangtze River in China is one of the largest dams in the world. The water impoundment of the Three-Gorges Reservoir started in June 2003, and the volume of water will continuously increase up to about 40 km3 in 2009, over a length of about 600 km. Although water-level changes along the Yangtze River and the Three Gorges Reservoir are measured by in situ water gauges, access to these data can be quite difficult. Estimates of inland water height and extent can also be recovered from altimetry measurements performed from satellite platforms, such as those acquired by the Geoscience laser Altimetry System (GLAS) on board the Ice, Cloud and Land Elevation Satellite (ICESat). ICESat has produced a comprehensive, highly precise, set of along-track elevation measurements, every three months since its launch in 2003, which intersect the Yangtze River along its East-West extent. In addition, the water impoundment of major artificial reservoirs induces variations of global geodetic quantities, such as the gravity field and Earth rotation (Chao, 1995, Boy & Chao, 2002). Water level changes within the reservoir are compared to GRACE (Gravity Recovery And Climate Experiment) recovered water mass changes. In addition, we compare the GRACE observations of mass change in the Yangtze region to hydrological changes computed from different global soil-moisture and snow models, such as GLDAS (Global Land Data Assimilation System).

  5. Waste Tyres as Heat Sink to Reduce the Driveway Surface Temperatures in Malaysia

    Directory of Open Access Journals (Sweden)

    Aniza Abdul Aziz

    2013-12-01

    Full Text Available The development of roads and driveways are on the rise as automobiles are now a necessity to all. This excessive development with its requirements increased the urban heat temperature and the generation of waste tyres. Waste tyre management has therefore been taken seriously by developed countries and since the European directive to ban used tyre products and whole tire disposal from landfill in 2003 and 2006 respectively, many researchers have looked for alternative ways to use the waste tyre. In Malaysia, The Smart and Cool Home Developer attempted to develop an eco-house by utilising waste tyre as the foundation for the driveway and claimed that the buried tyres act as a heat sink for the concrete and reduce the surface temperature of the driveway. Hence investigations were conducted on two sample houses to investigate this phenomenon. Findings from this pilot study show that waste tyres do act as a heat sink to the concrete driveways which affect the ambient temperature and relative humidity of the immediate surroundings.

  6. Assessment of management alternatives for LWR wastes. Volume 8. Cost and radiological impact associated with near-surface disposal of reactor waste (Spanish concept)

    International Nuclear Information System (INIS)

    Alamo Berna, S.; Sanchez Delgado, N.

    1993-01-01

    This report deals with the determination of the cost and the radiological impact associated with a near-surface disposal site (Spanish concept) for low and medium-level radioactive waste generated during operation of a 20 GWe nuclear park composed of LWRs for 30 years. This study is part of an overall theoretical exercise aimed at evaluating a selection of management routes for LWR waste based on economical and radiological criteria

  7. Assessment of management alternatives for LWR wastes. Volume 7. Cost and radiological impact associated with near-surface disposal of reactor waste (French concept)

    International Nuclear Information System (INIS)

    Malherbe, J.

    1993-01-01

    This report deals with the determination of the cost and the radiological impact associated with a near-surface disposal site (French concept) for low and medium-level radioactive waste generated during operation of a 20 GWe nuclear park composed of LWRs for 30 years. This study is part of an overall theoretical exercise aimed at evaluating a selection of management routes for LWR waste based on economical and radiological criteria

  8. Development of performance assessment methodology for establishment of quantitative acceptance criteria of near-surface radioactive waste disposal

    Energy Technology Data Exchange (ETDEWEB)

    Kim, C. R.; Lee, E. Y.; Park, J. W.; Chang, G. M.; Park, H. Y.; Yeom, Y. S. [Korea Hydro and Nuclear Power Co., Ltd., Seoul (Korea, Republic of)

    2002-03-15

    The contents and the scope of this study are as follows : review of state-of-the-art on the establishment of waste acceptance criteria in foreign near-surface radioactive waste disposal facilities, investigation of radiological assessment methodologies and scenarios, investigation of existing models and computer codes used in performance/safety assessment, development of a performance assessment methodology(draft) to derive quantitatively radionuclide acceptance criteria of domestic near-surface disposal facility, preliminary performance/safety assessment in accordance with the developed methodology.

  9. The role of cassiterite controlling arsenic mobility in an abandoned stanniferous tailings impoundment at Llallagua, Bolivia.

    Science.gov (United States)

    Romero, Francisco Martín; Canet, Carles; Alfonso, Pura; Zambrana, Rubén N; Soto, Nayelli

    2014-05-15

    The surface water contamination by potentially toxic elements (PTE) leached from mine tailings is a major environmental concern. However, the formation of insoluble solid phases can control the mobility of PTE, with subsequent decrease of the risk that tailings suppose to the environment. We characterized the tailings from a tin inactive mine in Llallagua, Bolivia in order to assess the risk for surface water quality. These tailings contain high concentrations of PTE, with up to 94,344 mg/kg Fe, 9,135 mg/kg Sn, 4,606 mg/kg As, 1,362 mg/kg Cu, 1,220 mg/kg Zn, 955 mg/kg Pb and 151 mg/kg Cd. Oxidation of sulfide minerals in these tailings generates acid leachates (pH=2.5-3.5), rich in SO4(2-) and dissolved PTE, thereby releasing contaminants to the surface waters. Nevertheless, the concentrations of dissolved Sn, As and Pb in acid leachates are low (Sntailing deposits; it should be the main solid phase controlling Sn and As mobility in the impoundment. Additionally, jarosite and plumbojarosite, identified among the secondary minerals, could also play an important role controlling the mobility of As and Pb. Taking into account (a) the low solubility constants of cassiterite (Ksp=10(-64.2)), jarosite (Ksp=10(-11)) and plumbojarosite (Ksp=10(-28.66)), and (b) the stability of these minerals under acidic conditions, we can conclude that they control the long-term fate of Sn, As and Pb in the studied tailings. Copyright © 2014 Elsevier B.V. All rights reserved.

  10. Planning for closures of hazardous waste land disposal units at the Oak Ridge Y-12 plant

    International Nuclear Information System (INIS)

    Welch, S.H.; Kelly, B.A.; DeLozier, M.F.P.; Manrod, W.E.

    1988-01-01

    Eight hazardous waste land disposal units at the Oak Ridge Y-12 Plant are being closed in accordance with the Resource Conservation and Recovery Act (RCRA) under an integrated multi-year program. The units, some of which date back to the early 1950s and include five surface impoundments, two landfills and a land treatment unit, have been used for the management of a variety of types of hazardous wastes. Closure plans for the units have been submitted and are in various stages of revision and regulatory review. The units will be closed by various combinations of methods, including liquid removal and treatment, sludge stabilization, contaminated sludge and/or soil removal, and capping. Closure of all eight units must be initiated by November 8, 1988. Funding for the eight closures is being provided by a new Department of Energy budget category, the environmental Restoration Budget Category (ERBC), which is intended to allow for a more rapid response to environmental problems and regulatory requirements. A major project, Closure and Post-Closure Activities (CAPCA) has been identified for ERBC funding to close the land disposal units in accordance with RCRA requirements. Establishing the project scope has required the development of a detailed set of assumptions and a confirmation program for each assumption. Other significant activities in the CAPCA project include risk assessments and the preparation of an integrated project schedule

  11. Surface erosion and hydrology of earth covers used in shallow land burial of low-level radioactive waste

    International Nuclear Information System (INIS)

    Bent, G.C.

    1988-01-01

    Shallow land burial is the current method of disposal of low-level radioactive waste in the United States. The most serious technical problems encountered in shallow land burial are water-related. Water is reported to come into contact with the waste by erosion of earth covers or through infiltration of precipitation through the earth covers. The objectives of this study were to: compare and evaluate the effects of crested wheatgrass and streambank wheatgrass on surface erosion of simulated earth covers at Idaho National Engineering Laboratory (INEL), characterize the surface hydrology, and estimate cumulative soil loss for average and extreme rainfall events and determine if the waste will become exposed during its burial life due to erosion. 30 refs., 26 figs., 21 tabs

  12. Evaluation of pressure transducers to measure surface level in the waste storage tanks

    International Nuclear Information System (INIS)

    Peters, T.J.; Colson, J.B.

    1994-06-01

    This report describes the results of tests conducted at the Pacific Northwest Laboratory (PNL) to determine if pressure transducers can be used to measure the surface level in the waste tanks. A survey was first conducted to evaluate which, if any, commercially available pressure transducers were available that could meet the requirements for use in the waste tanks. More than 35 companies were contacted to determine if they manufactured a pressure transducer that could be used in the 101-SY waste tank. The three basic requirements for a pressure transducer for this application were that they were radiation-hardened, could withstand a caustic environment, and were certified to be intrinsically safe. No manufacturer was able to meet all three of these requirements with a commercially available product. Seven companies were able to meet the requirements for being radiation-hardened and being able to withstand the caustic environment. However, only two of the nine companies were willing to supply a pressure transducer for laboratory testing. The two pressure transducers that were tested in this program were the VEGA D36-38 from HiTech Technologies, Inc., and the KP-1911-A from Kaman Instrumentation Corporation. Pressure transducers operate on the principle that the pressure at the location of a sensor increases directly with the depth of the liquid above it. A liquid is required in order for these devices to operate. For these tests, water was first used to determine the ideal operation of the devices, then the devices were placed in a 101-SY waste tank simulant. The simulant had a specific gravity of 1.96 and had the consistency similar to the convective layer in the 101-SY waste tank. In order to determine the surface level with pressure transducers, the density of the material needs to be known

  13. A methodology for evaluating alternative sites for a near-surface radioactive waste repository

    International Nuclear Information System (INIS)

    Watson, S.R.; Brownlow, S.A.

    1986-02-01

    This report addresses the issue of constructing an evaluation procedure for a near-surface radioactive waste repository. It builds on earlier work of the authors, and describes a basis for a practicable methodology for assessing the relative merits of different sites. (author)

  14. Seismic surface wave tomography of waste sites. 1997 annual progress report

    International Nuclear Information System (INIS)

    Long, T.L.

    1997-01-01

    'The objective of the Seismic Surface Wave Tomography of Waste Sites is to develop a robust technique for field acquisition and analysis of surface wave data for the interpretation of shallow structures, such as those associated with the burial of wastes. The analysis technique is to be developed and tested on an existing set of seismic data covering the K-901 burial site at the East Tennessee Technology Park. Also, a portable prototype for a field acquisition system will be designed and developed to obtain additional data for analysis and testing of the technique. The K-901 data have been examined and a preliminary Single Valued Decomposition inversion has been obtained. The preliminary data indicates a need for additional seismic data to ground-truth the inversion. The originally proposed gravity data acquisition has been dropped because sufficient gravity data are now available for a preliminary analysis and because the seismic data are considered more critical to the interpretation. The proposed prototype for the portable acquisition and analysis system was developed during the first year and will be used in part of the acquisition of additional seismic data.'

  15. Impact of metals in surface matrices from formal and informal electronic-waste recycling around Metro Manila, the Philippines, and intra-Asian comparison

    International Nuclear Information System (INIS)

    Fujimori, Takashi; Takigami, Hidetaka; Agusa, Tetsuro; Eguchi, Akifumi; Bekki, Kanae; Yoshida, Aya; Terazono, Atsushi; Ballesteros, Florencio C.

    2012-01-01

    Highlights: ► We quantified 11 metals in surface matrices from e-waste recycling sites at the Philippines. ► Dust had statistical higher levels of metal contamination and health risk compared to soil. ► Formal and informal sites had different metal contaminations. ► Intra-Asian comparison provided common insight on metal contamination from e-waste recycling. - Abstract: We report concentrations, enrichment factors, and hazard indicators of 11 metals (Ag, As, Cd, Co, Cu, Fe, In, Mn, Ni, Pb, and Zn) in soil and dust surface matrices from formal and informal electronic waste (e-waste) recycling sites around Metro Manila, the Philippines, referring to soil guidelines and previous data from various e-waste recycling sites in Asia. Surface dust from e-waste recycling sites had higher levels of metal contamination than surface soil. Comparison of formal and informal e-waste recycling sites (hereafter, “formal” and “informal”) revealed differences in specific contaminants. Formal dust contained a mixture of serious pollutant metals (Ni, Cu, Pb, and Zn) and Cd (polluted modestly), quite high enrichment metals (Ag and In), and crust-derived metals (As, Co, Fe, and Mn). For informal soil, concentration levels of specific metals (Cd, Co, Cu, Mn, Ni, Pb, and Zn) were similar among Asian recycling sites. Formal dust had significantly higher hazardous risk than the other matrices (p < 0.005), excluding informal dust (p = 0.059, almost significant difference). Thus, workers exposed to formal dust should protect themselves from hazardous toxic metals (Pb and Cu). There is also a high health risk for children ingesting surface matrices from informal e-waste recycling sites.

  16. Limnology and fisheries of three recently impounded reservoirs in Sri Lanka

    International Nuclear Information System (INIS)

    Silva, K.H.G.M De

    1990-01-01

    The hydroelectric reservoirs of Kotmale, Victoria, and Randenigala were impounded in 1985, 1984, and 1986, respectively, by damming the Mahaweli River. The surface area, maximum depth, and mean depth of the three reservoirs are 6.3 km 2 , 78 m, 27.6 m; 23.7 km 2 , 102 m, 30.8 m; and 23.5 km 2 , 90 m, 36.6 m respectively, at their full supply levels of 703, 438, and 232 m above mean sea level. Important physicochemical factors and phytoplankton were studied by sampling of subsurface waters every two weeks in 12 randomly chosen stations in Randenigala and Victoria, and in 10 stations in Kotmale over 24 months. Mean water temperature, pH, conductivity, and the total alkalinity during the study period were 25.6 degree C, 6.6, 50.7 μsieverts, and 0.31 millimoles/l in Kotmale, 26.9 degree C, 7.1, 77.4 μsieverts, and 0.62 millimoles/l in Victoria, and 28.3 degree C, 7.4, 90.0 μsieverts, and 0.79 millimoles/l in Randenigala. The gill-net catches of Kotmale and Victoria are ca 38 and 70 kg/hectare/y, respectively. Randenigala has a fishery potential of ca 70 kg/hectare/y. Tilapia formed ca 68%, 59%, and 69% of the catches of Kotmale, Victoria, and Randenigala, respectively. The catch at Kotmale was mainly Java tilapia and Nile tilapia, whereas at the other two reservoirs it was mainly Java tilapia. Indigenous species constituted only ca 10% of the catch. 16 refs., 2 figs., 4 tabs

  17. Control of Eolian soil erosion from waste site surface barriers

    International Nuclear Information System (INIS)

    Ligotke, M.W.

    1994-11-01

    Physical models were tested in a wind tunnel to determine optimum surface-ravel admixtures for protecting silt-loam soil from erosion by, wind and saltating, sand stresses. The tests were performed to support the development of a natural-material surface barrier for and waste sites. Plans call for a 2-m deep silt-loam soil reservoir to retain infiltrating water from rainfall and snowmelt. The objective of the study was to develop a gravel admixture that would produce an erosion-resistant surface layer during, periods of extended dry climatic stress. Thus, tests were performed using simulated surfaces representing dry, unvegetated conditions present just after construction, after a wildfire, or during an extended drought. Surfaces were prepared using silt-loam soil mixed with various grades of sand and Travel. Wind-induced surface shear stresses were controlled over the test surfaces, as were saltating, sand mass flow rates and intensities. Tests were performed at wind speeds that approximated and exceeded local 100-year peak gust intensities. Surface armors produced by pea gravel admixtures were shown to provide the best protection from wind and saltating sand stresses. Compared with unprotected silt-loam surfaces, armored surfaces reduced erosion rates by more than 96%. Based in part on wind tunnel results, a pea gravel admixture of 15% will be added to the top 1 in of soil in a prototype barrier under construction in 1994. Field tests are planned at the prototype site to provide data for comparison with wind tunnel results

  18. Estimation of mean time to failure of a near surface radioactive waste repository for PWR power stations

    International Nuclear Information System (INIS)

    Aguiar, Lais A. de; Frutuoso e Melo, P.F.; Alvim, Antonio C.M.

    2007-01-01

    This work aims at estimating the mean time to failure (MTTF) of each barrier of a near surface radioactive waste repository. It is assumed that surface water infiltrates through the barriers, reaching the matrix where radionuclides are contained, releasing them to the environment. Radioactive wastes considered in this work are low and medium level wastes (produced during operation of a PWR nuclear power station) fixed on cement. The repository consists of 6 saturated porous media barriers (top cover, upper layer, packages, basis, repository walls and geosphere). It has been verified that the mean time to failure (MTTF) of each barrier increases for radionuclides having higher retardation factor (Fr) and also that the MTTF for concrete is larger for Nickel , while for the geosphere, Plutonium gives the largest MTTF. (author)

  19. A model for evaluating effects of climate, water availability, and water management on wetland impoundments--a case study on Bowdoin, Long Lake, and Sand Lake National Wildlife Refuges

    Science.gov (United States)

    Tangen, Brian A.; Gleason, Robert A.; Stamm, John F.

    2013-01-01

    Many wetland impoundments managed by the U.S. Fish and Wildlife Service (USFWS) National Wildlife Refuge System throughout the northern Great Plains rely on rivers as a primary water source. A large number of these impoundments currently are being stressed from changes in water supplies and quality, and these problems are forecast to worsen because of projected changes to climate and land use. For example, many managed wetlands in arid regions have become degraded owing to the long-term accumulation of salts and increased salinity associated with evapotranspiration. A primary goal of the USFWS is to provide aquatic habitats for a diversity of waterbirds; thus, wetland managers would benefit from a tool that facilitates evaluation of wetland habitat quality in response to current and anticipated impacts of altered hydrology and salt balances caused by factors such as climate change, water availability, and management actions. A spreadsheet model that simulates the overall water and salinity balance (WSB model) of managed wetland impoundments is presented. The WSB model depicts various habitat metrics, such as water depth, salinity, and surface areas (inundated, dry), which can be used to evaluate alternative management actions under various water-availability and climate scenarios. The WSB model uses widely available spreadsheet software, is relatively simple to use, relies on widely available inputs, and is readily adaptable to specific locations. The WSB model was validated using data from three National Wildlife Refuges with direct and indirect connections to water resources associated with rivers, and common data limitations are highlighted. The WSB model also was used to conduct simulations based on hypothetical climate and management scenarios to demonstrate the utility of the model for evaluating alternative management strategies and climate futures. The WSB model worked well across a range of National Wildlife Refuges and could be a valuable tool for USFWS

  20. Impacts of Solid Waste Leachate on Groundwater and Surface Water Quality

    International Nuclear Information System (INIS)

    Karim, S.

    2010-01-01

    The present investigation was carried out to assess the impacts of solid waste leachate on groundwater and surface water quality at unlined dumping site. Six leachate samples collected from different locations have average values of COD and BOD 2563 mg/L and 442 mg/L, respectively. Surface water samples were collected in two different seasons (rainy and non- rainy). Samples collected during non-rainy season were found to be more contaminated than rainy season. Soil samples collected from the depth of 1.5 m are contaminated with heavy metals (Cd, Cr, Fe and Zn) and E.coli. Presence of E.coli shows that leachate has deteriorated groundwater quality. (author)

  1. Slurry discharge management-beach profile prediction

    Energy Technology Data Exchange (ETDEWEB)

    Bravo, R.; Nawrot, J.R. [Southern Illinois University at Carbondale, Carbondale, IL (United States). Dept. of Civil Engineering

    1996-11-01

    Mine tailings dams are embankments used by the mining industry to retain the tailings products after the mineral preparation process. Based on the acid-waste stereotype that all coal slurry is acid producing, current reclamation requires a four foot soil cover for inactive slurry disposal areas. Compliance with this requirement is both difficult and costly and in some case unnecessary, as not all the slurry, or portions of slurry impoundments are acid producing. Reduced costs and recent popularity of wetland development has prompted many operators to request reclamation variances for slurry impoundments. Waiting to address slurry reclamation until after the impoundment is full, limits the flexibility of reclamation opportunities. This paper outlines a general methodology to predict the formation of the beach profile for mine tailings dams, by the discharge volume and location of the slurry into the impoundment. The review is presented under the perspective of geotechnical engineering and waste disposal management emphasizing the importance of pre-planning slurry disposal land reclamation. 4 refs., 5 figs.

  2. A relationship between leach rate of nuclear waste glass and residual amount of sodium on the glass surface

    International Nuclear Information System (INIS)

    Kamizono, Hiroshi; Banba, Tsunetaka

    1984-12-01

    Leach tests of simulated high-level waste glass were carried out in order to examine the quantitative relationship between the amount of elements on the sample surface and that in the leachate. An experimental equation was obtained expressing the relationship between the amount of Na on the sample surface and that in the leachate. This shows that it is possible in some cases to estimate the amount of Na in the leachate by measuring the amount of Na on the sample surface. One example of such an estimation was observed with the simulated high-level waste glass leached at 100 0 C in the presence of a backfill material. (author)

  3. Mercury concentrations of fish in Southern Indian Lake and Issett Lake, Manitoba 1975-88: The effect of lake impoundment and Churchill River diversion

    International Nuclear Information System (INIS)

    Strange, N.E.; Bodaly, R.A.; Fudge, R.J.P.

    1991-01-01

    Southern Indian and Issett Lakes in northern Manitoba were flooded in 1976 as part of Manitoba Hydro's Churchill River diversion project. Fish were collected from 1975 to 1988 from five regional sites on the lakes to examine the effects of impoundment and river diversion on muscle mercury concentrations. Raw data for individual fish caught in 1987 and 1988 are presented, along with means and analyses calculated over the entire 1975-1988 study period. Mercury concentrations in whitefish, pike, and walleye increased significantly after impoundment. Whitefish mercury levels peaked in 1978 and have since declined to near pre-flooding levels. Northern pike and walleye mercury levels were much higher than for whitefish. Pike mercury concentrations showed no indication of declining after 12 years of impoundment, but walleye mercury levels at 2 of the 5 Southern Indian Lake sites declined from maximum recorded levels. Significant variability in fish mercury concentrations was noted both from year to year and among the sites. It is suggested that site-to-site variations are due to varying conditions in the reservoir which stimulate mercury methylation. Since there appears to be an ongoing long-term source of mercury and organic material from the eroding shorelines, pike and walleye mercury concentrations are expected to remain high for many years. 25 refs., 7 figs., 20 tabs

  4. Cocaine and metabolites in waste and surface water across Belgium

    Energy Technology Data Exchange (ETDEWEB)

    Nuijs, Alexander L.N. van [Toxicological Centre, Department of Pharmaceutical Sciences, University of Antwerp (Ukraine), Universiteitsplein 1, 2610 Antwerp (Belgium)], E-mail: alexander.vannuijs@ua.ac.be; Pecceu, Bert [Laboratory for Ecophysiology, Biochemistry and Toxicology, Department of Biology, University of Antwerp (Ukraine), Groenenborgerlaan 171, 2020 Antwerp (Belgium); Theunis, Laetitia; Dubois, Nathalie; Charlier, Corinne [Laboratory of Clinical, Forensic and Environmental Toxicology, University of Liege, (ULg), CHU Sart-Tilman, 4000 Liege (Belgium); Jorens, Philippe G. [Department of Clinical Pharmacology/Clinical Toxicology, University of Antwerp (Ukraine), University Hospital of Antwerp, Universiteitsplein 1, 2610 Antwerp (Belgium); Bervoets, Lieven; Blust, Ronny [Laboratory for Ecophysiology, Biochemistry and Toxicology, Department of Biology, University of Antwerp (Ukraine), Groenenborgerlaan 171, 2020 Antwerp (Belgium); Neels, Hugo [Toxicological Centre, Department of Pharmaceutical Sciences, University of Antwerp (Ukraine), Universiteitsplein 1, 2610 Antwerp (Belgium); Laboratory of Toxicology, ZNA Stuivenberg, Lange Beeldekensstraat 267, 2060 Antwerp (Belgium); Covaci, Adrian [Toxicological Centre, Department of Pharmaceutical Sciences, University of Antwerp (Ukraine), Universiteitsplein 1, 2610 Antwerp (Belgium); Laboratory for Ecophysiology, Biochemistry and Toxicology, Department of Biology, University of Antwerp (Ukraine), Groenenborgerlaan 171, 2020 Antwerp (Belgium)

    2009-01-15

    Cocaine abuse, a growing social problem, is currently estimated from population surveys, consumer interviews and crime statistics. A new approach based on the analysis of cocaine (COC) and metabolites, benzoylecgonine (BE) and ecgonine methyl ester (EME), in water samples was applied to 28 rivers and 37 waste water treatment plants in Belgium using solid-phase extraction and liquid chromatography coupled to tandem mass spectrometry. While EME was undetectable, COC and BE were detectable with concentrations ranging from <1 to 753 ng/L and <1 to 2258 ng/L, respectively. BE concentrations were employed to calculate the local amount of abused cocaine. The highest values (up to 1.8 g/day cocaine per 1000 inhabitants) were found in large cities and during weekends. The estimation of cocaine abuse through water analysis can be executed on regular basis without cooperation of patients. It also gives clear geographical information, while prevention campaigns can easily be implemented and evaluated. - Cocaine consumption can be evaluated through analysis of waste and surface water.

  5. Cocaine and metabolites in waste and surface water across Belgium

    International Nuclear Information System (INIS)

    Nuijs, Alexander L.N. van; Pecceu, Bert; Theunis, Laetitia; Dubois, Nathalie; Charlier, Corinne; Jorens, Philippe G.; Bervoets, Lieven; Blust, Ronny; Neels, Hugo; Covaci, Adrian

    2009-01-01

    Cocaine abuse, a growing social problem, is currently estimated from population surveys, consumer interviews and crime statistics. A new approach based on the analysis of cocaine (COC) and metabolites, benzoylecgonine (BE) and ecgonine methyl ester (EME), in water samples was applied to 28 rivers and 37 waste water treatment plants in Belgium using solid-phase extraction and liquid chromatography coupled to tandem mass spectrometry. While EME was undetectable, COC and BE were detectable with concentrations ranging from <1 to 753 ng/L and <1 to 2258 ng/L, respectively. BE concentrations were employed to calculate the local amount of abused cocaine. The highest values (up to 1.8 g/day cocaine per 1000 inhabitants) were found in large cities and during weekends. The estimation of cocaine abuse through water analysis can be executed on regular basis without cooperation of patients. It also gives clear geographical information, while prevention campaigns can easily be implemented and evaluated. - Cocaine consumption can be evaluated through analysis of waste and surface water

  6. Safety assessment methodologies and their application in development of near surface waste disposal facilities - the ASAM project

    International Nuclear Information System (INIS)

    Metcalf, P.

    2003-01-01

    The scope of ASAM project covers near surface disposal facilities for all types of low and intermediate level wastes with emphasis of the post-closure safety assessment.The objectives are to explore practical application to a range of disposal facilities for a number of purposes e.g. development of design concepts, safety re-assessment, upgrading safety and to develop practical approaches to assist regulators, operators and other experts in review of safety assessment. The task of the Co-ordination Group are: reassessment of existing facilities - use of safety assessment in decision making on selection of options (volunteer site Hungary); disused sealed sources - evaluation of disposability of disused sealed sources in near surface facilities (volunteer site Saratov, Russia); mining and minerals processing waste - evaluation of long-term safety (volunteer site pmc S. Africa). An agreement on the scope and objectives of the project are reached and the further consideration, such as human intrusion/institutional control/security; waste from oil/gas industry; very low level waste; categorization of sealed sources coordinated with other IAEA activities are outlined

  7. Synchronous response of sedimentary organic carbon accumulation on the inner shelf of the East China Sea to the water impoundment of Three Gorges and Gezhouba Dams

    Science.gov (United States)

    Lin, Jia; Zhu, Qing; Hong, Yuehui; Yuan, Lirong; Liu, Jinzhong; Xu, Xiaoming; Wang, Jianghai

    2018-01-01

    Coastal seas, located between continents and the open ocean, are an important active carbon pool. The sedimentary total organic carbon (TOC) in these areas is a mixture of terrestrial and marine sources, and can be a powerful proxy for tracing natural processes and human activities. In this study, one fine-grained sediment core (DH5-1) from the inner shelf of the East China Sea was systematically analyzed for TOC and black carbon (BC) contents and TOC stable carbon isotope ratios (δ13C). By combining these data with 210Pb dating, an improved carbon correction model and a two end-member mixing model, we reconstructed century-scale high-resolution sequences of corrected TOC, terrestrial TOC and marine TOC contents and identified two carbon depletion events in the DH5-1 record. The two events, shown as two minima in the TOC profiles, correspond temporally to 1985-1987 AD and 2003-2006 AD, which exactly matches the water impoundment of the Gezhouba Dam and Three Gorges Dam, respectively. In addition, the variations in TOC contents and δ13C values before, during or after the minima demonstrate a relationship between the depletion events and water impoundment of the dams on the Changjiang River. The TOC reductions may represent synchronous responses of sedimentary TOC and resultant ecological effects on the inner shelf of the East China Sea to the water impoundment of the dams. These new TOC records reflect the interaction between natural and anthropogenic processes and, accordingly, provide a deep insight and important references for assessing marine ecological effects resulting from water impoundment of largescale dams.

  8. Change characteristics of DSi and nutrition structure at the Yangtze River Estuary after Three Gorges Project impounding and their ecological effect

    Directory of Open Access Journals (Sweden)

    Li Lei

    2017-06-01

    Full Text Available The variation law of dissolved silica (DSi, dissolved inorganic nitrogen (DIN, dissolved inorganic phosphorus (DIP and nutrition structure after the Three Gorges Project (TGP impounding as well as their ecological effect were analyzed according to monitoring survey of the Yangtze River Estuary in spring (May and summer (August from 2004-2009. The results showed that after impounding, DSi and DIN concentration decreased and increased, respectively. During the study period, DSi decreased by about 63%, while DIN almost tripled. DIP concentration fluctuated slightly. With respect to nutrition structure, N:P increased, whereas Si:P and Si:N declined. According to chemometry standard of nutrient limits, nutrition structure tended to be imbalanced and the limiting factor of phytoplankton growth (P was studied. Changes of nutrition structure have largely decreased diatom and caused different composition of dominant phytoplankton species. This may change ecosystem structure of the Yangtze River Estuary.

  9. Geochemical characterisation of seepage and drainage water quality from two sulphide mine tailings impoundments: Acid mine drainage versus neutral mine drainage

    Science.gov (United States)

    Heikkinen, P.M.; Raisanen, M.L.; Johnson, R.H.

    2009-01-01

    Seepage water and drainage water geochemistry (pH, EC, O2, redox, alkalinity, dissolved cations and trace metals, major anions, total element concentrations) were studied at two active sulphide mine tailings impoundments in Finland (the Hitura Ni mine and Luikonlahti Cu mine/talc processing plant). The data were used to assess the factors influencing tailings seepage quality and to identify constraints for water treatment. Changes in seepage water quality after equilibration with atmospheric conditions were evaluated based on geochemical modelling. At Luikonlahti, annual and seasonal changes were also studied. Seepage quality was largely influenced by the tailings mineralogy, and the serpentine-rich, low sulphide Hitura tailings produced neutral mine drainage with high Ni. In contrast, drainage from the high sulphide, multi-metal tailings of Luikonlahti represented typical acid mine drainage with elevated contents of Zn, Ni, Cu, and Co. Other factors affecting the seepage quality included weathering of the tailings along the seepage flow path, process water input, local hydrological settings, and structural changes in the tailings impoundment. Geochemical modelling showed that pH increased and some heavy metals were adsorbed to Fe precipitates after net alkaline waters equilibrated with the atmosphere. In the net acidic waters, pH decreased and no adsorption occurred. A combination of aerobic and anaerobic treatments is proposed for Hitura seepages to decrease the sulphate and metal loading. For Luikonlahti, prolonged monitoring of the seepage quality is suggested instead of treatment, since the water quality is still adjusting to recent modifications to the tailings impoundment.

  10. Surface-type repository for low and intermediate level radioactive waste in the Republic of Croatia

    International Nuclear Information System (INIS)

    Kucar-Dragicevic, S.; Zarkovic, V.; Subasic, D.

    1995-01-01

    The low-level intermediate-level (LL/IL) radioactive waste repository siting and construction project is one of the activities related to establishing the rad waste management system in the Republic of Croatia. The repository project design is one in an array of project activities which also include the site selection procedure and public attitude issues. The prepared design documentation gives technical, safety and financial background relevant for making a final decision on the waste disposal type, and it includes the technological, mechanical, civil and financial documentation on the preliminary/basic design level. During the last few years, the preliminary design has been prepared and safety assessment conducted for the tunnel-type LL/IL rad waste repository. As the surface-type repository is one of alternatives for final disposal the design documentation for that repository type was prepared during 1994. (author)

  11. Definition of intrusion scenarios and example concentration ranges for the disposal of near-surface waste at the Hanford Site

    International Nuclear Information System (INIS)

    Aaberg, R.L.; Kennedy, W.E. Jr.

    1990-10-01

    The US Department of Energy (DOE) is in the process of conducting performance assessments of its radioactive waste sites and disposal systems to ensure that public health and safety are protected, the environment is preserved, and that no remedial actions after disposal are required. Hanford Site low-level waste performance assessments are technical evaluations of waste sites or disposal systems that provide a basis for making decisions using established criteria. The purpose of this document is to provide a family of scenarios to be considered when calculating radionuclide exposure to individuals who may inadvertently intrude into near-surface waste disposal sites. Specific performance assessments will use modifications of the general scenarios described here to include additional site/system details concerning the engineering design, waste form, inventory, and environmental setting. This document also describes and example application of the Hanford-specific scenarios in the development of example concentration ranges for the disposal of near-surface wastes. The overall goal of the example calculations is to illustrate the application of the scenarios in a performance assessment to assure that people in the future cannot receive a dose greater than an established limit. 24 refs., 2 figs., 5 tabs

  12. A literature review of surface alteration layer effects on waste glass behavior

    International Nuclear Information System (INIS)

    Feng, X.; Cunnane, J.C.; Bates, J.K.

    1993-01-01

    When in contact with an aqueous solution, nuclear waste glass is subject to a chemical attack that results in progressive alteration. During tills alteration, constituent elements of the glass pass into the solution; elements initially in solution diffuse into, or are adsorbed onto, the solid; and new phases appear. This results in the formation of surface layers on the reacted glass. The glass corrosion and radionuclide release can be better understood by investigating these surface layer effects. In the past decade, there have been numerous studies regarding the effects of surface layers on glass reactions. This paper presents a systematic analysis and summary of the past knowledge regarding the effects of surface layers on glass-water interaction. This paper describes the major formation mechanisms of surface layers; reviews the role of surface layers in controlling mass transport and glass reaction affinity (through crystalline phases, an amorphous silica, a gel layer, or all the components in the glass); and discusses how the surface layers contribute to the retention of radionuclides during glass dissolution

  13. Source tracking swine fecal waste in surface water proximal to swine concentrated animal feeding operations.

    Science.gov (United States)

    Heaney, Christopher D; Myers, Kevin; Wing, Steve; Hall, Devon; Baron, Dothula; Stewart, Jill R

    2015-04-01

    Swine farming has gone through many changes in the last few decades, resulting in operations with a high animal density known as confined animal feeding operations (CAFOs). These operations produce a large quantity of fecal waste whose environmental impacts are not well understood. The purpose of this study was to investigate microbial water quality in surface waters proximal to swine CAFOs including microbial source tracking of fecal microbes specific to swine. For one year, surface water samples at up- and downstream sites proximal to swine CAFO lagoon waste land application sites were tested for fecal indicator bacteria (fecal coliforms, Escherichia coli and Enterococcus) and candidate swine-specific microbial source-tracking (MST) markers (Bacteroidales Pig-1-Bac, Pig-2-Bac, and Pig-Bac-2, and methanogen P23-2). Testing of 187 samples showed high fecal indicator bacteria concentrations at both up- and downstream sites. Overall, 40%, 23%, and 61% of samples exceeded state and federal recreational water quality guidelines for fecal coliforms, E. coli, and Enterococcus, respectively. Pig-1-Bac and Pig-2-Bac showed the highest specificity to swine fecal wastes and were 2.47 (95% confidence interval [CI]=1.03, 5.94) and 2.30 times (95% CI=0.90, 5.88) as prevalent proximal down- than proximal upstream of swine CAFOs, respectively. Pig-1-Bac and Pig-2-Bac were also 2.87 (95% CI=1.21, 6.80) and 3.36 (95% CI=1.34, 8.41) times as prevalent when 48 hour antecedent rainfall was greater than versus less than the mean, respectively. Results suggest diffuse and overall poor sanitary quality of surface waters where swine CAFO density is high. Pig-1-Bac and Pig-2-Bac are useful for tracking off-site conveyance of swine fecal wastes into surface waters proximal to and downstream of swine CAFOs and during rain events. Copyright © 2014 Elsevier B.V. All rights reserved.

  14. Surface water management at a mixed waste remediation site

    International Nuclear Information System (INIS)

    Schlotzhauer, D.S.; Warbritton, K.R.

    1991-01-01

    The Weldon Spring Remedial Action Project (WSSRAP) deals with chemical and radiological contaminants. MK-Ferguson Company is managing the project under contract with the US Department of Energy. Remedial activities include demolishing buildings, constructing material storage and staging areas, excavating and consolidating waste materials, and treating and disposing of the materials in a land disposal facility. Due to the excavation and construction required during remediation, a well-planned surface water management system is essential. Planning involves characterization of source areas and surface water transport mechanisms and identification of applicable regulations. System components include: erosion control sediment control, flow attenuation, and management of contaminated water. Combinations of these components may be utilized during actual construction and remediation to obtain optimum control. Monitoring is performed during implementation in order to assess the effectiveness of control measures. This management scheme provides for comprehensive management of surface water at this site by providing control and/or treatment to appropriate standards. Although some treatment methodologies for contaminated water are specific to site contaminants, this comprehensive program provides a management approach which is applicable to many remedial projects in order to minimize contaminant release and meet Clean Water Act requirements

  15. A Risk Assessment Approach to Manage Inundation of Elseya albagula Nests in Impounded Waters: A Win-Win Situation?

    Science.gov (United States)

    McDougall, A. J.; Espinoza, T.; Hollier, C.; Limpus, D. J.; Limpus, C. J.

    2015-03-01

    A risk assessment process was used to trial the impact of potential new operating rules on the frequency of nest inundation for the White-throated snapping turtle, Elseya albagula, in the impounded waters of the Burnett River, Queensland, Australia. The proposed operating rules would increase the barrage storage level during the turtle nesting season (May-July) and then would be allowed to reduce to a lower level for incubation for the rest of the year. These proposed operating rules reduce rates of nest inundation by altering water levels in the Ben Anderson Barrage impoundment of the Burnett River. The rules operate throughout the turtle reproductive period and concomitantly improve stability of littoral habitat and fishway operation. Additionally, the proposed rules are expected to have positive socio-economic benefits within the region. While regulated water resources will inherently have a number of negative environmental implications, these potential new operating rules have the capacity to benefit the environment while managing resources in a more sustainable manner. The operating rules have now been enacted in subordinate legislation and require the operator to maintain water levels to minimize turtle nest inundation.

  16. Microcrustaceans (Branchipoda and Copepoda) of Wetland Impoundments on the Savannah River Site, Aiken, South Carolina

    Energy Technology Data Exchange (ETDEWEB)

    DeBiase, Adrienne E; Taylor, Barbara E

    2005-09-21

    The United States Department of Energy’s Savannah River Site (SRS) in Aiken, Allendale, and Barnwell Counties, South Carolina, contains an abundance of freshwater wetlands and impoundments. Four large impoundments, as well as several small, abandoned farm and mill ponds, and about 400 Carolina bays and other small, isolated depression wetland ponds are located within the 893 km2 area of the SRS. Crustaceans of the orders Branchiopoda and Copepoda are nearly ubiquitous in these water bodies. Although small in size, these organisms are often very abundant. They consequently play an important trophic role in freshwater food webs supporting fish, larval salamanders, larval insects, and numerous other animals, aquatic and terrestrial. This report provides an introduction to the free-living microcrustaceans of lentic water bodies on the SRS and a comprehensive list of species known to occur there. Occurrence patterns are summarized from three extensive survey studies, supplemented with other published and unpublished records. In lieu of a key, we provide a guide to taxonomic resources and notes on undescribed species. Taxa covered include the orders Cladocera, Anostraca, Laevicaudata, and Spinicaudata of the Subclass Branchiopoda and the Superorders Calanoida and Cyclopoida of Subclass Copepoda. Microcrustaceans of the Superorder Harpacticoida of the Subclass Copepoda and Subclass Ostracoda are also often present in lentic water bodies. They are excluded from this report because they have not received much study at the species level on the SRS.

  17. Vertical Drop Of 21-PWR Waste Package On Unyielding Surface

    International Nuclear Information System (INIS)

    S. Mastilovic; A. Scheider; S.M. Bennett

    2001-01-01

    The objective of this calculation is to determine the structural response of a 21-PWR (pressurized-water reactor) Waste Package (WP) subjected to the 2-m vertical drop on an unyielding surface at three different temperatures. The scope of this calculation is limited to reporting the calculation results in terms of stress intensities in two different WP components. The information provided by the sketches (Attachment I) is that of the potential design of the type of WP considered in this calculation, and all obtained results are valid for that design only

  18. Study of 'inadvertent human intrusion or rare natural event scenarios' for sub-surface disposal of radioactive waste

    International Nuclear Information System (INIS)

    Nakatani, Takayoshi; Ishitoya, Kimihide; Funabashi, Hideyuki; Sugaya, Toshikatsu; Sone, Tomoyuki; Shimada, Hidemitsu; Nakai, Kunihiro

    2010-03-01

    Japan Atomic Energy Agency (JAEA) is making preparations for the sub-surface disposal of radioactive wastes, in an integrated fashion according to the properties of the waste material regardless of the generators or waste sources. In this study, 'Inadvertent Human Intrusion or Rare Natural Event Scenarios' of 'Three Types scenarios' was considered according to the standard of the Atomic Energy Society of Japan (AESJ) on the sub-surface disposal system that was based on 'Basic Policy for Safety Regulation Concerning Land Disposal of Low-Level Radioactive Waste (Interim Report)' by Nuclear Safety Commission of Japan (NSC). Selection of the assessed scenarios, development of the assessment tool and preliminary exposure dose assessment for general public were conducted. Among the assessed scenarios, the exposure dose of 'well water drinking scenario' was the highest under the very conservative assessment condition. This scenario assumed that the groundwater in Excavation Disturbed Zone (EDZ) was directly used as drinking water without any dilution. Although this was very conservative condition and the result exceeded 10 mSv/y, it stayed under the upper limit of standard dose value for 'Inadvertent Human Intrusion or Rare Natural Event Scenarios' (10 - 100 mSv/y). (author)

  19. Surface hydrologic characteristics of proposed repository locations in the Palo Duro Basin of the Texas Panhandle

    International Nuclear Information System (INIS)

    1985-04-01

    This report provides a description of the surface hydrology in the two proposed locations of a high-level waste repository within the Palo Duro Basin of the Texas Panhandle. Included for consideration are the topography; the major drainage systems - Palo Duro, Tierra Blanca, and Tule Creeks, and Prairie Dog Town Fork of the Red River; and the most prominent impoundments, the playa lakes. The magnitude and frequency of precipitation throughout the region are discussed, and rainfall depth-duration-area data for the 100-year, 500-year, and probable maximum storms are presented. Soil properties are also described, with specific reference to the infiltration and runoff processes and the contribution of these processes to Ogallala aquifer recharge. A summary discussion of the local streams includes information on historical streamflow, a brief description of flooding, and results of a study of floodplains for the 100-year, 500-year, and probable maximum storms. The report concludes with a characterization of the water quality of these streams and an explanation of the local geologic influences on stream-water chemistry. 25 figures, 20 tables

  20. Safety Assessment Methodologies and Their Application in Development of Near Surface Waste Disposal Facilities--ASAM Project

    International Nuclear Information System (INIS)

    Batandjieva, B.; Metcalf, P.

    2003-01-01

    Safety of near surface disposal facilities is a primary focus and objective of stakeholders involved in radioactive waste management of low and intermediate level waste and safety assessment is an important tool contributing to the evaluation and demonstration of the overall safety of these facilities. It plays significant role in different stages of development of these facilities (site characterization, design, operation, closure) and especially for those facilities for which safety assessment has not been performed or safety has not been demonstrated yet and the future has not been decided. Safety assessments also create the basis for the safety arguments presented to nuclear regulators, public and other interested parties in respect of the safety of existing facilities, the measures to upgrade existing facilities and development of new facilities. The International Atomic Energy Agency (IAEA) has initiated a number of research coordinated projects in the field of development and improvement of approaches to safety assessment and methodologies for safety assessment of near surface disposal facilities, such as NSARS (Near Surface Radioactive Waste Disposal Safety Assessment Reliability Study) and ISAM (Improvement of Safety Assessment Methodologies for Near Surface Disposal Facilities) projects. These projects were very successful and showed that there is a need to promote the consistent application of the safety assessment methodologies and to explore approaches to regulatory review of safety assessments and safety cases in order to make safety related decisions. These objectives have been the basis of the IAEA follow up coordinated research project--ASAM (Application of Safety Assessment Methodologies for Near Surface Disposal Facilities), which will commence in November 2002 and continue for a period of three years

  1. Control of water infiltration into near-surface, low-level waste-disposal units in humid regions

    International Nuclear Information System (INIS)

    O'Donnell, E.; Ridky, R.W.; Schulz, R.K.

    1994-01-01

    This study's objective is to assess means for controlling water infiltration through waste-disposal unit covers in humid regions. Experimental work is being performed in large-scale lysimeters (75 ft x 45 ft x 10 ft) at Beltsville, Maryland. Results of the assessment are applicable to disposal of low-level radioactive waste (LLW), uranium mill tailings, hazardous waste, and sanitary landfills. Three kinds of waste-disposal unit covers or barriers to water infiltration are being investigated: (1) resistive layer barrier, (2) conductive layer barrier, and (3) bioengineering management. The resistive layer barrier consists of compacted earthen material (e.g., clay). The conductive layer barrier consists of a conductive layer in conjunction with a capillary break. As long as unsaturated flow conditions are maintained, the conductive layer will wick water around the capillary break. Below-grade layered covers such as (1) and (2) will fail if there is appreciable subsidence of the cover, and remedial action for this kind of failure will be difficult. A surface cover, called bioengineering management, is meant to overcome this problem. The bioengineering management surface barrier is easily repairable if damaged by subsidence; therefore, it could be the system of choice under active subsidence conditions. The bioengineering management procedure also has been shown to be effective in dewatering saturated trenches and could be used for remedial action efforts. After cessation of subsidence, that procedure could be replaced by a resistive layer barrier or, perhaps even better, by a resistive layer barrier/conductive layer barrier system. The latter system would then give long-term effective protection against water entry into waste without institutional care

  2. Acidic Microenvironments in Waste Rock Characterized by Neutral Drainage: Bacteria–Mineral Interactions at Sulfide Surfaces

    Directory of Open Access Journals (Sweden)

    John W. Dockrey

    2014-03-01

    Full Text Available Microbial populations and microbe-mineral interactions were examined in waste rock characterized by neutral rock drainage (NRD. Samples of three primary sulfide-bearing waste rock types (i.e., marble-hornfels, intrusive, exoskarn were collected from field-scale experiments at the Antamina Cu–Zn–Mo mine, Peru. Microbial communities within all samples were dominated by neutrophilic thiosulfate oxidizing bacteria. However, acidophilic iron and sulfur oxidizers were present within intrusive waste rock characterized by bulk circumneutral pH drainage. The extensive development of microbially colonized porous Fe(III (oxyhydroxide and Fe(III (oxyhydroxysulfate precipitates was observed at sulfide-mineral surfaces during examination by field emission-scanning electron microscopy-energy dispersive X-ray spectroscopy (FE-SEM-EDS. Linear combination fitting of bulk extended X-ray absorption fine structure (EXAFS spectra for these precipitates indicated they were composed of schwertmannite [Fe8O8(OH6–4.5(SO41–1.75], lepidocrocite [γ-FeO(OH] and K-jarosite [KFe3(OH6(SO42]. The presence of schwertmannite and K-jarosite is indicative of the development of localized acidic microenvironments at sulfide-mineral surfaces. Extensive bacterial colonization of this porous layer and pitting of underlying sulfide-mineral surfaces suggests that acidic microenvironments can play an important role in sulfide-mineral oxidation under bulk circumneutral pH conditions. These findings have important implications for water quality management in NRD settings.

  3. Chlorophyll Detection and Mapping of Shallow Water Impoundments Using Image Spectrometry

    International Nuclear Information System (INIS)

    Artigas, F.; Pechmann, I.; Marti, A.; Yao, N.; Pechmann, I.

    2008-01-01

    There exists a common perception that chlorophyll a concentrations in tidal coastal waters are unsuitable to be captured by remote sensing techniques because of high water turbidity. In this study, we use band index measurements to separate active chlorophyll pigments from other constituents in the water. Published single- and multiband spectral indices are used to establish a relationship between algal chlorophyll concentration and reflectance data. We find an index which is suitable to map chlorophyll gradients in the impoundments, ditches, and associated waterways of the Hackensack Meadow lands (NJ, USA). The resulting images clearly depict the spatial distribution of plant pigments and their relationship with the biological conditions of the waters in the estuary. Since these biological conditions are often determined by land usage, the methods in this paper provide a simple tool to address water quality management issues in fragmented urban estuaries.

  4. Hydrologic considerations for rock RIPRAP protection of uranium tailings impoundments

    International Nuclear Information System (INIS)

    Walters, W.H.; Skaggs, R.L.

    1984-02-01

    Pacific Northwest Laboratory is conducting an in-depth study of the application of rock riprap for the long-term protection of uranium tailings impoundments. Decommissioned tailings sites at Grand Junction and Slickrock, Colorado were selected to review the application of riprap design methods and evaluate variable sensitivity and data requirements. Preliminary results from the Grand Junction case study indicate that the use of a safety factor in sizing the rock riprap may provide an overly conservative design that may not be justified. Some safety factor, usually a value of 1.5 to 2.0 is normally used in riprap design to allow for the uncertainties in the hydraulic calculations. The computation of the hydraulic designs variables using the probable maximum flood (PMF) event introduces conservatism into the design and the added safety factor may not be warranted. This paper presents some preliminary results from the Grand Junction site concerning the implications of using a safety factor for riprap design. 9 references, 2 figures, 2 tables

  5. Sulfide oxidation and acid mine drainage formation within two active tailings impoundments in the Golden Quadrangle of the Apuseni Mountains, Romania.

    Science.gov (United States)

    Sima, Mihaela; Dold, Bernhard; Frei, Linda; Senila, Marin; Balteanu, Dan; Zobrist, Jurg

    2011-05-30

    Sulfidic mine tailings have to be classified as one of the major source of hazardous materials leading to water contamination. This study highlights the processes leading to sulfide oxidation and acid mine drainage (AMD) formation in the active stage of two tailings impoundments located in the southern part of the Apuseni Mountains, in Romania, a well-known region for its long-term gold-silver and metal mining activity. Sampling was undertaken when both impoundments were still in operation in order to assess their actual stage of oxidation and long-term behavior in terms of the potential for acid mine drainage generation. Both tailings have high potential for AMD formation (2.5 and 3.7 wt.% of pyrite equivalent, respectively) with lesser amount of carbonates (5.6 and 3.6 wt.% of calcite equivalent) as neutralization potential (ABA=-55.6 and -85.1 tCaCO(3)/1000 t ) and showed clear signs of sulfide oxidation yet during operation. Sequential extraction results indicate a stronger enrichment and mobility of elements in the oxidized tailings: Fe as Fe(III) oxy-hydroxides and oxides (transformation from sulfide minerals, leaching in oxidation zone), Ca mainly in water soluble and exchangeable form where gypsum and calcite are dissolved and higher mobility of Cu for Ribita and Pb for Mialu. Two processes leading to the formation of mine drainage at this stage could be highlighted (1) a neutral Fe(II) plume forming in the impoundment with ferrihydrite precipitation at its outcrop and (2) acid mine drainage seeping in the unsaturated zone of the active dam, leading to the formation of schwertmannite at its outcrop. Copyright © 2011 Elsevier B.V. All rights reserved.

  6. Fishers' knowledge identifies environmental changes and fish abundance trends in impounded tropical rivers.

    Science.gov (United States)

    Hallwass, Gustavo; Lopes, Priscila F; Juras, Anastácio A; Silvano, Renato A M

    2013-03-01

    The long-term impacts of large hydroelectric dams on small-scale fisheries in tropical rivers are poorly known. A promising way to investigate such impacts is to compare and integrate the local ecological knowledge (LEK) of resource users with biological data for the same region. We analyzed the accuracy of fishers' LEK to investigate fisheries dynamics and environmental changes in the Lower Tocantins River (Brazilian Amazon) downstream from a large dam. We estimated fishers' LEK through interviews with 300 fishers in nine villages and collected data on 601 fish landings in five of these villages, 22 years after the dam's establishment (2006-2008). We compared these two databases with each other and with data on fish landings from before the dam's establishment (1981) gathered from the literature. The data obtained based on the fishers' LEK (interviews) and from fisheries agreed regarding the primary fish species caught, the most commonly used type of fishing gear (gill nets) and even the most often used gill net mesh sizes but disagreed regarding seasonal fish abundance. According to the interviewed fishers, the primary environmental changes that occurred after the impoundment were an overall decrease in fish abundance, an increase in the abundance of some fish species and, possibly, the local extinction of a commercial fish species (Semaprochilodus brama). These changes were corroborated by comparing fish landings sampled before and 22 years after the impoundment, which indicated changes in the composition of fish landings and a decrease in the total annual fish production. Our results reinforce the hypothesis that large dams may adversely affect small-scale fisheries downstream and establish a feasible approach for applying fishers' LEK to fisheries management, especially in regions with a low research capacity.

  7. Types of safety assessments of near surface repository for radioactive waste

    International Nuclear Information System (INIS)

    Mateeva, M.

    2004-01-01

    The purpose of this article is to presents the classification of different types safety assessments of near surface repository for low and intermediate level radioactive waste substantiated with results of safety assessments generated in Bulgaria. The different approach of safety assessments applied for old existing repository as well as for site selection for construction new repository is outlined. The regulatory requirements in Bulgaria define three main types of assessments: Safety assessment; Technical substation of repository safety; Assessment of repository influence on environment that is in form of report prepared from the Ministry of environment and waters on the base of results obtained in two first types of assessments. Additionally first type is subdivided in three categories - preliminary safety assessment, safety assessment and post closure safety assessment, which are generated using deterministic approach. The technical substation of repository safety is generated using probabilistic approach. Safety assessment results that are presented here are based on evaluation of existing old repository type 'Radon' in Novi Han and real site selection procedure for new near surface repository for low and intermediate level radioactive waste from nuclear power station in Kozloduy. The important role of safety assessment for improvement the repository safety as well as for repository licensing, correct site selection and right choice of engineer barriers and repository design is discussed using generated results. (author)

  8. Hybrid selective surface hydrophilization and froth flotation separation of hazardous chlorinated plastics from E-waste with novel nanoscale metallic calcium composite

    Energy Technology Data Exchange (ETDEWEB)

    Mallampati, Srinivasa Reddy, E-mail: srireddys@ulsan.ac.kr; Heo, Je Haeng; Park, Min Hee

    2016-04-05

    Highlights: • Nanometallic Ca/CaO treatment significantly enhanced PVC surface hydrophilicity. • The contact angle of PVC significantly decreased compared to other E-waste plastics. • 100% of PVC was selectively separated with 96.4% purity from E-waste plastics. • SEM/XPS results indicated an oxidative degradation of chlorides on the PVC surface. • Hybrid treatment with nanometallic Ca/CaO and froth flotation is effective. - Abstract: Treatment by a nanometallic Ca/CaO composite has been found to selectively hydrophilize the surface of polyvinyl chloride (PVC), enhancing its wettability and thereby promoting its separation from E-waste plastics by means of froth flotation. The treatment considerably decreased the water contact angle of PVC, by about 18°. The SEM images of the PVC plastic after treatment displayed significant changes in their surface morphology compared to other plastics. The SEM-EDS results reveal that a markedly decrease of [Cl] concentration simultaneously with dramatic increase of [O] on the surface of the PCV samples. XPS results further confirmed an increase of hydrophilic functional groups on the PVC surface. Froth flotation at 100 rpm mixing speed was found to be optimal, separating 100% of the PVC into a settled fraction of 96.4% purity even when the plastics fed into the reactor were of nonuniform size and shape. The total recovery of PVC-free plastics in E-waste reached nearly 100% in the floated fraction, significantly improved from the 20.5 wt% of light plastics that can be recovered by means of conventional wet gravity separation. The hybrid method of nanometallic Ca/CaO treatment and froth flotation is effective in the separation of hazardous chlorinated plastics from E-waste plastics.

  9. Hybrid selective surface hydrophilization and froth flotation separation of hazardous chlorinated plastics from E-waste with novel nanoscale metallic calcium composite

    International Nuclear Information System (INIS)

    Mallampati, Srinivasa Reddy; Heo, Je Haeng; Park, Min Hee

    2016-01-01

    Highlights: • Nanometallic Ca/CaO treatment significantly enhanced PVC surface hydrophilicity. • The contact angle of PVC significantly decreased compared to other E-waste plastics. • 100% of PVC was selectively separated with 96.4% purity from E-waste plastics. • SEM/XPS results indicated an oxidative degradation of chlorides on the PVC surface. • Hybrid treatment with nanometallic Ca/CaO and froth flotation is effective. - Abstract: Treatment by a nanometallic Ca/CaO composite has been found to selectively hydrophilize the surface of polyvinyl chloride (PVC), enhancing its wettability and thereby promoting its separation from E-waste plastics by means of froth flotation. The treatment considerably decreased the water contact angle of PVC, by about 18°. The SEM images of the PVC plastic after treatment displayed significant changes in their surface morphology compared to other plastics. The SEM-EDS results reveal that a markedly decrease of [Cl] concentration simultaneously with dramatic increase of [O] on the surface of the PCV samples. XPS results further confirmed an increase of hydrophilic functional groups on the PVC surface. Froth flotation at 100 rpm mixing speed was found to be optimal, separating 100% of the PVC into a settled fraction of 96.4% purity even when the plastics fed into the reactor were of nonuniform size and shape. The total recovery of PVC-free plastics in E-waste reached nearly 100% in the floated fraction, significantly improved from the 20.5 wt% of light plastics that can be recovered by means of conventional wet gravity separation. The hybrid method of nanometallic Ca/CaO treatment and froth flotation is effective in the separation of hazardous chlorinated plastics from E-waste plastics.

  10. Contents and Sample Arguments of a Safety Case for Near Surface Disposal of Radioactive Waste

    International Nuclear Information System (INIS)

    2017-06-01

    This publication arises from the results of two projects to assist Member States in understanding and developing safety cases for near-surface radioactive waste disposal facilities. The objective of the publication is to give detailed information on the contents of safety cases for radioactive waste disposal and the types of arguments that may be included. It is written for technical experts preparing a safety case, and decision makers in the regulatory body and government. The publication outlines the key uses and aspects of the safety case, its evolution in parallel with that of the disposal facility, the key decision steps in the development of the waste disposal facility, the components of the safety case, their place in the Matrix of Arguments for a Safety Case (the MASC matrix), and a detailed description of the development of sample arguments that might be included in a safety case for each of two hypothetical radioactive waste disposal facilities.

  11. Effect of soil erosion on the long-term stability of FUSRAP near-surface waste-burial sites

    International Nuclear Information System (INIS)

    Knight, M.J.

    1983-04-01

    Decontamination of FUSRAP sites could result in the generation of large volumes (in excess of 400,000 m 3 ) of low-activity radioactive wastes (primarily contaminated soil and building materials) requiring subsequent disposal. It is likely that near-surface burial will be seriously considered as an option for disposal of these materials. A number of factors - including soil erosion - could adversely affect the long-term stability of a near-surface waste-burial site. The majority of FUSRAP sites are located in the humid eastern United States, where the principal cause of erosion is the action of water. This report examines the effect of soil erosion by water on burial-site stability based on analysis of four hypothetical near-surface burial sites. The Universal Soil Loss Equation was employed to estimate average annual soil loss from burial sites and the 1000-year effects of soil loss on the soil barrier (burial trench cap) placed over low-activity wastes. Results suggest that the land use of the burial site and the slope gradient of the burial trench cap significantly affect the rate of soil erosion. The development of measures limiting the potential land use of a burial site (e.g., mixing large rocks into the burial trench cap) may be required to preserve the integrity of a burial trench for long periods of time

  12. Technical considerations in the design of near surface disposal facilities for radioactive waste

    International Nuclear Information System (INIS)

    2001-11-01

    Good design is an important step towards ensuring operational as well as long term safety of low and intermediate level waste (LILW) disposal. The IAEA has produced this report with the objective of outlining the most important technical considerations in the design of near surface disposal facilities and to provide some examples of the design process in different countries. This guidance has been developed in light of experience gained from the design of existing near surface disposal facilities in a range of Member States. In particular the report provide information on design objective, design requirements, and design phases. The report focuses on: near surface disposal facilities accepting solidified LILW; disposal facilities on or just below the ground surface, where the final protective covering is of the order of a few metres thick; and disposal facilities several tens of metres below the ground surface (including rock cavern type facilities)

  13. 120-D-1 (100-D) Ponds supplemental information to the Hanford Facility Contingency Plan. Revision 2

    International Nuclear Information System (INIS)

    Petersen, S.W.; Zoric, J.P.

    1997-06-01

    This document is a supplement to the Hanford Facility Contingency Plan and provides the unit-specific information needed to fully comply with the Washington Administrative Code 173-303 for contingency plans. The 100-D ponds are unlined surface impoundments that were mainly used to dispose of nondangerous wastewater, The ponds are designated as a single treatment, storage, and/or disposal unit because of potential corrosive characteristics of the wastewater. No waste is currently present at the 100-D Ponds

  14. Near-surface groundwater responses to injection of geothermal wastes

    Energy Technology Data Exchange (ETDEWEB)

    Arnold, S.C.

    1984-06-01

    Experiences with injecting geothermal fluids have identified technical problems associated with geothermal waste disposal. This report assesses the feasibility of injection as an alternative for geothermal wastewater disposal and analyzes hydrologic controls governing the upward migration of injected fluids. Injection experiences at several geothermal developments are presented, including: Raft River, Salton Sea, East Mesa, Otake and Hatchobaru in Japan, and Ahuachapan in El Salvador. Hydrogeologic and design/operational factors affecting the success of an injection program are identified. Hydrogeologic factors include subsidence, near-surface effects of injected fluids, and seismicity. Design/operational factors include hydrodynamic breakthrough, condition of the injection system and reservoir maintenance. Existing and potential effects of production/injection on these factors are assessed.

  15. Enlargement of the Baldone near-surface radioactive waste repository

    International Nuclear Information System (INIS)

    Dreimanis, A.

    2007-01-01

    A unified analysis of the enlargement of the Baldone near-surface radioactive waste (RW) repository RADONS considers the interplay of the existing engineering, safety and infrastructure premises, with the foreseen newly socio-technical features. This enlargement consists in construction of two additional RW disposal vaults and in building a long-term storage facility for spent sealed sources at the RADONS territory. Our approach is based on consecutive analysis of following basic elements: - the origin of enlargement - the RADONS safety analysis and a set of optimal socio-technical solutions of Salaspils research reactor decommissioning waste management; - the enlargement - a keystone of the national RW management concept, including the long-term approach; - the enlargement concept - the result of international co-operation and obligations; - arrangement optimization of new disposal and storage space; - environmental impact assessment for the repository enlargement - the update of socio-technical studies. The study of the public opinion revealed: negative attitude to repository enlargement is caused mainly due to missing information on radiation level and on the RADONS previous operations. These results indicate: basic measures to improve the public attitude to repository enlargement: the safety upgrade, public education and compensation mechanisms. A detailed stakeholders engagement and public education plan is elaborated. (author)

  16. 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.)

  17. Hydrologic Change during the Colonial Era of the United States: Beavers and the Energy Cost of Impoundments (Invited)

    Science.gov (United States)

    Green, M. B.; Bain, D. J.; Arrigo, J. S.; Duncan, J. M.; Kumar, S.; Parolari, A.; Salant, N.; Vorosmarty, C. J.; Aloysius, N. R.; Bray, E. N.; Ruffing, C. M.; Witherell, B. B.

    2009-12-01

    Europeans colonized North America in the early 17th century with intentions ranging between long-term inhabitation and quick extraction of resources for economic gain in Europe. Whatever the intentions, the colonists relied on the landscape for resources resulting in dramatic change to the forest and fur-bearing mammal population. We demonstrate that initial exploitation of North American forest and furs caused a substantial decrease in mean water residence time (τ) between 1600 and 1800 A.D. That loss, which regionally changed from 51 to 41 days, contrasts with conventional wisdom that humans tend to diminish variability in water resources by increasing storage capacity and thus increasing τ. The loss of τ resulted from over-hunted beaver for the hat market in Europe. Analysis suggests that colonial era demographics and economics did not allow human resource allocation to impoundment construction on a level matching the historic beaver effort. However, the τ appears to have regionally increased during the 19th century, suggesting that humans eventually began replacing the water storage lost with the beaver. The analysis highlights the energy cost of impounding water, which is likely to continue to be an important factor given the increasing need for stable water resources and finite energy resources.

  18. The surface water model for assessing Canada's nuclear fuel waste disposal concept

    International Nuclear Information System (INIS)

    Bird, G.A.; Stephenson, M.; Cornett, R.J.

    1993-01-01

    Canada's Nuclear Fuel Waste Management Program (NFWMP) is investigating the concept of disposal of nuclear fuel waste in a vault excavated deep in crystalline rock on the Canadian Shield. Probabilistic vault, geosphere, and biosphere models are implemented using Monte Carlo simulation techniques to trace nuclides transported in groundwater to the surface environment and humans far into the future. This paper describes the surface water submodel and its parameter values, sensitivity analysis, and validation. The surface water model is a simple, time-dependent, mass balance model of a lake that calculates radioactive and stable isotope contaminant concentrations in lake water and sediment. These concentrations are input to the other submodels and used to predict the radiological dose to humans and other biota. Parameter values in the model are based on the literature and the author's own data, and are generic to Canadian Shield lakes. Most parameters are represented by log normally distributed probability density functions. Sensitivity analysis indicates that nuclide concentrations in lake water and sediment are governed primarily by hydrological flushing with catchment area being the most important parameter. When catchment area is held constant lake area and nuclide transfer rate from water to sediment strongly influence concentrations in both water and sediment. For volatile nuclides, gaseous evasion also has a marked influence on concentrations in both water and sediment, whereas sedimentation rate strongly influences sediment nuclide concentrations. Validation tests demonstrate that the models predictions for 60 Co, 134 Cs, 3 H, P, Cd and Ca are consistent with empirical data when uncertainties are taken into account

  19. Method and device of decontaminating radioactive solid wastes

    International Nuclear Information System (INIS)

    Hasegawa, Hiroshi; Tamada, Masami.

    1983-01-01

    Purpose: To surely enable grinding for the inner surface of hollow radioactive solid wastes such as pipeways or valves, as well as enable to decontaminate these solid wastes to such a level as being capable of processing in the same manner for the ordinary wastes. Method: A grinding piece abutting resiliently against the inner surface of a hollow radioactive solid wastes to be contaminated is attached at the top end of a flexible shaft, and the inner surface of the radioactive solid wastes is ground while rotating and slightly reciprocating, as well as axially moving the flexible shaft. Consequently, since the grinding piece is always abutted against the inner surface of the radioactive solid wastes just following after the profile of the inner surface, and the flexible shaft is resiliently flexed corresponding to the profile of the inner surface of the radioactive solid wastes, even an inner surface of radioactive solid wastes with a complicated configuration can surely be ground entirely. This surely enables to remove radioactive claddings and contaminated layers deposited on the surface. (Yoshihara, H.)

  20. Engineered surface barriers for waste disposal sites: lysimeter facility design and construction

    International Nuclear Information System (INIS)

    Phillips, S.J.; Ruben, M.S.; Kirkham, R.R.

    1988-01-01

    A facility to evaluate performance of engineered surface carriers for confinement of buried wastes has been designed, constructed, and operations initiated. The Field Lysimeter Test Facility is located at the US Department of Energy's Hanford Site in Richland, Washington. The facility consists of 18 one-dimensional drainage and weighing lysimeters used to evaluate 7 replicated barrier treatments. Distinct layers of natural earth materials were used to construct layered soil and rock barriers in each lysimeter. These barrier designs are capable in principal of significantly reducing or precluding infiltration of meteoric water through barriers into underlying contaminated zones. This paper summarizes salient facility design and construction features used in testing of the Hanford Site's engineered surface barriers

  1. The long-term safety and performance analyses of the surface disposal facility for the Belgian category a waste at Dessel

    Energy Technology Data Exchange (ETDEWEB)

    Cool, Wim; Vermarien, Elise; Wacquier, William [ONDRAF/NIRAS Avenue des Arts 14, BE-1210 Bruxelles (Belgium); Perko, Janez [SCK-CEN Boeretang 200, BE-2400 Mol (Belgium)

    2013-07-01

    ONDRAF/NIRAS, the Belgian Agency for Radioactive Waste and Enriched Fissile Materials, and its partners have developed long-term safety and performance analyses in the framework of the license application for a surface disposal facility for low level radioactive waste (category A waste) at Dessel, Belgium. This paper focusses on the methodology of the safety assessments and on key results from the application of this methodology. An overview is given (1) of the performance analyses for the containment safety function of the disposal system and (2) of the radiological impact analyses confirming that radiological impacts are below applicable reference values and constraints and leading to radiological criteria for the waste and the facility. In this discussion, multiple indicators for performance and safety are used to illustrate the multi-faceted nature of long-term performance and safety of the surface disposal. This contributes to the multiple lines of reasoning for confidence building that a positive decision to proceed to the next stage of construction is justified. (authors)

  2. Removal of selenium species from waters using various surface-modified natural particles and waste materials

    Energy Technology Data Exchange (ETDEWEB)

    Yigit, Nevzat O.; Tozum, Seda [Department of Environmental Engineering, Suleyman Demirel University, Isparta (Turkey)

    2012-07-15

    Waste red mud and natural pumice/volcanic slag particles were surface modified and their selenium adsorption from waters was investigated. Acid activation/heat treatment of original red mud (ORM) particles significantly increased their micropore and external surface area and cumulative volume of pores. Iron oxide coating of pumice/slags and acid activation of ORM decreased their pH{sub pzc} values and increased surface acidity. Selenite/selenate adsorption on iron oxide surfaces and acid activated red mud (AARM) was very fast with approximately first-order adsorption kinetics. Iron oxide coating of pumice/slag and acid activation of ORM particles significantly enhanced their selenite and selenate uptakes. Maximum Se adsorption capacities as high as 6.3 (mg Se/g adsorbent) were obtained by AARM. The extent of selenate uptakes by the surface modified particles was generally lower than those of selenite. Due to competition among Se species and other background water matrix for iron oxide adsorption sites, reduced selenite/selenate uptakes were found in natural water compared to single solute tests. Higher Se uptakes by iron oxide surfaces were found at pH 7.5 compared to pH 8.9, due to increased electrostatic repulsion among iron oxides and Se species at higher pH. The most effective adsorbents among the tested 17 different particles for Se uptake were AARM and iron oxide coated pumice. Se concentrations less than drinking water standards (5-10 {mu}g/L) can be achieved by these particles. These low-cost, natural, or recyclable waste particles appear to be promising adsorbents for Se removal after their surface modification. (Copyright copyright 2012 WILEY-VCH Verlag GmbH and Co. KGaA, Weinheim)

  3. Analysis of Surface Leaching Processes in Vitrified High-Level Nuclear Wastes Using In-Situ Raman Imaging and Atomistic Modeling - Final Report

    International Nuclear Information System (INIS)

    Simmons, Joseph H.

    2001-01-01

    The in situ analysis of surface conditions of vitrified nuclear wastes can provide an important check of the burial status of radioactive objects without risk of radiation exposure. Raman spectroscopy was initially chosen as the most promising method for testing the surface conditions of glasses undergoing chemical corrosion, and was used extensively during the first year. However, it was determined that infrared reflection spectroscopy was better suited to this particular need and was used for the remaining two years to investigate the surface corrosion behavior of model silicate glasses for extension to nuclear waste glasses. The developed methodology is consistent with the known theory of optical propagation of dielectric media and uses the Kramers-Kronig formalism. The results show that it is possible to study the corrosion of glass by analyzing the glass surface using reflection fast Fourier infrared measurements and the newly developed ''dispersion analysis method.'' The data show how this analysis can be used to monitor the corrosion behavior of vitrified waste glasses over extended periods of storage

  4. 30 CFR 816.87 - Coal mine waste: Burning and burned waste utilization.

    Science.gov (United States)

    2010-07-01

    ... 30 Mineral Resources 3 2010-07-01 2010-07-01 false Coal mine waste: Burning and burned waste...-SURFACE MINING ACTIVITIES § 816.87 Coal mine waste: Burning and burned waste utilization. (a) Coal mine... extinguishing operations. (b) No burning or burned coal mine waste shall be removed from a permitted disposal...

  5. Remaining Sites Verification Package for the 100-B-1 Surface Chemical and Solid Waste Dumping Area,. Attachment to Waste Site Reclassification Form 2006-003

    International Nuclear Information System (INIS)

    Carlson, R.A.

    2006-01-01

    The 100-B-1 waste site was a dumping site that was divided into two areas. One area was used as a laydown area for construction materials, and the other area was used as a chemical dumping area. The 100-B-1 Surface Chemical and Solid Waste Dumping Area site meets the remedial action objectives specified in the Remaining Sites ROD. The results demonstrate that residual contaminant concentrations support future unrestricted land uses that can be represented by a rural-residential scenario. The results also demonstrate that residual contaminant concentrations are protective of groundwater and the Columbia River

  6. Final waste classification and waste form technical position papers

    International Nuclear Information System (INIS)

    1983-05-01

    The waste classification technical position paper describes overall procedures acceptable to NRC staff which may be used by licensees to determine the presence and concentrations of the radionuclides listed in section 61.55, and thereby classifying waste for near-surface disposal. This technical position paper also provides guidance on the types of information which should be included in shipment manifests accompanying waste shipments to near-surface disposal facilities. The technical position paper on waste form provides guidance to waste generators on test methods and results acceptable to NRC staff for implementing the 10 CFR Part 61 waste form requirements. It can be used as an acceptable approach for demonstrating compliance with the 10 CFR Part 61 waste structural stability criteria. This technical position paper includes guidance on processing waste into an acceptable stable form, designing acceptable high-integrity containers, packaging cartridge filters, and minimizing radiation effects on organic ion-exchange resins. The guidance in the waste form technical position paper may be used by licensees as the basis for qualifying process control programs to meet the waste form stability requirements, including tests which can be used to demonstrate resistance to degradation arising from the effects of compression, moisture, microbial activity, radiation, and chemical changes. Generic test data (e.g., topical reports prepared by vendors who market solidification technology) may be used for process control program qualification where such generic data is applicable to the particular types of waste generated by a licensee

  7. Design and operational considerations of United States commercial nea-surface low-level radioactive waste disposal facilities

    International Nuclear Information System (INIS)

    Birk, Sandra M.

    1997-01-01

    Low-level radioactive waste disposal standards and techniques in the United States have evolved significantly since the early 1960's. Six commercial LLW disposal facilities(Barnwell, Richland, Ward Valley, Sierra Blanca, Wake County and Boyd County) operated and proposed between 1962 and 1997. This report summarizes each site's design and operational considerations for near-surface disposal of low-level radioactive waste. These new standards and mitigating efforts at closed facilities (Sheffield, Maxey Flats, Beatty and West Valley) have helped to ensure that the public has been safely protected from LLW. 15 refs

  8. Treatment of alumina refinery waste (red mud) through neutralization techniques: A review.

    Science.gov (United States)

    Rai, Suchita; Wasewar, K L; Agnihotri, A

    2017-06-01

    In the Bayer process of extraction of alumina from bauxite, the insoluble product generated after bauxite digestion with sodium hydroxide at elevated temperature and pressure is known as 'red mud' or 'bauxite residue'. This alumina refinery waste is highly alkaline in nature with a pH of 10.5-12.5 and is conventionally disposed of in mostly clay-lined land-based impoundments. The alkaline constituents in the red mud impose severe and alarming environmental problems, such as soil and air pollution. Keeping in view sustainable re-vegetation and residue management, neutralization/treatment of red mud using different techniques is the only alternative to make the bauxite residue environmentally benign. Hence, neutralization techniques, such as using mineral acids, acidic waste (pickling liquor waste), coal dust, superphosphate and gypsum as amenders, CO 2 , sintering with silicate material and seawater for treatment of red mud have been studied in detail. This paper is based upon and emphasizes the experimental work carried out for all the neutralization techniques along with a comprehensive review of each of the processes. The scope, applicability, limitations and feasibility of these processes have been compared exhaustively. Merits and demerits have been discussed using flow diagrams. All the techniques described are technically feasible, wherein findings obtained with seawater neutralization can be set as a benchmark for future work. Further studies should be focused on exploring the economical viability of these processes for better waste management and disposal of red mud.

  9. Socio-economic and other non-radiological impacts of the near surface disposal of radioactive waste

    International Nuclear Information System (INIS)

    2002-09-01

    The objective of this report is to introduce, in a generic sense, the elements that could comprise a socio-economic and non-radiological environmental impact assessment. The various social, economic and environmental impacts that could be associated with surface and near surface disposal are discussed through factors that could apply at the local, regional or national level. Impact management is also discussed. The report also introduces concepts to help Member States develop their own approaches to undertaking impact assessment and management. The report is intended to complement IAEA documents on the technology and safety aspects of the near surface disposal of radioactive waste. The scope of this report includes a discussion of a range of social, economic and nonradiological environmental impacts relevant to surface and near surface disposal and illustrations of some impact management measures

  10. Geologic waste disposal and a model for the surface movement of radionuclides

    International Nuclear Information System (INIS)

    Helton, J.; Iman, R.; Brown, J.; Schreurs, S.

    1979-01-01

    A model for the surface movement of radionuclides is presented. This model, which is referred to as the Pathways Model, was constructed in a NRC project to develop a methodology to assess the risk associated with the goelogic disposal of high-level radioactive waste. The methodology development involves work in two major areas: (a) models for physical processes, and (b) statistical techniques for the use and assessment of these models. The presentation of the Pathways Model involves topics from both areas

  11. Transuranic waste management program waste form development

    International Nuclear Information System (INIS)

    Bennett, W.S.; Crisler, L.R.

    1981-01-01

    To ensure that all technology necessary for long term management of transuranic (TRU) wastes is available, the Department of Energy has established the Transuranic Waste Management Program. A principal focus of the program is development of waste forms that can accommodate the very diverse TRU waste inventory and meet geologic isolation criteria. The TRU Program is following two approaches. First, decontamination processes are being developed to allow removal of sufficient surface contamination to permit management of some of the waste as low level waste. The other approach is to develop processes which will allow immobilization by encapsulation of the solids or incorporate head end processes which will make the solids compatible with more typical waste form processes. The assessment of available data indicates that dewatered concretes, synthetic basalts, and borosilicate glass waste forms appear to be viable candidates for immobilization of large fractions of the TRU waste inventory in a geologic repository

  12. Microcrustaceans (Branchiopoda and Copepoda) of Wetland Ponds and Impoundments on the Savannah River Site, Aiken, South Carolina

    Energy Technology Data Exchange (ETDEWEB)

    Adrienne E. DeBiase; Barbara E. Taylor

    2005-09-21

    The United States Department of Energy's Savannah River Site (SRS) in Aiken, Allendale, and Barnwell Counties, South Carolina, contains an abundance of freshwater wetlands and impoundments. Four large impoundments, as well as several small, abandoned farm and mill ponds, and about 400 Carolina bays and other small, isolated depression wetland ponds are located within the 893 km2 area of the SRS. Crustaceans of the orders Branchiopoda and Copepoda are nearly ubiquitous in these water bodies. Although small in size, these organisms are often very abundant. They consequently play an important trophic role in freshwater food webs supporting fish, larval salamanders, larval insects, and numerous other animals, aquatic and terrestrial. This report provides an introduction to the free-living microcrustaceans of lentic water bodies on the SRS and a comprehensive list of species known to occur there. Occurrence patterns are summarized from three extensive survey studies, supplemented with other published and unpublished records. In lieu of a key, we provide a guide to taxonomic resources and notes on undescribed species. Taxa covered include the orders Cladocera, Anostraca, Laevicaudata, and Spinicaudata of the Subclass Branchiopoda and the Superorders Calanoida and Cyclopoida of Subclass Copepoda. Microcrustaceans of the Superorder Harpacticoida of the Subclass Copepoda and Subclass Ostracoda are also often present in lentic water bodies. They are excluded from this report because they have not received much study at the species level on the SRS.

  13. The environmental restoration program of the United States Department of Energy

    International Nuclear Information System (INIS)

    Mitchell, S.J.; Schneider, K.J.; Lakey, L.T.; Luik, A.E. van

    1991-01-01

    The Office of Environmental Restoration and Waste Management of the U.S. Department of Energy (U.S. DOE) is responsible for the cleanup of hazardous waste sites and the disposal of nuclear and hazardous wastes from U.S. DOE operations. Operation of DOE facilities has resulted in the creation of burial grounds, storage facilities, underground tanks and pipes, surface impoundments, treatment facilities, and accumulation areas that have the potential for releasing radionuclides and hazardous chemicals into the environment. The primary contaminants at major DOE sites are summarized. As the standards for safe and environmentally sensitive management of wastes have become more stringent the old practices were, in some cases, found to be inadequate. The US Government is committed to effective waste management and the correction of past inadequacies at its facilities and the major initiative to restore its contaminated sites to satisfactory conditions and improve the management of current wastes is explained. (Author)

  14. The surface disposal concept for VLL waste

    International Nuclear Information System (INIS)

    2011-01-01

    Disposal facilities for very-low-level (VLL) waste have been designed to accommodate both residues originating from the decommissioning of nuclear facilities and used components. Those residues have very low specific-activity levels that lie below a few hundreds of becquerels per gram (Bq/g). As for the average activity found in any disposal facility, it never exceeds more than a few tens of becquerels per gram. In that case, waste disposal involves no special processing or conditioning, except for handling requirements or volume-gain purposes. The main barrier against radionuclide dispersion is provided by the geological formation being used for waste disposal. Basic disposal concept The design and construction provisions allow for the optimal operation of the disposal facility without any risk of altering the required safety level. They also ensure a satisfactory containment level for several centuries at the end of the operating lifetime. Hence, the natural materials in their original context constitute a particular advantage for the safety demonstration over the long term. With due account of the nature of VLL waste, their containment envelope (drums, big bags, etc.) has no role in confining radioactivity, but rather in facilitating handling and disposal operations, while protecting operators. Approximately 30% of all waste received at the CSTFA undergo a specific treatment before disposal. Low-density residues (plastics, thermal-insulation materials, etc.) are first compacted by a baling press, then strapped and wrapped in clear plastic-sheet. Another bundle press is used to reduce the volume of scrap metal. Some waste, such as the polluted waters generated on site or the sludges sent by producers, are processed in the solidification and stabilisation unit. Disposal cells are excavated progressively, as needed, directly in the clay formation down to a depth of 8 m and are operated in sequence. Cell design has evolved to maximize the disposal volume, and now

  15. The surface disposal concept for VLL waste

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2011-07-01

    Disposal facilities for very-low-level (VLL) waste have been designed to accommodate both residues originating from the decommissioning of nuclear facilities and used components. Those residues have very low specific-activity levels that lie below a few hundreds of becquerels per gram (Bq/g). As for the average activity found in any disposal facility, it never exceeds more than a few tens of becquerels per gram. In that case, waste disposal involves no special processing or conditioning, except for handling requirements or volume-gain purposes. The main barrier against radionuclide dispersion is provided by the geological formation being used for waste disposal. Basic disposal concept The design and construction provisions allow for the optimal operation of the disposal facility without any risk of altering the required safety level. They also ensure a satisfactory containment level for several centuries at the end of the operating lifetime. Hence, the natural materials in their original context constitute a particular advantage for the safety demonstration over the long term. With due account of the nature of VLL waste, their containment envelope (drums, big bags, etc.) has no role in confining radioactivity, but rather in facilitating handling and disposal operations, while protecting operators. Approximately 30% of all waste received at the CSTFA undergo a specific treatment before disposal. Low-density residues (plastics, thermal-insulation materials, etc.) are first compacted by a baling press, then strapped and wrapped in clear plastic-sheet. Another bundle press is used to reduce the volume of scrap metal. Some waste, such as the polluted waters generated on site or the sludges sent by producers, are processed in the solidification and stabilisation unit. Disposal cells are excavated progressively, as needed, directly in the clay formation down to a depth of 8 m and are operated in sequence. Cell design has evolved to maximize the disposal volume, and now

  16. Design and operational considerations of United States commercial near-surface low-level radioactive waste disposal facilities

    International Nuclear Information System (INIS)

    Birk, S.M.

    1997-10-01

    In accordance with the Low-Level Radioactive Waste Policy Amendments Act of 1985, states are responsible for providing for disposal of commercially generated low-level radioactive waste (LLW) within their borders. LLW in the US is defined as all radioactive waste that is not classified as spent nuclear fuel, high-level radioactive waste, transuranic waste, or by-product material resulting from the extraction of uranium from ore. Commercial waste includes LLW generated by hospitals, universities, industry, pharmaceutical companies, and power utilities. LLW generated by the country''s defense operations is the responsibility of the Federal government and its agency, the Department of Energy. The commercial LLRW disposal sites discussed in this report are located near: Sheffield, Illinois (closed); Maxey Flats, Kentucky (closed); Beatty, Nevada (closed); West Valley, New York (closed); Barnwell, South Carolina (operating); Richland, Washington (operating); Ward Valley, California, (proposed); Sierra Blanca, Texas (proposed); Wake County, North Carolina (proposed); and Boyd County, Nebraska (proposed). While some comparisons between the sites described in this report are appropriate, this must be done with caution. In addition to differences in climate and geology between sites, LLW facilities in the past were not designed and operated to today''s standards. This report summarizes each site''s design and operational considerations for near-surface disposal of low-level radioactive waste. The report includes: a description of waste characteristics; design and operational features; post closure measures and plans; cost and duration of site characterization, construction, and operation; recent related R and D activities for LLW treatment and disposal; and the status of the LLW system in the US

  17. 40 CFR 270.17 - Specific part B information requirements for surface impoundments.

    Science.gov (United States)

    2010-07-01

    ... migration of any hazardous constituents into the ground water or surface water at any future time; (2) The....19 of this chapter; (5) Proposed action leakage rate, with rationale, if required under § 264.222 of..., including the double liner system, leak detection system, cover system, and appurtenances for control of...

  18. “Sapsan”-carriages defrosting station of Nizhniy Novgorod railway service enterprise and its surface waste water purification

    Science.gov (United States)

    Strelkov, Alexander; Teplykh, Svetlana; Gorshkalev, Pavel; Bystranova, Anastasia

    2017-10-01

    Surface water disposal is one of the most relevant problems for Nizhniy Novgorod railway service enterprises. Waste water must be quickly removed with special drainage devices and water drainage facilities (culverts, slope drains, pipes, ditches, etc.). During “Sapsan”-carriages defrosting watse water is aggregated on railroad tracks. It leads to track bed structure sagging, roadbed washaway and damages to point switches. In this paper the authors describe a concrete system of waste water disposal from railway service enterprises. This system is realized through culverts readjusted at the foot of ballast section. Thereafter, the collected water is pumped into a water collector and to local sewage waste-disposal plants. For railway stations with three or more tracks surface runoff diversion scheme depends on topography, railway tracks types, flow discharge and is compiled individually for each object. This paper examines “Sapsan”-carriages defrosting station of Nizhniy Novgorod railway service enterprise. It presents a technology scheme and equipment consisting of Sand catcher LOS-P, Oil catcher LOS-N, pressure-tight flotation unit; drain feed pump; solution-consuming tank of the coagulant, the solution-consuming tank of flocculant. The proposed technology has been introduced into the project practice.

  19. Waste Field Characteristics, Ultimate Mixing and Dilution in Surface Discharge of Dense Jets into Stagnant Water Bodies

    Directory of Open Access Journals (Sweden)

    2012-04-01

    Full Text Available Direct discharges of municipal and industrial waste waters into water bodies through marine outfalls are considered as a common way to dispose the generated waste in coastal zones. Marine discharge, intensifying flow mixing and entrainment, decrease the concentration of polutant up to accepted concentration and meet the guideline values and to make possible continues discharge of flow into matine environment. During last years due to quick development of coastal desalination plants, surface discharge of preduced salty water into seas and oceans has increased significantly. In this study, releases of dense jets from surface rectangular channel into stagnant bodies are experimentally studied. The location of flow plunge point, impact point and discharge ultimate dilution were drown out by a digital video technology. In addition, using some conductivity probes located in ambient floor, waste filed dilution in flow impact point and discharge ultimate dilution were identified. Finally the obtained results were plotted and explained along with some diagrams to show flow non-dimensional behavior. The results showed that the properties of flow are changing directly with ambient water depth and discharge initial fluxes.

  20. 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

  1. Water treatment technologies for a mixed waste remedial action

    International Nuclear Information System (INIS)

    Reith, C.; Freeman, G.; Ballew, B.

    1992-01-01

    Water treatment is an important element of the Weldon Spring Site Remedial Action Project (WSSRAP), which is cleaning up a former uranium processing plant near St. Louis, Missouri. This project, under the management of the U.S. Department of Energy (DOE), includes treatment and release of contaminated surface water and possibly groundwater at the plant site and a nearby quarry, which was once used for waste disposal. The contaminants include uranium, thorium, radium, nitroaromatics, nitrates, and metals. Three water treatment plants will be used to treat contaminated water prior to its release to the Missouri River. The first, construction of which is nearly complete, will treat contaminated surface water and interstitial water in and around the quarry. A stepwise process of sedimentation, clarification, filtration, adsorption, and ion exchange will be used to remove the contaminants. A similar sequence will be used for the first train of the water treatment plant at the plant site, although process details have been adjusted to address the different contaminant concentrations. The site water treatment plant will also have a second train consisting of a vapor compression/ distillation (VCD) system. Train 2 is necessary to treat waters primarily from four raffinate pits containing high concentrations of inorganics (e.g., nitrates, sulfates, and chlorides) in addition to radionuclides, nitroaromatics, and metals contamination that are common in most of the waters at the site. Construction is under way on the First train of this facility. After it is treated, all water will be impounded and batch tested for compliance with the project's National Pollution Discharge Elimination System (NPDES) permits prior to release to the Missouri River. The third water treatment plant is a mobile system that will be used to treat waters in some of the building sumps. (author)

  2. Water treatment technologies for a mixed waste remedial action

    Energy Technology Data Exchange (ETDEWEB)

    Reith, C; Freeman, G [Weldon Spring Site Remedial Action Project, Jacobs Engineering Group, Inc., St. Charles, MO (United States); Ballew, B [Weldon Spring Site Remedial Action Project, Dames and Moore, St. Charles, MO (United States)

    1992-07-01

    Water treatment is an important element of the Weldon Spring Site Remedial Action Project (WSSRAP), which is cleaning up a former uranium processing plant near St. Louis, Missouri. This project, under the management of the U.S. Department of Energy (DOE), includes treatment and release of contaminated surface water and possibly groundwater at the plant site and a nearby quarry, which was once used for waste disposal. The contaminants include uranium, thorium, radium, nitroaromatics, nitrates, and metals. Three water treatment plants will be used to treat contaminated water prior to its release to the Missouri River. The first, construction of which is nearly complete, will treat contaminated surface water and interstitial water in and around the quarry. A stepwise process of sedimentation, clarification, filtration, adsorption, and ion exchange will be used to remove the contaminants. A similar sequence will be used for the first train of the water treatment plant at the plant site, although process details have been adjusted to address the different contaminant concentrations. The site water treatment plant will also have a second train consisting of a vapor compression/ distillation (VCD) system. Train 2 is necessary to treat waters primarily from four raffinate pits containing high concentrations of inorganics (e.g., nitrates, sulfates, and chlorides) in addition to radionuclides, nitroaromatics, and metals contamination that are common in most of the waters at the site. Construction is under way on the First train of this facility. After it is treated, all water will be impounded and batch tested for compliance with the project's National Pollution Discharge Elimination System (NPDES) permits prior to release to the Missouri River. The third water treatment plant is a mobile system that will be used to treat waters in some of the building sumps. (author)

  3. Environmental site characterization and remediation at Lawrence Livermore National Laboratory Site 300

    International Nuclear Information System (INIS)

    Lamarre, A.L.; Ferry, R.A.

    1992-04-01

    Lawrence Livermore National Laboratory (LLNL) is a research and development laboratory owned by the US Department of Energy (DOE) and operated by the University of California. The Laboratory operates its Site 300 test facility in support of DOE's national defense programs. In support of activities, at the 300 Site numerous industrial fluids are used and various process or rinse waters and solid wastes are produced. Some of these materials are hazardous by current standards. HE rinse waters were previously discharged to inlined lagoons; they now are discharged to a permitted Class II surface impoundment Solid wastes have been deposited in nine landfills. Waste HE compounds are destroyed by open burning at a burn pit facility. As a result of these practices, environmental contaminants have been released to the soil and ground water

  4. Geochemical and mineralogical characterization of a neutral, low-sulfide/high-carbonate tailings impoundment, Markušovce, eastern Slovakia.

    Science.gov (United States)

    Hiller, Edgar; Petrák, Marián; Tóth, Roman; Lalinská-Voleková, Bronislava; Jurkovič, L'ubomír; Kučerová, Gabriela; Radková, Anežka; Sottník, Peter; Vozár, Jaroslav

    2013-11-01

    mineral assemblage and their occurrence follows the order: chalcopyrite > pyrite > tetrahedrite>arsenopyrite. The mineralogical composition of the tailings corresponds well to the primary mineralization mined. The neutralization capacity of the tailings is high, as confirmed by the values of neutralization potential to acid generation potential ratio, ranging from 6.7 to 63.9, and neutral to slightly alkaline pH of the tailings (paste pH 7.16-8.12) and the waters (pH 7.00-8.52). This is explained by abundant occurrence of carbonate minerals in the tailings, which readily neutralize the acidity generated by sulfide oxidation. The total solid-phase concentrations of metal(loid)s decrease as Cu>Sb>Hg>As and reflect the proportions of sulfides present in the tailings. Sulfide oxidation generally extends to a depth of 2 m. μ-XRD and EMPA were used to study secondary products developed on the surface of sulfide minerals and within the tailings. The main secondary minerals identified are goethite and X-ray amorphous Fe oxyhydroxides and their occurrence decreases with increasing tailings depth. Secondary Fe phases are found as mineral coatings or individual grains and retain relatively high amounts of metal(loid)s (up to 57.6 wt% Cu, 1.60 wt% Hg, 23.8 wt% As, and 2.37 wt% Sb). Based on batch leaching tests and lysimeter results, the mobility of potentially toxic elements in the tailings is low. The limited mobility of metals and metalloids is due to their retention by Fe oxyhydroxides and low solubilities of metal(loid)-bearing sulfides. The observations are consistent with PHREEQC calculations, which predict the precipitation of Fe oxyhydroxides as the main solubility-controlling mineral phases for As, Cu, Hg, and Sb. Waters discharging from tailings impoundment are characterized by a neutral to slightly alkaline pH (7.52-7.96) and low concentrations of dissolved metal(loid)s (tailings impoundment.

  5. Treatability studies performed in support of an engineering evaluation/cost analysis

    International Nuclear Information System (INIS)

    Myers, J.M.; Mueller, J.P.; Sundquist, J.A.; Moore, G.W.

    1995-01-01

    The Southern Shipbuilding Corporation (SSC) site is located on 54 acres of wooded land adjacent to Bayou Bonfouca, approximately 1.8 miles downstream of the Bayou Bonfouca National Priorities List (NPL) Superfund site in Slidell, St. Tammany Parish, Louisiana. Two one-acre, impoundments on the SSC site were used to store wastes generated from vessel cleaning. Wastes stored in the impoundments are migrating into Bayou Bonfouca, which empties into Lake Pontchartrain. In addition, the impoundments are frequently invaded by flood waters. The US EPA Emergency Response Branch (EPA-ERB) performed a site investigation which indicated that the majority of the contamination is petroleum-related and that the compounds of concern are polycyclic aromatic hydrocarbons (PARs). The wastes are generally contained with the two impoundments and surrounding soils. As part of an Engineering Evaluation/Cost Basis (EE/CA) of potential response action alternatives, four treatability studies were performed. A thermal treatment (incineration) study was performed at the EPA's Incineration Research Facility (IRF). Biodegradation remedy selection feasibility assessment was conducted on-site. A remedy screening soil washing study was also performed by TAT. A solidification/stabilization (S/S) study was conducted through EPA's Risk Reduction Engineering Laboratory (RREL) to ascertain if the PAHs could be immobilized within a solid matrix. Experimental objectives, dead methodology and conclusions for these studies are presented as they relate to potential response actions being evaluated at the SSC site

  6. A review of construction techniques available for surface and underground radioactive waste repositories

    International Nuclear Information System (INIS)

    Godfrey, D.G.; Davies, I.L.; MacKenzie, R.D.

    1985-01-01

    In terms of engineering requirements the construction of surface or indeed underground radioactive waste repositories is not unduly difficult. The civil engineering techniques likely to be required have generally been carried out previously, albeit not in the context of radioactive waste repositories in this country. The emphasis will have to be very much on the quality of construction. This paper emphasises the need for quality construction and describes the techniques likely to be used in the construction of repositories. Reference is made to the materials likely to be used in the construction of repositories and also to the need for being able to convince the designers, regulating authorities and the general public that the materials used will indeed last for the required time. Brief reference is made at the end of the paper to the civil engineering parameters requiring consideration in the location of repository siting. (author)

  7. CONDITIONING OF INTERMEDIATE-LEVEL WASTE AT FORSCHUNGSZENTRUM JUELICH GMBH

    International Nuclear Information System (INIS)

    Krumbach, H.

    2003-01-01

    This contribution to the group of low-level, intermediate, mixed and hazardous waste describes the conditioning of intermediate-level mixed waste (dose rate above 10 mSv/h at the surface) from Research Centre Juelich (FZJ). Conditioning of the waste by supercompaction is performed at Research Centre Karlsruhe (FZK). The waste described is radioactive waste arising from research at Juelich. This waste includes specimens and objects from irradiation experiments in the research reactors Merlin (FRJ-1) and Dido (FRJ-2) at FZJ. In principle, radioactive waste at Forschungszentrum Juelich GmbH is differentiated by the surface dose rate at the waste package. Up to a surface dose rate of 10 mSv/h, the waste is regarded as low-level. The radioactive waste described here has a surface dose rate above 10 mSv/h. Waste up to 10 mSv/h is conditioned at the Juelich site according to different conditioning methods. The intermediate-level waste can only be conditioned by supercompaction in the processing facility for intermediate-level waste from plant operation at Research Centre Karlsruhe. Research Centre Juelich also uses this waste cell to condition its intermediate-level waste from plant operation

  8. Bacterial community dynamics in surface flow constructed wetlands for the treatment of swine waste.

    Science.gov (United States)

    Ibekwe, A M; Ma, J; Murinda, Shelton; Reddy, G B

    2016-02-15

    Constructed wetlands are generally used for the removal of waste from contaminated water. In the swine production system, wastes are traditionally flushed into an anaerobic lagoon which is then sprayed on agricultural fields. However, continuous spraying of lagoon wastewater on fields can lead to high N and P accumulations in soil or lead to runoff which may contaminate surface or ground water with pathogens and nutrients. In this study, continuous marsh constructed wetland was used for the removal of contaminants from swine waste. Using pyrosequencing, we assessed bacterial composition within the wetland using principal coordinate analysis (PCoA) which showed that bacterial composition from manure influent and lagoon water were significantly different (P=0.001) from the storage pond to the final effluent. Canonical correspondence analysis (CCA) showed that different bacterial populations were significantly impacted by ammonium--NH4 (P=0.035), phosphate--PO4(3-) (P=0.010), chemical oxygen demand--COD (P=0.0165), total solids--TS (P=0.030), and dissolved solids--DS (P=0.030) removal, with 54% of the removal rate explained by NH4+PO4(3-) according to a partial CCA. Our results showed that different bacterial groups were responsible for the composition of different wetland nutrients and decomposition process. This may be the major reason why most wetlands are very efficient in waste decomposition. Published by Elsevier B.V.

  9. Safety assessment on the human intrusion scenarios of near surface disposal facility for low and very low level radioactive waste

    Energy Technology Data Exchange (ETDEWEB)

    Hong, Sung Wook; Park, Jin Baek [Korea Radioactive Waste Agency, Daejeon (Korea, Republic of); Park, Sang Ho [Chungnam National University, Daejeon (Korea, Republic of)

    2016-03-15

    The second-stage near surface disposal facility for low and very low level radioactive waste's permanent disposal is to be built. During the institutional control period, the inadvertent intrusion of the general public is limited. But after the institutional control period, the access to the general public is not restricted. Therefore human who has purpose of residence and resource exploration can intrude the disposal facility. In this case, radioactive effects to the intruder should be limited within regulatory dose limits. This study conducted the safety assessment of human intrusion on the second-stage surface disposal facility through drilling and post drilling scenario. Results of drilling and post drilling scenario were satisfied with regulatory dose limits. The result showed that post-drilling scenario was more significant than drilling scenario. According to the human intrusion time and behavior after the closure of the facility, dominant radionuclide contributing to the intruder was different. Sensitivity analyses on the parameters about the human behavior were also satisfied with regulatory dose limits. Especially, manual redistribution factor was the most sensitive parameter on exposure dose. A loading plan of spent filter waste and dry active waste was more effective than a loading plan of spent filter waste and other wastes for the radiological point of view. These results can be expected to provide both robustness and defense in depth for the development of safety case further.

  10. Waste retrieval plan for the Waste Isolation Pilot Plant

    International Nuclear Information System (INIS)

    1993-03-01

    The US DOE has prepared this plan to meet the requirements of Public Law 102579, the Waste Isolation Pilot Plant (WIPP) LWA, The purpose. is to demonstrate readiness to retrieve from the WIPP underground transuranic radioactive waste that will be used for testing should retrieval be needed. The WIPP, a potential geologic repository for transuranic wastes generated in national-defense activities, has been constructed in southeastern New Mexico. Because the transuranic wastes will remain radioactive for a very long time, the WIPP must reasonably ensure safe performance over thousands of years. The DOE therefore decided to develop the facility in phases, to preclude premature decisions and to conduct the performance assessments needed to demonstrate long-term safety. Surface facilities for receiving waste have been built, and considerable underground excavation, 2150 feet below the surface, has been completed. The next step is a test phase, including underground experiments called ''bin tests'' and ''alcove test(s)'' with contact-handled transuranic waste. The objective of these waste tests is to collect relevant data about the gas-generation potential and volatile organic compound (VOC) source term of the waste for developing a basis for demonstrating long term safety by compliance with the applicable disposal regulations (40 CFR 191, 264 and 268). The test phase will end when a decision is made to begin disposal in the WIPP or to terminate the project if regulatory compliance cannot be determined and demonstrated. Authorization to receive transuranic waste at the WIPP for the test phase is given by the WIPP LWA provided certain requirements are met

  11. Environment on the Surfaces of the Drip Shield and Waste Package Outer Barrier

    Energy Technology Data Exchange (ETDEWEB)

    T. Wolery

    2005-02-22

    This report provides supporting analysis of the conditions at which an aqueous solution can exist on the drip shield or waste package surfaces, including theoretical underpinning for the evolution of concentrated brines that could form by deliquescence or evaporation, and evaluation of the effects of acid-gas generation on brine composition. This analysis does not directly feed the total system performance assessment for the license application (TSPA-LA), but supports modeling and abstraction of the in-drift chemical environment (BSC 2004 [DIRS 169863]; BSC 2004 [DIRS 169860]). It also provides analyses that may support screening of features, events, and processes, and input for response to regulatory inquiries. This report emphasizes conditions of low relative humidity (RH) that, depending on temperature and chemical conditions, may be dry or may be associated with an aqueous phase containing concentrated electrolytes. Concentrated solutions at low RH may evolve by evaporative concentration of water that seeps into emplacement drifts, or by deliquescence of dust on the waste package or drip shield surfaces. The minimum RH for occurrence of aqueous conditions is calculated for various chemical systems based on current understanding of site geochemistry and equilibrium thermodynamics. The analysis makes use of known characteristics of Yucca Mountain waters and dust from existing tunnels, laboratory data, and relevant information from the technical literature and handbooks.

  12. Environment on the Surfaces of the Drip Shield and Waste Package Outer Barrier

    International Nuclear Information System (INIS)

    T. Wolery

    2005-01-01

    This report provides supporting analysis of the conditions at which an aqueous solution can exist on the drip shield or waste package surfaces, including theoretical underpinning for the evolution of concentrated brines that could form by deliquescence or evaporation, and evaluation of the effects of acid-gas generation on brine composition. This analysis does not directly feed the total system performance assessment for the license application (TSPA-LA), but supports modeling and abstraction of the in-drift chemical environment (BSC 2004 [DIRS 169863]; BSC 2004 [DIRS 169860]). It also provides analyses that may support screening of features, events, and processes, and input for response to regulatory inquiries. This report emphasizes conditions of low relative humidity (RH) that, depending on temperature and chemical conditions, may be dry or may be associated with an aqueous phase containing concentrated electrolytes. Concentrated solutions at low RH may evolve by evaporative concentration of water that seeps into emplacement drifts, or by deliquescence of dust on the waste package or drip shield surfaces. The minimum RH for occurrence of aqueous conditions is calculated for various chemical systems based on current understanding of site geochemistry and equilibrium thermodynamics. The analysis makes use of known characteristics of Yucca Mountain waters and dust from existing tunnels, laboratory data, and relevant information from the technical literature and handbooks

  13. Comprehensive evaluation of dioxins and dioxin-like compounds in surface soils and river sediments from e-waste-processing sites in a village in northern Vietnam: Heading towards the environmentally sound management of e-waste

    OpenAIRE

    Go Suzuki; Masayuki Someya; Hidenori Matsukami; Nguyen Minh Tue; Natsuyo Uchida; Le Huu Tuyen; Pham Hung Viet; Shin Takahashi; Shinsuke Tanabe; Abraham Brouwer; Hidetaka Takigami

    2016-01-01

    The management of electronic waste (e-waste), which can be a source of both useful materials and toxic substances, depending on the processing method, is important for promoting material cycling. In this study, we used the dioxin-responsive chemical-activated luciferase gene expression (DR-CALUX) assay combined with gas chromatography–high-resolution mass spectrometry to evaluate the levels of dioxin-like compounds in surface soils and river sediments collected in and around an e-waste-proces...

  14. The significance of natural ground-water recharge in site selection for mill tailings disposal

    International Nuclear Information System (INIS)

    Stephens, D.B.

    1985-01-01

    Milling operations throughout the world have created vast amounts of waste by-products, or tailings, which are often disposed on the land surface. The wastes may be disposed behind dams, on untreated ground, or on compacted clay or synthetic liners of impoundments and trenches. Often one of the principle concerns of environmental regulatory agencies is whether seepage from the waste pile could move through the vadose zone to the water table and possibly contaminate an aquifer. The seepage may be generated by the drainage of liquids initially deposited along with the tailings or by infiltrating meteoric water which leaches soluted from the tailings. The purpose of this article is to discuss some of the commonly held assumptions regarding storage of seepage wastes in the unsaturated zone. The significance of recent studies of water movement in dry climates which pertain to tailings site selection are presented

  15. Effects of hydrologic variables on rock riprap design for uranium tailings impoundments

    International Nuclear Information System (INIS)

    Walters, W.H.; Skaggs, R.L.

    1985-01-01

    Pacific Northwest Laboratory is studying the mitigation of erosion of earthen radon suppression covers for uranium tailings impoundments. Because the covers will require erosion protection for upwards of 1000 years, rock riprap (armoring) has been proposed as the primary protection method. This study investigates the sensitivity of riprap design procedures to extreme flood events that can generate high flow velocities and shear stresses. The study uses two decommissioned tailings sites (Grand Junction and Slick Rock, Colorado) as case studies to evaluate the sensitivity of design rock size with respect to variables such as flood discharge, side slope, specific gravity, safety factor, and channel roughness. The results indicate that design rock size can vary significantly for different design procedures. Other significant results indicate that embankment side slopes of about 4H:1V are optimum for rock riprap and that the use of rock material with specific gravities less than about 2.50 may prove too costly

  16. Radioactive waste management and disposal in Australia

    International Nuclear Information System (INIS)

    Harries, J.R.

    1997-01-01

    A national near-surface repository at a remote and arid location is proposed for the disposal of solid low-level and short-lived intermediate-level radioactive wastes in Australia. The repository will be designed to isolate the radioactive waste from the human environment under controlled conditions and for a period long enough for the radioactivity to decay to low levels. Compared to countries that have nuclear power programs, the amount of waste in Australia is relatively small. Nevertheless, the need for a national disposal facility for solid low-level radioactive and short-lived intermediate-level radioactive wastes is widely recognised and the Federal Government is in the process of selecting a site for a national near-surface disposal facility for low and short-lived intermediate level wastes. Some near surface disposal facilities already exist in Australia, including tailings dams at uranium mines and the Mt Walton East Intractable Waste Disposal Facility in Western Australia which includes a near surface repository for low level wastes originating in Western Australia. 7 refs, 1 fig., 2 tabs

  17. Origin and evolution of cup-shaped structures on leached nuclear waste containment glass surfaces

    International Nuclear Information System (INIS)

    Dubois, C.; Villa, F.; Chambaudet, A.; Vernaz, E.

    1994-01-01

    A three-dimensional surface microanalysis system equipped with a sensitive topographical probe was used to quantify the evolution of cup-shaped structures formed by aqueous leaching of nuclear waste containment glass. A model of the dissolution phenomenon provides satisfactory correlation between calculated and measured cup radius and depth. Dissolution cups form from cracks on the initially cut glass surface. Large cracks control the phenomenon by forming the largest cups, which gradually absorb smaller ones. The evolution of the size and shape of the dissolution cups was described by a model that assumes a constant dissolution rate on the surface, diminishing with crack depth. The best fit with the experimental data was obtained with a dissolution rate one hundred times lower at the bottom of the crack than at the surface. Moreover, it is predictable that all the cups will gradually disappear as they grow larger and flatter over a leaching period of some 2 years, for the glass composition and experimental leaching procedures used in this work

  18. Optimization of quantitative waste volume determination technique for hanford waste tank closure

    International Nuclear Information System (INIS)

    Monts, David L.; Jang, Ping-Rey; Long, Zhiling; Okhuysen, Walter P.; Norton, Olin P.; Gresham, Lawrence L.; Su, Yi; Lindner, Jeffrey S.

    2011-01-01

    The Hanford Site is currently in the process of an extensive effort to empty and close its radioactive single-shell and double-shell waste storage tanks. Before this can be accomplished, it is necessary to know how much residual material is left in a given waste tank and the uncertainty with which that volume is known. The Institute for Clean Energy Technology (ICET) at Mississippi State University is currently developing a quantitative in-tank imaging system based on Fourier Transform Profilometry, FTP. FTP is a non-contact, 3-D shape measurement technique. By projecting a fringe pattern onto a target surface and observing its deformation due to surface irregularities from a different view angle, FTP is capable of determining the height (depth) distribution (and hence volume distribution) of the target surface, thus reproducing the profile of the target accurately under a wide variety of conditions. Hence FTP has the potential to be utilized for quantitative determination of residual wastes within Hanford waste tanks. In this paper, efforts to characterize the accuracy and precision of quantitative volume determination using FTP and the use of these results to optimize the FTP system for deployment within Hanford waste tanks are described. (author)

  19. Purifying waste waters in the surface treatment industry; Depuracion de las aguas residuales en la industria de tratamiento de superficies

    Energy Technology Data Exchange (ETDEWEB)

    Queralt Torrell, R.; Martinez Hidalgo, E. [Generalitat de Catalunya. Barcelona (Spain)

    1999-07-01

    The electrolytic coating industry in Spain comprises some 2,000 firms whose waste waters are highly problematic, mainly due to the presence of heavy metals and cyanides. This article sets out series of internal measures for conserving the baths, reducing entrainment and optimising washes, thereby minimising the volume and concentration of the waste waters. It also discusses the advantages and disadvantages of the different chemical reagents employed in the physicochemical treatment of waste waters during the oxidation/reduction and metal precipitation processes. In addition, it mentions other techniques such as the use of ion exchange resins, membranes and electro-coagulation, which are becoming increasingly widespread. Finally, it offers a summary report on 11 waste water treatment facilities installed in different surface treatment factories. (Author) 21 refs.

  20. Derivation of quantitative acceptance criteria for disposal of radioactive waste to near surface facilities: Development and implementation of an approach for the post-closure phase

    International Nuclear Information System (INIS)

    Torres, C.

    2000-01-01

    The International Atomic Energy Agency has established a project to develop and illustrate, through practical examples, an approach that allows the derivation of quantitative waste acceptance criteria for near surface disposal of radioactive waste. The first phase focussed on the derivation of example post-closure safety waste acceptance criteria through the use of a safety assessment approach that allows for the derivation of values in a clear and well documented manner. The approach consists of five steps: the specification of the assessment context; the description of the disposal system; the development and justification of scenarios; the formulation and implementation of models; and the calculation and derivation of example values. The approach has been successfully used to derive activity values for the disposal of radioactive waste to illustrative near surface facilities. (author)

  1. Conditioning of intermediate-level waste at Forschungszentrum Juelich GmbH

    International Nuclear Information System (INIS)

    Krumbach, H.

    2003-01-01

    This contribution to the group of low-level, intermediate, mixed and hazardous waste describes the conditioning of intermediate-level mixed waste (dose rate above 10 mSv/h at the surface) from Research Centre Juelich (FZJ). Conditioning of the waste by supercompaction is performed at Research Centre Karlsruhe (FZK). The waste described is radioactive waste arising from research at Juelich. This waste includes specimens and objects from irradiation experiments in the research reactors Merlin (FRJ-1) and Dido (FRJ-2) at FZJ. In principle, radioactive waste at Forschungszentrum Juelich GmbH is differentiated by the surface dose rate at the waste package. Up to a surface dose rate of 10 mSv/h, the waste is regarded as low-level. The radioactive waste described here has a surface dose rate above 10 mSv/h. Waste up to 10 mSv/h is conditioned at the Juelich site according to different conditioning methods. The intermediate-level waste can only be conditioned by supercompaction in the processing facility for intermediate-level waste from plant operation at Research Centre Karlsruhe. Research Centre Juelich also uses this waste cell to condition its intermediate-level waste from plant operation. (orig.)

  2. Management of Radioactive Wastes

    International Nuclear Information System (INIS)

    Tchokosa, P.

    2010-01-01

    Management of Radioactive Wastes is to protect workers and the public from the radiological risk associated with radioactive waste for the present and future. It application of the principles to the management of waste generated in a radioisotope uses in the industry. Any material that contains or is contaminated with radionuclides at concentrations or radioactivity levels greater than ‘exempt quantities’ established by the competent regulatory authorities and for which no further use is foreseen or intended. Origin of the Radioactive Waste includes Uranium and Thorium mining and milling, nuclear fuel cycle operations, Operation of Nuclear power station, Decontamination and decommissioning of nuclear facilities and Institutional uses of isotopes. There are types of radioactive waste: Low-level Waste (LLW) and High-level Waste. The Management Options for Radioactive Waste Depends on Form, Activity, Concentration and half-lives of the radioactive waste, Storage and disposal methods will vary according to the following; the radionuclides present, and their concentration, and radio toxicity. The contamination results basically from: Contact between radioactive materials and any surface especially during handling. And it may occur in the solid, liquid or gas state. Decontamination is any process that will either reduce or completely remove the amount of radionuclides from a contaminated surface

  3. Hybrid selective surface hydrophilization and froth flotation separation of hazardous chlorinated plastics from E-waste with novel nanoscale metallic calcium composite.

    Science.gov (United States)

    Mallampati, Srinivasa Reddy; Heo, Je Haeng; Park, Min Hee

    2016-04-05

    Treatment by a nanometallic Ca/CaO composite has been found to selectively hydrophilize the surface of polyvinyl chloride (PVC), enhancing its wettability and thereby promoting its separation from E-waste plastics by means of froth flotation. The treatment considerably decreased the water contact angle of PVC, by about 18°. The SEM images of the PVC plastic after treatment displayed significant changes in their surface morphology compared to other plastics. The SEM-EDS results reveal that a markedly decrease of [Cl] concentration simultaneously with dramatic increase of [O] on the surface of the PCV samples. XPS results further confirmed an increase of hydrophilic functional groups on the PVC surface. Froth flotation at 100rpm mixing speed was found to be optimal, separating 100% of the PVC into a settled fraction of 96.4% purity even when the plastics fed into the reactor were of nonuniform size and shape. The total recovery of PVC-free plastics in E-waste reached nearly 100% in the floated fraction, significantly improved from the 20.5wt% of light plastics that can be recovered by means of conventional wet gravity separation. The hybrid method of nanometallic Ca/CaO treatment and froth flotation is effective in the separation of hazardous chlorinated plastics from E-waste plastics. Copyright © 2015 Elsevier B.V. All rights reserved.

  4. Resource Conservation and Recovery Act ground-water monitoring projects for Hanford facilities: Progress Report for the Period April 1 to June 30, 1989

    Energy Technology Data Exchange (ETDEWEB)

    Smith, R.M.; Bates, D.J.; Lundgren, R.E.

    1989-09-01

    This report describes the progress of 13 Hanford ground-water monitoring projects for the period April 1 to June 30, 1989. These projects are for the 300 area process trenches (300 area), 183-H solar evaporation basins (100-H area), 200 areas low-level burial grounds, nonradioactive dangerous waste landfill (southeast of the 200 areas), 1301-N liquid waste disposal facility (100-N area), 1324-N surface impoundment and 1324-NA percolation pond (100-N area), 1325-N liquid waste disposal facility (100-N area), 216-A-10 crib (200-east area), 216-A-29 ditch (200-east area), 216-A-36B crib (200-east area), 216-B-36B crib (200-east area), 216-B-3 pond (east of the 200-east area), 2101-M pond (200-east area), grout treatment facility (200-east area).

  5. Seismic surface-wave tomography of waste sites. 1998 annual progress report

    International Nuclear Information System (INIS)

    Long, T.L.

    1998-01-01

    'The objective of the Seismic Surface Wave Tomography of Waste Sites is to develop a robust technique for field acquisition and analysis of surface wave data for the interpretation of shallow structures, such as those associated with the burial of wastes. The analysis technique is to be developed and tested on an existing set of seismic data covering the K-901 burial site at the East Tennessee Technology Park. Also, a portable prototype for a field acquisition system will be designed and developed to obtain additional data for analysis and testing of the technique. The portable analysis system will display an image representing the shear-wave velocity structure. The image would be developed in the field from successive data samples. As of May 1998, the author established compatibility with computer programs at Georgia Tech and computed a preliminary singular value decomposition solution for the K-901 data. The analysis included modeling of surface wave dispersion and analysis of velocity structure. The analysis demonstrated that the authors needed additional field data to verify the conclusions and provide independent confirmation of velocity structure. The K-901 site data were obtained with 8 Hz geophones. The frequencies below 8 Hz are strongly attenuated in such recording instruments and are difficult to analyze. In particular, group velocities can have multiple answers for a given frequency. Consequently, without a record of the low-frequency energy, the authors found it difficult to identify the portion of the dispersion curve responsible for the seismogram. In particular, it was difficult to determine if the reverse dispersion observed in the frequencies above 8 Hz was caused by a low velocity layer or caused by observing only the frequencies above the group velocity minimum. In either model, synthetic seismograms can be made to match the observed data for the higher frequencies. The contract for the proposed work was completed in December. The field work was

  6. Underground coal mine subsidence impacts on surface water

    International Nuclear Information System (INIS)

    Stump, D.E. Jr.

    1992-01-01

    This paper reports that subsidence from underground coal mining alters surface water discharge and availability. The magnitude and areal extent of these impacts are dependent on many factors, including the amount of subsidence, topography, geology, climate, surface water - ground water interactions, and fractures in the overburden. There alterations may have positive and/or negative impacts. One of the most significant surface water impacts occurred in July 1957 near West Pittston, Pennsylvania. Subsidence in the Knox Mine under the Coxton Yards of the Lehigh Valley Railroad allowed part of the discharge in the Susquehanna River to flow into the mine and create a crater 200 feet in diameter and 300 feet deep. Fourteen railroad gondola cars fell into the hole which was eventually filled with rock, sand, and gravel. Other surface water impacts from subsidence may include the loss of water to the ground water system, the gaining of water from the ground water system, the creation of flooded subsidence troughs, the increasing of impoundment storage capacity, the relocation of water sources (springs), and the alteration of surface drainage patterns

  7. 10 CFR 61.55 - Waste classification.

    Science.gov (United States)

    2010-01-01

    ... REGULATORY COMMISSION (CONTINUED) LICENSING REQUIREMENTS FOR LAND DISPOSAL OF RADIOACTIVE WASTE Technical Requirements for Land Disposal Facilities § 61.55 Waste classification. (a) Classification of waste for near surface disposal—(1) Considerations. Determination of the classification of radioactive waste involves two...

  8. Optimization of volatile fatty acid production with co-substrate of food wastes and dewatered excess sludge using response surface methodology.

    Science.gov (United States)

    Hong, Chen; Haiyun, Wu

    2010-07-01

    Central-composite design (CCD) and response surface methodology (RSM) were used to optimize the parameters of volatile fatty acid (VFA) production from food wastes and dewatered excess sludge in a semi-continuous process. The effects of four variables (food wastes composition in the co-substrate of food wastes and excess sludge, hydraulic retention time (HRT), organic loading rate (OLR), and pH) on acidogenesis were evaluated individually and interactively. The optimum condition derived via RSM was food wastes composition, 88.03%; HRT, 8.92 days; OLR, 8.31 g VSS/ld; and pH 6.99. The experimental VFA concentration was 29,099 mg/l under this optimum condition, which was well in agreement with the predicted value of 28,000 mg/l. Copyright (c) 2010 Elsevier Ltd. All rights reserved.

  9. 76 FR 45428 - National Oil and Hazardous Substances Pollution Contingency Plan; National Priorities List...

    Science.gov (United States)

    2011-07-29

    ..., potentially on the Site. The Site included the locations of the former wastewater impoundments, waste water... August 2001, consisted of the removal and off-site disposal of waste materials, water treatment, oil and water separation, and stabilization and off- site disposal of sludge materials. This Removal Action...

  10. Reservoir Operation Rules for Controlling Algal Blooms in a Tributary to the Impoundment of Three Gorges Dam

    Directory of Open Access Journals (Sweden)

    Jijian Lian

    2014-10-01

    Full Text Available Since the first impoundment of Three Gorges Dam in 2003, algal blooms occur frequently in the near-dam tributaries. It is widely recognized that the impoundment-induced change in hydrodynamic condition with the lower current velocity will make the eutrophication problem even more severe when an excessive amount of nutrients is already loaded into a reservoir and/or its tributaries. Operation tests carried out by Three Gorges Corporation in 2010 point to some feasible reservoir operation schemes that may have positive impacts on reducing the algal bloom level. In our study, an attempt is made to obtain, through a numerical hydrodynamic and water quality modeling and analysis, the reservoir operation rules that would reduce the level of algal blooms in the Xiangxi River (XXR, a near-dam tributary. Water movements and algal blooms in XXR are simulated and analyzed under different scenarios of one-day water discharge fluctuation or two-week water level variation. The model results demonstrate that the reservoir operations can further increase the water exchange between the mainstream of the Three Gorges Reservoir (TGR and the XXR tributary and thus move a larger amount of algae into the deep water where it will die. Analysis of the model results indicate that the water discharge fluctuation constituted of a lower valley-load flow and a larger flow difference for the short-term operation (within a day, the rise in water level for the medium-term operation (e.g., over weeks, and the combination of the above two for the long-term operation (e.g., over months can be the feasible reservoir operation rules in the non-flood season for TGR.

  11. 40 CFR 264.227 - Emergency repairs; contingency plans.

    Science.gov (United States)

    2010-07-01

    ... 40 Protection of Environment 25 2010-07-01 2010-07-01 false Emergency repairs; contingency plans... FACILITIES Surface Impoundments § 264.227 Emergency repairs; contingency plans. (a) A surface impoundment... days after detecting the problem. (c) As part of the contingency plan required in subpart D of this...

  12. A technique for the geometric modeling of underground surfaces: Nevada Nuclear Waste Storage Investigations Project

    International Nuclear Information System (INIS)

    Williams, R.L.

    1988-03-01

    There is a need within the Nevada Nuclear Waste Storage Investigation (NNWSI) project to develop three-dimensional surface definitions for the subterranean stratigraphies at Yucca Mountain, Nevada. The nature of the data samples available to the project require an interpolation technique that can perform well with sparse and irregularly spaced data. Following an evaluation of the relevant existing methods, a new technique, Multi-Kernel Modulation (MKM), is presented. MKM interpolates sparse and irregularly spaced data by modulating a polynomial trend surface with a linear summation of regular surfaces (kernels). A perspective discussion of MKM, Kriging, and Multiquadric Analysis reveals that MKM has the advantage of simplicity and efficiency when used with sparse samples. An example of the use of MKM to model a complex topography is presented. 24 refs., 6 figs., 2 tabs

  13. Site characterization field manual for near surface geologic disposal of low-level radioactive waste

    International Nuclear Information System (INIS)

    McCray, J.G.; Nowatzki, E.A.

    1985-01-01

    This field manual has been developed to aid states and regions to do a detailed characterization of a proposed near-surface low-level waste disposal site. The field manual is directed at planners, staff personnel and experts in one discipline to acquaint them with the requirements of other disciplines involved in site characterization. While it can provide a good review, it is not designed to tell experts how to do their job within their own discipline

  14. Novel Activated Carbons from Agricultural Wastes and their Characterization

    Directory of Open Access Journals (Sweden)

    S. Karthikeyan

    2008-01-01

    Full Text Available Solid waste disposal has become a major problem in India, Either it has to be disposed safely or used for the recovery of valuable materials as agricultural wastes like turmeric waste, ferronia shell waste, jatropha curcus seed shell waste, delonix shell waste and ipomea carnia stem. Therefore these wastes have been explored for the preparation of activated carbon employing various techniques. Activated carbons prepared from agricultural solid wastes by chemical activation processes shows excellent improvement in the surface characteristics. Their characterization studies such as bulk density, moisture content, ash content, fixed carbon content, matter soluble in water, matter soluble in acid, pH, decolourising power, phenol number, ion exchange capacity, ion content and surface area have been carried out to assess the suitability of these carbons as absorbents in the water and wastewater. For anionic dyes (reactive, direct, acid a close relationship between the surface area and surface chemical groups of the modified activated carbon and percentage of dye removal by adsorption can be observed. Cationic dyes large amount of surface chemical groups present in the sample (mainly carboxylic, anhydrides, lactones and phenols etc. are good anchoring sites for adsorption. The present study reveals the recovery of valuable adsorbents from readily and cheaply available agriculture wastes.

  15. Procedures and techniques for closure of near surface disposal facilities for radioactive waste

    International Nuclear Information System (INIS)

    2001-12-01

    The overall objective of this report is to provide Member States with guidance on planning and implementation of closure of near surface disposal facilities for low and intermediate level radioactive waste. The specific objectives are to review closure concepts, requirements, and components of closure systems; to discuss issues and approaches to closure, including regulatory, economic, and technical aspects; and to present major examples of closure techniques used and/or considered by Member States. Some examples of closure experience from Member States are presented in the Appendix and were indexed separately

  16. Activation/waste management

    International Nuclear Information System (INIS)

    Maninger, C.

    1984-10-01

    The selection of materials and the design of the blankets for fusion reactors have significant effects upon the radioactivity generated by neutron activation in the materials. This section considers some aspects of materials selection with respect to waste management. The activation of the materials is key to remote handling requirements for waste, to processing and disposal methods for waste, and to accident severity in waste management operations. In order to realize the desirable evnironmental potentials of fusion power systems, there are at least three major goals for waste management. These are: (a) near-surface burial; (b) disposal on-site of the fusion reactor; (c) acceptable radiation doses at least cost during and after waste management operations

  17. Apparatus for incinerating hazardous waste

    Science.gov (United States)

    Chang, R.C.W.

    1994-12-20

    An apparatus is described for incinerating wastes, including an incinerator having a combustion chamber, a fluid-tight shell enclosing the combustion chamber, an afterburner, an off-gas particulate removal system and an emergency off-gas cooling system. The region between the inner surface of the shell and the outer surface of the combustion chamber forms a cavity. Air is supplied to the cavity and heated as it passes over the outer surface of the combustion chamber. Heated air is drawn from the cavity and mixed with fuel for input into the combustion chamber. The pressure in the cavity is maintained at least approximately 2.5 cm WC higher than the pressure in the combustion chamber. Gases cannot leak from the combustion chamber since the pressure outside the chamber (inside the cavity) is higher than the pressure inside the chamber. The apparatus can be used to treat any combustible wastes, including biological wastes, toxic materials, low level radioactive wastes, and mixed hazardous and low level transuranic wastes. 1 figure.

  18. Evaluation of surface water treatment and discharge options for the Weldon Spring Site Remedial Action Project

    International Nuclear Information System (INIS)

    Goyette, M.L.; MacDonell, M.M.

    1992-01-01

    The US Department of Energy (DOE), under its Environmental Restoration and Waste Management Program, is responsible for conducting response actions at the Weldon Spring site in St. Charles County, Missouri. The site consists of two noncontiguous areas: (1) the chemical plant area, which includes four raffinate pits and two small ponds, and (2) a 3.6-ha (9-acre) quarry located about 6.4 km (4 mi) southwest of the chemical plant area. Both of these areas became chemically and radioactively contaminated as a result of processing and disposal activities that took place from the 1940s through 1960s. The Weldon Spring site, located about 48 km (30 mi) west of St. Louis, is listed on the National Priorities List of the US Environmental Protection Agency. Nitroaromatic explosives were processed by the Army at the chemical plant area during the 1940s, and radioactive materials were processed by DOE's predecessor agency (the Atomic Energy Commission) during the 1950s and 1960s. Overall remediation of the Weldon Spring site is being addressed through the Weldon Spring Site Remedial Action Project, and it consists of several components. One component is the management of radioactively and chemically contaminated surface water impoundments at the chemical plant area -- i.e., the four raffinate pits, Frog Pond, and Ash Pond which was addressed under a separate action and documented in an engineering evaluation/cost analysis report. This report discusses the evaluation of surface water treatment at the Weldon Spring site

  19. Surface displacements and pillar stresses associated with nuclear waste disposal in salt

    International Nuclear Information System (INIS)

    Hardy, M.P.; St John, C.M.

    1977-01-01

    A numerical model for regional analysis of stresses and displacement, resulting from heat generating waste placement in underground salt excavations, is presented. The model, which is an extension of that described by McClain and Starfield (1971), is based upon the displacement discontinuity method of stress analysis. It incorporates an empirical characterization of creep behavior of material on the excavation horizon and accounts for thermally induced stresses and displacements. The versatility of this approach is illustrated by the results of three relatively short simulations of test scale disposal facilities at shallow and greater depths. In addition, a three-dimensional code was used to evaluate the surface displacement history for a full-scale repository. This latter code, a thermoelastic analysis, gives an upper bound for the surface movements. It is concluded that the pillar stresses are the result of a complex non-linear interaction of many variables, and the maximum pillar stress can reach several multiples of the tributory-area pillar stress

  20. Radionuclide transport from near-surface repository for radioactive waste - The unsaturated zone approach

    Energy Technology Data Exchange (ETDEWEB)

    Jakimaviciute-Maseliene, V. [Vilnius University (Lithuania); Mazeika, J. [Nature Research Centre (Lithuania); Motiejunas, S. [Radioactive Waste Management Agency (Lithuania)

    2014-07-01

    About 100 000 m{sup 3} of solid conditioned Low and Intermediate Level Waste (LILW), generated during operation and decommissioning of the Ignalina nuclear power plant (INPP), are to be disposed of in a near-surface repository (NSR) - a 'hill'-type repository with reinforced concrete vaults and with engineered and natural barriers. The northeastern Lithuania and the environment of the INPP in particular were recognized as the areas most suitable for a near-surface repository (Stabatiske Site). The engineered barriers of the repository consist of concrete cells surrounded by clay-based material of low permeability with about the same isolating capacity in all directions. The clay materials must be effectively compactable so that required hydraulic conductivity is reached. The Lithuanian Triassic clay turned out to be sufficiently rich in smectites and was proposed as main candidate for sealing of the repository. When the concrete vaults are filled, the repository cover will be constructed. The surface of the mound will be planted with grass. In this study a computer code FEFLOW 5.0 was applied for simulating the transport of the most mobile radionuclides ({sup 3}H, {sup 14}C, {sup 59}Ni and {sup 94}Nb) with moisture through an unsaturated vault of the near-surface repository in Stabatiske Site. The HYDRUS-1D analysis was used to assess the radionuclide transport in the repository and to estimate initial activity concentrations of radionuclides transported from the cemented waste matrix. Radionuclide release from the vault in the unsaturated conditions after closure of the repository and consequent contaminant plume transport has been assessed taking into account site-specific natural and engineering conditions and based on a normal evolution scenario. The highest peak radionuclide activity concentrations were estimated applying the FEFLOW code. The highest value of {sup 14}C activity concentration(about 1.3x10{sup 8} Bq/m{sup 3}) at the groundwater table

  1. Preparation and Surface Sizing Application of Sizing Agent Based on Collagen from Leather Waste

    Directory of Open Access Journals (Sweden)

    Xuechuan Wang

    2015-09-01

    Full Text Available Collagen extracted from leather waste was modified with maleic anhydride. Then, using ammonium persulfate as an initiator, by pre-modifying collagen reacted with styrene and ethyl acrylate monomers, a vinyl-grafted collagen sizing agent (VGCSA for paper was prepared. Before the experiment, the performance of VGCSA was tested and VGCSA emulsion was applied to the surface sizing of the corrugated paper. Effects of the amount of VGCSA, the compound proportion of VGCSA, and starch and styrene-acrylic emulsion were studied relative to paper properties. The morphological changes of the paper before and after sizing were characterized by SEM. It was found that the collagen reacted with styrene and ethyl acrylate monomers. Through the grafting of vinyl and collagen, the crystallinity and thermal stability of VGCSA increased. The structure of VGCSA was spherical with a uniform size, and the average particle size was approximately 350 to 400 nm. After being sized, the surface fibers of paper became smooth and orderly. The optimal sizing of VGCSA was 8 g/m2. The optimal proportion of VGCSA with starch was 4:6, and the optimal proportion of VGCSA with SAE was 2:8. The research indicates that collagen extracted from leather waste could be used as a biomaterial, and environmental and economic benefits could be created as well.

  2. ORNL results for Test Case 1 of the International Atomic Energy Agency's research program on the safety assessment of Near-Surface Radioactive Waste Disposal Facilities

    International Nuclear Information System (INIS)

    Thorne, D.J.; McDowell-Boyer, L.M.; Kocher, D.C.; Little, C.A.; Roemer, E.K.

    1993-01-01

    The International Atomic Energy Agency (IAEA) started the Coordinated Research Program entitled '''The Safety Assessment of Near-Surface Radioactive Waste Disposal Facilities.'' The program is aimed at improving the confidence in the modeling results for safety assessments of waste disposal facilities. The program has been given the acronym NSARS (Near-Surface Radioactive Waste Disposal Safety Assessment Reliability Study) for ease of reference. The purpose of this report is to present the ORNL modeling results for the first test case (i.e., Test Case 1) of the IAEA NSARS program. Test Case 1 is based on near-surface disposal of radionuclides that are subsequently leached to a saturated-sand aquifer. Exposure to radionuclides results from use of a well screened in the aquifer and from intrusion into the repository. Two repository concepts were defined in Test Case 1: a simple earth trench and an engineered vault

  3. Pump station for radioactive waste water

    Science.gov (United States)

    Whitton, John P.; Klos, Dean M.; Carrara, Danny T.; Minno, John J.

    2003-11-18

    A pump station for transferring radioactive particle containing waste water, includes: (a.) an enclosed sump having a vertically elongated right frusto conical wall surface and a bottom surface and (b.) a submersible volute centrifugal pump having a horizontally rotating impeller and a volute exterior surface. The sump interior surface, the bottom surface and the volute exterior surface are made of stainless steel having a 30 Ra or finer surface finish. A 15 Ra finish has been found to be most cost effective. The pump station is used for transferring waste water, without accumulation of radioactive fines.

  4. Induction melting of simulated transuranic waste

    International Nuclear Information System (INIS)

    Tenaglia, R.D.; McCall, J.L.

    1983-06-01

    Coreless induction melting was investigated as a method to melt and consolidate waste material representative of the transuranic waste (TRU) stored at the Idaho National Engineering Laboratory (INEL). Waste material was introduced onto the surface of a molten cast iron bath in a coreless induction furnace. Waste metallics were incorporated into the bath. Noncombustibles formed a slag which was poured or skimmed from the bath surface. Stack sampling was performed to characterize the off-gas and particulate matter evolved. Experimental melting tests were performed for a variety of types of wastes including metallics, chemical sludge, soil, concrete, and glass. Each test also included a representative level of combustible materials consisting of paper, wood, cloth, polyvinyl chloride and polyethylene. Metallic wastes were readily processed by induction melting with a minimum of slag production. Test waste consisting primarily of chemical sludge provided fluid slags which could be poured from the bath surface. Processing of wastes consisting of soil, concrete, or glass was limited by the inability to achieve fluid slags. It appears from test results that coreless induction melting is a feasible method to process INEL-type waste materials if two problems can be resolved. First, slag fluidity must be improved to facilitate the collection of slags formed from soil, concrete, or glass containing wastes. Secondly, refractory life must be further optimized to permit prolonged processing of the waste materials. The use of a chrome-bearing high-alumina refractory was found to resist slag line attach much better than a magnesia refractory, although some attack was still noted

  5. Radiation transport in high-level waste form

    International Nuclear Information System (INIS)

    Arakali, V.S.; Barnes, S.M.

    1992-01-01

    The waste form selected for vitrifying high-level nuclear waste stored in underground tanks at West Valley, NY is borosilicate glass. The maximum radiation level at the surface of a canister filled with the high-level waste form is prescribed by repository design criteria for handling and disposition of the vitrified waste. This paper presents an evaluation of the radiation transport characteristics for the vitreous waste form expected to be produced at West Valley and the resulting neutron and gamma dose rates. The maximum gamma and neutron dose rates are estimated to be less than 7500 R/h and 10 mRem/h respectively at the surface of a West Valley canister filled with borosilicate waste glass

  6. Investigation of waste biomass co-pyrolysis with petroleum sludge using a response surface methodology.

    Science.gov (United States)

    Hu, Guangji; Li, Jianbing; Zhang, Xinying; Li, Yubao

    2017-05-01

    The treatment of waste biomass (sawdust) through co-pyrolysis with refinery oily sludge was carried out in a fixed-bed reactor. Response surface method was applied to evaluate the main and interaction effects of three experimental factors (sawdust percentage in feedstock, temperature, and heating rate) on pyrolysis oil and char yields. It was found that the oil and char yields increased with sawdust percentage in feedstock. The interaction between heating rate and sawdust percentage as well as between heating rate and temperature was significant on the pyrolysis oil yield. The higher heating value of oil originated from sawdust during co-pyrolysis at a sawdust/oily sludge ratio of 3:1 increased by 5 MJ/kg as compared to that during sawdust pyrolysis alone, indicating a synergistic effect of co-pyrolysis. As a result, petroleum sludge can be used as an effective additive in the pyrolysis of waste biomass for improving its energy recovery. Copyright © 2017 Elsevier Ltd. All rights reserved.

  7. The low to intermediate activity and short living waste storage facility. For a controlled management of radioactive wastes

    International Nuclear Information System (INIS)

    2006-01-01

    Sited at about 50 km of Troyes (France), the Aube facility started in 1992 and has taken over the Manche facility for the surface storage of low to intermediate and short living radioactive wastes. The Aube facility (named CSFMA) is the answer to the safe management of these wastes at the industrial scale and for 50 years onward. This brochure presents the facility specifications, the wastes stored at the center, the surface storage concept, the processing and conditioning of waste packages, and the environmental monitoring performed in the vicinity of the site. (J.S.)

  8. Nuclear power plants waste management practices in France

    International Nuclear Information System (INIS)

    Matsuda, Fumio

    1998-01-01

    This survey offers a complete review concerning the nuclear power plants waste management in France from generation to disposal, as well as future evolutions. Fundamental Safety Rule specified by the government defines safety objectives, design bases for surface disposals and preliminary terms for acceptance of waste packages on the surface disposal site. A governmental decree authorizes the creation of CSA (Centre de Stockage de l'Aude; French surface repository), and defines the limits of radiological inventory of the disposal facility. The national waste agency ANDRA was established in 1979 by government (turned into public in 1991), and ANDRA defines the technical specifications involving acceptance criteria of the waste packages. The main feature of the French management includes; Comprehensive quality assurance program that encompasses all area of the management. Centralized installation for the melting of contaminated scrap metals and incineration of low level technological wastes. Mobile unit for common treatment of ion exchange resin. Concrete package assuring the long term containment. Complete tracking system of wastes from generation to disposal. This survey would be useful in the consideration of Japanese waste management including miscellaneous wastes, high βγ wastes, large metallic wastes, etc. (author)

  9. Radioactivity and nuclear waste

    International Nuclear Information System (INIS)

    Saas, A.

    1996-01-01

    Radioactive wastes generated by nuclear activities must be reprocessed using specific treatments before packaging, storage and disposal. This digest paper gives first a classification of radioactive wastes according to their radionuclides content activity and half-life, and the amount of wastes from the different categories generated each year by the different industries. Then, the radiotoxicity of nuclear wastes is evaluated according to the reprocessing treatments used and to their environmental management (surface storage or burial). (J.S.)

  10. Management of radioactive mixed wastes in commercial low-level wastes

    International Nuclear Information System (INIS)

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

    1986-01-01

    Potential mixed wastes in commercial low-level wastes have been identified and management options applicable to these wastes have been evaluated. Both the identification and management evaluation have necessarily been based on review of NRC and EPA regulations and recommendations. The underlying intent of both agencies is protection of man and/or environment, but differences may occur in the means by which intent is achieved. Apparent discrepancies, data gaps and unresolved issues that have surfaced during the course of this work are discussed

  11. Assessing Resiliency in a Large Lake Receiving Mine Tailings Waste: Impacts of Major Environmental Disturbance.

    Science.gov (United States)

    Petticrew, Ellen; Owens, Philip; Albers, Sam

    2016-04-01

    On 4th August 2014, the tailings impoundment of the Mount Polley copper and gold mine in British Columbia failed. Material from the impoundment (surface area = 2.7 km2) flowed into nearby Polley Lake and Hazeltine Creek, before discharging into Quesnel Lake, a large (ca. 100 km long, >500 m deep), relatively pristine lake. Initial estimates suggest that approximately 25 Mm3 of tailings (water and solids) and eroded soils and surficial materials from Hazeltine Creek were delivered to Quesnel Lake, raising the lake by 7.7 cm. Much of this material was deposited at the bottom of Quesnel Lake but a plume of fine-grained sediment (D50 of ca. 1 μm) remained suspended in the water column. The impact of the distribution of this sediment was monitored over the next 15 months using water column profiling for temperature, conductivity, fluorescence and turbidity with depth. The plume movement was regulated by natural processes associated with the physical limnology of this large fjord lake, specifically, seiche events which transferred suspended particles both up-lake, against the flow regime, and down-lake into the Quesnel River. Samples of lake water and bottom sediment taken from the impacted area show elevated levels of total metals and other elements, which may have important ecosystem implications in this watershed. Indeed, the breach occurred at a time when a peak run of sockeye salmon were returning to their natal streams in the Quesnel basin. Zooplankton sampling for metals was initiated in fall 2014 to determine up take of metals into the food web. This poster describes the failure of the impoundment dam and presents results of sampling the aquatic environment over the first fifteen months of impact.

  12. High Level Waste (HLW) Processing Experience with Increased Waste Loading

    International Nuclear Information System (INIS)

    JANTZEN, CAROL

    2004-01-01

    The Defense Waste Processing Facility (DWPF) Engineering requested characterization of glass samples that were taken after the second melter had been operational for about 5 months. After the new melter had been installed, the waste loading had been increased to about 38 weight percentage after a new quasicrystalline liquidus model had been implemented. The DWPF had also switched from processing with refractory Frit 200 to a more fluid Frit 320. The samples were taken after DWPF observed very rapid buildup of deposits in the upper pour spout bore and on the pour spout insert while processing the high waste loading feedstock. These samples were evaluated using various analytical techniques to determine the cause of the crystallization. The pour stream sample was homogeneous, amorphous, and representative of the feed batch from which it was derived. Chemical analysis of the pour stream sample indicated that a waste loading of 38.5 weight per cent had been achieved. The data analysis indicated that surface crystallization, induced by temperature and oxygen fugacity gradients in the pour spout, caused surface crystallization to occur in the spout and on the insert at the higher waste loadings even though there was no crystallization in the pour stream

  13. Mechanisms governing the direct removal of wastes from the Waste Isolation Pilot Plant repository caused by exploratory drilling

    International Nuclear Information System (INIS)

    Berglund, J.W.

    1992-12-01

    Two processes are identified that can influence the quantity of wastes brought to the ground surface when a waste disposal room of the Waste Isolation Pilot Plant is inadvertently penetrated by an exploratory borehole. The first mechanism is due to the erosion of the borehole wall adjacent to the waste caused by the flowing drilling fluid (mud); a quantitative computational model based upon the flow characteristics of the drilling fluid (laminar or turbulent) and other drilling parameters is developed and example results shown. The second mechanism concerns the motion of the waste and borehole spall caused by the flow of waste-generated gas to the borehole. Some of the available literature concerning this process is discussed, and a number of elastic and elastic-plastic finite-difference and finite-element calculations are described that confirm the potential importance of this process in directly removing wastes from the repository to the ground surface. Based upon the amount of analysis performed to date, it is concluded that it is not unreasonable to expect that volumes of waste several times greater than that resulting from direct cutting of a gauge borehole could eventually reach the ground surface. No definitive quantitative model for waste removal as a result of the second mechanism is presented; it is concluded that decomposed waste constitutive data must be developed and additional experiments performed to assess further the full significance of this latter mechanism

  14. Trench 'bathtubbing' and surface plutonium contamination at a legacy radioactive waste site.

    Science.gov (United States)

    Payne, Timothy E; Harrison, Jennifer J; Hughes, Catherine E; Johansen, Mathew P; Thiruvoth, Sangeeth; Wilsher, Kerry L; Cendón, Dioni I; Hankin, Stuart I; Rowling, Brett; Zawadzki, Atun

    2013-01-01

    Radioactive waste containing a few grams of plutonium (Pu) was disposed between 1960 and 1968 in trenches at the Little Forest Burial Ground (LFBG), near Sydney, Australia. A water sampling point installed in a former trench has enabled the radionuclide content of trench water and the response of the water level to rainfall to be studied. The trench water contains readily measurable Pu activity (~12 Bq/L of (239+240)Pu in 0.45 μm-filtered water), and there is an associated contamination of Pu in surface soils. The highest (239+240)Pu soil activity was 829 Bq/kg in a shallow sample (0-1 cm depth) near the trench sampling point. Away from the trenches, the elevated concentrations of Pu in surface soils extend for tens of meters down-slope. The broader contamination may be partly attributable to dispersion events in the first decade after disposal, after which a layer of soil was added above the trenched area. Since this time, further Pu contamination has occurred near the trench-sampler within this added layer. The water level in the trench-sampler responds quickly to rainfall and intermittently reaches the surface, hence the Pu dispersion is attributed to saturation and overflow of the trenches during extreme rainfall events, referred to as the 'bathtub' effect.

  15. A reliability study on influence of the geosphere thickness over the activity release from a near surface radioactive waste repository

    Energy Technology Data Exchange (ETDEWEB)

    Aguiar, Lais Alencar de, E-mail: laguiar@cnen.gov.br [Comissao Nacional de Energia Nuclear (CNEN-RJ), Rio de Janeiro, RJ (Brazil); Damaso, Vinicius Correa, E-mail: vcdamaso@gmail.com [Estado-Maior do Exercito (EME/EB), Brasilia, DF (Brazil)

    2013-07-01

    Infiltration of water into a waste disposal facility and into the waste region is the main factor inducing the release of radionuclides from a disposal facility. Since infiltrating water flow is dependent on the natural percolation at the site and the performance of engineered barriers, its prediction requires modelling of unsaturated water flow through intact or partially/completely failed components of engineered barriers and through the rock layer of the geosphere on which the repository is constructed. The engineered barriers include the cover systems, concrete vault, backfill, waste forms, and overpacks. This paper aims to carry out a performance study regarding a near surface repository in terms of reliability engineering. It is assumed that surface water infiltrates through the barriers reaching the matrix where radionuclides are contained, thus releasing them into the environment. The repository consists of a set of barriers which are considered saturated porous medium. As results, this paper presents the relation between the thickness of the geosphere layer and the radionuclide release rate in terms of activity. Such results represent a useful information for choosing the repository sites in order to keep the released activity in acceptable levels over time. (author)

  16. A reliability study on influence of the geosphere thickness over the activity release from a near surface radioactive waste repository

    International Nuclear Information System (INIS)

    Aguiar, Lais Alencar de; Damaso, Vinicius Correa

    2013-01-01

    Infiltration of water into a waste disposal facility and into the waste region is the main factor inducing the release of radionuclides from a disposal facility. Since infiltrating water flow is dependent on the natural percolation at the site and the performance of engineered barriers, its prediction requires modelling of unsaturated water flow through intact or partially/completely failed components of engineered barriers and through the rock layer of the geosphere on which the repository is constructed. The engineered barriers include the cover systems, concrete vault, backfill, waste forms, and overpacks. This paper aims to carry out a performance study regarding a near surface repository in terms of reliability engineering. It is assumed that surface water infiltrates through the barriers reaching the matrix where radionuclides are contained, thus releasing them into the environment. The repository consists of a set of barriers which are considered saturated porous medium. As results, this paper presents the relation between the thickness of the geosphere layer and the radionuclide release rate in terms of activity. Such results represent a useful information for choosing the repository sites in order to keep the released activity in acceptable levels over time. (author)

  17. Control of water infiltration into near surface LLW [low-level radioactive waste] disposal units

    International Nuclear Information System (INIS)

    Schulz, R.K.; Ridky, R.W.; O'Donnell, E.O.

    1990-12-01

    Three kinds of waste disposal unit covers a barriers to water infiltration are being investigated. They are: (1) resistive layer barrier, (2) conductive layer barrier, and (3) bioengineering management. The resistive layer barrier consists of compacted earthen material (e.g. clay). The conductive layer barrier consists of a conductive layer in conjunction with a capillary break. As long as unsaturated flow conditions are maintained the conductive layer will wick water around the capillary break. Below grade layered covers such as (1) and (2) will fail if there is appreciable subsidence of the cover. Remedial action for this kind of failure will be difficult. A surface cover, called bioengineering management, is meant to overcome this problem. The bioengineering management surface barrier is easily repairable if damaged by subsidence; therefore, it could be the system of choice under active subsidence conditions. The bioengineering management procedure also has been shown to be effective in dewatering saturated trenches and could be used for remedial action efforts. After cessation of subsidence, that procedure could be replaced by a resistive layer barrier, or perhaps even better, a resistive layer barrier/conductive layer barrier system. This latter system would then give long-term effective protection against water entry to waste and without institutional care. These various concepts are being assessed in six large (70ft x 45ft x 10ft each) lysimeters at Beltsville, Maryland. 6 refs., 20 figs.,

  18. Formation of filtration fields close to near-surface radioactive waste storages

    International Nuclear Information System (INIS)

    Mart'yanov, V.V.

    2008-01-01

    Data on the formation of filtration fields in the location of near-surface radioactive waste storages for the conditions of uniformly isotropic properties of bearing strata are demonstrated. The possibility for changing parameters of mean-caused ground flow depending on water permeability of the storages and their dimensions in plan is noted. Comparison of different filtration fields permits to determine a state of its isolating properties. Assessment criteria of the storage engineering barriers integrity are given. Conditions for uniformly isotropic properties of bearing strata by three scenarios, when engineering barriers of the storage are waterproof, distracted or lost protective properties in full, have been determined. Changing filtration field, geochemical and radiochemical situations in bearing strata are noted to represent one of basic characteristics of the integrity of the storage [ru

  19. Evolution of Acid Mine Drainage Formation in Sulphidic Mine Tailings

    Directory of Open Access Journals (Sweden)

    Bernhard Dold

    2014-07-01

    Full Text Available Sulphidic mine tailings are among the largest mining wastes on Earth and are prone to produce acid mine drainage (AMD. The formation of AMD is a sequence of complex biogeochemical and mineral dissolution processes. It can be classified in three main steps occurring from the operational phase of a tailings impoundment until the final appearance of AMD after operations ceased: (1 During the operational phase of a tailings impoundment the pH-Eh regime is normally alkaline to neutral and reducing (water-saturated. Associated environmental problems include the presence of high sulphate concentrations due to dissolution of gypsum-anhydrite, and/or effluents enriched in elements such as Mo and As, which desorbed from primary ferric hydroxides during the alkaline flotation process. (2 Once mining-related operations of the tailings impoundment has ceased, sulphide oxidation starts, resulting in the formation of an acidic oxidation zone and a ferrous iron-rich plume below the oxidation front, that re-oxidises once it surfaces, producing the first visible sign of AMD, i.e., the precipitation of ferrihydrite and concomitant acidification. (3 Consumption of the (reactive neutralization potential of the gangue minerals and subsequent outflow of acidic, heavy metal-rich leachates from the tailings is the final step in the evolution of an AMD system. The formation of multi-colour efflorescent salts can be a visible sign of this stage.

  20. Waste Quantity, Mix and Throughput Study Report

    International Nuclear Information System (INIS)

    Ovadia E, Lev

    1997-01-01

    This report describes the impact that waste stream parameters have on repository design, including surface, subsurface and waste package designs. Two design basis waste streams and corresponding design levels are established for two documented inventories of wastes: (a) Mined Geologic Design System (MGDS) Baseline (Viability Assessment) (VA) and (b) Extended Baseline. The MGDS Baseline VA inventory is currently used as the basis for the VA design of the repository, and is limited by statutes to a total of 70,000 MTU. The Extended Baseline includes the total documented inventories of commercial spent nuclear fuel, high-level waste and US Department of Energy spent nuclear fuel. Impacts of the two design bases on surface, subsurface and waste package designs are projected. The impact of potential disposal of additional commercial and Department of Energy miscellaneous wastes on design is assessed qualitatively

  1. The management of radioactive wastes

    International Nuclear Information System (INIS)

    1998-01-01

    This educative booklet describes the role and missions of the ANDRA, the French national agency for the management of radioactive wastes, and the different aspects of the management of radioactive wastes: goal, national inventory, classification, transport (organisation, regulation, safety), drumming, labelling, surface storage of short life wastes, environmental control, management of long life wastes (composition, research, legal aspects) and the underground research laboratories (description, public information, projects, schedules). (J.S.)

  2. Organohalogen pollutants in surface particulates from workshop floors of four major e-waste recycling sites in China and implications for emission lists.

    Science.gov (United States)

    Zeng, Yan-Hong; Tang, Bin; Luo, Xiao-Jun; Zheng, Xiao-Bo; Peng, Ping-An; Mai, Bi-Xian

    2016-11-01

    To examine the environmental pollution associated with e-waste recycling activities, the concentrations of organohologenated pollutants (OHPs), i.e., short- and medium-chain chlorinated paraffins (SCCPs and MCCPs), polychlorinated biphenyls (PCBs), polybrominated diphenyl ethers (PBDEs), and several other halogenated flame retardants (OHFRs), were investigated in surface particulates from the workshop floors of four major e-waste recycling sites (Taizhou, Guiyu, Dali and Qingyuan) in China. The mean levels of SCCPs, MCCPs, PCBs, PBDEs and OHFRs in surface particulates ranged from 30,000-61,000, 170,000-890,000, 2700-27,000, 52,000-240,000, and 62,000-140,000ng/g dry weight (dw), respectively. OHFRs, including decabromodiphenyl ethane, dechlorane plus, 1,2-bis(2,4,6-tribromophenoxy)ethane, tetrabromobisphenol A, hexabromocyclododecanes, polybrominated biphenyls, hexabromobenzene, pentabromotoluene, and pentabromoethylbenzene, were frequently (>50% detection frequency) detected in surface particulates with mean concentration ranges of 39,000-63,000, 310-2700, 98-16,000, 21,000-56,000, 55-5700, 1700-27,000, 42-1600, 3.2-220, and 5.8-12ng/g dw, respectively. The composition of OHPs varied depend on the e-waste items processing in different regions. Guiyu and Dali were typical sites contaminated by halogenated flame retardants (HFRs) and CPs, respectively, while Qingyuan, and Taizhou were representative PCB-polluted regions. The evidence produced by this preliminary study indicated that electronic devices and plastics may account for the high content of HFRs and the metal products are likely the major source of CPs in these e-waste sites. Copyright © 2016. Published by Elsevier B.V.

  3. Adsorption of dyes by ACs prepared from waste tyre reinforcing fibre. Effect of texture, surface chemistry and pH.

    Science.gov (United States)

    Acevedo, Beatriz; Rocha, Raquel P; Pereira, Manuel F R; Figueiredo, José L; Barriocanal, Carmen

    2015-12-01

    This paper compares the importance of the texture and surface chemistry of waste tyre activated carbons in the adsorption of commercial dyes. The adsorption of two commercial dyes, Basic Astrazon Yellow 7GLL and Reactive Rifafix Red 3BN on activated carbons made up of reinforcing fibres from tyre waste and low-rank bituminous coal was studied. The surface chemistry of activated carbons was modified by means of HCl-HNO3 treatment in order to increase the number of functional groups. Moreover, the influence of the pH on the process was also studied, this factor being of great importance due to the amphoteric characteristics of activated carbons. The activated carbons made with reinforcing fibre and coal had the highest SBET, but the reinforcing fibre activated carbon samples had the highest mesopore volume. The texture of the activated carbons was not modified upon acid oxidation treatment, unlike their surface chemistry which underwent considerable modification. The activated carbons made with a mixture of reinforcing fibre and coal experienced the largest degree of oxidation, and so had more acid surface groups. The adsorption of reactive dye was governed by the mesoporous volume, whilst surface chemistry played only a secondary role. However, the surface chemistry of the activated carbons and dispersive interactions played a key role in the adsorption of the basic dye. The adsorption of the reactive dye was more favored in a solution of pH 2, whereas the basic dye was adsorbed more easily in a solution of pH 12. Copyright © 2015 Elsevier Inc. All rights reserved.

  4. Unresolved issues for the disposal of remote-handled transuranic waste in the Waste Isolation Pilot Plant

    International Nuclear Information System (INIS)

    Silva, M.K.; Neill, R.H.

    1994-09-01

    The purpose of the Waste Isolation Pilot Plant (WIPP) is to dispose of 176,000 cubic meters of transuranic (TRU) waste generated by the defense activities of the US Government. The envisioned inventory contains approximately 6 million cubic feet of contact-handled transuranic (CH TRU) waste and 250,000 cubic feet of remote handled transuranic (RH TRU) waste. CH TRU emits less than 0.2 rem/hr at the container surface. Of the 250,000 cubic feet of RH TRU waste, 5% by volume can emit up to 1,000 rem/hr at the container surface. The remainder of RH TRU waste must emit less than 100 rem/hr. These are major unresolved problems with the intended disposal of RH TRU waste in the WIPP. (1) The WIPP design requires the canisters of RH TRU waste to be emplaced in the walls (ribs) of each repository room. Each room will then be filled with drums of CH TRU waste. However, the RH TRU waste will not be available for shipment and disposal until after several rooms have already been filled with drums of CH TRU waste. RH TRU disposal capacity will be loss for each room that is first filled with CH TRU waste. (2) Complete RH TRU waste characterization data will not be available for performance assessment because the facilities needed for waste handling, waste treatment, waste packaging, and waste characterization do not yet exist. (3) The DOE does not have a transportation cask for RH TRU waste certified by the US Nuclear Regulatory Commission (NRC). These issues are discussed along with possible solutions and consequences from these solutions. 46 refs

  5. A summary of the sources of input parameter values for the Waste Isolation Pilot Plant final porosity surface calculations

    International Nuclear Information System (INIS)

    Butcher, B.M.

    1997-08-01

    A summary of the input parameter values used in final predictions of closure and waste densification in the Waste Isolation Pilot Plant disposal room is presented, along with supporting references. These predictions are referred to as the final porosity surface data and will be used for WIPP performance calculations supporting the Compliance Certification Application to be submitted to the U.S. Environmental Protection Agency. The report includes tables and list all of the input parameter values, references citing their source, and in some cases references to more complete descriptions of considerations leading to the selection of values

  6. A summary of the sources of input parameter values for the Waste Isolation Pilot Plant final porosity surface calculations

    Energy Technology Data Exchange (ETDEWEB)

    Butcher, B.M.

    1997-08-01

    A summary of the input parameter values used in final predictions of closure and waste densification in the Waste Isolation Pilot Plant disposal room is presented, along with supporting references. These predictions are referred to as the final porosity surface data and will be used for WIPP performance calculations supporting the Compliance Certification Application to be submitted to the U.S. Environmental Protection Agency. The report includes tables and list all of the input parameter values, references citing their source, and in some cases references to more complete descriptions of considerations leading to the selection of values.

  7. On release of radionuclides from a near-surface radioactive waste repository to the environment

    Directory of Open Access Journals (Sweden)

    Gudelis Arūnas

    2015-09-01

    Full Text Available A closed near-surface radioactive waste repository is the source of various radionuclides causing the human exposure. Recent investigations confirm an effectiveness of the engineering barriers installed in 2006 to prevent the penetration of radionuclides to the environment. The tritium activity concentration in groundwater decreased from tens of kBq/l to below hundreds of Bq/l. The monitoring and groundwater level data suggest the leaching of tritium from previously contaminated layers of unsaturated zone by rising groundwater while 210Pb may disperse as a decay product of 226Ra daughters.

  8. Radiolytic gas generation from cement-based waste hosts for DOE low-level radioactive wastes

    International Nuclear Information System (INIS)

    Dole, L.R.; Friedman, H.A.

    1986-01-01

    Using cement-based immobilization binders with simulated radioactive waste containing sulfate, nitrate, nitrite, phosphate, and fluoride anions, the gamma- and alpha-radiolytic gas generation factors (G/sub t/, molecules/100 eV) and gas compositions were measured on specimens of cured grouts. These tests studied the effects of; (1) waste composition; (2) the sample surface-to-volume ratio; (3) the waste slurry particle size; and (4) the water content of the waste host formula. The radiolysis test vessels were designed to minimize the ''dead'' volume and to simulate the configuration of waste packages

  9. ASAM - The international programme on application of safety assessment methodologies for near surface radioactive waste disposal facilities

    International Nuclear Information System (INIS)

    Batandjieva, B.

    2002-01-01

    The IAEA has launched a new Co-ordinated Research Project (CRP) on Application of Safety Assessment Methodologies for Near Surface Waste Disposal Facilities (ASAM). The CRP will focus on the practical application of the safety assessment methodology, developed under the ISAM programme, for different purposes, such as developing design concepts, licensing, upgrading existing repositories, reassessment of operating disposal facilities. The overall aim of the programme is to assist safety assessors, regulators and other specialists involved in the development and review of safety assessment for near surface disposal facilities in order to achieve transparent, traceable and defendable evaluation of safety of these facilities. (author)

  10. The surface disposal concept for LIL/SL waste

    International Nuclear Information System (INIS)

    2011-01-01

    Most low-level and intermediate-level short-lived (LIL/SL) waste result from the nuclear-power industry. Their specific activity level is sufficiently high to justify a protective conditioning and to ensure proper confinement until that level has decreased to harmless levels for human beings and the environment (a few centuries considering the half lives of the radionuclides contained in LIL/SL waste). The disposal concept for such residues relies on a multi-barrier protective system, each barrier being designed to fulfil different or redundant functions in order to delay or mitigate radionuclide transfers first into the environment and onwards to human beings. The originality of the concept pertains to its flexibility, since: it is adaptable to various geological environments and its overall performance may be guaranteed by modulating that of the engineered barriers, and it is suitable for the disposal of different types and sizes of waste packages, as long as their characteristics are consistent with acceptance criteria, which are de facto specific to each case. To provide its wide-ranging competences in the field of waste management and disposal, ANDRA offers multiple solutions, from consultancy and documents reviewing, to technology transfer and turnkey projects. The safety of the disposal facility is guaranteed by the combination of the package, the concrete structures, the filling materials between packages and the watertight clay cap that will be installed at the end of the operating lifetime of the facility. That layout also takes all natural risks into account. Lastly, all disposal structures are built away from any potential flood zones and from the highest possible level of the groundwater table. Concrete and metal packages are disposed of in slightly different structures. Once a structure is full, concrete packages are immobilised with gravel, whereas metal packages are blocked in place by pouring concrete between them. Once a disposal structure is

  11. The surface disposal concept for LIL/SL waste

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2011-07-01

    Most low-level and intermediate-level short-lived (LIL/SL) waste result from the nuclear-power industry. Their specific activity level is sufficiently high to justify a protective conditioning and to ensure proper confinement until that level has decreased to harmless levels for human beings and the environment (a few centuries considering the half lives of the radionuclides contained in LIL/SL waste). The disposal concept for such residues relies on a multi-barrier protective system, each barrier being designed to fulfil different or redundant functions in order to delay or mitigate radionuclide transfers first into the environment and onwards to human beings. The originality of the concept pertains to its flexibility, since: it is adaptable to various geological environments and its overall performance may be guaranteed by modulating that of the engineered barriers, and it is suitable for the disposal of different types and sizes of waste packages, as long as their characteristics are consistent with acceptance criteria, which are de facto specific to each case. To provide its wide-ranging competences in the field of waste management and disposal, ANDRA offers multiple solutions, from consultancy and documents reviewing, to technology transfer and turnkey projects. The safety of the disposal facility is guaranteed by the combination of the package, the concrete structures, the filling materials between packages and the watertight clay cap that will be installed at the end of the operating lifetime of the facility. That layout also takes all natural risks into account. Lastly, all disposal structures are built away from any potential flood zones and from the highest possible level of the groundwater table. Concrete and metal packages are disposed of in slightly different structures. Once a structure is full, concrete packages are immobilised with gravel, whereas metal packages are blocked in place by pouring concrete between them. Once a disposal structure is

  12. Chemical decontamination method for radioactive metal waste

    International Nuclear Information System (INIS)

    Onuma, Tsutomu; Akimoto, Hidetoshi

    1991-01-01

    The invention relates to a decontamination method for radioactive metal waste products derived from equipment that handles radioactive materials whose surfaces have been contaminated; in particular it concerns a decontamination method that reduces the amount of radioactive waste by decontaminating radioactive waste substances to a level of radioactivity in line with normal waste products. In order to apply chemical decontamination to metal waste products whose surfaces are divided into carbon steel waste and stainless steel waste; the carbon steel waste is treated using only a primary process in which the waste is immersed in a sulfuric acid solution, while the stainless steel waste must be treated with both the primary process and then electrolytically reduces it for a specific length of time and a secondary process that uses a solution of sulfuric acid mixed with oxidizing metal salts. The method used to categorize metal waste into carbon steel waste and stainless steel waste involves determining the presence, or absence, of magnetism. Voltage is applied for a fixed duration; once that has stopped, electrolytic reduction repeats the operative cycle of applying, then stopping voltage until the potential of the radioactive metal waste is retained in the active region. 1 fig. 2 tabs

  13. Effect of sugarcane waste in the control of interrill erosion

    Directory of Open Access Journals (Sweden)

    Wander Cardoso Valim

    2016-06-01

    Full Text Available The cultivation of sugarcane uses different cropping systems that result in varying quantities of crop waste, this may influence soil erosion. The objective of this study was to evaluate the loss of soil and water, the infiltration rate, and soil surface roughness in an area cultivated with sugarcane (Saccharum spp.. Six treatments with different levels of plant waste were evaluated: sugarcane without plant waste; sugarcane with 4.0 Mg ha-1 of waste; sugarcane with 8.0 Mg ha-1 of waste; sugarcane with 12.0 Mg ha-1 of waste; sugarcane with 16.0 Mg ha-1 of waste; and burned sugarcane. The treatments were arranged in a randomized block design with four replications, totalling 24 experimental plots. As soil depth increased, there is reduction in macroporosity, total soil porosity, organic carbon content, mean geometric diameter and weighted mean diameter of the soil aggregates, whereas the bulk density of the soil displays the opposite trend. The presence of sugarcane waste on the soil surface increases the time required for the initiation of surface runoff. Sugarcane waste does not alter soil surface roughness, and at the minimum amount of waste administered (4 Mg ha-1 reduces losses of soil and water and increases the infiltration rate. The lack of soil surface coverage after harvesting the sugarcane contributes to soil and water loss, and reduces the rate of stable infiltration of water into the soil.

  14. Dynamics of radioactive waste generation

    International Nuclear Information System (INIS)

    Dogaru, Daniela; Virtopeanu, Cornelia; Ivan, Alexandrina

    2008-01-01

    In Romania there are in operation three facilities licensed for collection, treatment and storage of radioactive waste resulted from industry, research, medicine, and agriculture, named institutional radioactive waste. The repository, which is of near surface type, is designed for disposing institutional radioactive waste. The institutional radioactive wastes generated are allowed to be disposed into repository according to the waste acceptance criteria, defined for the disposal facility. The radioactive wastes which are not allowed for disposal are stored on the site of each facility which is special authorised for this. The paper describes the dynamics of generation of institutional waste in Romania, both for radioactive waste which are allowed to be disposed into repository and for radioactive waste which are not allowed to be disposed of. (authors)

  15. Near-surface land disposal

    International Nuclear Information System (INIS)

    Kittel, J.H.

    1989-01-01

    The Radioactive Waste Management Handbook provides a comprehensive, systematic treatment of nuclear waste management. Near-Surface Land Disposal, the first volume, is a primary and secondary reference for the technical community. To those unfamiliar with the field, it provides a bridge to a wealth of technical information, presenting the technology associated with the near-surface disposal of low or intermediate level wastes. Coverage ranges from incipient planning to site closure and subsequent monitoring. The book discusses the importance of a systems approach during the design of new disposal facilities so that performance objectives can be achieved; gives an overview of the radioactive wastes cosigned to near-surface disposal; addresses procedures for screening and selecting sites; and emphasizes the importance of characterizing sites and obtaining reliable geologic and hydrologic data. The planning essential to the development of particular sites (land acquisition, access, layout, surface water management, capital costs, etc.) is considered, and site operations (waste receiving, inspection, emplacement, closure, stabilization, etc.) are reviewed. In addition, the book presents concepts for improved confinement of waste, important aspects of establishing a monitoring program at the disposal facility, and corrective actions available after closure to minimize release. Two analytical techniques for evaluating alternative technologies are presented. Nontechnical issues surrounding disposal, including the difficulties of public acceptance are discussed. A glossary of technical terms is included

  16. 40 CFR 436.181 - Specialized definitions.

    Science.gov (United States)

    2010-07-01

    .... (b) The term “mine dewatering” shall mean any water that is impounded or that collects in the mine... include any other water which becomes commingled with such waste water in a pit, pond lagoon, mine, or other facility used for settling or treatment of such waste water. [43 FR 9809, Mar. 10, 1978] ...

  17. Annular air space effects on nuclear waste canister temperatures in a deep geologic waste repository

    International Nuclear Information System (INIS)

    Lowry, W.E.; Cheung, H.; Davis, B.W.

    1980-01-01

    Air spaces in a deep geologic repository for nuclear high level waste will have an important effect on the long-term performance of the waste package. The important temperature effects of an annular air gap surrounding a high level waste canister are determined through 3-D numerical modeling. Air gap properties and parameters specifically analyzed and presented are the air gap size, surfaces emissivity, presence of a sleeve, and initial thermal power generation rate; particular emphasis was placed on determining the effect of these variables have on the canister surface temperature. Finally a discussion based on modeling results is presented which specifically relates the results to NRC regulatory considerations

  18. Survivability of ancient man-made earthen mounds: implications for uranium mill tailings impoundments

    International Nuclear Information System (INIS)

    Lindsey, C.G.; Mishima, J.; King, S.E.; Walters, W.H.

    1983-06-01

    As part of a study for the Nuclear Regulatory Commission (NRC), the Pacific Northwest Laboratory (PNL) is investigating long-term stabilization techniques for uranium mill impoundments. Part of this investigation involves the design of a rock armoring blanket (riprap) to mitigate wind and water erosion of the underlying soil cover, which in turn prevents exposure of the tailings to the environment. However, the need for the armoring blanket, as well as the blanket's effectiveness, depends on the stability of the underlying soil cap (radon suppression cover) and on the tailings themselves. Compelling evidence in archaeological records suggests that large man-made earthen structures can remain sound and intact for time periods comparable to those required for the stabilization of the tailings piles if properly constructed. We present archaeological evidence on the existence and survivability of man-made earthen and rock structures through specific examples of such structures from around the world. We also review factors contributing to their survival or destruction and address the influence of climate, building materials, and construction techniques on survivability

  19. ANDRA's Centre de l'Aube: Design, construction, operation of a state of the art surface disposal facility for low and intermediate level waste

    International Nuclear Information System (INIS)

    Potier, J.M.

    2001-01-01

    The ANDRA's Centre de I'Aube disposal facility for low and intermediate level radioactive waste may be considered as a state-of-the-art repository. Since its implementation in the early nineties, the French facility has been used as a model by many countries worldwide for the surface disposal of radioactive waste. The disposal concept developed by ANDRA, the French Radioactive Waste Management Agency, consists of a multiple-barrier system designed to isolate radioactivity and provide protection to the public and to the environment. Waste operations at ANDRA's Centre de I'Aube are largely automated to ensure better protection to site workers. The paper reviews all aspects of the repository implementation: siting, design, construction, operation and future closure, and environmental monitoring. (author)

  20. Surface radiological investigations at the 0816 Site, Waste Area Grouping 13, Oak Ridge National Laboratory, Oak Ridge, Tennessee

    International Nuclear Information System (INIS)

    Tiner, P.F.; Uziel, M.S.

    1994-12-01

    A surface radiological investigation was conducted intermittently from July through September 1994 at the 0816 site, located within Waste Area Grouping (WAG) 13. The survey was performed by members of the Measurement Applications and Development Group, Health Sciences Research Division, Oak Ridge National Laboratory (ORNL) at the request of ORNL Site Environmental Restoration Program Facility Management. The purpose of the survey was to ascertain and document the surface radiological condition of the site subsequent to remedial action activities completed in May 1994. The survey was designed to determine whether any residual surface sod contamination in excess of 120 pCi/g 137 Cs (Specified by the Interim Record of Decision) remained at the site

  1. Method of decontaminating radioactive metal wastes

    International Nuclear Information System (INIS)

    Miyaji, Nobuyoshi.

    1985-01-01

    Purpose: To completely prevent the surface contamination of an equipment and decrease the amount of radioactive wastes to be resulted. Method: The surfaces of vessels, pipeways or the likes of nuclear reactor facilities to be contaminated with radioactive materials are appended with thin plates of metals identical or different from the constituents of the surfaces so as to be releasable after use. The material and the thickness of the plates and the method of appending then are determined depending on the state of use of the appended portions. Since only the stripped plates have to be processed as radioactive wastes, the amount of wastes can be decreased and, since the scrap materials can be reused, it is advantageous in view of the resource-saving. (Sekiya, K.)

  2. Enhanced Production of Cellulase from Pineapple Waste by Response Surface Methodology

    Directory of Open Access Journals (Sweden)

    P. Saravanan

    2013-01-01

    Full Text Available Optimization of the media components for cellulase production using Trichoderma reesei was carried out. The optimization of cellulase production using pineapple waste as substrate was performed with statistical methodology based on experimental designs. The screening of nutrients and their influence on the cellulase production was studied using a Plackett-Burman design. Avicel, soybean cake flour, KH2PO4, and yeast extract were found to have the positive influence for the production of cellulase. The selected components were optimized using response surface methodology. The optimum concentrations are avicel: 26.5 g/L, soybean cake flour: 22.5 g/L, KH2PO4: 4.5 g/L, and yeast extract: 12.3 g/L. A maximum cellulase activity of 8.61 IU/mL was obtained under the optimized medium in the validation experiment.

  3. Regional waste treatment with monolith disposal for low-level radioactive waste

    International Nuclear Information System (INIS)

    Forsberg, C.W.

    1983-01-01

    An alternative system is proposed for the disposal of low-level radioactive waste. This system, called REgional Treatment with MOnolith Disposal (RETMOD), is based on integrating three commercial technologies: automated package warehousing, whole-barrel rotary kiln incineration, and cement-based grouts for radioactive waste disposal. In the simplified flowsheet, all the sludges, liquids, resins, and combustible wastes are transported to regional facilities where they are incinerated. The ash is then mixed with special cement-based grouts, and the resulting mixture is poured into trenches to form large waste-cement monoliths. Wastes that do not require treatment, such as damaged and discarded equipment, are prepositioned in the trenches with the waste-cement mixture poured on top. The RETMOD system may provide higher safety margins by conversion of wastes into a solidified low-leach form, creation of low-surface area waste-cement monoliths, and centralization of waste processing into a few specialized facilities. Institutional problems would be simplified by placing total responsibility for safe disposal on the disposal site operator. Lower costs may be realized through reduced handling costs, the economics of scale, simplified operations, and less restrictive waste packaging requirements

  4. Radioactive waste management

    International Nuclear Information System (INIS)

    Alfredson, P.G.; Levins, D.M.

    1975-08-01

    Present and future methods of managing radioactive wastes in the nuclear industry are reviewed. In the stages from uranium mining to fuel fabrication, the main purpose of waste management is to limit and control dispersal into the environment of uranium and its decay products, particularly radium and radon. Nuclear reactors produce large amounts of radioactivity but release rates from commercial power reactors have been low and well within legal limits. The principal waste from reprocessing is a high activity liquid containing essentially all the fission products along with the transuranium elements. Most high activity wastes are currently stored as liquids in tanks but there is agreement that future wastes must be converted into solids. Processes to solidify wastes have been demonstrated in pilot plant facilities in the United States and Europe. After solidification, wastes may be stored for some time in man-made structures at or near the Earth's surface. The best method for ultimate disposal appears to be placing solid wastes in a suitable geological formation on land. (author)

  5. Radioactive wastes. The management of nuclear wastes. Waste workshop, first half-year - Year 2013-2014

    International Nuclear Information System (INIS)

    Esteoulle, Lucie; Rozwadowski, Elodie; Duverger, Clara

    2014-01-01

    The first part of this report first presents radioactive wastes with their definition, and their classification (radioactivity level, radioactive half-life). It addresses the issue of waste storage by presenting the different types of storage used since the 1950's (offshore storage, surface warehousing, storage in deep geological layer), and by discussing the multi-barrier approach used for storage safety. The authors then present the French strategy which is defined in the PNGMDR to develop new management modes on the long term, to improve existing management modes, and to take important events which occurred between 2010 and 2012 into account. They also briefly present the Cigeo project (industrial centre of geological storage), and evoke controversies related to the decision to locate this project in Bure (existence of geological cracks and defects, stability and tightness of the clay layer, geothermal potential of the region, economic cost). The second part proposes an overview of the issue of nuclear waste management. The author recalls the definition of a radioactive waste, indicates the origins of these wastes and their classification. She proposes a history of the radioactive waste: discovery of radioactivity, military industrialisation and awareness of the dangerousness of radioactive wastes, nuclear wastes and recent incidents (West Valley, La Hague, Windscale). An overview of policies of nuclear waste management is given: immersion of radioactive wastes, major accidental releases, solutions on the short term and on the medium term

  6. Transportation packagings for high-level wastes and unprocessed transuranic wastes

    International Nuclear Information System (INIS)

    Wilmot, E.L.; Romesberg, L.E.

    1982-01-01

    Packagings used for nuclear waste transport are varied in size, shape, and weight because they must accommodate a wide variety of waste forms and types. However, this paper will discuss the common characteristics among the packagings in order to provide a broad understanding of packaging designs. The paper then discusses, in some detail, a design that has been under development recently at Sandia National Laboratories (SNL) for handling unprocessed, contact-handled transuranic (CHTRU) wastes as well as a cask design for defense high-level wastes (HLW). As presently conceived, the design of the transuranic package transporter (TRUPACT) calls for inner and outer boxes that are separated by a rigid polyurethane foam. The inner box has a steel frame with stainless steel surfaces; the outer box is similarly constructed except that carbon steel is used for the outside surfaces. The access to each box is through hinged doors that are sealed after loading. To meet another waste management need, a cask is being developed to transport defense HLW. The cask, which is at the preliminary design stage, is being developed by General Atomic under the direction of the TTC. The cask design relies heavily on state-of-the-art spent-fuel cask designs though it can be much simpler due to the characteristics of the HLW. A primary purpose of this paper is to show that CHTRU waste and defense HLW currently are and will be transported in packagings designed to meet the hazards of transportation that are present in general commerce

  7. 30 CFR 816.89 - Disposal of noncoal mine wastes.

    Science.gov (United States)

    2010-07-01

    ... surface runoff do not degrade surface or ground water, that fires are prevented, and that the area remains... underground water. Wastes shall be routinely compacted and covered to prevent combustion and wind-borne waste...

  8. Nondestructive and destructive measurements, a synergy for the wastes characterization

    International Nuclear Information System (INIS)

    Amoravain, S.; Dogny, S.

    2001-01-01

    The waste generated by nuclear industry have to be treated and conditioned to be stored in sites managed by ANDRA. Three channels are conceivable, the storage of very low activity waste, the surface storage of short live and low and intermediate activity waste, and the deep storage for long life or high activity waste. At this day, only the surface storage for waste at short life and low and intermediate activity is operational and allows to evacuate the radioactive waster. (N.C.)

  9. Organohalogen pollutants in surface particulates from workshop floors of four major e-waste recycling sites in China and implications for emission lists

    Energy Technology Data Exchange (ETDEWEB)

    Zeng, Yan-Hong [State Key Laboratory of Organic Geochemistry and Guangdong Key Laboratory of Environmental Protection and Resources Utilization, Guangzhou Institute of Geochemistry, Chinese Academy of Sciences, Guangzhou 510640 (China); Tang, Bin [State Key Laboratory of Organic Geochemistry and Guangdong Key Laboratory of Environmental Protection and Resources Utilization, Guangzhou Institute of Geochemistry, Chinese Academy of Sciences, Guangzhou 510640 (China); Graduate University of Chinese Academy of Sciences, Beijing 100049 (China); Luo, Xiao-Jun [State Key Laboratory of Organic Geochemistry and Guangdong Key Laboratory of Environmental Protection and Resources Utilization, Guangzhou Institute of Geochemistry, Chinese Academy of Sciences, Guangzhou 510640 (China); Zheng, Xiao-Bo [College of Natural Resources and Environment, South China Agricultural University, Guangzhou 510642 (China); Peng, Ping-An [State Key Laboratory of Organic Geochemistry and Guangdong Key Laboratory of Environmental Protection and Resources Utilization, Guangzhou Institute of Geochemistry, Chinese Academy of Sciences, Guangzhou 510640 (China); Mai, Bi-Xian, E-mail: nancymai@gig.ac.cn [State Key Laboratory of Organic Geochemistry and Guangdong Key Laboratory of Environmental Protection and Resources Utilization, Guangzhou Institute of Geochemistry, Chinese Academy of Sciences, Guangzhou 510640 (China)

    2016-11-01

    To examine the environmental pollution associated with e-waste recycling activities, the concentrations of organohologenated pollutants (OHPs), i.e., short- and medium-chain chlorinated paraffins (SCCPs and MCCPs), polychlorinated biphenyls (PCBs), polybrominated diphenyl ethers (PBDEs), and several other halogenated flame retardants (OHFRs), were investigated in surface particulates from the workshop floors of four major e-waste recycling sites (Taizhou, Guiyu, Dali and Qingyuan) in China. The mean levels of SCCPs, MCCPs, PCBs, PBDEs and OHFRs in surface particulates ranged from 30,000–61,000, 170,000–890,000, 2700–27,000, 52,000–240,000, and 62,000–140,000 ng/g dry weight (dw), respectively. OHFRs, including decabromodiphenyl ethane, dechlorane plus, 1,2-bis(2,4,6-tribromophenoxy)ethane, tetrabromobisphenol A, hexabromocyclododecanes, polybrominated biphenyls, hexabromobenzene, pentabromotoluene, and pentabromoethylbenzene, were frequently (> 50% detection frequency) detected in surface particulates with mean concentration ranges of 39,000–63,000, 310–2700, 98–16,000, 21,000–56,000, 55–5700, 1700–27,000, 42–1600, 3.2–220, and 5.8–12 ng/g dw, respectively. The composition of OHPs varied depend on the e-waste items processing in different regions. Guiyu and Dali were typical sites contaminated by halogenated flame retardants (HFRs) and CPs, respectively, while Qingyuan, and Taizhou were representative PCB-polluted regions. The evidence produced by this preliminary study indicated that electronic devices and plastics may account for the high content of HFRs and the metal products are likely the major source of CPs in these e-waste sites. - Highlights: • Report of characterizing the types and possible sources of OHPs in e-waste sites • Guiyu was a typical site contaminated by HFRs, while Dali was dominated by CPs. • Qingyuan and Taizhou were representative PCB-polluted regions. • Electronic devices and plastics may account for the

  10. Organohalogen pollutants in surface particulates from workshop floors of four major e-waste recycling sites in China and implications for emission lists

    International Nuclear Information System (INIS)

    Zeng, Yan-Hong; Tang, Bin; Luo, Xiao-Jun; Zheng, Xiao-Bo; Peng, Ping-An; Mai, Bi-Xian

    2016-01-01

    To examine the environmental pollution associated with e-waste recycling activities, the concentrations of organohologenated pollutants (OHPs), i.e., short- and medium-chain chlorinated paraffins (SCCPs and MCCPs), polychlorinated biphenyls (PCBs), polybrominated diphenyl ethers (PBDEs), and several other halogenated flame retardants (OHFRs), were investigated in surface particulates from the workshop floors of four major e-waste recycling sites (Taizhou, Guiyu, Dali and Qingyuan) in China. The mean levels of SCCPs, MCCPs, PCBs, PBDEs and OHFRs in surface particulates ranged from 30,000–61,000, 170,000–890,000, 2700–27,000, 52,000–240,000, and 62,000–140,000 ng/g dry weight (dw), respectively. OHFRs, including decabromodiphenyl ethane, dechlorane plus, 1,2-bis(2,4,6-tribromophenoxy)ethane, tetrabromobisphenol A, hexabromocyclododecanes, polybrominated biphenyls, hexabromobenzene, pentabromotoluene, and pentabromoethylbenzene, were frequently (> 50% detection frequency) detected in surface particulates with mean concentration ranges of 39,000–63,000, 310–2700, 98–16,000, 21,000–56,000, 55–5700, 1700–27,000, 42–1600, 3.2–220, and 5.8–12 ng/g dw, respectively. The composition of OHPs varied depend on the e-waste items processing in different regions. Guiyu and Dali were typical sites contaminated by halogenated flame retardants (HFRs) and CPs, respectively, while Qingyuan, and Taizhou were representative PCB-polluted regions. The evidence produced by this preliminary study indicated that electronic devices and plastics may account for the high content of HFRs and the metal products are likely the major source of CPs in these e-waste sites. - Highlights: • Report of characterizing the types and possible sources of OHPs in e-waste sites • Guiyu was a typical site contaminated by HFRs, while Dali was dominated by CPs. • Qingyuan and Taizhou were representative PCB-polluted regions. • Electronic devices and plastics may account for the

  11. Technical Performance Capability of Fourier Transform Profilometry for Quantitative Waste Volume Determination under Hanford Waste Tank Condition

    International Nuclear Information System (INIS)

    Monts, D.L.; Jang, P.R.; Long, Z.; Norton, O.P.; Okhuysen, W.P.; Su, Y.; Waggoner, Ch.A.

    2009-01-01

    The Hanford Site is currently in the process of an extensive effort to empty and close its radioactive single-shell and double-shell waste storage tanks. Before this can be accomplished, it is necessary to know how much residual material is left in a given waste tank and the chemical makeup of the residue. The Institute for Clean Energy Technology (ICET) at Mississippi State University is currently developing a quantitative in-tank inspection system based on Fourier Transform Profilometry (FTP). FTP is a non-contact, 3-D shape measurement technique. By projecting a fringe pattern onto a target surface and observing its deformation due to surface irregularities from a different view angle, FTP is capable of determining the height (depth) distribution (and hence volume distribution) of the target surface, thus reproducing the profile of the target accurately under a wide variety of conditions. Hence FTP has the potential to be utilized for quantitative determination of residual wastes within Hanford waste tanks. We report the results of a technical feasibility study to document the accuracy and precision of quantitative volume determination using the Fourier transform profilometry technique under simulated Hanford waste tank conditions. (authors)

  12. Study of waterproof capabilities of the engineered barrier containing bentonite in near surface radioactive waste repositories

    International Nuclear Information System (INIS)

    Luu Cao Nguyen; Nguyen Ba Tien; Doan Thi Thu Hien; Nguyen Van Chinh; Vuong Huu Anh

    2017-01-01

    In Vietnam, the study of nuclear fuel cycle is in first steps, such as the exploitation and uranium processing. These processes generated large amounts of radioactive waste over-timing. The naturally occurring radioactive material and technologically enhanced radioactive material (NORM/TENORM) waste, which would be large, needs to be managed and disposed reasonably by effective methods. These wastes were used to be disposal in the near surface. It was therefore very important to study the model of radioactive waste repository, where bentonite waterproofing layer would be applied for the engineered barrier. The aim of this study was to obtain the preliminary parameters for low-level radioactive waste disposal site being suitable with the conditions of Vietnam. The investigation of the ratio between soil and bentonite was taken part. The experiments with some layers of waterproofing material with the ratio of soil and bentonite as 75/25, 50/50 and 25/75 were carried out to test the moving of uranium nuclide through these waterproofing material layers. Analyzing the uranium content in each layer (0.1 cm) of pressed soil - bentonite mixture (as a block) to determine the uranium nuclide adsorption from solution into the materials in the different ratios at the different times: 1, 2 and 3 months was carried out. The results showed that the calculated average rate of uranium nuclide migration into the soil - bentonite layer was 5.4x10 -10 , 5.4x10 -10 and 3.85x10 -10 m/s corresponding to the waterproofing layer thickness (for 300 years) 4.86 m, 4.86 m and 3.63 m respectively, which was due on the ratio of soil and bentonite 75/25, 50/50, 25/75 to keep the safety for the repository. (author)

  13. Radioactive wastes management

    International Nuclear Information System (INIS)

    Albert, Ph.

    1999-01-01

    This article presents the French way to deal with nuclear wastes. 4 categories of radioactive wastes have been defined: 1) very low-level wastes (TFA), 2) low or medium-wastes with short or medium half-life (A), 3) low or medium-level wastes with long half-life (B), and 4) high-level wastes with long half-life (C). ANDRA (national agency for the management of radioactive wastes) manages 2 sites of definitive surface storage (La-Manche and Aube centers) for TFA-wastes. The Aube center allows the storage of A-wastes whose half-life is less than 30 years. This site will receive waste packages for 50 years and will require a regular monitoring for 300 years after its decommissioning. No definitive solutions have been taken for B and C wastes, they are temporarily stored at La Hague processing plant. Concerning these wastes the French parliament will have to take a decision by 2006. At this date and within the framework of the Bataille law (1991), scientific studies concerning the definitive or retrievable storage, the processing techniques (like transmutation) will have been achieved and solutions will be proposed. These studies are numerous, long and complex, they involve fresh knowledge in geology, chemistry, physics,.. and they have implied the setting of underground facilities in order to test and validate solutions in situ. This article presents also the transmutation technique. (A.C.)

  14. A disposal centre for immobilized nuclear waste

    International Nuclear Information System (INIS)

    1980-02-01

    This report describes a conceptual design of a disposal centre for immobilized nuclear waste. The surface facilities consist of plants for the preparation of steel cylinders containing nuclear waste immobilized in glass, shaft headframe buildings and all necessary support facilities. The underground disposal vault is located on one level at a depth of 1000 m. The waste cylinders are emplaced into boreholes in the tunnel floors. All surface and subsurface facilities are described, operations and schedules are summarized, and cost estimates and manpower requirements are given. (auth)

  15. Radioactive waste management

    International Nuclear Information System (INIS)

    Pahissa Campa, Jaime; Pahissa, Marta H. de

    2000-01-01

    Throughout this century, the application of nuclear energy has produced many benefits, in industry, in research, in medicine, and in the generation of electricity. These activities generate wastes in the same way as do other human activities. The primary objective of radioactive waste management is to protect human health and environment now and in the future without imposing undue burden on future generations, through sound, safe and efficient radioactive waste management. This paper briefly describes the different steps of the management of short lived low and intermediate level wastes, and presents and overview of the state of art in countries involved in nuclear energy, describing their organizations, methodologies used in the processing of these wastes and the final disposal concepts. It also presents the Argentine strategy, its technical and legal aspects. Worldwide experience during the past 50 years has shown that short lived low and intermediate level wastes can be successfully isolated from human and environment in near surface disposal facilities. (author)

  16. Levels and isomer profiles of Dechlorane Plus in the surface soils from e-waste recycling areas and industrial areas in South China

    Energy Technology Data Exchange (ETDEWEB)

    Yu Zhiqiang [State Key Laboratory of Organic Geochemistry, Guangdong Key Laboratory of Environment and Resources, Guangzhou Institute of Geochemistry, Chinese Academy of Sciences, Guangzhou 510640 (China); Lu Shaoyou; Gao Shutao; Wang Jingzhi [State Key Laboratory of Organic Geochemistry, Guangdong Key Laboratory of Environment and Resources, Guangzhou Institute of Geochemistry, Chinese Academy of Sciences, Guangzhou 510640 (China); Graduate School of the Chinese Academy of Sciences, Beijing 100039 (China); Li Huiru, E-mail: huiruli@gig.ac.c [State Key Laboratory of Organic Geochemistry, Guangdong Key Laboratory of Environment and Resources, Guangzhou Institute of Geochemistry, Chinese Academy of Sciences, Guangzhou 510640 (China); Zeng Xiangying; Sheng Guoying; Fu Jiamo [State Key Laboratory of Organic Geochemistry, Guangdong Key Laboratory of Environment and Resources, Guangzhou Institute of Geochemistry, Chinese Academy of Sciences, Guangzhou 510640 (China)

    2010-09-15

    Dechlorane Plus (DP) is a highly chlorinated flame retardant. Levels of DP were measured in surface soils from e-waste recycling areas and industrial areas in South China. Higher DP levels were found in e-waste recycling areas (undetectable-47.4 ng/g) than those in industrial areas (0.0336-4.65 ng/g) in South China. The highest DP concentration (3327 ng/g) was found at the e-waste recycling site in Qingyuan, while DP levels fell dramatically with increasing distance away from the recycling site, suggesting that the e-waste recycling activities are an important source of DP emissions. The mean ratios of anti-DP to total DP (f{sub anti}) for different sampling areas ranged from 0.58 to 0.76 and showed no significant difference from the ratio for the technical DP products (t-test, p > 0.05). Further intensive studies are needed to investigate the process of DP degradation and its degradation products. - High DP concentrations were found in the soils from e-waste recycling regions, and e-waste recycling was the major source of DP emissions in South China.

  17. Preparation of safety analysis reports (SARs) for near surface radioactive waste disposal facilities. Format and content of SARs

    International Nuclear Information System (INIS)

    1995-02-01

    All facilities at which radioactive wastes are processed, stored and disposed of have the potential for causing hazards to humans and to the environment. Precautions must be taken in the siting, design and operation of the facilities to ensure that an adequate level of safety is achieved. The processes by which this is evaluated is called safety assessment. An important part of safety assessment is the documentation of the process. A well prepared safety analysis report (SAR) is essential if approval of the facility is to be obtained from the regulatory authorities. This TECDOC describes the format and content of a safety analysis report for a near surface radioactive waste disposal facility and will serve essentially as a checklist in this respect

  18. Use of artificial barriers in a site for surface storage of radioactive waste

    International Nuclear Information System (INIS)

    Gros, J.C.; Madoz-Escande, C.; Metivier, J.M.; Grimaud, P.

    1990-01-01

    The objective is the on site study of the influence of an injection screen on the flow in a water table of a porous medium, in order to improve the safety of a surface radioactive waste storage site. A hydrodispersive study has provided information for the definition of the role of the screen: the transfer times of the pollutant in the water table are increased by a factor of 2 and, in comparison, the concentration are clearly reduced by a factor of 10. The implantation of an injection screen in the ground should result in an improvement in the restrictive quality of the barrier and the contamination of an aquifer should be slower without interruption to the flow

  19. Treatment of radioactive waste water by flocculation method, (1)

    International Nuclear Information System (INIS)

    Kimura, Syojiro; Tsutsui, Tenson.

    1976-01-01

    Coagulation property of particle on the treatment of radioactive waste water by floculation method is varied with its electrical potential and mixing condition. The surface state of the particle is influenced by contents of coexistent materials in the waste water and added materials at the treatment process. In the case of using ferric hydroxide as coagulant, assuming the ions which decide the potential of the particle surface are Fe(OH) 2 + and Fe(OH) 4 - , calculated values of the potential agree with zeta-potential of ferric hydroxide particle which is formed from FeCl 4 and NaOH in demineralized water. When Na 2 CO 3 is in the waste water as coexistent materials, anion HCO 3 - adsorbs on the particle surface in connection with pH variation and thus the surface charge is being minus. If Ca 2+ ion is present in the waste water, the surface charge plus. ABS acts as single molecule anion at low concentration, but it forms micell at high concentration and influences zeta-potential of the particle. The potential of the particle is correlated to the coprecipitation rate of 90 Sr in the waste water. (auth.)

  20. Determination of Intrinsic Permeability for Packed Waste of Indonesian Solid Waste

    Directory of Open Access Journals (Sweden)

    Benno Rahardyan

    2010-11-01

    Full Text Available Gas permeability and intrinsic permeability are the major parameters to promote aeration for packed waste. The objectives of this research are to identify physical parameters of gas transfer from a various type of packed wastes and examine ventilation design theory for landfill to enhance waste stabilization. Method to determine value of gas permeability and intrinsic permeability for packed waste is by flushing the packed column containing various type and physical characteristics of wastes with an air pump. Permeability was calculated by measuring pressure gradient on sampling points of the column using inclined manometer at distance 10 cm, 23 cm, 46 cm, 69 cm, 92 cm and 115 cm from origin. Gas permeability is specifically relied on physical parameters of wastes as follows, density, moisture content, particle size and gas velocity on the surface of compacted waste layer. Compost has finer pore structure and smaller pore size than leaves as well as mixed organic (65% and inorganic wastes (35%. The experiment found the intrinsic permeability of leaves waste are in the order of 10-11 to 10-8 m2, 10-11 to 10-9 m2 for compost and 10-9 m2 for mixed organic (65% and inorganic wastes (35%.

  1. Modeling of 3d Space-time Surface of Potential Fields and Hydrogeologic Modeling of Nuclear Waste Disposal Sites

    Science.gov (United States)

    Shestopalov, V.; Bondarenko, Y.; Zayonts, I.; Rudenko, Y.

    Introduction After the Chernobyl Nuclear Power Plant (CNPP) disaster (04.26.1986) a huge amount (over 2000 sq. km) of nuclear wastes appeared within so-called "Cher- nobyl Exclusion Zone" (CEZ). At present there are not enough storage facilities in the Ukraine for safe disposal of nuclear wastes and hazardous chemical wastes. The urgent problem now is safe isolation of these dangerous wastes. According to the developed state program of radioactive waste management, the construction of a na- tional storage facility of nuclear wastes is planned. It is also possible to create regional storage facilities for hazardous chemical wastes. The region of our exploration cov- ers the eastern part of the Korosten Plutone and its slope, reaching the CNPP. 3D Space-Time Surface Imaging of Geophysical Fields. There are only three direct meth- ods of stress field reconstruction in present practice, namely the field investigations based on the large-scale fracturing tests, petrotectonic and optical polarization meth- ods. Unfortunately, all these methods are extremely laborious and need the regular field tests, which is difficult to conduct in the areas of anisotropic rock outcrops. A compilation of magnetic and gravity data covering the CNPP area was carried out as a prelude to an interpretation study. More than thirty map products were generated from magnetic, gravity and geodesy data to prepare the 3D Space-Time Surface Images (3D STSI). Multi-layer topography and geophysic surfaces included: total magnetic intensity, isostatically-corrected Bouguer gravity, aspect and slope, first and second derivatives, vertical and horizontal curvature, histogram characteristics and space cor- relation coefficients between the gradient fields. Many maps shows the first and sec- ond derivatives of the potential fields, with the results of lineament (edge) structure detection superimposed. The lineament or edges of the potential fields are located from maximal gradient in many directions

  2. Validation and application of help code used for design and review of cover of low and intermediate level radioactive waste disposal in near-surface facilities

    International Nuclear Information System (INIS)

    Fan Zhiwen; Gu Cunli; Zhang Jinsheng; Liu Xiuzhen

    1996-01-01

    The authors describes validation and application of HELP code used by the United States Environmental Protective Agency for design and review of cover of low and intermediate level radioactive waste disposal in near-surface facilities. The HELP code was validated using data of field aerated moisture movement test by China Institute for Radiation Protection. The results show that simulation of HELP code is reasonable. Effects of surface layer thickness and surface treatment on moisture distribution in a cover was simulated with HELP code in the conditions of south-west China. The simulation results demonstrated that surface plantation of a cover plays very important role in moisture distribution in the cover. Special attention should be paid in cover design. In humid area, radioactive waste disposal safety should take full consideration with functions of chemical barrier. It was recommended that engineering economy should be added in future cover research so as to achieve optimization of cover design

  3. Review to give the public clear information on near surface disposal project of low-level radioactive wastes generated from research, industrial and medical facilities

    International Nuclear Information System (INIS)

    Shobu, Nobuhiro; Amazawa, Hiroya; Koibuchi, Hiroto; Nakata, Hisakazu; Kato, Masatoshi; Takao, Tomoe; Terashima, Daisuke; Tanaka, Yoshie; Shirasu, Hisanori

    2013-12-01

    Japan Atomic Energy Agency (hereafter abbreviated as “JAEA”) has promoted near surface disposal project for low-level radioactive wastes generated from research, industrial and medical facilities after receiving project approval from the government in November 2009. JAEA has carried out public information about low-level radioactive wastes disposal project on the web site. When some town meetings are held toward mutual understanding with the public, more detailed and clear explanations for safety management of near surface disposal are needed especially. Therefore, the information provision method to make the public understand should be reviewed. Moreover, a web-based survey should be carried out in order to get a sense of what the public knows, what it values and where it stands on nuclear energy and radiation issues, because the social environment surrounding nuclear energy and radiation issues has drastically changed as a result of the accident at the Fukushima Daiichi Nuclear Power Station on March 11, 2011. This review clarified the points to keep in mind about public information on near surface disposal project for low-level radioactive wastes generated from research, industrial and medical facilities, and that public awareness and understanding toward nuclear energy and radiation was changed before and after the accident at Fukushima Daiichi Nuclear Power Plant. (author)

  4. Effects of dams in river networks on fish assemblages in non-impoundment sections of rivers in Michigan and Wisconsin, USA

    Science.gov (United States)

    Stewart, Jana S.; Lizhu Wang,; Infante, Dana M.; Lyons, John D.; Arthur Cooper,

    2011-01-01

    Regional assessment of cumulative impacts of dams on riverine fish assemblages provides resource managers essential information for dam operation, potential dam removal, river health assessment and overall ecosystem management. Such an assessment is challenging because characteristics of fish assemblages are not only affected by dams, but also influenced by natural variation and human-induced modification (in addition to dams) in thermal and flow regimes, physicochemical habitats and biological assemblages. This study evaluated the impacts of dams on river fish assemblages in the non-impoundment sections of rivers in the states of Michigan and Wisconsin using multiple fish assemblage indicators and multiple approaches to distinguish the influences of dams from those of other natural and human-induced factors. We found that environmental factors that influence fish assemblages in addition to dams should be incorporated when evaluating regional effects of dams on fish assemblages. Without considering such co-influential factors, the evaluation is inadequate and potentially misleading. The role of dams alone in determining fish assemblages at a regional spatial scale is relatively small (explained less than 20% of variance) compared with the other environmental factors, such as river size, flow and thermal regimes and land uses jointly. However, our results do demonstrate that downstream and upstream dams can substantially modify fish assemblages in the non-impoundment sections of rivers. After excluding river size and land-use influences, our results clearly demonstrate that dams have significant impacts on fish biotic-integrity and habitat-and-social-preference indicators. The influences of the upstream dams, downstream dams, distance to dams, and dam density differ among the fish indicators, which have different implications for maintaining river biotic integrity, protecting biodiversity and managing fisheries.

  5. Flammable gas tank waste level reconciliation tank 241-SX-105

    International Nuclear Information System (INIS)

    Brevick, C.H.; Gaddie, L.A.

    1997-01-01

    Fluor Daniel Northwest was authorized to address flammable gas issues by reconciling the unexplained surface level increases in Tank 241-SX-105 (SX-105, typical). The trapped gas evaluation document states that Tank SX-105 exceeds the 25% of the lower flammable limit criterion, based on a surface level rise evaluation. The Waste Storage Tank Status and Leak Detection Criteria document, commonly referred to as the Welty Report is the basis for this letter report. The Welty Report is also a part of the trapped gas evaluation document criteria. The Welty Report contains various tank information, including: physical information, status, levels, and dry wells. The unexplained waste level rises were attributed to the production and retention of gas in the column of waste corresponding to the unaccounted for surface level rise. From 1973 through 1980, the Welty Report tracked Tank SX-105 transfers and reported a net cumulative change of 20.75 in. This surface level increase is from an unknown source or is unaccounted for. Duke Engineering and Services Hanford and Lockheed Martin Hanford Corporation are interested in determining the validity of unexplained surface level changes reported in the Welty Report based upon other corroborative sources of data. The purpose of this letter report is to assemble detailed surface level and waste addition data from daily tank records, logbooks, and other corroborative data that indicate surface levels, and to reconcile the cumulative unaccounted for surface level changes as shown in the Welty Report from 1973 through 1980. Tank SX-105 initially received waste from REDOX starting the second quarter of 1955. After June 1975, the tank primarily received processed waste (slurry) from the 242-S Evaporator/Crystallizer and transferred supernate waste to Tanks S-102 and SX-102. The Welty Report shows a cumulative change of 20.75 in. from June 1973 through December 1980

  6. Egg shell waste as heterogeneous nanocatalyst for biodiesel production: Optimized by response surface methodology.

    Science.gov (United States)

    Pandit, Priti R; Fulekar, M H

    2017-08-01

    Worldwide consumption of hen eggs results in availability of large amount of discarded egg waste particularly egg shells. In the present study, the waste shells were utilized for the synthesis of highly active heterogeneous calcium oxide (CaO) nanocatalyst to transesterify dry biomass into methyl esters (biodiesel). The CaO nanocatalyst was synthesied by calcination-hydration-dehydration technique and fully characterized by infrared spectroscopy, X-ray powder diffraction (XRD), scanning electron microscope (SEM), transmission electron microscope (TEM), brunauer-emmett-teller (BET) elemental and thermogravimetric analysis. TEM image showed that the nano catalyst had spherical shape with average particle size of 75 nm. BET analysis indicated that the catalyst specific surface area was 16.4 m 2  g -1 with average pore diameter of 5.07 nm. The effect of nano CaO catalyst was investigated by direct transesterification of dry biomass into biodiesel along with other reaction parameters such as catalyst ratio, reaction time and stirring rate. The impact of the transesterification reaction parameters and microalgal biodiesel yield were analyzed by response surface methodology based on a full factorial, central composite design. The significance of the predicted mode was verified and 86.41% microalgal biodiesel yield was reported at optimal parameter conditions 1.7% (w/w), catalyst ratio, 3.6 h reaction time and stirring rate of 140.6 rpm. The biodiesel conversion was determined by 1 H nuclear magnetic resonance spectroscopy (NMR). The fuel properties of prepared biodiesel were found to be highly comply with the biodiesel standard ASTMD6751 and EN14214. Copyright © 2017 Elsevier Ltd. All rights reserved.

  7. Low-level radioactive wastes

    International Nuclear Information System (INIS)

    Garbay, H.; Chapuis, A.M.

    1988-01-01

    During dismantling operations of nuclear facilities radioctive and non radioactive wastes are produced. The distinction between both kinds of wastes is not easy. In each dismantling operation special care and rules are defined for the separation of wastes. Each case must be separately studied. The volume and the surface activites are analyzed. Part of the wastes had been disposed in a public environment. The regulations, the international recommendations, thetheoretical and experimental investigations in this field are presented. A regulation principle and examples of radioactivity limits, on the basis of international recommendations, are provided. Those limits are calculated from individual radiation dose that may reach human beings [fr

  8. Charging for waste motivates generators to optimize waste control at the source

    International Nuclear Information System (INIS)

    Berry, J.B.; Homan, F.J.

    1988-01-01

    The Department of Energy (DOE) has recognized the need for waste management that incorporates improved waste-handling techniques and more stringent regulatory requirements to prevent future liabilities such as Superfund sites. DOE-Oak Ridge Operations (DOE-ORO) has recognized that an effective waste management program focuses on control at the source and that the burden for responsible waste management can be placed on generators by charging for waste management costs. The principle of including the waste management costs in the total cost of the product, even when the product is research and development, is being implemented at Oak Ridge National Laboratory (ORNL). Charging waste management costs to generators creates an incentive to optimize processes so that less waste is produced, and it provides a basis for determining the cost effectiveness of capital improvements so that the mature phase of waste management can be attained. Improving waste management practices requires a long-range commitment and consistent administration. Making this commitment and providing adequate funding for proper waste disposal are most cost-effective measures than the alternative of paying for remedial actions after improper disposal. This paper summarizes a plan to charge waste generators, the administrative structure of the plan, a comparison between the rate structure and changes in waste disposal operations, and issues that have surfaced as the plan is implemented

  9. Charging generators for waste management costs

    International Nuclear Information System (INIS)

    Berry, J.B.; Homan, F.J.

    1988-01-01

    Implementation of a plan to charge waste management costs to the facility that generates such waste requires a long-term commitment and consistent administration. The benefit is that generators are provided the incentive to optimize waste management practices if the charges are appropriately applied. This paper summarizes (1) a plan to charge waste generators, (2) the administrative structure of the plan, (3) a comparison between the rate structure and changes in waste disposal operations, and (4) issues that have surfaced as the plan is implemented. 2 refs., 1 fig., 1 tab

  10. Nuclear waste: the political realities

    International Nuclear Information System (INIS)

    Arnott, D.

    1983-01-01

    The land dumping of nuclear waste has again come to the attention of anti-nuclear groups, environmentalists and the media, following the announcement of the proposed sites for intermediate-level nuclear waste at Billingham and Bedford. Opposition has already surfaced on a large scale, with public meetings in both areas and a revitalisation of the waste dumping network. This article explains some of the political realities in the nuclear debate, and suggests how we can tackle the issue of waste dumping, remembering that, even if the industry closes tomorrow, there are vast quantities of waste which must be safely and democratically dealt with. (author)

  11. Mass transfer of CO2 to groundwaters from a near-surface waste disposal site

    International Nuclear Information System (INIS)

    Caron, F.; Wilkinson, S.R.; Manni, G.; Torok, J.

    1995-01-01

    Gaseous 14 CO 2 originating from buried low-level radioactive wastes (LLRW) in a near-surface disposal site can be released to the environment via two major paths: gas-phase diffusion through soils to the atmosphere, and dissolution in groundwater, followed by aqueous migration. Aqueous migration would give the highest dose to an individual, especially if C-14 was converted to an organic form and ingested. Gaseous diffusion would give a lower dose, largely because of atmospheric dispersion and dilution. The objective of this study was to develop the capability to estimate which of the two paths will likely be dominant for typical near-surface disposal facilities. The main missing parameter for making this estimate was a mass-transfer coefficient (K L ) of 14 CO 2 to groundwaters, which was determined experimentally using a large sand box. The K L thus determined was approximately 10 to 20 times smaller than for an open liquid surface. This suggests that there is a potential resistance to mass transfer, probably caused by the capillary fringe. The value obtained was incorporated into a simple model of CO 2 transport around a typical near-surface disposal site. The model suggests that CO 2 transport via both gaseous release and aqueous migration paths are of similar magnitude for a repository located ∼2 m above the water table. (author). 11 refs., 2 tabs., 2 figs

  12. Application of autonomous robotics to surveillance of waste storage containers for radioactive surface contamination

    International Nuclear Information System (INIS)

    Sweeney, F.J.; Beckerman, M.; Butler, P.L.; Jones, J.P.; Reister, D.B.

    1991-01-01

    This paper describes a proof-of-principal demonstration performed with the HERMIES-III mobile robot to automate the inspection of waste storage drums for radioactive surface contamination and thereby reduce the human burden of operating a robot and worker exposure to potentially hazardous environments. Software and hardware for the demonstration were developed by a team consisting of Oak Ridge National Laboratory, and the Universities of Florida, Michigan, Tennessee, and Texas. Robot navigation, machine vision, manipulator control, parallel processing and human-machine interface techniques developed by the team were demonstrated utilizing advanced computer architectures. The demonstration consists of over 100,000 lines of computer code executing on nine computers

  13. Saltstone: cement-based waste form for disposal of Savannah River Plant low-level radioactive salt waste

    International Nuclear Information System (INIS)

    Langton, C.A.

    1984-01-01

    Defense waste processing at the Savannah River Plant will include decontamination and disposal of approximately 400 million liters of waste containing NaNO 3 , NaOH, Na 2 SO 4 , and NaNO 2 . After decontamination, the salt solution is classified as low-level waste. A cement-based waste form, saltstone, has been designed for disposal of Savannah River Plant low-level radioactive salt waste. Bulk properties of this material have been tailored with respect to salt leach rate, permeability, and compressive strength. Microstructure and mineralogy of leached and unleached specimens were characterized by SEM and x-ray diffraction analyses. The disposal system for the DWPF salt waste includes reconstitution of the crystallized salt as a solution containing 32 wt % solids. This solution will be decontaminated to remove 137 Cs and 90 Sr and then stabilized in a cement-based waste form. Laboratory and field tests indicate that this stabilization process greatly reduces the mobility of all of the waste constitutents in the surface and near-surface environment. Engineered trenches for subsurface burial of the saltstone have been designed to ensure compatibility between the waste form and the environment. The total disposal sytem, saltstone-trench-surrounding soil, has been designed to contain radionuclides, Cr, and Hg by both physical encapsulation and chemical fixation mechanisms. Physical encapsulation of the salts is the mechanism employed for controlling N and OH releases. In this way, final disposal of the SRP low-level waste can be achieved and the quality of the groundwater at the perimeter of the disposal site meets EPA drinking water standards

  14. 40 CFR 264.1085 - Standards: Surface impoundments.

    Science.gov (United States)

    2010-07-01

    ... materials of construction and designing the cover and closure devices shall include: Organic vapor... closure device in the closed position, as applicable. (B) To remove accumulated sludge or other residues... construction and designing the cover and closure devices shall include: Organic vapor permeability; the effects...

  15. 40 CFR 265.1086 - Standards: Surface impoundments.

    Science.gov (United States)

    2010-07-01

    ... materials of construction and designing the cover and closure devices shall include: Organic vapor... closure device in the closed position, as applicable. (B) To remove accumulated sludge or other residues... construction and designing the cover and closure devices shall include: Organic vapor permeability; the effects...

  16. Geochemical processes to mobilization of radionuclides from radioactive waste

    International Nuclear Information System (INIS)

    Bragea, M.

    2005-01-01

    On time to alteration the waste by natural weather in isolated area of waste dumps we can notice chemical, biochemical and geochemical modification. Disposability and flow of water are two of the most important parameter which affect the waste chemistry and migration of contamination from wastes. The water behaves like a mechanism of transport for cationic and anionic components and influenced solubility and salt migration from dump. The salt migration towards residue surfaces is affected by short distance between water and surface. The salts are redissolving and moving through the capillary towards the surface when precipitate. The reactions inside of waste are influenced by geochemical point of view mainly by the amount of sulfated salts and chloride, by the disposability of water, pH and by the chemical mineral heterogeneous of waste. Obviously, if the process of alteration by atmospherically agents and those effects about waste can be minimized we could minimize even chemical modification in order to form the salts. This paper examines the mechanism by which 226 Ra and U nat can enter in groundwater and those, which control its concentration. (author)

  17. Radioactive waste disposal process geological structure for the waste disposal

    International Nuclear Information System (INIS)

    Courtois, G.; Jaouen, C.

    1983-01-01

    The process described here consists to carry out the two phases of storage operation (intermediate and definitive) of radioactive wastes (especially the vitrified ones) in a geological dispositif (horizontal shafts) at an adequate deepness but suitable for a natural convection ventilation with fresh air from the land surface and moved only with the calorific heat released by the burried radioactive wastes when the radioactive decay has reached the adequate level, the shafts are totally and definitely occluded [fr

  18. Surface Water Modeling Using an EPA Computer Code for Tritiated Waste Water Discharge from the heavy Water Facility

    International Nuclear Information System (INIS)

    Chen, K.F.

    1998-06-01

    Tritium releases from the D-Area Heavy Water Facilities to the Savannah River have been analyzed. The U.S. EPA WASP5 computer code was used to simulate surface water transport for tritium releases from the D-Area Drum Wash, Rework, and DW facilities. The WASP5 model was qualified with the 1993 tritium measurements at U.S. Highway 301. At the maximum tritiated waste water concentrations, the calculated tritium concentration in the Savannah River at U.S. Highway 301 due to concurrent releases from D-Area Heavy Water Facilities varies from 5.9 to 18.0 pCi/ml as a function of the operation conditions of these facilities. The calculated concentration becomes the lowest when the batch releases method for the Drum Wash Waste Tanks is adopted

  19. Identifying sources of groundwater pollution using trace element signatures

    International Nuclear Information System (INIS)

    Olmez, I.; Hayes, M.J.

    1990-01-01

    A simple receptor modeling approach has been applied to groundwater pollution studies and has shown that marker trace elements can be used effectively in source identification and apportionment. Groundwater and source materials from one coal-fired and five oil-fired power plants, and one coal-tar deposit site have been analyzed by instrumental neutron activation analysis for more than 20 minor and trace elements. In one of the oil-fired power plants, trace element patterns indicated a leak from the hazardous waste surface impoundments owing to the failure of a hypolon liner. Also, the extent and spatial distribution of groundwater contamination have been determined in a coal-tar deposit site

  20. 30 CFR 817.89 - Disposal of noncoal mine wastes.

    Science.gov (United States)

    2010-07-01

    ... INTERIOR PERMANENT PROGRAM PERFORMANCE STANDARDS PERMANENT PROGRAM PERFORMANCE STANDARDS-UNDERGROUND MINING... surface runoff do not degrade surface or ground water, that fires are prevented, and that the area remains... underground water. Wastes shall be routinely compacted and covered to prevent combustion and wind-borne waste...

  1. Storage of radioactive waste

    International Nuclear Information System (INIS)

    Pittman, F.K.

    1974-01-01

    Four methods for managing radioactive waste in order to protect man from its potential hazards include: transmutation to convert radioisotopes in waste to stable isotopes; disposal in space; geological disposal; and surface storage in shielded, cooled, and monitored containers. A comparison of these methods shows geologic disposal in stable formations beneath landmasses appears to be the most feasible with today's technology. (U.S.)

  2. Trench ‘Bathtubbing’ and Surface Plutonium Contamination at a Legacy Radioactive Waste Site

    Science.gov (United States)

    2013-01-01

    Radioactive waste containing a few grams of plutonium (Pu) was disposed between 1960 and 1968 in trenches at the Little Forest Burial Ground (LFBG), near Sydney, Australia. A water sampling point installed in a former trench has enabled the radionuclide content of trench water and the response of the water level to rainfall to be studied. The trench water contains readily measurable Pu activity (∼12 Bq/L of 239+240Pu in 0.45 μm-filtered water), and there is an associated contamination of Pu in surface soils. The highest 239+240Pu soil activity was 829 Bq/kg in a shallow sample (0–1 cm depth) near the trench sampling point. Away from the trenches, the elevated concentrations of Pu in surface soils extend for tens of meters down-slope. The broader contamination may be partly attributable to dispersion events in the first decade after disposal, after which a layer of soil was added above the trenched area. Since this time, further Pu contamination has occurred near the trench-sampler within this added layer. The water level in the trench-sampler responds quickly to rainfall and intermittently reaches the surface, hence the Pu dispersion is attributed to saturation and overflow of the trenches during extreme rainfall events, referred to as the ‘bathtub’ effect. PMID:24256473

  3. Waste disposal

    International Nuclear Information System (INIS)

    2005-01-01

    Radioactive waste, as a unavoidable remnant from the use of radioactive substances and nuclear technology. It is potentially hazardous to health and must therefore be managed to protect humans and the environment. The main bulk of radioactive waste must be permanently disposed in engineered repositories. Appropriate safety standards for repository design and construction are required along with the development and implementation of appropriate technologies for the design, construction, operation and closure of the waste disposal systems. As backend of the fuel cycle, resolving the issue of waste disposal is often considered as a prerequisite to the (further) development of nuclear energy programmes. Waste disposal is therefore an essential part of the waste management strategy that contributes largely to build confidence and helps decision-making when appropriately managed. The International Atomic Energy Agency provides assistance to Member States to enable safe and secure disposal of RW related to the development of national RWM strategies, including planning and long-term project management, the organisation of international peer-reviews for research and demonstration programmes, the improvement of the long-term safety of existing Near Surface Disposal facilities including capacity extension, the selection of potential candidate sites for different waste types and disposal options, the characterisation of potential host formations for waste facilities and the conduct of preliminary safety assessment, the establishment and transfer of suitable technologies for the management of RW, the development of technological solutions for some specific waste, the building of confidence through training courses, scientific visits and fellowships, the provision of training, expertise, software or hardware, and laboratory equipment, and the assessment of waste management costs and the provision of advice on cost minimisation aspects

  4. Glass Ceramic Waste Forms for Combined CS+LN+TM Fission Products Waste Streams

    International Nuclear Information System (INIS)

    Crum, Jarrod V.; Turo, Laura A.; Riley, Brian J.; Tang, Ming; Kossoy, Anna; Sickafus, Kurt E.

    2010-01-01

    In this study, glass ceramics were explored as an alternative waste form for glass, the current baseline, to be used for immobilizing alkaline/alkaline earth + lanthanide (CS+LN) or CS+LN+transition metal (TM) fission-product waste streams generated by a uranium extraction (UREX+) aqueous separations type process. Results from past work on a glass waste form for the combined CS+LN waste streams showed that as waste loading increased, large fractions of crystalline phases precipitated upon slow cooling.(1) The crystalline phases had no noticeable impact on the waste form performance by the 7-day product consistency test (PCT). These results point towards the development of a glass ceramic waste form for treating CS+LN or CS+LN+TM combined waste streams. Three main benefits for exploring glass ceramics are: (1) Glass ceramics offer increased solubility of troublesome components in crystalline phases as compared to glass, leading to increased waste loading; (2) The crystalline network formed in the glass ceramic results in higher heat tolerance than glass; and (3) These glass ceramics are designed to be processed by the same melter technology as the current baseline glass waste form. It will only require adding controlled canister cooling for crystallization into a glass ceramic waste form. Highly annealed waste form (essentially crack free) with up to 50X lower surface area than a typical High-Level Waste (HLW) glass canister. Lower surface area translates directly into increased durability. This was the first full year of exploring glass ceramics for the Option 1 and 2 combined waste stream options. This work has shown that dramatic increases in waste loading are achievable by designing a glass ceramic waste form as an alternative to glass. Table S1 shows the upper limits for heat, waste loading (based on solubility), and the decay time needed before treatment can occur for glass and glass ceramic waste forms. The improvements are significant for both combined waste

  5. Glass Ceramic Waste Forms for Combined CS+LN+TM Fission Products Waste Streams

    Energy Technology Data Exchange (ETDEWEB)

    Crum, Jarrod V.; Turo, Laura A.; Riley, Brian J.; Tang, Ming; Kossoy, Anna; Sickafus, Kurt E.

    2010-09-23

    In this study, glass ceramics were explored as an alternative waste form for glass, the current baseline, to be used for immobilizing alkaline/alkaline earth + lanthanide (CS+LN) or CS+LN+transition metal (TM) fission-product waste streams generated by a uranium extraction (UREX+) aqueous separations type process. Results from past work on a glass waste form for the combined CS+LN waste streams showed that as waste loading increased, large fractions of crystalline phases precipitated upon slow cooling.[1] The crystalline phases had no noticeable impact on the waste form performance by the 7-day product consistency test (PCT). These results point towards the development of a glass ceramic waste form for treating CS+LN or CS+LN+TM combined waste streams. Three main benefits for exploring glass ceramics are: (1) Glass ceramics offer increased solubility of troublesome components in crystalline phases as compared to glass, leading to increased waste loading; (2) The crystalline network formed in the glass ceramic results in higher heat tolerance than glass; and (3) These glass ceramics are designed to be processed by the same melter technology as the current baseline glass waste form. It will only require adding controlled canister cooling for crystallization into a glass ceramic waste form. Highly annealed waste form (essentially crack free) with up to 50X lower surface area than a typical High-Level Waste (HLW) glass canister. Lower surface area translates directly into increased durability. This was the first full year of exploring glass ceramics for the Option 1 and 2 combined waste stream options. This work has shown that dramatic increases in waste loading are achievable by designing a glass ceramic waste form as an alternative to glass. Table S1 shows the upper limits for heat, waste loading (based on solubility), and the decay time needed before treatment can occur for glass and glass ceramic waste forms. The improvements are significant for both combined waste

  6. Decreased blood hepatitis B surface antibody levels linked to e-waste lead exposure in preschool children

    Energy Technology Data Exchange (ETDEWEB)

    Xu, Xijin [Laboratory of Environmental Medicine and Developmental Toxicology, and Guangdong Provincial Key Laboratory of Infectious Diseases, Shantou University Medical College, Shantou 515041, Guangdong (China); Department of Cell Biology and Genetics, Shantou University Medical College, Shantou 515041, Guangdong (China); Chen, Xiaojuan; Zhang, Jian [Laboratory of Environmental Medicine and Developmental Toxicology, and Guangdong Provincial Key Laboratory of Infectious Diseases, Shantou University Medical College, Shantou 515041, Guangdong (China); Guo, Pi [Department of Public Health, Shantou University Medical College, Shantou 515041, Guangdong (China); Fu, Tingzao; Dai, Yifeng [Laboratory of Environmental Medicine and Developmental Toxicology, and Guangdong Provincial Key Laboratory of Infectious Diseases, Shantou University Medical College, Shantou 515041, Guangdong (China); Lin, Stanley L. [Department of Pathophysiology and Key Immunopathology Laboratory of Guangdong Province, Shantou University Medical College, Shantou 515041, Guangdong (China); Huo, Xia, E-mail: xhuo@stu.edu.cn [Laboratory of Environmental Medicine and Developmental Toxicology, and Guangdong Provincial Key Laboratory of Infectious Diseases, Shantou University Medical College, Shantou 515041, Guangdong (China)

    2015-11-15

    Highlights: • Secondary exploratory analyses displayed a correlation of blood Pb to HBsAb levels. • Generalized linear mixed models were used to analyze two-phase data. • Children from an e-waste area had higher blood Pb levels and lower HBsAb titers. • Nearly 50% of Pb-exposed children fail to develop sufficient HBV immunity. • Different vaccination strategies are required for in e-waste areas. - Abstract: Lead (Pb) is a widespread environmental contaminant that can profoundly affect the immune system in vaccinated children. To explore the association between blood Pb and HBsAb levels in children chronically exposed to Pb, we measured hepatitis B surface antibody (HBsAb) titers, to reflect the immune response in the children of Guiyu, an electronic and electrical waste (e-waste) recycling area well known for environmental Pb contamination. We performed secondary exploratory analyses of blood Pb levels and plasma HBsAb titers in samples, taken in two phases between 2011 and 2012, from 590 children from Guiyu (exposed group) and Haojiang (reference group). Children living in the exposed area had higher blood Pb levels and lower HBsAb titers compared with children from the reference area. At each phase, generalized linear mixed models (GLMMs) showed that HBsAb titers were significantly negatively associated with child blood Pb levels. This work shows that a decreased immune response to hepatitis B vaccine and immune system might have potential harm to children with chronic Pb exposure. Importantly, nearly 50% of chronically exposed children failed to develop sufficient immunity to hepatitis in response to vaccination. Thus different vaccination strategies are needed for children living under conditions of chronic Pb exposure.

  7. Decreased blood hepatitis B surface antibody levels linked to e-waste lead exposure in preschool children

    International Nuclear Information System (INIS)

    Xu, Xijin; Chen, Xiaojuan; Zhang, Jian; Guo, Pi; Fu, Tingzao; Dai, Yifeng; Lin, Stanley L.; Huo, Xia

    2015-01-01

    Highlights: • Secondary exploratory analyses displayed a correlation of blood Pb to HBsAb levels. • Generalized linear mixed models were used to analyze two-phase data. • Children from an e-waste area had higher blood Pb levels and lower HBsAb titers. • Nearly 50% of Pb-exposed children fail to develop sufficient HBV immunity. • Different vaccination strategies are required for in e-waste areas. - Abstract: Lead (Pb) is a widespread environmental contaminant that can profoundly affect the immune system in vaccinated children. To explore the association between blood Pb and HBsAb levels in children chronically exposed to Pb, we measured hepatitis B surface antibody (HBsAb) titers, to reflect the immune response in the children of Guiyu, an electronic and electrical waste (e-waste) recycling area well known for environmental Pb contamination. We performed secondary exploratory analyses of blood Pb levels and plasma HBsAb titers in samples, taken in two phases between 2011 and 2012, from 590 children from Guiyu (exposed group) and Haojiang (reference group). Children living in the exposed area had higher blood Pb levels and lower HBsAb titers compared with children from the reference area. At each phase, generalized linear mixed models (GLMMs) showed that HBsAb titers were significantly negatively associated with child blood Pb levels. This work shows that a decreased immune response to hepatitis B vaccine and immune system might have potential harm to children with chronic Pb exposure. Importantly, nearly 50% of chronically exposed children failed to develop sufficient immunity to hepatitis in response to vaccination. Thus different vaccination strategies are needed for children living under conditions of chronic Pb exposure

  8. National briefing summaries: Nuclear fuel cycle and waste management

    International Nuclear Information System (INIS)

    Schneider, K.J.; Harmon, K.M.; Lakey, L.T.; Silviera, D.J.; Leigh, I.W.

    1987-09-01

    This report is a compilation of publicly-available information concerning the nuclear fuel cycle and radioactive waste management strategies and programs of 20 nations and three international agencies that have publicized their activities in this field. The information in this document is compiled to provide summary information on radioactive waste management activities in other countries. This document indicates what is occurring in other countries with regard to strategies, activities, and facilities. This document first presents a short overview of the activities and trends for managing low- to high-level radioactive waste and spent fuel by the entities covered in this review. This is followed by information for each country for nuclear power; fuel cycle and waste management strategy/policy; highlights and major milestones; institutional considerations/organizations; nuclear fuel production; fuel recycle; spent fuel storage and transport; waste conditioning, storage and transport; surface and near-surface waste disposal; geologic waste disposal; management of uranium mine and mill wastes; decommissioning; international; and references. 406 refs

  9. Method of processing liquid waste containing fission product

    International Nuclear Information System (INIS)

    Funabashi, Kiyomi; Kawamura, Fumio; Matsuda, Masami; Komori, Itaru; Miura, Eiichi.

    1988-01-01

    Purpose: To prepare solidification products of low surface dose by removing cesium which is main radioactive nuclides from re-processing plants. Method: Liquid wastes containing a great amount of fission products are generated accompanying the reprocessing for spent nuclear fuels. After pH adjustment, the liquid wastes are sent to a concentrator to concentrate the dissolved ingredients. The concentrated liquid wastes are pumped to an adsorption tower in which radioactive cesium contributing much to the surface dose is removed. Then, the liquid wastes are sent by way of a surge tank to a mixing tank, in which they are mixed under stirring with solidifying agents such as cements. Then, the mixture is filled in a drum-can and solidified. According to this invention, since radioactive cesium is removed before solidification, it is possible to prepare solidification products at low surface dose and facilitate the handling of the solidification products. (Horiuchi, T.)

  10. Waste gas combustion in a Hanford radioactive waste tank

    International Nuclear Information System (INIS)

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

    1994-01-01

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

  11. Permanent isolation surface barrier: Functional performance

    International Nuclear Information System (INIS)

    Wing, N.R.

    1993-10-01

    This document presents the functional performance parameters for permanent isolation surface barriers. Permanent isolation surface barriers have been proposed for use at the Hanford Site (and elsewhere) to isolate and dispose of certain types of waste in place. Much of the waste that would be disposed of using in-place isolation techniques is located in subsurface structures, such as solid waste burial grounds, tanks, vaults, and cribs. Unless protected in some way, the wastes could be transported to the accessible environment via transport pathways, such as water infiltration, biointrusion, wind and water erosion, human interference, and/or gaseous release

  12. Method of storing radioactive wastes

    International Nuclear Information System (INIS)

    Adachi, Toshio; Hiratake, Susumu.

    1980-01-01

    Purpose: To reduce the radiation doses externally irradiated from treated radioactive waste and also reduce the separation of radioactive nuclide due to external environmental factors such as air, water or the like. Method: Radioactive waste adhered with radioactive nuclide to solid material is molten to mix and submerge the radioactive nuclide adhered to the surface of the solid material into molten material. Then, the radioactive nuclide thus mixed is solidified to store the waste in solidified state. (Aizawa, K.)

  13. 77 FR 69769 - Solid Waste Rail Transfer Facilities

    Science.gov (United States)

    2012-11-21

    ...] Solid Waste Rail Transfer Facilities AGENCY: Surface Transportation Board, DOT. ACTION: Final rules. SUMMARY: These final rules govern land-use-exemption permits for solid waste rail transfer facilities. The... Transportation Board over solid waste rail transfer facilities. The Act also added three new statutory provisions...

  14. Revised Earthquake Catalog and Relocated Hypocenters Near Fluid Injection Wells and the Waste Isolation Pilot Plant (WIPP) in Southeastern New Mexico

    Science.gov (United States)

    Edel, S.; Bilek, S. L.; Garcia, K.

    2014-12-01

    Induced seismicity is a class of crustal earthquakes resulting from human activities such as surface and underground mining, impoundment of reservoirs, withdrawal of fluids and gas from the subsurface, and injection of fluids into underground cavities. Within the Permian basin in southeastern New Mexico lies an active area of oil and gas production, as well as the Waste Isolation Pilot Plant (WIPP), a geologic nuclear waste repository located just east of Carlsbad, NM. Small magnitude earthquakes have been recognized in the area for many years, recorded by a network of short period vertical component seismometers operated by New Mexico Tech. However, for robust comparisons between the seismicity patterns and the injection well locations and rates, improved locations and a more complete catalog over time are necessary. We present results of earthquake relocations for this area by using data from the 3-component broadband EarthScope Flexible Array SIEDCAR experiment that operated in the area between 2008-2011. Relocated event locations tighten into a small cluster of ~38 km2, approximately 10 km from the nearest injection wells. The majority of events occurred at 10-12 km depth, given depth residuals of 1.7-3.6 km. We also present a newly developed more complete catalog of events from this area by using a waveform cross-correlation algorithm and the relocated events as templates. This allows us to detect smaller magnitude events that were previously undetected with the short period network data. The updated earthquake catalog is compared with geologic maps and cross sections to identify possible fault locations. The catalog is also compared with available well data on fluid injection and production. Our preliminary results suggest no obvious connection between seismic moment release, fluid injection, or production given the available monthly industry data. We do see evidence in the geologic and well data of previously unidentified faults in the area.

  15. Effect on localized waste-container failure on radionuclide transport from an underground nuclear waste vault

    International Nuclear Information System (INIS)

    Cheung, S.C.H.; Chan, T.

    1983-07-01

    In the geological disposal of nuclear fuel waste, one option is to emplace the waste container in a borehole drilled into the floor of the underground vault. In the borehole, the waste container is surrounded by a compacted soil material known as the buffer. A finite-element simulation has been performed to study the effect of localized partial failure of the waste container on the steady-state radionuclide transport by diffusion from the container through the buffer to the surrounding rock and/or backfill. In this study, the radionuclide concentration at the buffer-backfill interface is assumed to be zero. Two cases are considered at the interface between the buffer and the rock. In case 1, a no-flux boundary condition is used to simulate intact rock. In case 2, a constant radionuclide concentration condition is used to simulate fractured rock with groundwater flow. The results show that the effect of localized partial failure of the waste container on the total flux is dependent on the boundary condition at the buffer-rock interface. For the intact rock condition, the total flux is mainly dependent on the location of the failure. The total flux increases as the location changes from the bottom to the top of the emplaced waste container. For a given localized failure of the waste container, the total flux remains unaffected by the area of failed surface below the top of the failure. For fractured rock, the total flux is directly proportional to the failed surface area of the waste container regardless of the failure location

  16. Development of nuclear waste concrete drum

    International Nuclear Information System (INIS)

    Wen Yinghui

    1995-06-01

    The raw materials selection and the properties for nuclear waste concrete drum, the formula and properties of the concrete, the specification and technical quality requirement of the drum were described. The manufacture essentials and technology, the experiments and checks as well as the effective quality control and quality assurance carried out in the course of production were presented. The developed nuclear waste drum has a simple structure, easily available raw materials and rational formula for concrete. The compressive strength of the drum is more than 70 MPa, the tensile strength is more than 5 MPa, the nitrogen permeability is (2.16∼3.6) x 10 -18 m 2 . The error of the drum in dimensions is +-2 mm. The external surface of the drum is smooth. The drum accords with China standards in the sandy surface, void and crack. The results shows China has the ability to develop and manufacture nuclear waste concrete container and lays the foundation for standardization and series of the nuclear waste container for packing and transporting nuclear wastes in China. (5 figs., 10 tabs.)

  17. Assessment of soil and groundwater contamination by potentially toxic and trace elements in an impounded vehicle scrapyard: Case study: Ribeirão Pires, SP, Brazil

    International Nuclear Information System (INIS)

    Lange, Camila Neves

    2018-01-01

    Impounded vehicle scrapyard (IVS) overcrowding is currently a subject of concern in Brazilian scenario. The aim of this study was to assess the total levels of potentially toxic elements (PTEs) and trace elements (TE) in soil and groundwater in an IVS located in the city of Ribeirão Pires. In order to achieve this objective, topsoil, three soil cores and groundwater of three monitoring wells were analyzed. It was verified that the area is mainly affected by three factors: (1) a landfill layer with construction waste; (2) an oily residue from past industrial activities in the area; (3) vehicles parked on topsoil. For the evaluation of the results, statistical techniques, such as multivariate analysis, calculation of pollution, ecological and human health risk index were used. Mass fractions of all PTEs, except Co, Cu, Mo and Zn, were higher than reference values. Hot spots were observed for most elements suggesting vehicular source. The Geoaccumulation Index showed minimal to moderate pollution in soil for most elements, except for As and Ba, which showed higher accumulation than other elements. The enrichment factor pointed to a significant enrichment of As and Pb. Arsenic content in soil may pose a moderate to high potential ecological risk. The results of PTEs and as statistical approaches indicated that As, Ce, Co, Cu, Mn, Nb, Ni, Pb and Zn are mainly from anthropogenic sources. The content of most PTEs in topsoil does not pose a potential human health risk, except Cr content. Groundwater levels for most PTEs were below the drinking water recommendation limits, except Mn and Fe content. (author)

  18. Safety of radioactive waste management in France

    International Nuclear Information System (INIS)

    Raimbault, P.

    2002-01-01

    Radioactive waste produced in France vary considerably by their activity level, their half lives, their volume or even their nature. In order to manage them safely, the treatment and final disposal solution must be adapted to the type of waste considered by setting up specific waste management channels. A strong principle in France is that it is the responsibility of the nuclear operators as waste producers to dispose of their waste or have them disposed of in a suitable manner. The competent authorities regulate and control the radioactive waste management activities. At present, only short-lived low and intermediate level waste have a definitive solution, the surface repository, where adequate waste packages are disposed of in concrete structures. Other types of radioactive waste are in interim storage facilities at the production sites. For very low level waste coming mainly from dismantling of nuclear facilities a dedicated repository is planned to be built in the coming years. Dedicated repositories are also planned for radiferous, tritiated and graphite waste. As for high level waste and long-lived waste coming mainly from reprocessing of spent nuclear fuel the disposal options are being sought along the lines specified by law 91-1381 concerning research on radioactive waste management, passed on December 30, 1991: research of solutions to partition and transmute long-lived radionuclides in the waste; studies of retrievable and non retrievable disposal in deep geological layers with the help of underground laboratories; studies of processes for conditioning and long term surface storage of these waste. In 2006, the French Parliament will assess the results of the research conducted by ANDRA relative to deep geological disposal as well as the work conducted by CEA in the two other areas of research and, if this research is conclusive, pass a law defining the final disposal option. (author)

  19. 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

  20. Very low level waste disposal in France. A key tool for the management for decommissioning wastes in France

    Energy Technology Data Exchange (ETDEWEB)

    Duetzer, Michel [Andra - Agence Nationale pour la Gestion des Dechets Radioactives, Chatenay-Malabry (France). Direction Industrielle

    2015-07-01

    At the end of the 90{sup th}, France had to deal with the emerging issue of the management of wastes resulting from decommissioning operations of nuclear facilities. A specific regulation was issued and Andra, the French National Radioactive Waste Management Agency, developed a dedicated near surface disposal facility to accommodate very low level radioactive wastes. After more than 10 years of operation, this facility demonstrated it can provide efficient and flexible solutions for the management of decomissioning wastes.

  1. Method of solidifying radioactive waste by plastics

    International Nuclear Information System (INIS)

    Yasumura, Keijiro; Tomita, Toshihide.

    1976-01-01

    Purpose: To prevent leakage of radioactivity by providing corrosion-resistant layer on the inner surface of a waste container for radioactive waste. Constitution: The inner periphery and bottom of a drum can is lined with an non-flammable cloth of such material as asbestos. This drum is filled with a radioactive waste in the form of powder or pellets. Then, a mixture of a liquid plastic monomer and a polymerization starting agent is poured at a normal temperature, and the surface is covered with a non-flammable cloth. The plastic monomer and radioactive waste are permitted to impregnate the non-flammable cloth and are solidified there. Thus, even if the drum can is corroded at the sea bottom after disposal it in the ocean, it is possible to prevent the waste from permeating into the outer sea water because of the presence of the plastic layer on the inside. Styrene is used as the monomer. (Aizawa, K.)

  2. A case study on the safety assessment for groundwater pathway in a near-surface radioactive waste disposal facility

    International Nuclear Information System (INIS)

    Park, Joo Wan; Chang, Keun Moo; Kim, Chang Lak

    2002-01-01

    A safety assessment is carried out for the near-surface radioactive waste disposal in the reference engineered vault facility. The analysis is mainly divided into two parts. One deals with the release and transport of radionuclide in the vault and unsaturated zone. The other deals with the transport of radionuclide in the vault and unsaturated zone. The other deals with the transport of radionuclide in the saturated zone and radiological impacts to a human group under well drinking water scenario. The parameters for source-term, geosphere and biosphere models are mainly obtained from the site specific data. The results show that the annual effective doses are dominated by long lived, mobile radionuclides and their associated daughters. And it is found that the total effective dose for drinking water is far below the general criteria of regulatory limit for radioactive waste disposal facility

  3. Public debate on radioactive wastes

    International Nuclear Information System (INIS)

    2005-01-01

    The definition and implementation of safe and perennial solutions for the management of radioactive wastes is a necessity from the point of view of both the nuclear industrialists and the public authorities, but also of the overall French citizens. For the low- or medium-level or short living radioactive wastes, some solutions have been defined are are already implemented. On the other hand, no decision has been taken so far for the long living medium to high-level radioactive wastes. Researches are in progress in this domain according to 3 ways of research defined by the law from December 30, 1991: separation-transmutation, disposal in deep underground, and long duration surface or sub-surface storage. This paper presents in a digest way, the principle, the results obtained so far, and the perspectives of each of the three solutions under study. (J.S.)

  4. Recovery of Zircaloy-4 waste

    International Nuclear Information System (INIS)

    Flores, A.V; Banchik, A.D; Reale, H.F

    2002-01-01

    Different types of waste with different degrees of contamination are generated by the production of Zry-4 products. Because of this alloy's added value the wastes are routinely recycled internationally. To date the local manufacturer only recovered the solid wastes by refusion, while the shavings were stored. A process for recovering Zry-4 shavings is studied using the existing plant and local industry equipment. The type of contamination produced by the shavings was defined and then the capacity of the ultrasound vibrating method was analyzed as a degreasing for the removal of the materials adhering to the surface of the shavings. The results show that the shavings are contaminated with lubricant film, zirconium oxide, iron oxide and different particles sticking to the surface and that the ultrasound vibration method can be used for their removal (CW)

  5. Preparation and characterization of high-surface-area activated carbon fibers from silkworm cocoon waste for congo red adsorption

    International Nuclear Information System (INIS)

    Li, Jia; Ng, Dickon H.L.; Song, Peng; Kong, Chao; Song, Yi; Yang, Ping

    2015-01-01

    Herein, we report the preparation of activated carbon fibers from silkworm cocoon waste via the combination of (NH 4 ) 2 HPO 4 -pretreatment and KOH activation. The morphology, phase structure and surface chemistry constitute of the obtained ACFs were characterized by X-ray diffraction, IR spectroscopy, Micro Raman spectroscopy, X-ray photoelectron spectroscopy, scanning electron microscopy, thermal analysis and N 2 adsorption–desorption isotherm. The effects of various factors such as the concentration of (NH 4 ) 2 HPO 4 and the activation time of KOH were also evaluated. These results demonstrated that the synthesized ACFs retained the fibrous morphology of silkworm cocoon waste, and exhibited highly defective graphite layer structure. A large amount of surface oxygen-containing functional groups were found on the ACFs surface. The obtained samples exhibited high BET surface areas ranging from 1153 to 2797 m 2  g −1 , total pore volumes of 0.64–1.74 cm 3  g −1 with micropore volume fractions between 75.2 and 93.6%. In addition, we also evaluated the congo red (CR) adsorption performance of the obtained ACFs. The CR adsorption fitted well to the pseudo-second-order kinetic model. Adsorption isotherm data indicated that the adsorption of CR onto ACFs was monolayer adsorption which followed well the Langmuir isotherm model. The maximum adsorption capacity of CR was 512 g kg −1 . The mechanism of the adsorption process was also described from the intraparticle diffusion model. - Highlights: • A new biomass fibroin precursor for activated carbon fibers (ACFs) was proposed. • High specific surface area (2797 m 2  g −1 ) and total pore volume (1.74 cm 3  g −1 ) were obtained. • The original fibrous structure of raw silkworm cocoons was retained in the ACF product. • Congo red maximum monolayer adsorption capacity of our ACF product was up to 1100 g kg −1

  6. Charging generators for waste management costs

    International Nuclear Information System (INIS)

    Berry, J.B.; Homan, F.J.

    1988-01-01

    The Department of Energy (DOE) has recognized the need for waste management that incorporates improved waste-handling techniques and more stringent regulatory requirements to prevent future liabilities such as Superfund sites. DOE-Oak Ridge Operations (DOE-ORO) has recognized that an effective waste management program focuses on control at the source and that the burden for responsible waste management can be placed on generators by charging for waste management costs. The principle of including the waste management costs in the total cost of the product, even when the product is research and development, is being implemented at Oak Ridge National Laboratory (ORNL). This paper summarizes a plan to charge waste generators, the administrative structure of the plan, a comparison between the rate structure and changes in waste disposal operations, and issues that have surfaced as the plan is implemented

  7. [Microbiological Aspects of Radioactive Waste Storage].

    Science.gov (United States)

    Safonov, A V; Gorbunova, O A; German, K E; Zakharova, E V; Tregubova, V E; Ershov, B G; Nazina, T N

    2015-01-01

    The article gives information about the microorganisms inhabiting in surface storages of solid radioactive waste and deep disposal sites of liquid radioactive waste. It was shown that intensification of microbial processes can lead to significant changes in the chemical composition and physical state of the radioactive waste. It was concluded that the biogeochemical processes can have both a positive effect on the safety of radioactive waste storages (immobilization of RW macrocomponents, a decreased migration ability of radionuclides) and a negative one (biogenic gas production in subterranean formations and destruction of cement matrix).

  8. Environmental restoration waste materials co-disposal

    International Nuclear Information System (INIS)

    Phillips, S.J.; Alexander, R.G.; England, J.L.; Kirdendall, J.R.; Raney, E.A.; Stewart, W.E.; Dagan, E.B.; Holt, R.G.

    1993-09-01

    Co-disposal of radioactive and hazardous waste is a highly efficient and cost-saving technology. The technology used for final treatment of soil-washing size fractionization operations is being demonstrated on simulated waste. Treated material (wasterock) is used to stabilize and isolate retired underground waste disposal structures or is used to construct landfills or equivalent surface or subsurface structures. Prototype equipment is under development as well as undergoing standardized testing protocols to prequalify treated waste materials. Polymer and hydraulic cement solidification agents are currently used for geotechnical demonstration activities

  9. Radioactive waste processing device

    International Nuclear Information System (INIS)

    Seki, Shuji.

    1992-01-01

    Liquid wastes are supplied to a ceramic filter to conduct filtration. In this case, a device for adding a powdery inorganic ion exchanger is disposed to the upstream of the ceramic filter. When the powdery inorganic ion exchanger is charged to the addition device, it is precoated to the surface of the ceramic filter, to conduct separation of suspended matters and separation of ionic nuclides simultaneously. Liquid wastes returned to a collecting tank are condensed while being circulated between the ceramic filter and the tank and then contained in a condensation liquid waste tank. With such a constitution, both of radioactive nuclides accompanied by suspended matters in the radioactive liquid wastes and ionic nuclides can be captured efficiently. (T.M.)

  10. The Danish inventory of radioactive waste and the required repository type

    Energy Technology Data Exchange (ETDEWEB)

    Schmidt, Gerhard [Oeko-Institut e.V., Darmstadt (Germany). Div. on Nuclear Engineering and Facility Safety

    2014-11-15

    Denmark has a relatively small inventory of radioactive wastes. As Denmark never built and operated nuclear power plants, the wastes resulted only from various research activities. In order to manage those wastes, the Danish Government has ordered to describe those wastes and the available management options. Based on vague criteria, most of the waste types were termed as ''short-lived'' and as suitable for a surface-near disposal facility. The Government then ordered the Geological survey organization of Denmark, GEUS, to scan Denmark for suitable locations. ''Suitable'' depth was defined as 0 to 100 m below ground. Neither were isolation properties or other requirements for geological layers defined nor were those criteria agreed in a broader sense (with experts, with the public). GEUS identified a number of potentially suitable locations and selected six of those as the most promising. In this paper the basic decision of preferring surface-near disposal for most of the waste types is analysed. As a central criterion for the suitability of the waste types for surface-near disposal is defined that those waste types decay within 300 years to below today's clearance levels. The results show, that none of the Danish types of waste meets this simple requirement. All are above that criterion, most of them by several orders of magnitude and over very much longer times such as 100.000 years or even longer. The basic assumption of the performed site selection procedure, to search for near-surface locations for short-lived wastes, so proves to be invalid. The whole process should be re-done on the basis that the long-term isolation of those wastes in impermeable layers has to be guaranteed. The suitability criteria should focus on the long-term isolation of all wastes and should be agreed in advance.

  11. Permanent isolation surface barrier development plan

    International Nuclear Information System (INIS)

    Wing, N.R.

    1994-01-01

    The exhumation and treatment of wastes may not always be the preferred alternative in the remediation of a waste site. In-place disposal alternatives, under certain circumstances, may be the most desirable alternatives to use in the protection of human health and the environment. The implementation of an in-place disposal alternative will likely require some type of protective covering that will provide long-term isolation of the wastes from the accessible environment. Even if the wastes are exhumed and treated, a long-term barrier may still be needed to adequately dispose of the treated wastes or any remaining waste residuals. Currently, no open-quotes provenclose quotes long-term barrier is available. The Hanford Site Permanent Isolation Surface Barrier Development Program (BDP) was organized to develop the technology needed to provide a long-term surface barrier capability for the Hanford Site. The permanent isolation barrier technology also could be used at other sites. Permanent isolation barriers use engineered layers of natural materials to create an integrated structure with redundant protective features. Drawings of conceptual permanent isolation surface barriers are shown. The natural construction materials (e.g., fine soil, sand, gravel, riprap, asphalt) have been selected to optimize barrier performance and longevity. The objective of current designs is to use natural materials to develop a maintenance-free permanent isolation surface barrier that isolates wastes for a minimum of 1,000 years by limiting water drainage to near-zero amounts; reducing the likelihood of plant, animal, and human intrusion; controlling the exhalation of noxious gases; and minimizing erosion-related problems

  12. Permanent isolation surface barrier development plan

    Energy Technology Data Exchange (ETDEWEB)

    Wing, N.R.

    1994-01-01

    The exhumation and treatment of wastes may not always be the preferred alternative in the remediation of a waste site. In-place disposal alternatives, under certain circumstances, may be the most desirable alternatives to use in the protection of human health and the environment. The implementation of an in-place disposal alternative will likely require some type of protective covering that will provide long-term isolation of the wastes from the accessible environment. Even if the wastes are exhumed and treated, a long-term barrier may still be needed to adequately dispose of the treated wastes or any remaining waste residuals. Currently, no {open_quotes}proven{close_quotes} long-term barrier is available. The Hanford Site Permanent Isolation Surface Barrier Development Program (BDP) was organized to develop the technology needed to provide a long-term surface barrier capability for the Hanford Site. The permanent isolation barrier technology also could be used at other sites. Permanent isolation barriers use engineered layers of natural materials to create an integrated structure with redundant protective features. Drawings of conceptual permanent isolation surface barriers are shown. The natural construction materials (e.g., fine soil, sand, gravel, riprap, asphalt) have been selected to optimize barrier performance and longevity. The objective of current designs is to use natural materials to develop a maintenance-free permanent isolation surface barrier that isolates wastes for a minimum of 1,000 years by limiting water drainage to near-zero amounts; reducing the likelihood of plant, animal, and human intrusion; controlling the exhalation of noxious gases; and minimizing erosion-related problems.

  13. Methods in the treatment of sodium wastes

    International Nuclear Information System (INIS)

    Rodriguez, G.

    1997-01-01

    In the domain of sodium waste processing, we have followed a logical route that has enabled us to propose a global method with respect to sodium wastes. This approach has led to: The choice of only those sodium processes using water; The development of sodium purification methods; The development of methods for cutting metallic wastes soiled by or filled with sodium; The transformation of the resulting sodium hydroxide into ultimate solid wastes for surface storage. (author)

  14. The long-term management of radioactive waste

    International Nuclear Information System (INIS)

    Faussat, A.

    1988-01-01

    After setting out the terms of reference of ANDRA (National agency for the management of radioactive waste), the author describes the current situation and the projects for the surface storage of waste of low and medium activity. He then discusses the work which has started on the construction of an underground laboratory for studying the storage of long life waste [fr

  15. Waste behavior analysis for tank 241-SY-103

    International Nuclear Information System (INIS)

    Wilkins, N.E.

    1994-01-01

    Tank 241-SY-103 is on the Flammable Gas Watch List. The waste in this tank behaves similarly to that in tank 241-Sy-101. Both show slurry growth and periodic surface level drops. However, the surface level drops are much smaller than those in tank 101-SY. A standard hydrogen monitoring system (SHMS) was recently installed in tank 103-SY, and waste auger samples were recently taken. This document covers the characterization results to date for the auger samples, and the behavior of the tank waste during both steady state periods and gas release events

  16. Processing method for discharged radioactive laundry water waste

    International Nuclear Information System (INIS)

    Izumida, Tatsuo; Kitsukawa, Ryozo; Tsuchiya, Hiroyuki; Kiuchi, Yoshimasa; Hattori, Yasuo.

    1995-01-01

    In order to process discharged radioactive laundry water wastes safely and decrease radioactive wastes, bubbling of a surface active agent in a detergent which causes a problem upon its condensation is suppressed, so that the liquid condensate are continuously and easily dried into a powder. A nonionic surface active agent is used against the bubbling of the surface active agent. In addition, the bubbling in an the evaporation can is reduced, and the powderization is facilitated by adding an appropriate inorganic builder. (T.M.)

  17. Effect of advanced fuel cycles on waste management policies

    International Nuclear Information System (INIS)

    Cavedon, J.M.; Haapalehto, T.

    2005-01-01

    The study aims at analysing a range of future fuel cycle options from the perspective of their impact on waste repository demand and specification. The study would focus on: Assessment of the characteristics of radioactive wastes arising from advanced nuclear fuel cycle options, repository performance analysis studies using source terms for waste arising from such advanced nuclear fuel cycles, identification of new options for waste management and disposal. Three families of fuel cycles having increasing recycling capabilities are assessed. Each cycle is composed of waste generating and management processes. Examples of waste generating processes are fuel factories (7 types) and reprocessing plants (7 types). Packaging and conditioning plants (7) and disposal facilities are examples of waste management processes. The characteristic of all these processes have been described and then total waste flows are summarised. In order to simplify the situation, three waste categories have been defined based on the IAEA definitions in order to emphasize the major effects of different types of waste. These categories are: short-life waste for surface or sub-surface disposal, long-life low heat producing waste for geological disposal, high-level waste for geological disposal. The feasibilities of the fuel cycles are compared in terms of economics, primary resource consumption and amount of waste generated. The effect of high-level waste composition for the repository performance is one of the tools in these comparisons. The results of this will be published as an NEA publication before the end of 2005. (authors)

  18. Review on waste inventory, waste characteristics and candidate site for LLW disposal in Thailand

    International Nuclear Information System (INIS)

    Yamkate, P.; Sriyotha, P.; Punnachaiya, M.; Danladkaew, K.

    1997-01-01

    It is a worldwide practice that radioactive waste has to be kept under control to be ensured of low potential impact on man and his environment. In Thailand, the OAEP is responsible for all radioactive waste management activities, both operation and the competent authority. The radioactive waste in Thailand consists of low level wastes from the application of radioisotopes in medical treatment and industry, the operation of the 2 MW TRIGA Mark III Research Reactor and the production of radioisotopes at OAEP. A plan for central disposal site has been set up. The near surface disposal method is chosen for this aspect because of its simple, inexpensive and adequate safe and very well know process. 8 refs., 6 tabs

  19. Durability test of geomembrane liners presumed to avail near surface disposal facilities for low-level waste generated from research, industrial and medical facilities

    International Nuclear Information System (INIS)

    Nakata, Hisakazu; Amazawa, Hiroya; Sakai, Akihiro; Kurosawa, Ryohei; Sakamoto, Yoshiaki; Kanno, Naohiro; Kashima, Takahiro

    2014-02-01

    The Low-level Radioactive Waste Disposal Project Center will construct near surface disposal facilities for radioactive wastes from research, industrial and medical facilities. The disposal facilities consist of “concrete pit type” for low-level radioactive wastes and “trench type” for very low level radioactive wastes. As for the trench type disposal facility, two kinds of facility designs are on projects – one for a normal trench type disposal facility without any of engineered barriers and the other for a trench type disposal facility with geomembrane liners that could prevent from causing environmental effects of non radioactive toxic materials contained in the waste packages. The disposal facility should be designed taking basic properties of durability on geomembrane liners into account, for it is exposed to natural environment on a long-term basis. This study examined mechanical strength and permeability properties to assess the durability on the basis of an indoor accelerated exposure experiment targeting the liner materials presumed to avail the conceptual design so far. Its results will be used for the basic and detailed design henceforth by confirming the empirical degradation characteristic with the progress of the exposure time. (author)

  20. Evidence for serial discontinuity in the fish community of a heavily impounded river

    Science.gov (United States)

    Miranda, Leandro E.; Dembkowski, D.J.

    2016-01-01

    In the Tennessee River, USA, we examined lengthwise patterns in fish community structure and species richness within and among nine reservoirs organized in sequence and connected through navigational locks. Within reservoirs, the riverine, transition and lacustrine zones supported distinct, although overlapping, nearshore fish assemblages; differences were also reflected in measures of species richness. Spatial patterns were most apparent for rheophilic species, which increased in species richness and representation upstream within each reservoir and downstream across the chain of reservoirs. This pattern resembled a sawtooth wave, with the amplitude of the wave peaking in the riverine zone below each dam, and progressively higher wave amplitude developing downstream in the reservoir chain. The observed sawtooth pattern supports the serial discontinuity concept in that the continuity of the riverine fish community is interrupted by the lacustrine conditions created behind each dam. Upstream within each reservoir, and downstream in the chain of reservoirs, habitat characteristics become more riverine. To promote sustainability of rheophilic fishes and maintain biodiversity in impounded rivers, conservation plans could emphasize maintenance and preservation of riverine environments of the reservoir's upper reaches, while remaining cognizant of the broader basin trends that provide opportunities for a lengthwise array of conservation and management policy. 

  1. 300 Area Process Trenches Supplemental Information to the Hanford Contingency Plan (DOE/RL-93-75)

    International Nuclear Information System (INIS)

    R.A. Carlson

    1997-01-01

    The 300 Area Process Trenches are surface impoundments which were used to receive routine discharges of nonregulated process cooling water from operations in the 300 Area and dangerous waste from several research and development laboratories and the 300 Area Fuels Fabrication process. Discharges to the trenches ceased in 1994, and they were physically isolated in 1995. Remediation of the trenches is scheduled to begin during July 1997. Currently, there are no waste management activities required at the 300 Area Process Trenches and the unit does not present any significant hazards to adjacent units, personnel, or the environment. It is unlikely that any incidents presenting hazards to public health or the environment would occur at the 300 Area Process Trenches, however, during remediation, exposure, spill, fire, and industrial hazards will exist. This contingency plan addresses the emergency organization, equipment and evacuation routes pertinent to the process trenches during remediation

  2. Impact test for solid waste forms

    International Nuclear Information System (INIS)

    Wallace, R.M.; Kelley, J.A.

    1976-03-01

    Samples of concretes and glasses being considered for incorporation of radioactive waste sludge were subjected to impact tests to determine the relationship between the energy of the impact and the resulting increase in surface area of the damaged sample. Test results indicate that the increased surface area per unit of energy input for glass waste forms is less by a factor of about three than that for concretes containing 40 wt percent simulated sludge (average values of 9.6 cm 2 /Joule and 24.7 cm 2 /Joule for glass and concrete, respectively)

  3. Underground storage of nuclear waste

    International Nuclear Information System (INIS)

    Russell, J.E.

    1977-06-01

    The objective of the National Waste Terminal Storage (NWTS) Program is to provide facilities in various deep geologic formations at multiple locations in the United States which will safely dispose of commerical radioactive waste. The NWTS Program is being administered for the Energy Research and Development Administration (ERDA) by the Office of Waste Isolation (OWI), Union Carbide Corporation, Nuclear Division. OWI manages projects that will lead to the location, construction, and operation of repositories, including all surface and underground engineering and facility design projects and technical support projects. 7 refs., 5 figs

  4. Underground storage of nuclear waste

    Energy Technology Data Exchange (ETDEWEB)

    Russell, J E

    1977-12-01

    The objective of the National Waste Terminal Storage (NWTS) Program is to provide facilities in various deep geologic formations at multiple locations in the United States which will safely dispose of commercial radioactive waste. The NWTS Program is being administered for the Energy Research and Development Administration (ERDA) by the Office of Waste Isolation (OWI), Union Carbide Corporation, Nuclear Division. OWI manages projects that will lead to the location, construction, and operation of repositories, including all surface and underground engineering and facility design projects and technical support projects.

  5. The safety case in support of the license application of the surface repository of low-level waste in Dessel, Belgium

    International Nuclear Information System (INIS)

    Wacquier, William; Cool, Wim

    2014-01-01

    The modern concept of the safety case, developed by the OECD/NEA for geological repositories of high- and medium-level waste has been successfully applied by ONDRAF/ NIRAS for a surface repository for Category A waste (i.e. low-level waste) in Belgium in the current project phase 2006-2012. This resulted in the submission on 31 January 2013 by ONDRAF/NIRAS of an application for a 'construction and operation license' to the safety authorities. The benefits of using the notion of the safety case have been that: i) safety has been incorporated in an integrated manner within all assessment basis, design and safety assessment activities; ii) the process of development of the license application has gained in clarity and traceability; iii) the documentation of the license application contains multiple lines of argumentation for safety rather than argumentation based only on quantitative radiological impact calculations. To offer a comprehensive view on the safety argumentation and its development, it has been found useful to develop the argumentation not only along a safety statements structure but also along the safety report structure. (authors)

  6. Groundwater monitoring and modelling of the “Vector” site for near-surface radioactive waste disposal in the Chornobyl exclusion zone

    Directory of Open Access Journals (Sweden)

    D. Bugai

    2017-12-01

    Full Text Available Results of purposeful groundwater monitoring and modelling studies are presented, which were carried out in order to better understand groundwater flow patterns from the “Vector” site for near-surface radioactive waste disposal and storage in the Chornobyl exclusion zone towards river network. Both data of observations at local-scale monitoring well network at “Vector” site carried out in 2015 - 2016 and modelling analyses using the regional groundwater flow model of Chornobyl exclusion zone suggest that the groundwater discharge contour for water originating from “Vector” site is Sakhan River, which is the tributary to Pripyat River. The respective groundwater travel time is estimated at 210 - 340 years. The travel times in subsurface for 90Sr, 137Cs, and transuranium radionuclides (Pu isotopes, 241Am are estimated respectively at thousands, tenths of thousands, hundreds of thousands – million of years. These results, as well as presented data of analyses of lithological properties of the geological deposits of the unsaturated zone at “Vector” site, provide evidence for good protection of surface water resources from radioactivity sources (e.g., radioactive wastes to be disposed in the near-sursface facilities at “Vector” site.

  7. The development of surface barriers at the Hanford Site

    International Nuclear Information System (INIS)

    Wing, N.R.; Gee, G.W.

    1994-03-01

    Engineered barriers are being developed to isolate wastes disposed of near the earth's surface at the US Department of Energy's (DOE) Hanford Site near Richland, Washington. Much of the waste that would be disposed of by in-place stabilization currently is located in relatively shallow subsurface structures such as solid waste burial grounds, tanks, vaults, and cribs. Unless protected in some way, the wastes could be transported to the accessible environment via the following pathways: plant, animal, and human intrusion; water infiltration; erosion; and the exhalation of noxious gases. Permanent isolation surface barriers have been proposed to protect wastes disposed of ''in place'' from the transport pathways identified previously (Figure 1). The protective barrier consists of a variety of different materials (e.g., fine soil, sand, gravel, riprap, asphalt, etc.) placed in layers to form an above-grade mound directly over the waste zone. Surface markers are being considered for placement around the periphery of the waste sites to inform future generations of the nature and hazards of the buried wastes. In addition, throughout the protective barrier, subsurface markers could be placed to warn any inadvertent human intruders of the dangers of the buried wastes (Figure 2)

  8. Fugitive emissions control on dry copper tailing with crushed rock armor

    International Nuclear Information System (INIS)

    Haase, E.F.

    1992-01-01

    Four inactive copper tailing impoundments totalling 1,900 acres near Ajo in southwestern Arizona were covered on horizontal surfaces with a 2 in. nominal thickness of crushed rock to control particulate emissions. The tailings are typically dominated by sand-sized particles but may also include significant PM 10 fractions towards the centers of the impoundments. The technology was selected by Phelps Dodge Corporation, after investigation of several alternatives, as a permanent and practical cover that essentially eliminates fugitive emissions. It simulates the natural desert pavement that characterizes this arid area of the Sonoran Desert. Rocky overburden was crushed to minus 3 in. diameter and broadcast on dry surfaces of tailing impoundments with all-terrain, balloon-tired spreaders. Stony residues in the rock armor tend to cement together following rainfall, forming a crust that enhances surface stability and erosion control. Slopes with windblown tailing deposition were covered to a nominal 6 in. thickness by conventional dozer pushing and blading of minus 10 in. rock over the sides. Athel trees, planted extensively since 1970 on two of the four inactive impoundments, provided partial control of fugitives, but were subjected to harsh environmental conditions, including abrasion from saltating particles. The rock armor functions as a mulch which is expected to improve water relations for existing vegetation and areas seeded with native species. New surface microenvironments, and the virtual elimination of surface creep and saltation, are expected to support native plant growth under favorable climatic conditions

  9. 30 CFR 77.216-2 - Water, sediment, or slurry impoundments and impounding structures; minimum plan requirements...

    Science.gov (United States)

    2010-07-01

    ... SAFETY AND HEALTH MANDATORY SAFETY STANDARDS, SURFACE COAL MINES AND SURFACE WORK AREAS OF UNDERGROUND... instrumentation. (9) Graphs showing area-capacity curves. (10) A statement of the runoff attributable to the probable maximum precipitation of 6-hour duration and the calculations used in determining such runoff. (11...

  10. Monitoring of surface deformation and microseismicity applied to radioactive waste disposal through hydraulic fracturing at Oak Ridge National Laboratory

    International Nuclear Information System (INIS)

    Stow, S.H.; Haase, C.S.; Switek, J.; Holzhausen, G.R.; Majer, E.; Applied Geomechanics, Inc., Santa Cruz, CA; Lawrence Berkeley Lab., CA)

    1985-01-01

    Low-level liquid nuclear wastes are disposed of at Oak Ridge National Laboratory by the hydrofracture process. Wastes are mixed with cement and other additives to form a slurry that is injected into shale of low permeability at 300 m depth. The slurry spreads radially along bedding plane fractures before setting as a grout. Different methods for monitoring the location and behavior of the fractures have been investigated. Radioactive grout sheets can be located by gamma-ray logging of cased observation wells. Two other methods are based on the fact that the ground surface is deformed by the injection. The first entails surface leveling of a series of benchmarks; uplift up to 2.5 cm occurs. The second method involves use of tiltmeters that are sensitive and measure ground deformation in real time during an injection. Both methods show subsidence during the weeks following an injection. Interpretive models for the tiltmeter data are based on the elastic response of isotropic and anisotropic media to the inflation of a fluid-filled fracture. A fourth monitoring method is based on microseismicity. Geophone arrays were used to characterize the fracture process and to provide initial assessment of the feasibility of using seismic measurements to map the fractures as they form. An evaluation of each method is presented

  11. Development of Risk Insights for Regulatory Review of a Near-Surface Disposal Facility for Radioactive Waste

    International Nuclear Information System (INIS)

    Esh, D.W.; Ridge, A.C.; Thaggard, M.

    2006-01-01

    Section 3116 of the Ronald W. Reagan National Defense Authorization Act for Fiscal Year 2005 (NDAA) requires the Department of Energy (DOE) to consult with the Nuclear Regulatory Commission (NRC) about non-High Level Waste (HLW) determinations. In its consultative role, NRC performs technical reviews of DOE's waste determinations but does not have regulatory authority over DOE's waste disposal activities. The safety of disposal is evaluated by comparing predicted disposal facility performance to the performance objectives specified in NRC regulations for the disposal of low-level waste (10 CFR Part 61 Subpart C). The performance objectives contain criteria for protection of the public, protection of inadvertent intruders, protection of workers, and stability of the disposal site after closure. The potential radiological dose to receptors typically is evaluated with a performance assessment (PA) model that simulates the release of radionuclides from the disposal site, transport of radionuclides through the environment, and exposure of potential receptors to residual contamination for thousands of years. This paper describes NRC's development and use of independent performance assessment modeling to facilitate review of DOE's non-HLW determination for the Saltstone Disposal Facility (SDF) at the Savannah River Site. NRC's review of the safety of near-surface disposal of radioactive waste at the SDF was facilitated and focused by risk insights developed with an independent PA model. The main components of NRC's performance assessment model are presented. The development of risk insights that allow the staff to focus review efforts on those areas that are most important to satisfying the performance objectives is discussed. Uncertainty analysis was performed of the full stochastic model using genetic variable selection algorithms. The results of the uncertainty analysis were then used to guide the development of simulations of other scenarios to understand the key risk

  12. HIGH ALUMINUM HLW (HIGH LEVEL WASTE) GLASSES FOR HANFORD'S WTP (WASTE TREATMENT PROJECT)

    International Nuclear Information System (INIS)

    Kruger, A.A.; Bowan, B.W.; Joseph, I.; Gan, H.; Kot, W.K.; Matlack, K.S.; Pegg, I.L.

    2010-01-01

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

  13. Underground radioactive waste disposal concept

    International Nuclear Information System (INIS)

    Frgic, L.; Tor, K.; Hudec, M.

    2002-01-01

    The paper presents some solutions for radioactive waste disposal. An underground disposal of radioactive waste is proposed in deep boreholes of greater diameter, fitted with containers. In northern part of Croatia, the geological data are available on numerous boreholes. The boreholes were drilled during investigations and prospecting of petroleum and gas fields. The available data may prove useful in defining safe deep layers suitable for waste repositories. The paper describes a Russian disposal design, execution and verification procedure. The aim of the paper is to discuss some earlier proposed solutions, and present a solution that has not yet been considered - lowering of containers with high level radioactive waste (HLW) to at least 500 m under the ground surface.(author)

  14. Risk-based approach to long-term safety assessment for near surface disposal of radioactive waste in Korea

    International Nuclear Information System (INIS)

    Jeong, C.W.; Kim, K.I.; Lee, J.I.

    2000-01-01

    This paper presents the Korean regulatory approach to safety assessment consistent with probabilistic, risk-based long-term safety requirements for near surface disposal facilities. The approach is based on: (1) From the standpoint of risk limitation, normal processes and probabilistic disruptive events should be integrated in a similar manner in terms of potential exposures; and (2) The uncertainties inherent in the safety assessment should be reduced using appropriate exposure scenarios. In addition, this paper emphasizes the necessity of international guidance for quantifying potential exposures and the corresponding risks from radioactive waste disposal. (author)

  15. Waste classification sampling plan

    International Nuclear Information System (INIS)

    Landsman, S.D.

    1998-01-01

    The purpose of this sampling is to explain the method used to collect and analyze data necessary to verify and/or determine the radionuclide content of the B-Cell decontamination and decommissioning waste stream so that the correct waste classification for the waste stream can be made, and to collect samples for studies of decontamination methods that could be used to remove fixed contamination present on the waste. The scope of this plan is to establish the technical basis for collecting samples and compiling quantitative data on the radioactive constituents present in waste generated during deactivation activities in B-Cell. Sampling and radioisotopic analysis will be performed on the fixed layers of contamination present on structural material and internal surfaces of process piping and tanks. In addition, dose rate measurements on existing waste material will be performed to determine the fraction of dose rate attributable to both removable and fixed contamination. Samples will also be collected to support studies of decontamination methods that are effective in removing the fixed contamination present on the waste. Sampling performed under this plan will meet criteria established in BNF-2596, Data Quality Objectives for the B-Cell Waste Stream Classification Sampling, J. M. Barnett, May 1998

  16. Investigation on the oxygen transport mechanisms in the Sarcheshmeh waste rock dumps

    Directory of Open Access Journals (Sweden)

    Saeed Yousefi

    2015-04-01

    . Considering the presence of coarse grain and poorly graded material as a proper media for air convection and also hardpan layer as a confining factor in molecular diffusion of oxygen, it can be deduced that the air convection is the main important mechanism to supply oxygen for weathering and oxidation reactions in the waste rock dumps. The abundance of oxygen and high temperatures in such conditions are also favorable for bacterial activities, which can then accelerate the pyrite oxidation in lower depth of dump. It is expected that the results of this study could be useful as a basis for providing the remediation strategies to control acidic drainage. So that knowing the domination of air convection and presence of hardpan justify controlling the flux of oxygen from the coarse material in bottom of waste dump. Therefore, it would be wrong to construct the impermeable layer on the surface of waste dump for arresting the oxygen diffusion as a traditional method in the remediation. Acknowledgement The authors appreciate the cooperation of the Research and Development Division of the Sarcheshmeh Copper Complex for financial support and access to sampling and analysis facilities. Reference Blowes, D.W., Reardon, E.J., Jambor, J.L. and Cherry, J.A., 1991. The formation and potential importance of cemented layers in inactive sulfide mine tailings. Geochimica et Cosmochimica Acta, 55(4: 965-978. Borden, R.K., 2003. Environmental geochemistry of the Bingham Canyon porphyry copper deposit, Utah. Environmental Geology, 43(7: 752-758. Cathles, L.M. and Apps, J.A., 1975. A model of the dump leaching process that incorporates oxygen balance, heat balance, and air convection. Metallurgical Transactions B, 6(4: 617-624. Davis, G.B. and Ritchie A.I.M., 1986. A model of oxidation in pyritic mine wastes: part 1: Equations and approximate solution. Applied Mathematical Modeling, 10(5: 314-322. Elberling, B., Nicholson, R.V., Reardon, E.J. and Tibble, R., 1994. Evaluation of sulphide oxidation

  17. Alpha waste management at the Valduc Research Center

    International Nuclear Information System (INIS)

    Jouan, A.; Cartier, R.; Durec, J.P.; Flament, T.

    1995-01-01

    Operation of the reprocessing facilities at the Valduc Research Center of the French Atomic Energy Commission (CEA) generates waste with a variety of characteristics. The waste compatible with surface storage requirements is transferred to the French Radioactive Waste Management Agency (ANDRA); rest is reprocessed under a program which enables storage in compliance with the requirements of permits issued by safety Authorities. The waste reprocessing program provides for the construction of an incinerator capable of handling nearly all of the combustible waste generated by the Center and vitrification facility for treating liquid waste generated by the plutonium handling plant. (authors)

  18. 216-A-29 Ditch supplemental information to the Hanford Facility Contingency Plan (DOE/RL-93-75)

    International Nuclear Information System (INIS)

    Ingle, S.J.

    1996-05-01

    This document is a unit-specific contingency plan for the 216-A-29 Ditch and is intended to be used as a supplement to DOE/RL-93-75, Hanford Facility Contingency Plan (DOE-RL 1993). This unit-specific plan is to be used to demonstrate compliance with the contingency plan requirements of the Washington Administrative Code, Chapter 173- 303 for certain Resource Conservation and Recovery Act of 1976 waste management units. The 216-A-29 Ditch is a surface impoundment that received nonregulated process and cooling water and other dangerous wastes primarily from operations of the Plutonium/Uranium Extraction Plant. Active between 1955 and 1991, the ditch has been physically isolated and will be closed. Because it is no longer receiving discharges, waste management activities are no longer required at the unit. The ditch does not present a significant hazard to adjacent units, personnel, or the environment. It is unlikely that any incidents presenting hazards to public health or the environment would occur at the 216-A-29 Ditch

  19. 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

  20. 30 CFR 779.25 - Cross sections, maps, and plans.

    Science.gov (United States)

    2010-07-01

    ... waste disposal, dams, embankments, other impoundments, and water treatment and air pollution control... locations of monitoring stations used to gather data for water quality and quantity, fish and wildlife, and... known workings of active, inactive, or abandoned underground mines, including mine openings to the...

  1. Surface complexation modeling of uranyl adsorption on corrensite from the Waste Isolation Pilot Plant Site

    Energy Technology Data Exchange (ETDEWEB)

    Park, Sang-Won; Leckie, J.O. [Stanford Univ., CA (United States); Siegel, M.D. [Sandia National Labs., Albuquerque, NM (United States)

    1995-09-01

    Corrensite is the dominant clay mineral in the Culebra Dolomite at the Waste Isolation Pilot Plant. The surface characteristics of corrensite, a mixed chlorite/smectite clay mineral, have been studied. Zeta potential measurements and titration experiments suggest that the corrensite surface contains a mixture of permanent charge sites on the basal plane and SiOH and AlOH sites with a net pH-dependent charge at the edge of the clay platelets. Triple-layer model parameters were determined by the double extrapolation technique for use in chemical speciation calculations of adsorption reactions using the computer program HYDRAQL. Batch adsorption studies showed that corrensite is an effective adsorbent for uranyl. The pH-dependent adsorption behavior indicates that adsorption occurs at the edge sites. Adsorption studies were also conducted in the presence of competing cations and complexing ligands. The cations did not affect uranyl adsorption in the range studied. This observation lends support to the hypothesis that uranyl adsorption occurs at the edge sites. Uranyl adsorption was significantly hindered by carbonate. It is proposed that the formation of carbonate uranyl complexes inhibits uranyl adsorption and that only the carbonate-free species adsorb to the corrensite surface. The presence of the organic complexing agents EDTA and oxine also inhibits uranyl sorption.

  2. Surface complexation modeling of uranyl adsorption on corrensite from the Waste Isolation Pilot Plant Site

    International Nuclear Information System (INIS)

    Park, Sang-Won; Leckie, J.O.; Siegel, M.D.

    1995-09-01

    Corrensite is the dominant clay mineral in the Culebra Dolomite at the Waste Isolation Pilot Plant. The surface characteristics of corrensite, a mixed chlorite/smectite clay mineral, have been studied. Zeta potential measurements and titration experiments suggest that the corrensite surface contains a mixture of permanent charge sites on the basal plane and SiOH and AlOH sites with a net pH-dependent charge at the edge of the clay platelets. Triple-layer model parameters were determined by the double extrapolation technique for use in chemical speciation calculations of adsorption reactions using the computer program HYDRAQL. Batch adsorption studies showed that corrensite is an effective adsorbent for uranyl. The pH-dependent adsorption behavior indicates that adsorption occurs at the edge sites. Adsorption studies were also conducted in the presence of competing cations and complexing ligands. The cations did not affect uranyl adsorption in the range studied. This observation lends support to the hypothesis that uranyl adsorption occurs at the edge sites. Uranyl adsorption was significantly hindered by carbonate. It is proposed that the formation of carbonate uranyl complexes inhibits uranyl adsorption and that only the carbonate-free species adsorb to the corrensite surface. The presence of the organic complexing agents EDTA and oxine also inhibits uranyl sorption

  3. Low temperature ozone oxidation of solid waste surrogates

    Science.gov (United States)

    Nabity, James A.; Lee, Jeffrey M.

    2015-09-01

    Solid waste management presents a significant challenge to human spaceflight and especially, long-term missions beyond Earth orbit. A six-month mission will generate over 300 kg of solid wastes per crewmember that must be dealt with to eliminate the need for storage and prevent it from becoming a biological hazard to the crew. There are several methods for the treatment of wastes that include oxidation via ozone, incineration, microbial oxidation or pyrolysis and physical methods such as microwave drying and compaction. In recent years, a low temperature oxidation process using ozonated water has been developed for the chemical conversion of organic wastes to CO2 and H2O. Experiments were conducted to evaluate the rate and effectiveness with which ozone oxidized several different waste materials. Increasing the surface area by chopping or shredding the solids into small pieces more than doubled the rate of oxidation. A greater flow of ozone and agitation of the ozonated water system also increased processing rates. Of the materials investigated, plastics have proven the most difficult to oxidize. The processing of plastics above the glass transition temperatures caused the plastics to clump together which reduced the exposed surface area, while processing at lower temperatures reduced surface reaction kinetics.

  4. Groundwater quality assessment plan for the 1324-N/NA Site: Phase 1 (first determination)

    International Nuclear Information System (INIS)

    Hartman, M.J.

    1998-05-01

    The 1324-N Surface Impoundment and 1324-NA Percolation Pond (1324-N/NA Site) are treatment/storage/disposal sites regulated under the Resource Conservation and Recovery Act of 1976 (RCRA). They are located in the 100-N Area of the Hanford Site, and were used to treat and dispose of corrosive waste from a water treatment plant. Groundwater monitoring under an interim-status detection program compared indicator parameters from downgradient wells to background values established from an upgradient well. One of the indicator parameters, total organic carbon (TOC), exceeded its background value in one downgradient well, triggering an upgrade from a detection program to an assessment program. This plan presents the first phase of the assessment program

  5. Groundwater Monitoring Plan for the 1301-N, 1324-N/NA, and 1325-N RCRA Facilities

    International Nuclear Information System (INIS)

    Hartman, Mary J.

    2001-01-01

    The 1301-N and 1325-N Liquid Waste Disposal Facilities, the 1324-N Surface Impoundment, and the 1324-NA Percolation Pond, located in the 100 N Area of the Hanford Site, are regulated under the Resource Conservation and Recovery Act of 1976 (RCRA). The closure plans for these facilities stipulate that groundwater is monitored according to the 100-N Pilot Project: Proposed Consolidated Groundwater Monitoring Program (BHI-00725). This document supplements the consolidated plan by providing information on sampling and analysis protocols, quality assurance, data management, and a conceptual model for the RCRA sites. Monitoring well networks, constituents, and sampling frequency remain the same as in the consolidated plan or the previous groundwater monitoring plan (Hartman 1996)

  6. Steel Industry Wastes.

    Science.gov (United States)

    Schmidtke, N. W.; Averill, D. W.

    1978-01-01

    Presents a literature review of wastes from steel industry, covering publications of 1976-77. This review covers: (1) coke production; (2) iron and steel production; (3) rolling operations; and (4) surface treatment. A list of 133 references is also presented. (NM)

  7. Conditioning of radioactive waste from the waste collection centers of the German states as illustrated by radioactive waste from industrial production processes

    International Nuclear Information System (INIS)

    Stellmacher, J.; Sickert, T.

    2011-01-01

    The amount of negligible heat generating waste in Germany is increasing due to deconstruction of decommissioned nuclear facilities. Until 2040 277.000 m 3 are expected. By conditioning processes the wastes are transferred into a chemical stabile and water insoluble state and packaged in appropriate containers for final repository disposal. The radioactive waste in the collection containers are coated with wax for immobilization of the surface contamination, in the next step the containers are filled with pressurized geopolymer, a thixotropic fluid (under pressure the viscosity is decreased, so that cavities are filled). The conditioned material, the so called interim product is stored in trays for the final packaging in appropriate containers.

  8. The dispersal and impact of salt from surface storage piles the Waste Isolation Pilot Plant

    International Nuclear Information System (INIS)

    Reith, C.C.; Louderbough, E.T.

    1986-01-01

    A comprehensive program of ecological studies occurs at the Waste Isolation Pilot Plant (WIPP) in an effort to detect and quantify impacts of excavated salt which is stored on the surface in two piles: one having originated in 1980, the other in 1984. Both piles are surrounded by berms which channel runoff to holding ponds, so nearly all dispersal is due to the resuspension, transport, and deposition of salt particles by wind. Ecological parameters which have been monitored since 1984 include: visual evidence (via photography), soil properties, microbial activity, leaf-litter decomposition, seedling emergence, plant foliar cover, and plant species diversity. These are periodically assessed at experimental plots near the salt piles, and at control plots several kilometers away

  9. Disposing of fluid wastes

    International Nuclear Information System (INIS)

    Bradley, J.S.

    1984-01-01

    Toxic liquid waste, eg liquid radioactive waste, is disposed of by locating a sub-surface stratum which, before removal of any fluid, has a fluid pressure in the pores thereof which is less than the hydrostatic pressure which is normal for a stratum at that depth in the chosen area, and then feeding the toxic liquid into the stratum at a rate such that the fluid pressure in the stratum never exceeds the said normal hydrostatic pressure. (author)

  10. Experiences with treatment of mixed waste

    International Nuclear Information System (INIS)

    Dziewinski, J.; Marczak, S.; Smith, W.H.; Nuttall, E.

    1996-01-01

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

  11. Experiences with treatment of mixed waste

    Energy Technology Data Exchange (ETDEWEB)

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

    1996-04-10

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

  12. Development plan. High activity-long living wastes project. Abstract

    International Nuclear Information System (INIS)

    2007-01-01

    This brochure presents the actions that the ANDRA (the French national agency of radioactive wastes) has to implement in the framework of the project of high activity-long living (HALL) radioactive wastes (HAVL project) conformably to the requirements of the program defined in the law from June 28, 2006 (law no 2006-739). This law precises the three, complementary, research paths to explore for the management of this type of wastes: separation and transmutation of long-living radioactive elements, reversible disposal in deep geologic underground, and long duration storage. The ANDRA's action concerns the geologic disposal aspect. The following points are presented: the HALL wastes and their containers, the reversible disposal procedure, the HAVL project: financing of researches, storage concepts, development plan of the project (dynamics, information and dialogue approach, input data, main steps, schedule); the nine programs of the HAVL project (laboratory experiments and demonstration tests, surface survey, scientific program, simulation program, surface engineering studies and technological tests, information and communication program, program of environment and facilities surface observation and monitoring, waste packages management, monitoring and transport program, disposal program); the five transverse technical and scientific activities (safety, reversibility, cost, health and occupational safety, impact study). (J.S.)

  13. Radioactive wastes. Safety of storage facilities

    International Nuclear Information System (INIS)

    Devillers, Ch.

    2001-01-01

    A radioactive waste storage facility is designed in a way that ensures the isolation of wastes with respect to the biosphere. This function comprises the damping of the gamma and neutron radiations from the wastes, and the confinement of the radionuclides content of the wastes. The safety approach is based on two time scales: the safety of the insulation system during the main phase of radioactive decay, and the assessment of the radiological risks following this phase. The safety of a surface storage facility is based on a three-barrier concept (container, storage structures, site). The confidence in the safety of the facility is based on the quality assurance of the barriers and on their surveillance and maintenance. The safety of a deep repository will be based on the site quality, on the design and construction of structures and on the quality of the safety demonstration. This article deals with the safety approach and principles of storage facilities: 1 - recall of the different types of storage facilities; 2 - different phases of the life of a storage facility and regulatory steps; 3 - safety and radiation protection goals (time scales, radiation protection goals); 4 - safety approach and principles of storage facilities: safety of the isolation system (confinement system, safety analysis, scenarios, radiological consequences, safety principles), assessment of the radiation risks after the main phase of decay; 5 - safety of surface storage facilities: safety analysis of the confinement system of the Aube plant (barriers, scenarios, modeling, efficiency), evaluation of radiological risks after the main phase of decay; experience feedback of the Manche plant; variants of surface storage facilities in France and abroad (very low activity wastes, mine wastes, short living wastes with low and average activity); 6 - safety of deep geological disposal facilities: legal framework of the French research; international context; safety analysis of the confinement system

  14. What to do with radioactive wastes?

    International Nuclear Information System (INIS)

    2006-01-01

    This power point presentation (82 slides) gives information on what is a radioactive waste, radioactivity and historical review of radioactivity, radioactive period, natural radioactivity (with examples of data), the three main radiation types (α, β, γ), the origin of radioactive wastes (nuclear power, research, defense, other), the proportion of radioactive wastes in the total of industrial wastes in France, the classification of nuclear wastes according to their activity and period, the quantities and their storage means, the 1991 december 30 law (France) related to the radioactive waste management, the situation in other countries (Germany, Belgium, Canada, USA, Finland, Japan, Netherlands, Sweden, Switzerland), volume figures and previsions for the various waste types in 2004, 2010 and 2020, the storage perspectives, the French national debate on radioactive waste management and the objective of perpetuated solutions, the enhancement of the public information, the 15 June 2006 law on a sustainable management of radioactive materials and wastes with three main axis (deep separation and transmutation, deep storage, waste conditioning and long term surface storage), and the development of a nuclear safety and waste culture that could be extended to other types of industry

  15. Analysis of surface leaching processes in vitrified high-level nuclear wastes using in-situ raman imaging and atomistic modeling. 1998 annual progress report

    International Nuclear Information System (INIS)

    Clark, D.E.; Simmons, J.H.

    1998-01-01

    'The research objective was to test and develop optical methods for real-time, remote and in-situ testing of corrosion processes on the surface of vitrified nuclear wastes. This report summarizes the research conducted in the first 1.5 years of a 3 year grant. At this point, the authors have identified the conditions for optimal tests and demonstrated that both IR reflection and Raman spectroscopies can be used to determine the dealkalization process in the surface of simple glasses in real time.'

  16. Polybrominated diphenyl ethers in e-waste: Level and transfer in a typical e-waste recycling site in Shanghai, Eastern China

    Energy Technology Data Exchange (ETDEWEB)

    Li, Yue; Duan, Yan-Ping, E-mail: duanyanping@tongji.edu.cn; Huang, Fan; Yang, Jing; Xiang, Nan; Meng, Xiang-Zhou; Chen, Ling

    2014-06-01

    Highlights: • PBDEs were detected in the majority of e-waste. • PBDEs were found in TVs made in China after 1990. • The levels of ΣPBDEs in e-waste made in Japan far exceed the threshold limit of RoHS. • The inappropriate recycling and disposal of e-waste is an important source of PBDEs. - Abstract: Very few data for polybrominated diphenyl ethers (PBDEs) were available in the electronic waste (e-waste) as one of the most PBDEs emission source. This study reported concentrations of PBDEs in e-waste including printer, rice cooker, computer monitor, TV, electric iron and water dispenser, as well as dust from e-waste, e-waste dismantling workshop and surface soil from inside and outside of an e-waste recycling plant in Shanghai, Eastern China. The results showed that PBDEs were detected in the majority of e-waste, and the concentrations of ΣPBDEs ranged from not detected to 175 g/kg, with a mean value of 10.8 g/kg. PBDEs were found in TVs made in China after 1990. The mean concentrations of ΣPBDEs in e-waste made in Korea, Japan, Singapore and China were 1.84 g/kg, 20.5 g/kg, 0.91 g/kg, 4.48 g/kg, respectively. The levels of ΣPBDEs in e-waste made in Japan far exceed the threshold limit of RoHS (1.00 g/kg). BDE-209 dominated in e-waste, accounting for over 93%. The compositional patterns of PBDEs congeners resembled the profile of Saytex 102E, indicating the source of deca-BDE. Among the samples of dust and surface soil from a typical e-waste recycling site, the highest concentrations of Σ{sub 18}PBDEs and BDE-209 were found in dust in e-waste, ranging from 1960 to 340,710 ng/g and from 910 to 320,400 ng/g, which were 1–2 orders of magnitude higher than other samples. It suggested that PBDEs released from e-waste via dust, and then transferred to surrounding environment.

  17. Surface water sampling and analysis plan for environmental monitoring in Waste Area Grouping 6 at Oak Ridge National Laboratory, Oak Ridge, Tennessee. Environmental Restoration Program

    Energy Technology Data Exchange (ETDEWEB)

    1994-06-01

    This Sampling and Analysis Plan addresses surface water monitoring, sampling, and analysis activities that will be conducted in support of the Environmental Monitoring Plan for Waste Area Grouping (WAG) 6. WAG 6 is a shallow-burial land disposal facility for low-level radioactive waste at the Oak Ridge National Laboratory, a research facility owned by the US Department of Energy and managed by Martin Marietta Energy Systems, Inc. Surface water monitoring will be conducted at nine sites within WAG 6. Activities to be conducted will include the installation, inspection, and maintenance of automatic flow-monitoring and sampling equipment and manual collection of various water and sediment samples. The samples will be analyzed for various organic, inorganic, and radiological parameters. The information derived from the surface water monitoring, sampling, and analysis will aid in evaluating risk associated with contaminants migrating off-WAG, and will be used in calculations to establish relationships between contaminant concentration (C) and flow (Q). The C-Q relationship will be used in calculating the cumulative risk associated with the off-WAG migration of contaminants.

  18. Surface water sampling and analysis plan for environmental monitoring in Waste Area Grouping 6 at Oak Ridge National Laboratory, Oak Ridge, Tennessee. Environmental Restoration Program

    International Nuclear Information System (INIS)

    1994-06-01

    This Sampling and Analysis Plan addresses surface water monitoring, sampling, and analysis activities that will be conducted in support of the Environmental Monitoring Plan for Waste Area Grouping (WAG) 6. WAG 6 is a shallow-burial land disposal facility for low-level radioactive waste at the Oak Ridge National Laboratory, a research facility owned by the US Department of Energy and managed by Martin Marietta Energy Systems, Inc. Surface water monitoring will be conducted at nine sites within WAG 6. Activities to be conducted will include the installation, inspection, and maintenance of automatic flow-monitoring and sampling equipment and manual collection of various water and sediment samples. The samples will be analyzed for various organic, inorganic, and radiological parameters. The information derived from the surface water monitoring, sampling, and analysis will aid in evaluating risk associated with contaminants migrating off-WAG, and will be used in calculations to establish relationships between contaminant concentration (C) and flow (Q). The C-Q relationship will be used in calculating the cumulative risk associated with the off-WAG migration of contaminants

  19. Radioactive Waste Management Complex low-level waste radiological performance assessment

    Energy Technology Data Exchange (ETDEWEB)

    Maheras, S.J.; Rood, A.S.; Magnuson, S.O.; Sussman, M.E.; Bhatt, R.N.

    1994-04-01

    This report documents the projected radiological dose impacts associated with the disposal of radioactive low-level waste at the Radioactive Waste Management Complex at the Idaho National Engineering Laboratory. This radiological performance assessment was conducted to evaluate compliance with applicable radiological criteria of the US Department of Energy and the US Environmental Protection Agency for protection of the public and the environment. The calculations involved modeling the transport of radionuclides from buried waste, to surface soil and subsurface media, and eventually to members of the public via air, groundwater, and food chain pathways. Projections of doses were made for both offsite receptors and individuals inadvertently intruding onto the site after closure. In addition, uncertainty and sensitivity analyses were performed. The results of the analyses indicate compliance with established radiological criteria and provide reasonable assurance that public health and safety will be protected.

  20. Radioactive Waste Management Complex low-level waste radiological performance assessment

    International Nuclear Information System (INIS)

    Maheras, S.J.; Rood, A.S.; Magnuson, S.O.; Sussman, M.E.; Bhatt, R.N.

    1994-04-01

    This report documents the projected radiological dose impacts associated with the disposal of radioactive low-level waste at the Radioactive Waste Management Complex at the Idaho National Engineering Laboratory. This radiological performance assessment was conducted to evaluate compliance with applicable radiological criteria of the US Department of Energy and the US Environmental Protection Agency for protection of the public and the environment. The calculations involved modeling the transport of radionuclides from buried waste, to surface soil and subsurface media, and eventually to members of the public via air, groundwater, and food chain pathways. Projections of doses were made for both offsite receptors and individuals inadvertently intruding onto the site after closure. In addition, uncertainty and sensitivity analyses were performed. The results of the analyses indicate compliance with established radiological criteria and provide reasonable assurance that public health and safety will be protected