WorldWideScience

Sample records for sanitary landfill tritium

  1. Sanitary landfill liners

    DEFF Research Database (Denmark)

    Christiansen, Ole V.; Stentsøe, Steen; Petersen, Søren

    DS/INF 466 is the revised Danish recommendation for investigations, design and construction of landfill liners.......DS/INF 466 is the revised Danish recommendation for investigations, design and construction of landfill liners....

  2. Sanitary Landfill Supplemental Test Final Report

    International Nuclear Information System (INIS)

    Altman, D.J.

    1999-01-01

    This report summarizes the performance of the Sanitary Landfill Supplemental Test data, an evaluation of applicability, conclusions, recommendations, and related information for implementation of this remediation technology at the SRS Sanitary Landfill

  3. Analysis of biogas in sanitary landfill Caieiras

    Directory of Open Access Journals (Sweden)

    Giovano Candiani

    2011-06-01

    Full Text Available In this work, the biogas in the Sanitary Landfill Caieiras is qualitatively evaluated, emphasizing the influence of the geomembrana and cover system of vertical drains in the vicinity to capture the landfill. It was possible to detect an increase in the percentage of methane and oxygen reduction, aiming at the commercialization of carbon credits and electricity production.

  4. Behavior of radionuclides in sanitary landfills.

    Science.gov (United States)

    Chang, K C; Chian, E S; Pohland, F G; Cross, W H; Roland, L; Kahn, B

    1984-01-01

    his study was undertaken to evaluate the possibility of disposing low-level radioactive waste in sanitary landfills with leachate containment to prevent environmental releases. To meet this objective, two simulated landfills, each 200 l. in volume and containing 55 kg of municipal refuse, were operated in the laboratory with simulated rainfall additions for a 9-month period to observe the extent to which radio-cobalt, -cesium, -strontium and tritium were leached into the liquid phase. One of the units was operated with leachate recycle, the other as a single pass control. Liquid samples were analyzed weekly for 3H, 58Co, 85Sr and 134Cs tracers. Weekly analyses were also performed for approximately 30 parameters to define the degree of stabilization of the waste. Major parameters included BOD, COD, pH and concentrations of specific organics, metals and gases. Concentrations of stable cobalt, strontium and cesium were also measured periodically. Soluble radioactivity levels in both systems were reduced by factors of 50 for 58Co, 5 for 85Sr and 7 for 134Cs, taking radioactive decay and dilution into account. Some radionuclide removal from the liquid phase was associated with major chemical changes in the landfills that occurred within 80 days for the control system and within 130 days for the recycle unit. Observed acid, sulfide, and CO2 concentrations suggested mechanisms for removing some of the radionuclides from leachate. Detection of 3H in the off-gas indicated that less than 1% of tritiated waste became airborne. The waste in the leachate recycle unit was more completely stabilized than in the control unit.

  5. Sanitary landfill in situ bioremediation optimization test. Final report

    International Nuclear Information System (INIS)

    1996-01-01

    This work was performed as part of a corrective action plan for the Savannah River Site Sanitary Landfill. This work was performed for the Westinghouse Savannah River Company Environmental Restoration Department as part of final implementation of a groundwater remediation system for the SRS Sanitary Landfill. Primary regulatory surveillance was provided by the South Carolina Department of Health and Environmental Control and the US Environmental Protection Agency (Region IV). The characterization, monitoring and remediation systems in the program generally consisted of a combination of innovative and baseline methods to allow comparison and evaluation. The results of these studies will be used to provide input for the full-scale groundwater remediation system for the SRS Sanitary Landfill. This report summarizes the performance of the Sanitary Landfill In Situ Optimization Test data, an evaluation of applicability, conclusions, recommendations, and related information for implementation of this remediation technology at the SRS Sanitary Landfill

  6. Sanitary landfill groundwater monitoring report. Fourth quarter 1994 and 1994 summary

    International Nuclear Information System (INIS)

    1995-02-01

    Eighty-nine wells of the LFW series monitor groundwater quality in the Steed Pond Aquifer (Water Table) beneath the Sanitary Landfill at the Savannah River Site (SRS). These wells are sampled quarterly to comply with the South Carolina Department of Health and Environmental Control Domestic Waste Permit DWP-087A and as part of the SRS Groundwater Monitoring Program. Dichloromethane, a common laboratory contaminant, and trichloroethylene were the most widespread constituents exceeding standards during 1994. Benzene, chloroethene (vinyl chloride), 1,2-dichloroethane, 1,1-dichloroethylene, 1,2-dichloropropane, gross alpha, mercury, nonvolatile beta, tetrachloroethylene, and tritium also exceeded standards in one or more wells. The groundwater flow direction in the Steed Pond Aquifer (Water Table) beneath the Sanitary Landfill was to the southeast (universal transverse Mercator coordinates). The flow rate in this unit was approximately 140 ft/year during first and fourth quarters 1994

  7. Sanitary Landfill Groundwater Monitoring Report, Second Quarter 1999

    Energy Technology Data Exchange (ETDEWEB)

    Chase, J.

    1999-07-29

    This report contains analytical data for samples taken during Second Quarter 1999 from wells of the LFW series located at the Sanitary Landfill at the Savannah River Site. The data are submitted in reference to the Sanitary Landfill Operating Permit. The report presents monitoring results that equaled or exceeded the Safe Drinking Water Act final Primary Drinking Water Standards or screening levels, established by the US Environmental Protection Agency, the South Carolina final Primary Drinking Water Standard for lead, or the SRS flagging criteria.

  8. Sanitary landfill groundwater monitoring report, Third Quarter 1999

    Energy Technology Data Exchange (ETDEWEB)

    Chase, J.

    1999-12-08

    This report contains analytical data for samples taken during Third Quarter 1999 from wells of the LFW series located at the Sanitary Landfill at the Savannah River Site. The data are submitted in reference to the Sanitary Landfill Operating Permit. The report presents monitoring results that equaled or exceeded the Safe Drinking Water Act final Primary Drinking Water Standards or screening levels, established by the U.S. Environmental Protection Agency, the South Carolina final Primary Drinking Water Standard for lead, or the SRS flagging criteria.

  9. Sanitary landfill groundwater monitoring report. Third quarter 1995

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1995-11-01

    This report contains analytical data for samples taken during third quarter 1995 from wells of the LFW series located at the Sanitary Landfill at the Savannah River Site (SRS). The data are submitted in reference to the Sanitary Landfill Operating Permit (DWP-087A). The report presents monitoring results that equaled or exceeded the Safe Drinking Water Act final Primary Drinking Water Standards (PDWS) or screening levels, established by the U.S. Environmental Protection Agency, the South Carolina final Primary Drinking Water Standard for lead, or the SRS flagging criteria.

  10. Sanitary landfill groundwater monitoring report, Third Quarter 1999

    International Nuclear Information System (INIS)

    Chase, J.

    1999-01-01

    This report contains analytical data for samples taken during Third Quarter 1999 from wells of the LFW series located at the Sanitary Landfill at the Savannah River Site. The data are submitted in reference to the Sanitary Landfill Operating Permit. The report presents monitoring results that equaled or exceeded the Safe Drinking Water Act final Primary Drinking Water Standards or screening levels, established by the U.S. Environmental Protection Agency, the South Carolina final Primary Drinking Water Standard for lead, or the SRS flagging criteria

  11. Sanitary landfill groundwater monitoring report. Third quarter 1995

    International Nuclear Information System (INIS)

    1995-11-01

    This report contains analytical data for samples taken during third quarter 1995 from wells of the LFW series located at the Sanitary Landfill at the Savannah River Site (SRS). The data are submitted in reference to the Sanitary Landfill Operating Permit (DWP-087A). The report presents monitoring results that equaled or exceeded the Safe Drinking Water Act final Primary Drinking Water Standards (PDWS) or screening levels, established by the U.S. Environmental Protection Agency, the South Carolina final Primary Drinking Water Standard for lead, or the SRS flagging criteria

  12. Sanitary landfill energetic potential analysis: a real case study

    International Nuclear Information System (INIS)

    Desideri, Umberto; Di Maria, Francesco; Leonardi, Daniela; Proietti, Stefania

    2003-01-01

    Waste disposal represents an important problem in developed countries. Many different techniques are available to reduce the amount of waste production and its environmental impact. In most cases, sanitary landfills have been and continue to be one of the most common ways to dispose of urban and industrial wastes. It is well known how landfilling produces an important environmental drawback due to gaseous, liquid and solid emissions that are dangerous for the environment. Landfill biogas emissions contain mainly carbon dioxide and methane. In particular, the methane concentration can be higher than 50% by volume. This means that the calorific value of sanitary landfill biogas can be higher than 18,000 kJ/N m 3 . The utilization of such gas as fuel for electrical and thermal energy production can be an important way to reduce the landfill impact on the environment and represent an easy way to use a renewable energy source. In the following, the amount and composition of the biogas produced in a sanitary landfill situated in central Italy have been analysed. Experimental results have been discussed, and an energetic potential evaluation has been performed

  13. Sanitary landfill energetic potential analysis: a real case study

    Energy Technology Data Exchange (ETDEWEB)

    Desideri, Umberto E-mail: umberto.desideri@unipg.it; Di Maria, Francesco E-mail: fdm@unipg.it; Leonardi, Daniela; Proietti, Stefania

    2003-07-01

    Waste disposal represents an important problem in developed countries. Many different techniques are available to reduce the amount of waste production and its environmental impact. In most cases, sanitary landfills have been and continue to be one of the most common ways to dispose of urban and industrial wastes. It is well known how landfilling produces an important environmental drawback due to gaseous, liquid and solid emissions that are dangerous for the environment. Landfill biogas emissions contain mainly carbon dioxide and methane. In particular, the methane concentration can be higher than 50% by volume. This means that the calorific value of sanitary landfill biogas can be higher than 18,000 kJ/N m{sup 3}. The utilization of such gas as fuel for electrical and thermal energy production can be an important way to reduce the landfill impact on the environment and represent an easy way to use a renewable energy source. In the following, the amount and composition of the biogas produced in a sanitary landfill situated in central Italy have been analysed. Experimental results have been discussed, and an energetic potential evaluation has been performed.

  14. Interim Sanitary Landfill Groundwater Monitoring Report. 1997 Annual Report

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1998-01-01

    Eight wells of the LFW series monitor groundwater quality in the Steed Pond Aquifer (Water Table) beneath the Interim Sanitary Landfill at the Savannah River Site (SRS). These wells are sampled semiannually to comply with the South Carolina Department of Health and Environmental Control Modified Municipal Solid Waste Permit 025500-1120 (formerly dWP-087A) and as part of the SRS Groundwater Monitoring Program.

  15. Sanitary landfill groundwater monitoring report: First quarter 1997

    Energy Technology Data Exchange (ETDEWEB)

    Chase, J.A.

    1997-05-01

    This report contains analytical data for samples taken during first quarter 1997 from wells of the LFW series located at the Sanitary Landfill at the Savannah River Site (SRS). The data are submitted in reference to the Sanitary Landfill Operating permit (DWP-087A). The report presents monitoring results that equaled or exceeded the Safe Drinking Water Act final primary Drinking Water Standards (PDWS) or screening levels, established by the U.S. Environmental Protection Agency, the South Carolina final Primary Drinking Water Standard for lead, or the SRS flagging criteria. Wells LFW6R, LFW8R, LFW10A, LFW18, LFW21, and LFW23R were not sampled due to their proximity to the Sanitary Landfill Closure Cap activities. Wells LFW61D and LFW62D are Purge Water Containment Wells and contain mercury. These wells were not sampled since the purge water cannot be treated at the M-1 Air Stripper until the NPDES permit for the stripper is modified.

  16. US EPA record of decision review for landfills: Sanitary landfill (740-G), Savannah River Site

    Energy Technology Data Exchange (ETDEWEB)

    1993-06-01

    This report presents the results of a review of the US Environmental Protection Agency (EPA) Record of Decision System (RODS) database search conducted to identify Superfund landfill sites where a Record of Decision (ROD) has been prepared by EPA, the States or the US Army Corps of Engineers describing the selected remedy at the site. ROD abstracts from the database were reviewed to identify site information including site type, contaminants of concern, components of the selected remedy, and cleanup goals. Only RODs from landfill sites were evaluated so that the results of the analysis can be used to support the remedy selection process for the Sanitary Landfill at the Savannah River Site (SRS).

  17. US EPA record of decision review for landfills: Sanitary landfill (740-G), Savannah River Site

    International Nuclear Information System (INIS)

    1993-06-01

    This report presents the results of a review of the US Environmental Protection Agency (EPA) Record of Decision System (RODS) database search conducted to identify Superfund landfill sites where a Record of Decision (ROD) has been prepared by EPA, the States or the US Army Corps of Engineers describing the selected remedy at the site. ROD abstracts from the database were reviewed to identify site information including site type, contaminants of concern, components of the selected remedy, and cleanup goals. Only RODs from landfill sites were evaluated so that the results of the analysis can be used to support the remedy selection process for the Sanitary Landfill at the Savannah River Site (SRS)

  18. Tritium distribution in leachates from domestic solid waste landfills

    International Nuclear Information System (INIS)

    Park, Soon Dal; Kim, Jung Suk; Joe, Kih Soo; Kim, Jong Gu; Kim, Won Ho

    2004-01-01

    It is for the purpose of investigating the tritium distribution in the leachates, the raw and treated leachates and the condensates of the methane gas, which have occurred from domestic solid waste landfills. Also it aims to measure the tritium distribution level on the colloid size of the leachates, the raw and treated leachates. It was found that the major inorganic contaminants of the leachates were Na, K, Ca, Mg, NH 4 + -N and Cl - . The mean tritium level of the raw leachates of the investigated 13 landfill sites for 6 months was 17∼1196 TU. It corresponded to a several scores or hundreds of magnitude higher value than that of the normal environmental sample level except for two landfill sites. Also such a high concentration of the tritium was found in the treated leachates and methane gas condensates as well. Nevertheless it is important to emphasize that the tritium level which was found in this research is about 100 times lower than the tritium limit for the drinking water quality. And most of the tritium existed in the dissolved colloid of the leachate of which the colloid size is below 0.45 μm. Also, according to the tritium analysis results of the leachates after filtration with 0.45μm membrane filter for some landfills, it is likely that some tritium of the leachate would be distributed in a colloid size over 0.45μm. In general the relationship between the tritium and other contaminants in the raw leachate was low, but it was relatively high between the tritium and TOC. However, the tritium content in the leachate had no meaningful relationship with the scale, hydrological characteristics and age of the landfill

  19. MATERIALS FOR THE FINAL COVER OF SANITARY LANDFILLS

    Directory of Open Access Journals (Sweden)

    Davorin Kovačić

    1994-12-01

    Full Text Available The paper deals with the selection of materials for the sea¬ling layer in the final cover of sanitary landfills. The sealing la¬yer is the most critical component of the final cover. Its role is to minimize percolation of water through the final cover. Ma¬terials used for the construction of the sealing layer are either of mineral origin (compacted clay or geosynthetic (geomem¬brane. They are most often used in combination creating com¬posite liners. Recently alternative materials are also used like paper mill sludge or discarded swelling clay.

  20. MATERIALS FOR THE FINAL COVER OF SANITARY LANDFILLS

    OpenAIRE

    Davorin Kovačić

    1994-01-01

    The paper deals with the selection of materials for the sea¬ling layer in the final cover of sanitary landfills. The sealing la¬yer is the most critical component of the final cover. Its role is to minimize percolation of water through the final cover. Ma¬terials used for the construction of the sealing layer are either of mineral origin (compacted clay) or geosynthetic (geomem¬brane). They are most often used in combination creating com¬posite liners. Recently alternative materials are also ...

  1. Quality prediction of a leached produced in a sanitary landfills

    International Nuclear Information System (INIS)

    Agudelo Garcia, Ruben Alberto; Garcia R, Francisco Fernando; Rivera Mesa, Carolina

    2002-01-01

    This paper presents a mathematical model developed with the purpose of predicting the concentration of pollutants in the leached produced by the biological degradation of the solid wastes disposed in sanitary landfills. The model consists in a kinetic equation of first level, able to describe the degradation of the organic matter being the solid residuals. This model was calibrated using the results obtained from six laboratory scale lysimeters operated under different conditions. The model predicted the concentration of the pollutants in the leached with an accuracy of 94%

  2. Sanitary landfill groundwater quality assessment plan Savannah River Site

    Energy Technology Data Exchange (ETDEWEB)

    Wells, D.G.; Cook, J.W.

    1990-06-01

    This assessment monitoring plan has been prepared in accordance with the guidance provided by the SCDHEC in a letter dated December 7, 1989 from Pearson to Wright and a letter dated October 9, 1989 from Keisler to Lindler. The letters are included a Appendix A, for informational purposes. Included in the plan are all of the monitoring data from the landfill monitoring wells for 1989, and a description of the present monitoring well network. The plan proposes thirty-two new wells and an extensive coring project that includes eleven soil borings. Locations of the proposed wells attempt to follow the SCDHEC guidelines and are downgradient, sidegradient and in the heart of suspected contaminant plumes. Also included in the plan is the current Savannah River Site Sampling and Analysis Plan and the well construction records for all of the existing monitoring wells around the sanitary landfill.

  3. Sanitary Landfill Groundwater Monitoring Report, Fourth Quarter 1999 and 1999 Summary

    International Nuclear Information System (INIS)

    Chase, J.

    2000-01-01

    A maximum of thirty eight-wells of the LFW series monitor groundwater quality in the Steed Pond Aquifer (Water Table) beneath the Sanitary Landfill Area at the Savannah River Site (SRS). These wells are sampled quarterly to comply with the South Carolina Department of Health and Environmental Control Domestic Water Permit DWP-087A and as part of the SRS Groundwater Monitoring Program. Iron (Total Recoverable), Chloroethene (Vinyl Chloride) and 1,1-Dichloroethane were the most widespread constituents exceeding the Final Primary Drinking Water Standards during 1999. Trichloroethylene, 1,1-Dichloroethylene, 1,2-Dichloroethane, 1,4-Dichlorobenzene, Aluminum (Total Recoverable), Benzene, cis-1,2-Dichloroethylene, Dichlorodifluoromethane, Dichloromethane (Methylene Chloride), Gross Alpha, Mercury (Total Recoverable), Nonvolatile Beta, Tetrachloroethylene, Total Organic Halogens, Trichlorofluoromethane, Tritium also exceeded standards in one or more wells. The groundwater flow direction in the Steed Pond Aquifer (Water Table) beneath the Sanitary Landfill is to the southeast (universal transverse Mercator coordinates). The flow rate in this unit was approximately 144.175 ft/year during first quarter 1999 and 145.27 ft/year during fourth quarter 1999

  4. Interim sanitary landfill groundwater monitoring report. 1996 Annual report

    International Nuclear Information System (INIS)

    Bagwell, L.A.

    1997-01-01

    Eight wells of the LFW series monitor groundwater quality in the Steed Pond Aquifer (Water Table) beneath the Interim Sanitary Landfill at the Savannah River Site. These wells are sampled semiannually to comply with the South Carolina Department of Health and Environmental Control Modified Municipal Solid Waste Permit 025500-1120 and as part of the SRS Groundwater Monitoring Program. Trichlorofluoromethane and 1,1,1-trichloroethane were elevated in one sidegradient well and one downgradient well during 1996. Zinc was elevated in three downgradient wells and also was detected in the associated laboratory blanks for two of those wells. Specific conductance was elevated in one background well and one sidegradient well. Barium and copper exceeded standards in one sidegradient well, and dichloromethane (a common laboratory contaminant) was elevated in another sidegradient well. Barium, copper, and dichloromethane were detected in the associated blanks for these wells, also. The groundwater flow direction in the Steed Pond Acquifer (Water Table) beneath the Interim Sanitary Landfill was to the southeast (universal transverse Mercator coordinates). The flow rate in this unit was approximately 210 ft/year during first quarter 1996 and 180 ft/yr during third quarter 1996

  5. Sanitary Landfill groundwater monitoring report. Fourth quarterly report and summary 1993

    Energy Technology Data Exchange (ETDEWEB)

    1994-02-01

    Fifty-seven wells of the LFW series monitor groundwater quality in Steed Pond Aquifer (Water Table) beneath the Sanitary Landfill at the Savannah River Site (SRS). These wells are sampled quarterly to comply with the South Carolina Department of Health and Environmental Control Domestic Waste Permit DWP-087A and as part of the SRS Groundwater Monitoring Program. Dichloromethane a common laboratory contaminant, and trichloroethylene were the most widespread constituents exceeding standards during 1993. Benzene, chlorobenzene, chloroethene 1,2 dichloroethane, 1,1-dichloroethylene, 1,2-dichloropropane, gross alpha, lindane, mercury, tetrachloroethylene, and tritium also exceeded standards in one or more wells. No groundwater contaminants were observed in wells screened in the lower section of Steed Pond Aquifer.

  6. Study on the Environmental Tritium in Surrounding of Bantar Gebang - Bekasi and Leuwigajah - Bandung Landfill Areas

    International Nuclear Information System (INIS)

    Satrio; Syafalni; Evarista Ristin

    2004-01-01

    The investigation of environmental tritium distribution in surrounding of Bantar Gebang - Bekasi and Leuwigajah landfill areas has been carried out. The aim of this investigation was to know tritium concentration in surrounding of both landfill areas. Normally, tritium concentration in the nature is around 0-5 TU. The results of this investigation showed that the tritium concentration in both shallow groundwater of both landfill areas were still in the range of its normal limit, whereas tritium concentration in stream along both landfill areas and leached water showed higher value. Tritium concentration in deep groundwater of Bantar Gebang landfill showed about the zero value, it means is the normal condition. (author)

  7. Control and monitoring of landfill gas underground migration at the City of Montreal sanitary landfill site

    International Nuclear Information System (INIS)

    Heroux, M.; Turcotte, L.

    1997-01-01

    The proposed paper covers the various aspects of control and monitoring of potential landfill gas (LFG) migration through soil voids or rock fractures at the City of Montreal sanitary landfill site. It depicts the social, geographical and geological context and presents a brief history of the landfill site. It describes the LFG collecting system and LFG migration monitoring equipment and programs. Finally it presents monitoring data taken over last few years. The landfill site is located in a well populated urban area. Since 1968, about 33 million metric tons of domestic and commercial waste have been buried in a former limestone quarry. Because of houses and buildings in the vicinity, 100 m in some locations, LFG underground migration is a major risk. LFG could indeed infiltrate buildings and reach explosive concentrations. So it must be controlled. The City of Montreal acquired the site in 1988 and has progressively built a LFG collecting system, composed of more than 288 vertical wells, to pump out of the landfill 280 million m 3 of gas annually. To verify the efficiency of this system to minimize LFG underground migration, monitoring equipment and programs have also been designed and put into operation. The monitoring network, located all around the landfill area, is composed of 21 well nests automated to monitor presence of gas in the ground in real time. In addition, 55 individual wells, where manual measurements are made, are also available. To complete the monitoring program, some measurements are also taken in buildings, houses and underground utilities in the neighborhood of the site. Monitoring data show that LFG underground migration is well controlled. They also indicate significant decrease of migration over the years corresponding to improvements to the LFG collecting system

  8. Ecotoxicological evaluation of leachate from the Limeira sanitary landfill with a view to identifying acute toxicity

    OpenAIRE

    José Euclides Stipp Paterniani; Ronaldo Teixeira Pelegrini; Núbia Natália de Brito Pelegrini

    2007-01-01

    Final disposal of solid waste is still a cause for serious impacts on the environment. In sanitary landfills, waste undergoes physical, chemical, and biological decomposition, generating biogas and leachate. Leachate is a highly toxic liquid with a very high pollution potential. The purpose of this work is to evaluate toxicity of in natura leachate samples collected from Limeira Sanitary Landfill, in Limeira, SP. The ecotoxicological evaluation comprised acute toxicity assays using as test or...

  9. Determination of the gaseous emission of toxic substances in the Curva de Rodas sanitary landfill in Medellin

    International Nuclear Information System (INIS)

    Garcia Renteria, Francisco Fernando; Agudelo Garcia, Ruben Alberto

    2005-01-01

    Results of the investigation conducted at the sanitary landfill Curva de Rodas, aimed to determine the emission and migration of toxic substances are presented. Traces of benzene, toluene, hexane, vinyl chloride and xylene were found. Concentrations of these substances were, however, below threshold limits at the landfill and below detectable limits in the air of populated areas adjacent to the sanitary landfill

  10. Innovative in situ treatment approach for DOE Savannah River Site Sanitary Landfill

    International Nuclear Information System (INIS)

    Knapp, J.; Suer, A.

    1994-01-01

    Pursuant to a settlement agreement reached between the US Department of Energy (DOE) and the South Carolina Department of Health and Environmental Control (SCDHEC), the Sanitary Landfill at the Savannah River Site will be closed. This paper addresses the approach used to select the innovative in situ treatment alternative for the groundwater and the vadose zone associated with the landfill

  11. Biogas recuperation in sanitary landfills; Recuperacao de biogas em aterros sanitarios

    Energy Technology Data Exchange (ETDEWEB)

    Lima, Luiz Mario Queiroz [Companhia Paulista de Forca e Luz (CPFL), Campinas, SP (Brazil)

    1988-12-31

    This work shoes a retrospective about recovering biogas activity in sanitary landfill, where in the genesis of methane is emphasized. Also, a conceptual review was made and discussed focusing the technological aspects of the landfill methods. Further, two important aspects of the genesis of methane were discussed: the enhancement mechanisms for acceleration of the formation of methane and the production of biological input from leachate in landfill. (author) 36 refs., 3 figs.

  12. FLORIDA HAZARDOUS WASTE AND SANITARY LANDFILL REPORT, COUNTY DATA. GENERATOR DATA AND CHARACTERISTICS OF SANITARY LANDFILLS. PART 2. COUNTIES: BROWARD, CALHOUN, CHARLOTTE, CITRUS, CLAY, COLLIER

    Science.gov (United States)

    The report provides data on the use of sanitary landfills (Subtitle D facilities) for hazardous waste disposal in Florida by small quantity generators. It consists of eleven parts including a part called Study Area Data which contains the data aggregated across the counties cover...

  13. Methodology for the design of Santa Rosa de Cabal sanitary landfill, Risaralda

    International Nuclear Information System (INIS)

    Tabares, J; Orozco, J

    1992-01-01

    In 1987 the Regional Autonomous Corporation of Risaralda, CARDER and the Risaralda Government, they signed a cooperation agreement, in order to endowing from sanitary landfill to the municipalities of the department. In the mark of this agreement it was carried out the design of Santa Rosa's sanitary landfill, that with near 50.000 inhabitants it is constituted in the third city of the department. This city generates some 25 tons/day of garbage that at the present time are heady directly to the waters of San Eugenio River. The present work contains the most important methodological aspects in the design of the sanitary landfill and some comments about the approaches ideal Vs real approaches of selection of places

  14. SOIL AND “CERRADO” TREES NUTRIENTS AND METALS IN ADJACENT SANITARY LANDFILL AREA

    OpenAIRE

    Otacílio Antunes Santana; José Imanã Encinas; Rodrigo Studart Corrêa; Antônio Felipe Couto Júnior

    2008-01-01

    This research verified the influence of a Sanitary Landfill located at the Jockey Club of the Brasilia City (JCB) on the chemical contents in the tree species of “Cerrado”. Six 25 x 500 m blocks were established in the PNB to sample the soil and the trees to chemical analysis. Three blocks were established near the landfill area and three in the control area. Nitrogen, phosphorus, potassium, calcium, lead, chromium, copper and mercury were analyzed. The highest nutrients and metals concentrat...

  15. Evaluation of new location of Isfahan′s sanitary landfill site with Oleckno method

    OpenAIRE

    Maryam Salimi; Afshin Ebrahimi; Afsane Salimi

    2013-01-01

    Aims: The objective of present study was to evaluate the new location of Isfahan solid waste sanitary landfill using Geographical Information System (GIS) based on the Oleckno index method (OIM). Materials and Methods: This study was on the field- and library-based data collection and surveys of relevant data. Assessment parameters included average annual rainfall, soil type and ground water beneath and adjucent to the landfill site. To analyze data, ArcGIS version 9.3 was used. Resul...

  16. The removal of ammonia from sanitary landfill leachate using a series of shallow waste stabilization ponds.

    Science.gov (United States)

    Leite, V D; Pearson, H W; de Sousa, J T; Lopes, W S; de Luna, M L D

    2011-01-01

    This study evaluated the efficiency of a shallow (0.5 m deep) waste stabilization pond series to remove high concentrations of ammonia from sanitary landfill leachate. The pond system was located at EXTRABES, Campina Grande, Paraiba, Northeast Brazil. The pond series was fed with sanitary landfill leachate transported by road tanker to the experimental site from the sanitary landfill of the City of Joao Pessoa, Paraiba. The ammoniacal-N surface loading on the first pond of the series was equivalent to 364 kg ha(-1) d(-1) and the COD surface loading equivalent to 3,690 kg ha(-1) d(-1). The maximum mean ammonia removal efficiency was 99.5% achieved by the third pond in the series which had an effluent concentration of 5.3 mg L(-1) ammoniacal-N for an accumulative HRT of 39.5 days. The removal process was mainly attributed to ammonia volatilization (stripping) from the pond surfaces as a result of high surface pH values and water temperatures of 22-26°C. Shallow pond systems would appear to be a promising technology for stripping ammonia from landfill leachate under tropical conditions.

  17. SOIL AND “CERRADO” TREES NUTRIENTS AND METALS IN ADJACENT SANITARY LANDFILL AREA

    Directory of Open Access Journals (Sweden)

    Otacílio Antunes Santana

    2008-09-01

    Full Text Available This research verified the influence of a Sanitary Landfill located at the Jockey Club of the Brasilia City (JCB on the chemical contents in the tree species of “Cerrado”. Six 25 x 500 m blocks were established in the PNB to sample the soil and the trees to chemical analysis. Three blocks were established near the landfill area and three in the control area. Nitrogen, phosphorus, potassium, calcium, lead, chromium, copper and mercury were analyzed. The highest nutrients and metals concentrations in soil were sampled in landfill adjacent area. The significant, crescent and directly proportional relationship (R2 > 0.80; p < 0.001 were observed between the elements concentration analyzed in soil with the leaves tissues. Therefore, the studied landfill presences increased nutrients and metals concentrations in soil and leaf tissue, fact that did not occur in the control area.

  18. Life cycle analysis of sanitary landfill and incineration of municipal solid waste

    Institute of Scientific and Technical Information of China (English)

    倪晋仁; 韦洪莲; 刘阳生; 赵智杰

    2002-01-01

    Environmental consequences from sanitary landfill as well as incineration with power generation were compared in terms of life cycle analysis (LCA) for Laohukeng Waste-disposal Plant that is under consideration in Shenzhen. A variety of differences will be resulted from the two technologies, from which the primary issue that affects the conclusion is if the compensatory phase in power generation can be properly considered in the boundary definition of LCA. Upon the compensatory phase is taken into account in the landfill system, the negative environmental consequences from the landfill will be more significant than those from the incineration with power generation, although the reversed results can be obtained as the compensatory phase is neglected. In addition, mitigation of environmental impacts through the pollutant treatment in the incineration process will be more effective than in the landfill process.

  19. Environmental characterization foundry sands used in sanitary landfills

    International Nuclear Information System (INIS)

    Domingues, L.G.F.; Ferreira, G.C.S.; Pires, M.S.G.; Teixeira, I.; Carnin, R.; Sarro, W.S.

    2016-01-01

    The national solid waste policy recommends reducing solid waste generation and reusing them in different applications. Preliminary studies show that the foundry sand generated from cast metal parts undercut, has excellent applicability in grain size stabilization of soils for geotechnical functions, and therefore, should not be discarded as waste. This study aimed at environmental characterization of two lots of waste foundry sand (WFS), from different industries, to the particle size stabilization of a clayey soil for use in coverage of solid waste in landfills. The methodology included physicochemical characterization tests (grain size, permeability, XRF and heavy metals) and environmental (NBR 10004: 2004, NBR 10005: 2004, NBR 10006: 20004 and acute toxicity with Vibrio fischeri). The results prove the environmental viability of using these lots of WFS as functional material in the composition of landfills. (author)

  20. Final Disposal of Solid Waste in Sanitary Landfills and Human Health

    Directory of Open Access Journals (Sweden)

    Gustavo Silveira Graudenz

    2012-06-01

    Full Text Available This article presents a critical review of scientific literature on waste sanitary landfills and its effects on human health, with an approach to the adverse effects that are most commonly associated to living near waste landfills. The health variables included were low birth weight, congenital abnormalities, some types of neoplasms, allergies, asthma and other respiratory diseases using the MEDLINE, LILACS and CAPES’ thesis post graduation database for systematic review. In spite of the fact that some studies indicate positive asssociation between health risks and living close to landfills, the majority of the studies, mainly the most recent ones, do not demonstrate a significant health risk in this condition. Some common limitations and bias of the work in the field are discussed. The lack of direct quantification of exposure, lack of prospective approach and no comparaison of the different types and quality of management of the residues are common limitations to most studies. So far, there is weak evidence to support significant epidemiological health risks associated to landfills. More interdisciplinary research should improve the knoledge of the health risks related to living in the proximity to sanitary landfills.

  1. Evaluation of new location of Isfahan′s sanitary landfill site with Oleckno method

    Directory of Open Access Journals (Sweden)

    Maryam Salimi

    2013-01-01

    Full Text Available Aims: The objective of present study was to evaluate the new location of Isfahan solid waste sanitary landfill using Geographical Information System (GIS based on the Oleckno index method (OIM. Materials and Methods: This study was on the field- and library-based data collection and surveys of relevant data. Assessment parameters included average annual rainfall, soil type and ground water beneath and adjucent to the landfill site. To analyze data, ArcGIS version 9.3 was used. Results: In 2010 the total rainfall in the landfill location was less than 150 mm/year. The soil type was clay loam, and the average distance from the floor of the landfill to the groundwater level was 3-9 meters. As calculated results showed that, the Oleckno index (OI score in the study area was 40. Conclusion: The new Isfahan′s sanitary solid waste landfill site had a good OI and the possibility of contamination of groundwater by leachate production based on this method also was low.

  2. Effects of supplement with sanitary landfill leachate in gas exchange of sunflower (Helianthus annuus L.) seedlings under drought stress.

    Science.gov (United States)

    Nunes Junior, Francisco H; Freitas, Valdineia S; Mesquita, Rosilene O; Braga, Brennda B; Barbosa, Rifandreo M; Martins, Kaio; Gondim, Franklin A

    2017-10-01

    Sanitary landfill leachate is one of the major problems arising from disposal of urban waste. Sanitary landfill leachate may, however, have use in agriculture. This study, therefore, aimed to analyze initial plant growth and gas exchange in sunflower seedlings supplemented with sanitary landfill leachate and subjected to drought stress through variables of root fresh mass (RFM), shoot fresh mass (SFM), total fresh mass (TFM), relative chlorophyll content (CL), stomatal conductance (g s ), transpiration rate (E), net photosynthetic rate (A), ratio of internal to external CO 2 concentration (Ci/Ca),water use efficiency (EUA), instantaneous carboxylation efficiency (A/Ci), and electron transport rate (ETR). The experimental design was a completely randomized 2 (irrigated and non-irrigated) × 4 (sand, sand + 100 kg N ha -1 organic fertilizer, sand + 100 kg N ha -1 sanitary landfill leachate, and sand + 150 kg N ha -1 sanitary landfill leachate) factorial with five replicates. Under drought stress conditions, leachate treatment supplemented with 100 kg N ha -1 exhibited higher plant fresh weights than those of the treatment containing 150 kg N ha -1 . Increases in fresh mass in plant treatments supplemented with 100 and 150 kg N ha -1 sanitary landfill leachate were related to higher photosynthetic rates.

  3. Energetic utilization of biogas arising of sanitary landfills

    International Nuclear Information System (INIS)

    Calderon U, R.

    1995-01-01

    The biogas is the gaseous product that is obtained from the fermentation of biodegradable organic matter; this process is known as anaerobic digestion. In this exposition, the formation process of biogas is described in its three continuos phases: 1. Hydrolysis phase, 2. Phase of acid generation and the acetic acid generation and 3. Phase of methane generation. Also, the biogas composition (methane, carbon dioxide, hydrogen, nitrogen, oxygen and traces) is present. Different types of anaerobic digestion as discontinuous digestion, continuo digestion, digestion with suspended biomass, digestion with adhered biomass, and digestion of two phases are shown. Finally, the process that occur in a landfill and its different phases of aerobic and anaerobic decomposition, are describe from its initial stage until the biogas generation

  4. Conceptual model elaboration for the safety assessment of phosphogypsum use in sanitary landfills

    International Nuclear Information System (INIS)

    Cota, Stela D.; Braga, Leticia T.P.; Jacomino, Vanusa F.

    2009-01-01

    Phosphogypsum is a by-product of the phosphatic fertilizer production from the beneficiation of phosphate minerals (apatites). Produced in large quantities throughout the world and stored temporally in stacks, the final destination of this product is nowadays a subject of investigation. Due to the presence of radionuclides ( 226 Ra, 232 Th and 40 K, mainly), possible applications for the phosphogypsum must be verified for radiological safety. The goal of this paper was to elaborate a representative water flow conceptual model of a sanitary landfill for the safety assessment of the impact of using phosphogypsum as a cover material. For this, the ground water flow in variably saturated conditions and solute transport model HYDRUS-2D has been used for simulating the impact in the saturated zone of potential radionuclides leaching. The conceptual model was developed by collecting and analyzing the data from environmental license documentation of municipal sanitary landfills located on the State of Minas Gerais, Brazil. In order to fulfill the requirements of HDRUS-2D model in terms of the necessary parameters, the physical characteristics and typical configuration of the landfills, as well as the hydrogeological parameters of soils and aquifers related to the local of placement of the landfills, were taken in account for the formulation of the conceptual model. (author)

  5. Post-remediation use of macrophytes as composting materials for sustainable management of a sanitary landfill.

    Science.gov (United States)

    Song, Uhram

    2017-04-03

    To increase the remediation ability and life expectancy of a leachate channel in a sanitary landfill, the plants used for remediation were composted as a post-remediation management technique. Phragmites australis or Typha angustifolia used for phytoremediation in a landfill leachate channel was harvested and used as a co-composting material with sewage sludge. The macrophyte compost was applied to the slope of a landfill on which plants were introduced for revegetation and to plants grown in pots to test for acute effects of the compost. The compost of the macrophytes successfully increased soil moisture and nutrient contents both on the landfill slope and in the soil of the pot experiment. Additionally, the rates of photosynthesis and the nutrient contents increased for plants grown in macrophyte compost. Thus, the revegetation or restoration management of the landfill would improve with the macrophyte compost used as a soil conditioner. The harvest of the macrophytes has the additional benefit of improving the remediation function of the leachate channel. Therefore, to sustainably manage both the leachate channel and the landfill, the composting of post-remediation macrophytes is an environmentally friendly and economically affordable method.

  6. Modelization of Biogas production in Sanitary landfills; Modelizacion de la produccion de Biogas en vertederos controlados

    Energy Technology Data Exchange (ETDEWEB)

    Rodriguez-Iglesias, J.; Castrillon, L.; Maranon, E.; Sastre, H. [Universidad de Oviedo (Spain)

    2000-07-01

    Amongst all the different alternatives for the eliminator or treatment of MSW (Municipal Solid Waste), sanitary landfills is probably the one that is most widely employed to date, due to its economic advantages. With the coming into effect of the Spanish Containers and Packaging Law, alongside that of the Council Directive 1999/31/CE, concerning waste disposal, this situation will be substantially modified. At the same time, the application of said Directive will influence the amount of biogas generated in landfills. The present research work a study of the influence that the aforementioned Directive will have on the production of biogas in a sanitary landfill which currently disposes of around 400.000 Tm/year of MSW, 52% of which is easily biodegradable organic matter. The model proposed by Marticorena was applied and the kinetic parameters, MPO and d, were experimentally obtained by means of a pilot-plant study of MSW anaerobic degradation, the values employed being 173 Nm3 of biogas/Tm of the organic fraction of MSW for MPO, and 3 years for d. The results obtained in the model are compared with those obtained experimentally at the COGERSA landfill, Asturias, Spain. Twenty wells were chosen to analyse the production of biogas, giving an overall average yield of 70%. In 1999, around 4,100 m''3/h of biogas were extracted at the COGERSA landfill. Application of the model gave an estimation for 1999 of an average production of 5,369 m''3/h giving a maximum yield in the extraction of biogas of around 75%. The difference between the two average yields obtained may be due to the fact that the model only takes into account the easily biodegradable organic fraction, whilst in the landfill, given that more time has passed, other substances with a longer period of degradation, such as paper and cardboard, may also be degraded. (Author) 10 refs.

  7. The organic geochemistry of a sanitary landfill leachate plume

    Science.gov (United States)

    Barker, J. F.; Tessmann, J. S.; Plotz, P. E.; Reinhard, M.

    1986-02-01

    Leachate from the North Bay municipal landfill has contaminated an unconfined, sandy aquifer throughout the 700 m flow system from the site to a discharge zone at a creek. The major organic contaminants identified are aromatic hydrocarbons, especially substituted benzenes. The high groundwater velocity of about 75 m yr -1 and the low organic sorption properties of the sand have permitted non-transformed contaminants to spread throughout the total flow system. There is considerable temporal and spatial variability in groundwater chemistry. Most of the aqueous organic carbon has a nominal molecular weight of anarobic segment of the flow system 1,2,4-trimethylbenzene and 1,4-dichlorobenzene are equally persistent, but in the final, less anaerobic segment, the former appears to be degraded more rapidly than the latter. Contaminant distributions in aquifers reflect the results of a number of processes integrated in a complex manner and so are difficult to interpret in terms of specific processes. However, they do provide evidence for what processes are most significant in real groundwater systems and they will also provide critical tests of how well laboratory-derived information relates to real groundwater contamination situations.

  8. Mathematical numeric models for assessing the groundwater pollution from Sanitary landfills

    Science.gov (United States)

    Petrov, Vasil; Stoyanov, Nikolay; Sotinev, Petar

    2014-05-01

    Landfills are among the most common sources of pollution in ground water. Their widespread deployment, prolonged usage and the serious damage they cause to all of the elements of the environment are the reasons, which make the study of the problem particularly relevant. Most dangerous of all are the open dumps used until the middle of the twentieth century, from which large amounts of liquid emissions flowed freely (landfill infiltrate). In recent decades, the problem is solved by the construction of sanitary landfills in which they bury waste or solid residue from waste utilization plants. The bottom and the sides of the sanitary landfills are covered with a protective waterproof screen made of clay and polyethylene and the landfill infiltrate is led outside through a drainage system. This method of disposal severely limits any leakage of gas and liquid emissions into the environment and virtually eliminates the possibility of contamination. The main topic in the conducted hydrogeological study was a quantitative assessment of groundwater pollution and the environmental effects of re-landfilling of an old open dump into a new sanitary landfill, following the example of the municipal landfill of Asenovgrad, Bulgaria. The study includes: 1.A set of drilling, geophysical and hydrogeological field and laboratory studies on: -the definition and designation of the spatial limits of the main hydrogeological units; -identification of filtration parameters and migration characteristics of the main hydrogeological units; -clarifying the conditions for the sustentation and drainage of groundwater; -determininng the structure of the filtration field; -identifying and assessing the size and the extent of groundwater contamination from the old open dump . 2.Mathematical numeric models of migration and entry conditions of contaminants below the bottom of the landfill unit, with which the natural protection of the geological environment, the protective effect of the engineering

  9. Environmental review report of an electrical generation facility to be located at the Oaks Sanitary Landfill

    International Nuclear Information System (INIS)

    Goldstein, D.; Ross, J.; Mountain, D.; Kahal, M.

    1998-05-01

    The Bentech Group, Inc. (Bentech) applied for a certificate of public convenience and necessity (CPCN) to construct and operate an electric generating system at the Oaks Sanitary Landfill in Laytonsville, Maryland. The focus of the environmental review is to evaluate potential impacts of the proposed electric generation system to air quality, noise, terrestrial, ecological, ground water, surface water, socioeconomic, aesthetic, and cultural resources. This document presents the results of the environmental review analysis, and includes the State's recommended license conditions for operating the electric generating system, which the PSC incorporated into the CPCN

  10. Choice of noxious facilities: case of a solid waste incinerator versus a sanitary landfill in Malaysia.

    Science.gov (United States)

    Othman, Jamal; Khee, Pek Chuen

    2014-05-01

    A choice experiment analysis was conducted to estimate the preference for specific waste disposal technologies in Malaysia. The study found that there were no significant differences between the choice of a sanitary landfill or an incinerator. What matters is whether any disposal technology would lead to obvious social benefits. A waste disposal plan which is well linked or integrated with the community will ensure its acceptance. Local authorities will be challenged to identify solid waste disposal sites that are technically appropriate and also socially desirable.

  11. Tritium as tracer of groundwater pollution extension: case study of Andralanitra landfill site, Antananarivo-Madagascar

    Science.gov (United States)

    Ramaroson, Voahirana; Rakotomalala, Christian Ulrich; Rajaobelison, Joel; Fareze, Lahimamy Paul; Razafitsalama, Falintsoa A.; Rasolofonirina, Mamiseheno

    2018-05-01

    This study aims to understand the extension of groundwater pollution downstream of a landfill, Andralanitra-Antananarivo-Madagascar. Twenty-one samples, composed of dug well waters, spring waters, river, and lake, were measured in stable isotopes ( δ 2H, δ 18O) and tritium. Results showed that only two dug well waters, collected at the immediate vicinity of the landfill, have high tritium activities (22.82 TU and 10.43 TU), probably of artificial origin. Both upstream and further downstream of the landfill, tritium activities represent natural source, with values varying from 0.17 TU to 1.46 TU upstream and from 0.88 TU to 1.88 TU further downstream. Stable isotope data suggest that recharge occurs through infiltration of slightly evaporated rainfall. Using the radioactive decay equation, the calculated tracer ages related to two recent ground water samples collected down gradient of the landfill lay between [8-15] years and [4-7] years, taking into account the uncertainty of tritium measurements. For the calculation, a value of 2.36 TU was taken as A o. The latter was estimated based on similarity between stable isotope compositions of nearby spring and dug well waters as well as tritium activities of the local precipitation. Calculation of the tritium activities from the contaminated water point having 22.82 TU to further downstream using the calculated tracer ages showed values of one order of magnitude higher than the measured values. The absence of hydrological connection from the contaminated water point to further downstream the landfill would explain the lower tritium activities measured. Groundwater pollution seems to be limited to the closest proximity of the landfill.

  12. Grouting of fly ash in sanitary landfills; Injektering av flygaska i hushaallsavfallsdeponi

    Energy Technology Data Exchange (ETDEWEB)

    Wikman, Karin; Berg, Magnus [AaF-Energi och Miljoe AB, Stockhom (Sweden); Andreas, Lale; Lagerkvist, Anders [Luleaa Univ. of Technology (Sweden); Jannes, Sara; Tham, Gustav [Telge Aatervinning AB, Soedertaelje (Sweden); Sjoeblom, Rolf [Tekedo AB, Nykoeping (Sweden)

    2003-10-01

    The purpose of the study was to investigate the potential for stabilization of sanitary landfills by injecting fly ash. The method is supposed to prevent differential settlements in landfills and by that to counteract damages in the final cover. Injecting fly ash may also affect the chemical development in a positive way and prevent metal leaching. Pilot experiments at the Tveta waste recycling center (Tveta Aatervinningsanlaeggning) have been performed in order to estimate if the grouting technology is a suitable method for sanitary landfills. Fly ashes from the combustion of bio fuels were used in these tests. A literature study and laboratory experiments in order to prepare the field experiments were also part of the project. About 100 tons of ash slurry were injected during the pilot experiments. This corresponds to a filling degree of approximately 12-16 % of the available pores in the landfill body. As a result of the pilot test, the following conclusions can be drawn: Ash can be mixed with water to a pumpable slurry which can be injected without hardening inside the equipment. Neither the waste nor the grouting material caused a backpressure during the injection and nothing indicates that the injected ash deforms the landfilled waste. The ash-water-slurry flows through the voids in the waste easily. Thus, the ash may dispread quite far from the injection holes. Using a more powerful equipment backpressure and movements in the waste might occur. It was not possible to estimate the flow required for backpressure in this study. Large variations are possible but for safety reasons the maximal pressure should be limited with regard to the expected stability in the actual area. The grouted ash will harden within the landfill body within a couple of days. It accumulates in hard but brittle lumps, which may result in an increased stability of the landfill. Further studies are necessary in order to evaluate how the stability is affected and what amounts of ash are

  13. Sanitary landfill leachate as a source of nutrients on the initial growth of sunflower plants

    Directory of Open Access Journals (Sweden)

    Francisco H. Nunes Júnior

    Full Text Available ABSTRACT The aim of this study was to evaluate the initial growth of sunflower seedlings under different concentrations of sanitary landfill leachate, considering the feasibility of its use as source of nutrients for agricultural production. Biometric and vigor variables were analyzed through the measurements of collar diameter, shoot height, number of leaves and shoot and root fresh and dry matters, from January to February 2015. The experimental design was completely randomized in a 5 x 4 factorial scheme: five leachate concentrations (0, 40, 60, 80 and 100 kg N ha-1 x four harvest periods (14, 21, 25 and 29 days after sowing, with five replicates each containing two plants. The data were subjected to analysis of variance and polynomial regression, and the results of the last harvest (29 DAS were compared by Tukey test (p ≤ 0.05. The use of sanitary landfill leachate increased all analyzed variables in sunflower plants when compared to the control plants (without leachate, especially in the treatment of 100 kg N ha-1. There was no inhibitory effect of the leachate on the initial growth of sunflower seedlings under adopted experimental conditions.

  14. Environmental impact assessment on the construction and operation of municipal solid waste sanitary landfills in developing countries: China case study

    DEFF Research Database (Denmark)

    Yang, Na; Damgaard, Anders; Lü, Fan

    2014-01-01

    An inventory of material and energy consumption during the construction and operation (C&O) of a typical sanitary landfill site in China was calculated based on Chinese industrial standards for landfill management and design reports. The environmental impacts of landfill C&O were evaluated through...... life cycle assessment (LCA). The amounts of materials and energy used during this type of undertaking in China are comparable to those in developed countries, except that the consumption of concrete and asphalt is significantly higher in China. A comparison of the normalized impact potential between...

  15. The determination of engineering parameters for the sanitary landfill, Savannah River Site

    International Nuclear Information System (INIS)

    McMullin, S.R.; Smalley, R.C.; Flood, P.J.

    1993-01-01

    The Savannah River Site is a 315 square mile, Department of Energy production facility located in western South Carolina. This facility has multiple operational areas which generate a variety of waste materials. Over the nearly 40 years of operation, sanitary wastes were deposited in a 60-acre, permitted solid waste disposal facility located on the site. Refuse and other clean wastes were deposited in shallow, slit trenches, ranging in size from 20 to 50 feet-wide and approximately 400 feet long. The historical depth of deposition appears to range between 12 and 15 feet below the ground surface. Recent changes in regulations has classified some wastes contained within the landfill as hazardous wastes, necessitating the closure of this facility as a RCRA hazardous waste management facility. The focus of this paper is to present the innovative techniques used to fully determine the engineering parameters necessary to reasonably predict future settlements, for input into the closure system design

  16. Characterization and anaerobic treatment of the sanitary landfill leachate in Istanbul.

    Science.gov (United States)

    Inanc, B; Calli, B; Saatci, A

    2000-01-01

    In this study, characterization and anaerobic treatability of leachate from Komurcuoda Sanitary Landfill located on the Asian part of Istanbul were investigated. Time based fluctuations in characteristics of leachate were monitored for an 8 month period. Samples were taken from a 200 m3 holding tank located at the lowest elevation of the landfill. COD concentrations have ranged between 18,800 and 47,800 mg/l while BOD5 between 6820 and 38,500 mg/L. COD and BOD5 values were higher in summer and lower in winter due to dilution by precipitation. On the other hand, it was quite interesting that such a dilution effect was not observed for ammonia. The highest ammonia concentration, 2690 mg/L was in November 1998. BOD5/COD ratio was larger than 0.7 for most samples indicating high biodegradability, and acidic phase of decomposition in the landfill. For anaerobic treatability, three different reactors, namely an upflow anaerobic sludge bed reactor, an anaerobic upflow filter and a hybrid bed reactor, were used. The anaerobic reactors were operated for more than 230 days and were continuing operation when this paper was prepared. Organic loading was increased gradually from 1.3 kg COD/m3.day to 8.2 kg COD/m3.day while hydraulic retention time was reduced from 2.4 days to 2.0 days. All the reactors showed similar performances against organic loadings with efficiencies between 80% and 90%. However the reactors have experienced high ammonia concentrations several times throughout the experimental period, and showed different inhibition levels. Anaerobic filter was the least affected reactor while UASB was the most. Hybrid bed reactor has exhibited a similar performance to anaerobic filter although not to the same degree.

  17. Report: the current situation of sanitary landfills in Brazil and the importance of the application of economic models

    OpenAIRE

    Oliveira Neto, Raúl; Otávio Petter, Carlos; Cortina Pallás, José Luís

    2009-01-01

    We present the development stage of the sanitary landfills in Brazil in the context of urban solid residue management, demonstrating the necessity and importance of the employment of economic models. In the article, a cost estimate model is proposed as the basis for studies to be applied by sector management, including the city council, companies, consultants and engineers, contributing to the choice of new areas, public bids, municipal consortia and private public partnerships. Peer Re...

  18. Utilisation of forage grasses for decontamination of spray-irrigated leachate from a municipal sanitary landfill

    Energy Technology Data Exchange (ETDEWEB)

    Menser, H.A.; Winant, W.M.; Bennett, O.L.; Lundberg, P.E.

    1979-01-01

    Spray irrigation was used to test the survival and efficiency of forage grasses as a concentrating mechanism for the inorganic waste elements in leachate from a municipal solid waste sanitary landfill. Lime (0.67 metric tonnes ha), rock phosphate, and superphosphate (each at 11.2 metric tonnes ha) were applied in a randomised complete block design to reed canarygrass Phalaris arundinacea L., tall fescue Festuca arundinacea Schreb., cv. Ky31, orchardgrass Dactylis glomerata L., bromegrass Bromus inermis Leyss., and bermudagrass Cynodon dactylon (L.) Pers. cvs. Midland and Tufcote. Leachate was applied by overhead rotary sprinklers in weekly 8-h applications from 22 October 1974 to 28 April 1975. The total application averages about 155 cm. Sprayed leachate contained about 500 ppM of Ca, 150 to 200 ppM of Na, Fe, and Cl, 50 to 100 ppM of Mn, K, Mg, and N, 2 to 5 ppM of Al, Sr, Zn, and P, and less than 0.5 ppM of Ni, Co, Cr, Cu, Pb, and Cd. Chemical oxygen demand (COD) decreased from approximately 7500 mg liter in water emerging from landfill drains to 5000 mg litre in sprayed leachate. Electroconductivity ranged from 3000 to 4000 ..mu..mhos cm and pH from 5.3 to about 5.5. Leachate irrigation appreciably increased Na, Fe, Mn, Cl, and S levels in all forages except orchardgrass. Lime significantly prevented Mn accumulation and benefited forage grass persistence. Reed canarygrass generally contained the highest levels of most elements and along with Tufcote bermudagrass was more leachate-tolerant than other grasses. Seasonal factors affected the uptake of several elements, e.g. Na, Fe, Mn, Zn, K and Co were significantly lower in regrowth cuttings as compared with first cuttings of Midland bermudagrass and reed canarygrass.

  19. Seasonal trends in vegetation and atmospheric concentrations of PAHs and PBDEs near a sanitary landfill

    Science.gov (United States)

    St-Amand, Annick D.; Mayer, Paul M.; Blais, Jules M.

    Spruce needle and atmospheric (gaseous and particulate-bound) concentrations were surveyed near a sanitary landfill from February 2004 to June 2005. The influence of several parameters such as temperature, relative humidity, wind speed and direction, as well as increased domestic heating during the winter was assessed. In general, polybrominated diphenyl ethers (PBDE) and polycyclic aromatic hydrocarbons (PAH) concentrations in spruce needles increased over time and decreased following snowmelt with a minimum coinciding with bud burst of deciduous trees. Atmospheric concentrations of PBDE and PAH, both particulate-bound and gaseous phase, were linked to daily weather events and thus showed more variability than those in spruce needles. Highest PAH concentrations were encountered during the winter, likely reflecting increased emission from heating homes. Pseudo Clausius-Clapeyron plots revealed higher PBDE gaseous concentrations with increasing temperature, but showed no correlation between PAH gaseous concentrations and temperature as this effect was obscured by seasonal emission patterns. Finally, air mass back trajectories and local wind directions revealed that particulate-bound PBDEs, along with both gaseous and particulate-bound PAHs were from local sources, whereas gaseous PBDEs were likely from distant sources.

  20. Electro-Fenton oxidation of reverse osmosis concentrate from sanitary landfill leachate: Evaluation of operational parameters.

    Science.gov (United States)

    Fernandes, Annabel; Labiadh, Lazhar; Ciríaco, Lurdes; Pacheco, Maria José; Gadri, Abdellatif; Ammar, Salah; Lopes, Ana

    2017-10-01

    The electro-Fenton oxidation of a concentrate from reverse osmosis of a sanitary landfill leachate, with an initial chemical oxygen demand (COD) of 42 g L -1 , was carried out using a carbon-felt cathode and a boron doped diamond anode. The influence of the applied current intensity, initial pH and dissolved iron initial concentration on the electro-Fenton process was assessed. For the experimental conditions used, results showed that the initial pH is the parameter that more strongly influences the current efficiency of the electro-Fenton process, being this influence more pronounced on the oxidation rate than on the mineralization rate of the organic matter. The increase in iron initial concentration was found to be detrimental, since the natural amount of iron present in the effluent, 73 mg L -1 of total iron and 61 mg L -1 of dissolved iron, was sufficient to ensure the electro-Fenton process at the applied intensities - 0.2-1.4 A. For the more favourable conditions studied, initial pH of 3 and natural iron concentration, it was found an increase in the organic load and nitrogen removals with the applied current intensity. For the highest current intensity applied, a COD removal of 16.7 g L -1 was achieved after 8-h experiments. Copyright © 2017 Elsevier Ltd. All rights reserved.

  1. Biogas from sanitary landfills for electricity production; Biogas de rellenos sanitarios para produccion de electricidad

    Energy Technology Data Exchange (ETDEWEB)

    Arvizu F, Jose L; Huacuz V, Jorge M. [Instituto de Investigaciones Electricas, Cuernavaca, Morelos (Mexico)

    2003-07-01

    There are many ways to eliminate the municipal solid wastes, but only a few help to treat them and to dispose of them suitably. Some of the forms to avoid the problems that the trash originate are: not to produce it, recycling it in a 100% or creating a fictitious market where its value is equal to or greater than the product that gave origin to it; in any case, these alternatives are not absolutely practical. The trash can be incinerated, be segregated, be recycled partially or also be arranged in sanitary landfills. Anyway, the trash has always existed and it will continue existing for sure. [Spanish] Existen muchas maneras de eliminar los residuos solidos municipales, pero solo unas pocas ayudan a tratarlos y disponerlos adecuadamente. Algunas de las formas para evitar los problemas que ocasiona la basura son: no produciendola, reciclandola en un 100% o creando un mercado ficticio donde su valor sea igual o mayor al del producto que le dio origen; en cualquier caso, estas alternativas no son del todo practicas. La basura tambien se puede incinerar, segregar, reciclar parcialmente o disponer en rellenos sanitarios. De cualquier manera, la basura siempre ha existido y seguramente seguira existiendo.

  2. Environmental impact assessment on the construction and operation of municipal solid waste sanitary landfills in developing countries: China case study.

    Science.gov (United States)

    Yang, Na; Damgaard, Anders; Lü, Fan; Shao, Li-Ming; Brogaard, Line Kai-Sørensen; He, Pin-Jing

    2014-05-01

    An inventory of material and energy consumption during the construction and operation (C&O) of a typical sanitary landfill site in China was calculated based on Chinese industrial standards for landfill management and design reports. The environmental impacts of landfill C&O were evaluated through life cycle assessment (LCA). The amounts of materials and energy used during this type of undertaking in China are comparable to those in developed countries, except that the consumption of concrete and asphalt is significantly higher in China. A comparison of the normalized impact potential between landfill C&O and the total landfilling technology implies that the contribution of C&O to overall landfill emissions is not negligible. The non-toxic impacts induced by C&O can be attributed mainly to the consumption of diesel used for daily operation, while the toxic impacts are primarily due to the use of mineral materials. To test the influences of different landfill C&O approaches on environmental impacts, six baseline alternatives were assessed through sensitivity analysis. If geomembranes and geonets were utilized to replace daily and intermediate soil covers and gravel drainage systems, respectively, the environmental burdens of C&O could be mitigated by between 2% and 27%. During the LCA of landfill C&O, the research scope or system boundary has to be declared when referring to material consumption values taken from the literature; for example, the misapplication of data could lead to an underestimation of diesel consumption by 60-80%. Copyright © 2014 Elsevier Ltd. All rights reserved.

  3. A study of the presence of methane and other gases at the Pulau Burung sanitary landfill site, Penang, Malaysia

    International Nuclear Information System (INIS)

    Roslanzairi Mostapa; Mohd Tadza Abdul Rahman; Kamarudin Samuding; Lakam Mejus; Mohd Rifaie Mohd Murtadza

    2006-01-01

    This paperwork explains the investigation and measurement of the presence of the landfill gases that is methane (CH 4 ) and other gases that include oxygen (O 2 ), carbon dioxide (CO 2 ), sulphur dioxide (SO 2 ), oxides of nitrogen (NO x ), chlorine (Cl 2 ), hydrogen cyanide (HCN) and hydrogen sulphide (H 2 S) that were carried out at the Pulau Burung Sanitary Landfill disposal site, Penang on the month of March and June 2005. The objectives of this study are to investigate the presence of methane which could contribute to the safety aspect on explosion hazard and discuss briefly the viability of methane for power generation. For this purpose, direct gas measurements were taken from 31 gas wells from the first phase of the landfill. Pulau Burung Sanitary Landfill which is located in the state of Penang, Malaysia with the amount of design volume capacity of 0.85 million m3 and received approximately 350 ton of solid waste per day. From the study, it was found that the concentration of CH 4 averagely ranges from 3.66 % vol to 65.96 % vol. Other gases concentrations are; CO 2 (1.46 %vol - 39.66 % vol), O 2 (0.4 %vol - 14.2 %vol), SO 2 (1.8 ppm - 8.6 ppm), NO x (0.14 ppm - 0.46 ppm), Cl 2 (0.1 ppm - 0.58 ppm), HCN (1 ppm - 138.4 ppm) and H 2 S (0.4 ppm - 140 ppm). Methane dilution down to Explosion Limit (EL) levels that is between 5% (Lower Explosion Limit, LEL) and 15% (Upper Explosion Limit, UEL) is always possible and could poses explosion risk at the site. The viability of power generation from methane gas depends on many factors which will be discussed further in this paper. Most of these factors will rely on the nature of the operation by the landfill operator. (Author)

  4. Public health assessment for Freeway Sanitary Landfill, Burnsville, Dakota County, Minnesota, Region 5. CERCLIS No. MND038384004. Final report

    International Nuclear Information System (INIS)

    1993-01-01

    The Freeway Sanitary Landfill National Priorities List (NPL) site in Burnsville, Minnesota is situated in the Lower Minnesota River Valley. Shallow groundwater beneath the site is contaminated with low levels of volatile organic hydrocarbons and heavy metals. Under current conditions, no human exposures to site-related contaminants are known to occur at levels of health concern. Based on currently available information, the Minnesota Department of Health concludes that the site poses an indeterminate public health hazard under current conditions because exposure to volatile gases released to the air is possible, but cannot be evaluated from the very limited information available. There are also a few physical hazards on the site which pose a risk of accident or injury if trespassing occurs. Otherwise, there are no indications that people have been, or are being, exposed to site-related contaminants at levels that would be of health concern. The Agency For Toxic Substances and Disease Registry (ATSDR) Health Activities Recommendation Panel has evaluated the Freeway Sanitary Landfill Public Health Assessment for appropriate follow-up activities. The Panel has recommended that health education be considered to assist site workers in better understanding their potential for exposure to landfill gases

  5. Leachate treatment system using constructed wetlands, Town of Fenton sanitary landfill, Broome County, New York. Final report

    Energy Technology Data Exchange (ETDEWEB)

    1993-11-01

    Municipal sanitary landfills generate leachate that New York State regulations require to be collected and treated to avoid contaminating surface water and groundwater. One option for treating leachate is to haul it to municipal wastewater treatment facility. This option may be expensive, may require excessive energy for transportation, and may require pretreatment to protect the receiving facility`s processes. An alternative is on-site treatment and discharge. Personnel from the Town of Fenton, New York; Hawk Engineering, P.C.; Cornell University; and Ithaca College designed, built, and operated a pilot constructed wetland for treating leachate at the Town of Fenton`s municipal landfill. The system, consisting of two overland flow beds and two subsurface flow beds has been effective for 18 months in reducing levels of ammonia (averaging 85% removal by volatilization and denitrification) and total iron (averaging 95% removal by precipitation and sedimentation), two key constituents of the Fenton landfill`s leachate. The system effects these reductions with zero chemical and energy inputs and minimal maintenance. A third key constituent of the leachate, manganese, apparently passes through the beds with minimal removal. Details and wetland considerations are described.

  6. Methodology for the design of Santa Rosa de Cabal sanitary landfill, Risaralda; Metodologia para el diseno del relleno sanitario de Santa Rosa de Cabal, Risaralda

    Energy Technology Data Exchange (ETDEWEB)

    Tabares, J; Orozco, J

    1992-07-01

    In 1987 the Regional Autonomous Corporation of Risaralda, CARDER and the Risaralda Government, they signed a cooperation agreement, in order to endowing from sanitary landfill to the municipalities of the department. In the mark of this agreement it was carried out the design of Santa Rosa's sanitary landfill, that with near 50.000 inhabitants it is constituted in the third city of the department. This city generates some 25 tons/day of garbage that at the present time are heady directly to the waters of San Eugenio River. The present work contains the most important methodological aspects in the design of the sanitary landfill and some comments about the approaches ideal Vs real approaches of selection of places.

  7. Identifying suitable sanitary landfill locations in the state of Morelos, México, using a Geographic Information System

    Science.gov (United States)

    Marín, Luis E.; Torres, Vicente; Bolongaro, Andrea; Reyna, José A.; Pohle, O.; Hernández-Espriú, A.; Chavarría, Jerónimo; García-Barrios, R.; Tabla, Hugo Francisco Parra

    GIS is a powerful tool that may help to better manage natural resources. In this paper, we present a GIS model developed for the state of Morelos as an aid to determine whether a potential site, Loma de Mejia, met the Mexican Federal Guidelines. The Mexican Government has established federal guidelines for sanitary landfill site selection (NOM-083-SERMARNAT-2003). These guidelines were translated into a water-based Geographic Information System and applied to the state of Morelos, Mexico. For these examples, we used the SIGAM® (Sistema de Información Geográfico del Agua en México; a water-based GIS for Mexico) which has at least 60 layers from the National Water Commission (CONAGUA), the national mapping agency (INEGI; Instituto Nacional de Estadística, Geografía e Informática), NASA, and academic institutions. Results show that a GIS is a powerful tool that may allow federal, state and municipal policy makers to conduct an initial regional site reconnaissance rapidly. Once potential sites are selected, further characterization must be carried out in order to determine if proposed locations are suitable or not for a sanitary landfill. Based on the SIGAM© software, the Loma de Mejia would not comply with the Mexican Federal Guidelines.

  8. Sustainable sanitary landfills for neglected small cities in developing countries: The semi-mechanized trench method from Villanueva, Honduras

    Energy Technology Data Exchange (ETDEWEB)

    Oakley, Stewart M., E-mail: soakley@csuchico.edu [Department of Civil Engineering, Chico State University, California State University, Chico, CA 95929 (United States); Jimenez, Ramon, E-mail: rjimenez1958@yahoo.com [Public Works, Municipality of Villanueva, Cortes (Honduras)

    2012-12-15

    Highlights: Black-Right-Pointing-Pointer Open dumping is the most common form of waste disposal in neglected small cities. Black-Right-Pointing-Pointer Semi-mechanized landfills can be a sustainable option for small cities. Black-Right-Pointing-Pointer We present the theory of design and operation of semi-mechanized landfills. Black-Right-Pointing-Pointer Villanueva, Honduras has operated its semi-mechanized landfill for 15 years. Black-Right-Pointing-Pointer The cost of operation is US$4.60/ton with a land requirement of 0.2m{sup 2}/person-year. - Abstract: Open dumping is the most common practice for the disposal of urban solid wastes in the least developed regions of Africa, Asia and Latin America. Sanitary landfill design and operation has traditionally focused on large cities, but cities with fewer than 50,000 in population can comprise from 6% to 45% of a given country's total population. These thousands of small cities cannot afford to operate a sanitary landfill in the way it is proposed for large cities, where heavy equipment is used to spread and compact the waste in daily cells, and then to excavate, transport and apply daily cover, and leachate is managed with collection and treatment systems. This paper presents an alternative approach for small cities, known as the semi-mechanized trench method, which was developed in Villanueva, Honduras. In the semi-mechanized trench method a hydraulic excavator is used for 1-3 days to dig a trench that will last at least a month before it is filled with waste. Trucks can easily unload their wastes into the trench, and the wastes compact naturally due to semi-aerobic biodegradation, after which the trenches are refilled and covered. The exposed surface area is minimal since only the top surface of the wastes is exposed, the remainder being covered by the sides and bottom of the trench. The surplus material from trench excavation can be valorized for use as engineering fill onsite or off. The landfill in

  9. Sustainable sanitary landfills for neglected small cities in developing countries: The semi-mechanized trench method from Villanueva, Honduras

    International Nuclear Information System (INIS)

    Oakley, Stewart M.; Jimenez, Ramón

    2012-01-01

    Highlights: ► Open dumping is the most common form of waste disposal in neglected small cities. ► Semi-mechanized landfills can be a sustainable option for small cities. ► We present the theory of design and operation of semi-mechanized landfills. ► Villanueva, Honduras has operated its semi-mechanized landfill for 15 years. ► The cost of operation is US$4.60/ton with a land requirement of 0.2m 2 /person-year. - Abstract: Open dumping is the most common practice for the disposal of urban solid wastes in the least developed regions of Africa, Asia and Latin America. Sanitary landfill design and operation has traditionally focused on large cities, but cities with fewer than 50,000 in population can comprise from 6% to 45% of a given country’s total population. These thousands of small cities cannot afford to operate a sanitary landfill in the way it is proposed for large cities, where heavy equipment is used to spread and compact the waste in daily cells, and then to excavate, transport and apply daily cover, and leachate is managed with collection and treatment systems. This paper presents an alternative approach for small cities, known as the semi-mechanized trench method, which was developed in Villanueva, Honduras. In the semi-mechanized trench method a hydraulic excavator is used for 1–3 days to dig a trench that will last at least a month before it is filled with waste. Trucks can easily unload their wastes into the trench, and the wastes compact naturally due to semi-aerobic biodegradation, after which the trenches are refilled and covered. The exposed surface area is minimal since only the top surface of the wastes is exposed, the remainder being covered by the sides and bottom of the trench. The surplus material from trench excavation can be valorized for use as engineering fill onsite or off. The landfill in Villanueva has operated for 15 years, using a total land area of approximately 11 ha for a population that grew from 23,000 to 48

  10. Fort George G. Meade Active Sanitary Landfill and Clean Fill Dump, Remedial Investigation Report

    National Research Council Canada - National Science Library

    1992-01-01

    ...) and a Site Inspection at the inactive Clean Fill Dump (CFD) sites. The objective of the ASL study involved obtaining additional data to evaluate the potential environmental impacts associated with the landfill operations...

  11. Application of Deuterium and Oxygen-18 to Trace Leachate Movement in Bantar Gebang Sanitary Landfill

    International Nuclear Information System (INIS)

    Pujiindiyati, E.R.

    2011-01-01

    Bantar Gebang landfill was constructed in 1986 with total area of 108 ha and approximately 6000 ton/day solid waste is disposed to this landfill. Mostly, the people living surrounding landfill get afraid of impact of the hazardous chemicals produced by waste disposal to their health. The purpose of this investigation was to study the migration of leachate to Cibitung River water and shallow groundwaters near to the river. It is possible to be done because chemical contents and isotopic characteristics of municipal landfill leachate are unique, relative to aqueous media in the most natural environments. Laser absorption method developed by the LGR (Los Gatos Research) was used to measure absolute abundances of 2 HHO, HH 18 O and HHO in a number of water samples. In-situ measurements were also conducted as an additional parameter besides their isotopes. The δ 2 H of the H 2 O in landfill leachate was significantly enriched, with values of - 22.6 0/00 to + 4.3 0/00. This deuterium enrichment was undoubtedly due to the extensive production of microbial methane within the limited reservoir of the landfill. However, the enriched deuterium value in leachate was not detected in the river which still had depleted values. It was probably caused by the amount of natural water in the river was comparatively large, with respect to limited leachate discarded to the river. The electrical conductivity of the leachate was higher (3200 to 7600 μS) and the decreasing values were still monitored in the river to approximately 12 km after streaming the landfills. The effect of the high electrical conductivity and enriched deuterium of leachate was not clearly indicated in the groundwater samples which still represented the local precipitation recharge, except a monitoring well located in Bantar Gebang landfill area which has an indication of leachate contamination. (author)

  12. Application of Deuterium and Oxygen-18 to Trace Leachate Movement in Bantar Gebang Sanitary Landfill

    Directory of Open Access Journals (Sweden)

    E.R. Pujiindiyati

    2011-08-01

    Full Text Available Bantar Gebang landfill was constructed in 1986 with total area of 108 ha and approximately 6000 ton/day solid waste is disposed to this landfill. Mostly, the people living surrounding landfill get afraid of impact of the hazardous chemicals produced by waste disposal to their health. The purpose of this investigation was to study the migration of leachate to Cibitung River water and shallow groundwaters near to the river. It is possible to be done because chemical contents and isotopic characteristics of municipal landfill leachate are unique, relative to aqueous media in the most natural environments. Laser absorption method developed by the LGR (Los Gatos Research was used to measure absolute abundances of 2HHO, HH18O and HHO in a number of water samples. In-situ measurements were also conducted as an additional parameter besides their isotopes. The δ2H of the H2O in landfill leachate was significantly enriched, with values of - 22.6 ‰ to + 4.3 ‰. This deuterium enrichment was undoubtedly due to the extensive production of microbial methane within the limited reservoir of the landfill. However, the enriched deuterium value in leachate was not detected in the river which still had depleted values. It was probably caused by the amount of natural water in the river was comparatively large, with respect to limited leachate discarded to the river.The electrical conductivity of the leachate was higher (3200 to 7600 S and the decreasing values were still monitored in the river to approximately 12 km after streaming the landfills. The effect of the high electrical conductivity and enriched deuterium of leachate was not clearly indicated in the groundwater samples which still represented the local precipitation recharge, except a monitoring well located in Bantar Gebang landfill area which has an indication of leachate contamination.

  13. The effect of sanitary landfill leachate aging on the biological treatment and assessment of photoelectrooxidation as a pre-treatment process

    Energy Technology Data Exchange (ETDEWEB)

    Müller, Gabriel Timm [Universidade Estadual do Rio Grande do Sul (UERGS), R. Gal. João Manoel, 50, CEP 90010-030 Porto Alegre, RS (Brazil); Giacobbo, Alexandre [Universidade Federal do Rio Grande do Sul (UFRGS), Av. Bento Gonçalves, 9500, Setor 4, Prédio 74, CEP 91501-970 Porto Alegre, RS (Brazil); Santos Chiaramonte, Edson Abel dos [Universidade Estadual do Rio Grande do Sul (UERGS), R. Gal. João Manoel, 50, CEP 90010-030 Porto Alegre, RS (Brazil); Rodrigues, Marco Antônio Siqueira [Universidade FEEVALE, ICET, RS 239, 2755, CEP 93352-000 Novo Hamburgo, RS (Brazil); Meneguzzi, Alvaro [Universidade Federal do Rio Grande do Sul (UFRGS), Av. Bento Gonçalves, 9500, Setor 4, Prédio 74, CEP 91501-970 Porto Alegre, RS (Brazil); Bernardes, Andréa Moura, E-mail: amb@ufrgs.br [Universidade Federal do Rio Grande do Sul (UFRGS), Av. Bento Gonçalves, 9500, Setor 4, Prédio 74, CEP 91501-970 Porto Alegre, RS (Brazil)

    2015-02-15

    Highlights: • Photoelectrooxidation (PEO) emerges as a new technology for leachate treatment. • Aging of sanitary landfills acts on leachate composition and biodegradability. • PEO is applied as leachate pretreatment before the biological processes. • PEO produced significant changes in the leachate matrix, easing biological process. - Abstract: The sanitary landfill leachate is a dark liquid, of highly variable composition, with recalcitrant features that hamper conventional biological treatment. The physical–chemical characteristics of the leachate along the landfill aging, as well as their effects on the efficiency of the conventional treatment, were evaluated at this paper. The feasibility of photoelectrooxidation process as an alternative technique for treatment of landfill leachates was also determined. Photoelectrooxidation experiments were conducted in a bench-scale reactor. Analysis of the raw leachate revealed many critical parameters demonstrating that the recalcitrance of leachate tends to increase with time, directly influencing the decline in efficiency of the conventional treatment currently employed. The effects of current density and lamp power were investigated. Using a 400 W power lamp and a current density of 31.5 mA cm{sup −2}, 53% and 61% efficiency for the removal of ammoniacal nitrogen and chemical oxygen demand were respectively achieved by applying photoelectrooxidation process. With the removal of these pollutants, downstream biological treatment should be improved. These results demonstrate that photoelectrooxidation is a feasible technique for the treatment of sanitary landfill leachate, even considering this effluent’s high resistance to treatment.

  14. The effect of sanitary landfill leachate aging on the biological treatment and assessment of photoelectrooxidation as a pre-treatment process

    International Nuclear Information System (INIS)

    Müller, Gabriel Timm; Giacobbo, Alexandre; Santos Chiaramonte, Edson Abel dos; Rodrigues, Marco Antônio Siqueira; Meneguzzi, Alvaro; Bernardes, Andréa Moura

    2015-01-01

    Highlights: • Photoelectrooxidation (PEO) emerges as a new technology for leachate treatment. • Aging of sanitary landfills acts on leachate composition and biodegradability. • PEO is applied as leachate pretreatment before the biological processes. • PEO produced significant changes in the leachate matrix, easing biological process. - Abstract: The sanitary landfill leachate is a dark liquid, of highly variable composition, with recalcitrant features that hamper conventional biological treatment. The physical–chemical characteristics of the leachate along the landfill aging, as well as their effects on the efficiency of the conventional treatment, were evaluated at this paper. The feasibility of photoelectrooxidation process as an alternative technique for treatment of landfill leachates was also determined. Photoelectrooxidation experiments were conducted in a bench-scale reactor. Analysis of the raw leachate revealed many critical parameters demonstrating that the recalcitrance of leachate tends to increase with time, directly influencing the decline in efficiency of the conventional treatment currently employed. The effects of current density and lamp power were investigated. Using a 400 W power lamp and a current density of 31.5 mA cm −2 , 53% and 61% efficiency for the removal of ammoniacal nitrogen and chemical oxygen demand were respectively achieved by applying photoelectrooxidation process. With the removal of these pollutants, downstream biological treatment should be improved. These results demonstrate that photoelectrooxidation is a feasible technique for the treatment of sanitary landfill leachate, even considering this effluent’s high resistance to treatment

  15. Design of manuals sanitary landfills (II). Diseo de rellenos sanitarios manuales (II)

    Energy Technology Data Exchange (ETDEWEB)

    Jaramillo, J.

    1994-01-01

    This period includes engineering projects, landscape and details of building; taking into account the circumstances that govern them, it must be made looking at the simplicity and quickness required to these type of works and trying to respect sanitary requirements. (Author)

  16. Sanitary Landfill. Sludge Treatment and Disposal Course #166. Instructor's Guide [and] Student Workbook.

    Science.gov (United States)

    Sharman, Ronald M.

    This lesson is an introduction to disposal of sludge by landfill. A brief explanation of the complete process is provided, including discussions of sludge suitability, site selection, method selection and operation, site closure, and ultimate reuse. The lesson includes an instructor's guide and student workbook. The instructor's guide contains a…

  17. Development of a fibre-optic sensor system for the continuous monitoring of a sanitary landfill for low-halogenated hydrocarbons, polycyclic aromatic hydrocarbons, and other pollutants

    International Nuclear Information System (INIS)

    Baumann, M.; Baumann, T.; Gahr, A.; Mueller-Ackermann, E.; Panne, U.; Niessner, R.

    1992-01-01

    The aim of the project is to develop a mobile fibre-optic sensor system for monitoring the ground water aquifer in the area of a landfill. Not only are the analytical methods to be developed further; but the system's performance in the field is to be tested as well. As a large part of knowledge on the long-time safety of mineral sealing systems of sanitary landfills derives from damage events, a measuring area was additionally established at the Augsburg-Nord landfill. This measuring area is to permit monitoring of the sealing also during operation and reclamation. Within the measuring area and in the environs of the landfill, both conventional sensors for temperature, conductibility, etc., and the specially developed fibre-optic sensors for on-line in-situ monitoring will be used. (orig.) [de

  18. Greenhouse gases emission from sanitary landfills in Lombardy: estimation and uncertainty analysis

    International Nuclear Information System (INIS)

    Antognazza, F.; Moretti, M.; Caserini, S.

    2009-01-01

    Quantification of methane emissions from landfills is important to evaluate measures for reduction of greenhouse gas emissions. A census has been conducted across all landfills in Lombardy in order to get a double assessment of greenhouse gas emissions in the period 1973-2007. The first approach is of a deterministic kind: it produced a GHG emission assessment of about 2,240 ktCO 2 (like 2.4% of GHG emission in Lombardy in 2005). The second approach is a probabilistic approach according to Monte Carlo simulation, and allows an assessment of probabilistic distribution of emissions and uncertainty. Uncertainty in GHG emission from landfill in Lombardy is about 20% and efficiency of LFG collection and biodegradable carbon content are the most relevant parameters in this assessment. Also, a projection of GHG emission was made. Two scenarios were analyzed for the 2008-2020 period: a business as usual (BAU) one and an alternative one. It results that we are expecting a 50% reduction of GHG emission, with alternative scenario, from 2007 level: at regional scale it is like a 1% of overall GHG emissions in Lombardy. [it

  19. Public concerns about and perceptions of solid waste dump sites and selection of sanitary landfill sites in the West Bank, Palestinian territory.

    Science.gov (United States)

    Al-Khatib, Issam A; Abu Hammad, Ahmad; Sharkas, Othman A; Sato, Chikashi

    2015-04-01

    Palestinian inhabitants have disposed of their solid wastes at open dumpsites over the past 40 years without an adequate solid waste management (SWM) plans. Recently, the Palestinian Authority initiated SWM planning to establish controlled sanitary landfills, based on a participatory approach. The purpose of this study was to assess public concerns about existing solid waste dumpsites and public perceptions of sanitary landfill site selection. The study will also take into consideration the effect of diverse social, economic, and environmental related factors of the inhabitants on sitting suitable landfill sites in three Palestinian districts in the West Bank, namely, "Nablus," "Salfit," and "Ramallah and Al-Bireh." The results of this study showed that 64.9% of the sample population are aware of the problems and potential impacts associated with random dumpsites, and 41.6% think that they are suffering from the dumps. Among the environmental, socioeconomic, and political factors, the environmental factors, air pollution in particular, are thought be the most important consideration in selecting a landfill site. The "fairness in selecting a landfill site" was chosen to be one of the most important socioeconomic factors, possibly as a reaction to the Israeli occupation and subsequent land use restrictions in the West Bank, Palestinian territory.

  20. Landfills

    Science.gov (United States)

    To provide information on landfills, including laws/regulations, and technical guidance on municipal solid waste, hazardous waste, industrial, PCBs, and construction and debris landfills. To provide resources for owners and operators of landfills.

  1. Effects of ferric ions on the catalytic ozonation process on sanitary landfill leachates

    Directory of Open Access Journals (Sweden)

    Messias Borges Silva

    2013-04-01

    Full Text Available Leachates exhibiting an unstable ratio of biochemical oxygen demand (BOD and chemical oxygen demand (COD of approximately 0.45 are typical of new landfills in the City of Cachoeira Paulista, Brazil. Although the organic matter portion is bio-treatable, the presence of refractory leached organic material requires unconventional effluent-treatment processes. Leachate treatment with ozone oxidation, in the presence of ferric ions, acts as catalyst in the formation of hydroxyl radicals. Ozone was obtained by corona-discharge from high-purity O2 gas. The treatment was performed in natura in a jacketed borosilicate glass reactor containing 900 ml of leachate. The analyzed response variable was expressed as the concentration of dissolved organic carbon (DOC. In order to determine the optimal proportions to produce the greatest degradation rate for organic materials, variations in experimental O2 flow-fed to the generator, the Fe(iii concentration, and the output of the ozonator were conducted over two experimental runs. Experimental models showed a DOC degradation on the order of 81.25%.

  2. Landfills

    Data.gov (United States)

    Vermont Center for Geographic Information — This data set defines both current and historic landfills/waste disposal storage sites for the State of Vermont. Historic landfills were identified with the...

  3. Tritium

    International Nuclear Information System (INIS)

    Anon.

    1975-01-01

    The role played the large amount supply of tritium and its effects are broadly reviewed. This report is divided into four parts. The introductory part includes the history of tritium research. The second part deals with the physicochemical properties of tritium and the compounds containing tritium such as tritium water and labeled compounds, and with the isotope effects and self radiation effects of tritium. The third part deals with the tritium production by artificial reaction. Attention is directed to the future productivity of tritium from B, Be, N, C, O, etc. by using the beams of high energy protons or neutrons. The problems of the accepting market and the accuracy of estimating manufacturing cost are discussed. The expansion of production may bring upon the reduction of cost but also a large possibility of social impact. The irradiation problem and handling problem in view of environmental preservation are discussed. The fourth part deals with the use of tritium as a target, as a source of radiation or light, and its utilization for geochemistry. The future development of the solid tritium target capable of elongating the life of neutron sources is expected. The rust thickness of the surface of iron can be measured with the X-ray of Ti-T or Zr-T. The tritium can substitute self-light emission paint or lamp. The tritium is suitable for tracing the movement of sea water and land surface water because of its long half life. (Iwakiri, K.)

  4. Environmental Isotopes Method For Study Of The Migration Of Nitrate Pollutant In The Shallow Groundwater Of Bantar Gebang Sanitary Landfill, Bekasi

    International Nuclear Information System (INIS)

    Syafalni

    2002-01-01

    An investigation was carried out to determine the influence of sanitary landfill of the Bantar Gebang, Bekasi on the origin and migration of pollutant in the shallow groundwater situated in and around the disposal site of Bantar Gebang landfill. The study revealed that domestic shallow wells are becoming increasingly polluted with nitrate in the region which have been distributed more than I Ian from the site. Based on the environmental isotope method (analysis of 18 O and 2 H) and hydrochemistry evaluation, it showed the same trend. The level of nitrate in the observation wells were found vary widely from 0.0 to 94.43 ppm for sampling period of April-May 2001 and 0.0 to 23.9 ppm for sampling period of August-September 2001. Some of the observation wells have indicated exceeding the maximum permissible limit specified for drinking water

  5. Insights into solar photo-Fenton reaction parameters in the oxidation of a sanitary landfill leachate at lab-scale.

    Science.gov (United States)

    Silva, Tânia F C V; Ferreira, Rui; Soares, Petrick A; Manenti, Diego R; Fonseca, Amélia; Saraiva, Isabel; Boaventura, Rui A R; Vilar, Vítor J P

    2015-12-01

    This work evaluates the effect of the main photo-Fenton (PF) reaction variables on the treatment of a sanitary landfill leachate collected at the outlet of a leachate treatment plant, which includes aerated lagooning followed by aerated activated sludge and a final coagulation-flocculation step. The PF experiments were performed in a lab-scale compound parabolic collector (CPC) photoreactor using artificial solar radiation. The photocatalytic reaction rate was determined while varying the total dissolved iron concentration (20-100 mg Fe(2+)/L), solution pH (2.0-3.6), operating temperature (10-50 °C), type of acid used for acidification (H2SO4, HCl and H2SO4 + HCl) and UV irradiance (22-68 W/m(2)). This work also tries to elucidate the role of ferric hydroxides, ferric sulphate and ferric chloride species, by taking advantage of ferric speciation diagrams, in the efficiency of the PF reaction when applied to leachate oxidation. The molar fraction of the most photoactive ferric species, FeOH(2+), was linearly correlated with the PF pseudo-first order kinetic constants obtained at different solution pH and temperature values. Ferric ion speciation diagrams also showed that the presence of high amounts of chloride ions negatively affected the PF reaction, due to the decrease of ferric ions solubility and scavenging of hydroxyl radicals for chlorine radical formation. The increment of the PF reaction rates with temperature was mainly associated with the increase of the molar fraction of FeOH(2+). The optimal parameters for the photo-Fenton reaction were: pH = 2.8 (acidification agent: H2SO4); T = 30 °C; [Fe(2+)] = 60 mg/L and UV irradiance = 44 WUV/m(2), achieving 72% mineralization after 25 kJUV/L of accumulated UV energy and 149 mM of H2O2 consumed. Copyright © 2015 Elsevier Ltd. All rights reserved.

  6. Tritium

    International Nuclear Information System (INIS)

    Fiege, A.

    1992-07-01

    This report contains information on chemical and physical properties, occurence, production, use, technology, release, radioecology, radiobiology, dose estimates, radioprotection and legal aspects of tritium. The objective of this report is to provide a reliable data base for the public discussion on tritium, especially with regard to its use in future nuclear fusion plants and its radiological assessment. (orig.) [de

  7. Estimate the potential production of electricity: a case study of the sanitary landfill of Santo Andre, Sao Paulo, Brazil; Estimativa do potencial de producao de eletricidade: estudo de caso do aterro sanitario de Santo Andre, Sao Paulo, Brasil

    Energy Technology Data Exchange (ETDEWEB)

    Silva, Elissando Rocha da; Moreira, Joao M. L.; Candiani, Giovano [Instituto Federal de Educacao, Ciencia e Tecnologia de Sao Paulo (IFSP), SP (Brazil)

    2010-07-01

    The recovery of the biogas generated from sanitary landfills, associated to its energetic use has been widely discussed. Thus, this paper aims to estimate the potential production of electric energy from sanitary landfill Santo Andre-SP. The biogas production was estimated using the rate of deposition of solid wastes in the landfill, using some mathematical models with parameters suggested by two models: LanGEM-USEPA (conventional landfill) and Word Bank. These results indicate that the potential of biogas production will be approximately 11 x 10{sup 6} Kg of methane/year in 2017 and production of electric energy in that year will be approximately 32,000 MWh, considering an of 75% over collection of biogas. (author)

  8. Analysis of the role of the sanitary landfill in waste management strategies based upon a review of lab leaching tests and new tools to evaluate leachate production

    Directory of Open Access Journals (Sweden)

    Francesco Lombardi

    2017-08-01

    Full Text Available This paper reviews the role of sanitary landfills in current and future waste management strategies based upon the principles and the goals established by the European Framework Directive on Waste (2008/98/EC. Specific reference is made to studies of our research group regarding new tools developed to evaluate leachate production, taking into account the different characteristics of municipal solid waste (MSW. Laboratory leaching tests and a methodology proposed to interpret the results are described and discussed, as well as tools developed to estimate landfill leachate production. Residual flows produced by mechanical-biological treatment (MBT plants, mainly Solid Recovered Fuel (SRF and Stabilized Organic Waste (SOW, incineration and composting plants are considered in particular. Experimental results showed that the most suitable end-uses or disposal options for the outputs of waste treatment plants are site-specific and should be defined on the basis of a detailed characterization. The application of the model developed to assess landfill leachate production showed a very good agreement with field data.

  9. Study of biogas production parameters in the sanitary landfill; Estudio de los parametros que afectan la produccion de biogas en un vertedero controlado

    Energy Technology Data Exchange (ETDEWEB)

    Alvarez Domenech, G.; Gordillo Bolasell, M. A.; Sanchez Ferrer, A.

    2001-07-01

    The following article contents a study about some of the parameters affecting the evolution of the gas production in a sanitary landfill placed in the province of Barcelona. The work is focused on the quality of biogas produced, measured as the percentage of methane and thus its energy profitability. The parameters included in this paper are: -Situation of the gas extraction station -Age of the wastes. -Reinfiltration of concentrated liquid leachate in the considered cell. Among the previous factors, the situation of the gas station and the age of wastes showed a critical influence on the methane content, whereas the use of leachate reinfiltration did not produce significant differences in the quality of biogas in the short-term applications. (Author) 5 refs.

  10. Comparison of potential greenhouse gas emissions from disposal of MSW in sanitary landfills vs. waste-to-energy facilities

    International Nuclear Information System (INIS)

    Taylor, H.F.

    1991-01-01

    The Environmental Protection Agency (EPA) estimates the US currently generates about 160 million tons of municipal solid waste (MSW) per year, and this figure will exceed 200 million tons annually by the year 2000. About 80 percent of the MSW will be disposed of in landfills and waste-to-energy (WTE) facilities, both of which generate greenhouse gases, namely methane and carbon dioxide. This paper provides an introductory level analysis of the potential long term greenhouse gas emissions from these two MSW disposal alternatives. Carbon dioxide credits are derived for fossil fuel offset by WTE and methane emissions are converted to equivalent CO 2 emissions in order to derive a single emission figure for comparison of the greenhouse contribution of the two disposal strategies. A secondary analysis is presented to compare the net equivalent CO 2 emissions from WTE facilities to those from landfills with methane gas recovery, combustion and energy generation. The conclusion is, that for a given amount of MSW, landfilling contributes to the greenhouse effect about 10 times more than a modern Waste-To-Energy facility. Even with 50% of all landfill methane emissions recovered and converted to electricity, the contribution to the greenhouse effect by the landfill alternative is about 6 times greater than the waste-to-energy alternative

  11. Innovative technologies of liquid media treatment in the system of ecological and sanitary-hygienic control of waste landfills

    Directory of Open Access Journals (Sweden)

    Shevchenko Andrey

    2017-01-01

    Full Text Available The article focuses on the scientific and practical aspects of establishing a comprehensive system of environmental compliance for industrial and household waste landfills, including the system of industrial and environmental monitoring and control, modern innovations in the field of instrumental-analytical control of the state of environmental components, new methods of neutralization of complex industrial pollution. Priority is given to wastewater treatment from toxic compounds coming from the surface and drainage water seepage of landfill sites into surface and underground water sources.

  12. Determination of the coefficient of uranium and thorium distribution in phosphogypsum for their use in sanitary landfills

    Energy Technology Data Exchange (ETDEWEB)

    Marchesi, Marcos Vinicius A.; Hama, Naruhiko; Jacomino, Vanusa M. F.; Ladeira, Ana Claudia Q.; Cota, Stela D. S., E-mail: mvmarchesi@hotmail.com, E-mail: sdsc@cdtn.br, E-mail: vmfj@cdtn.br, E-mail: ana.ladeira@cdtn.br, E-mail: naruhikohama@hotmail.com [Centro de Desenvolvimento da Tecnologia Nuclear (CDTN/CNEN-MG), Belo Horizonte, MG (Brazil); Nascimento, Marcos Roberto Lopes do; Taddei, Maria Helena, E-mail: pmarcos@cnen.gov.br, E-mail: mhtaddei@cnen.gov.br [Comissao Nacional de Energia Nuclear (LAPOC/CNEN), Pocos de Caldas, MG (Brazil). Laboratorio de Pocos de Caldas

    2013-07-01

    Phosphogypsum is a byproduct from the production of phosphoric acid, and contain radionuclides, heavy metals and metalloids from phosphate rock. It represents a risk to the environment if improperly stored. Because it is composed mainly of dihydrated calcium sulphate, phosphogypsum can be used in anaerobic environments such as those found in landfills to accelerate microbial processes of decomposition of municipal solid waste and thus increase the life of these facilities. One of the options of your application being studied is the use of phosphogypsum replacing the covers of soil/clay in landfills. Besides reducing the demand for soil and clay, this application would be an alternative to disposal of the waste, since the alternatives are not sufficient for more than five million tons produced per year in Brazil. To ensure the safety of this application, the potential environmental impact of contaminants in phosphogypsum should be evaluated. The rate of leaching of contaminants are being studied by determining the coefficient of distribution of the contaminants in the phosphogypsum. Batch tests were performed by mixing different proportions of slurry and phosphogypsum. This work presents the results for the chain of uranium and natural thorium.

  13. Sensitivity analysis of the leaching rate parameter in assessing the environmental risk of phosphogypsum application in sanitary landfills

    Energy Technology Data Exchange (ETDEWEB)

    Marchesi, Marcos Vinicius A.; Hama, Naruhiko; Jacomino, Vanusa M.F.; Ladeira, Ana Claudia Q.; Cota, Stela D.S., E-mail: mvmarchesi@hotmail.com, E-mail: sdsc@cdtn.br, E-mail: vmfj@cdtn.br, E-mail: ana.ladeira@cdtn.br, E-mail: naruhikohama@hotmail.com [Centro de Desenvolvimento da Tecnologia Nuclear (CDTN/CNEN-MG), Belo Horizonte, MG (Brazil)

    2013-07-01

    The attack with sulfuric acid to phosphate rock produces both phosphoric acid, basic raw material in the manufacture of fertilizers, as a by-product called phosphogypsum. Phosphogypsum is composed mostly of calcium sulfate dihydrated, but may have high levels of impurities from the phosphate rock matrix as a series of natural radionuclides, and heavy metals (e.g. Cd, Zn) and metalloids (e.g. , As and Se). Although it is used for agricultural purposes and more recently in construction, in Brazil the generation rate estimated at six million tons per year is much higher than the amount spent on existing alternatives, and therefore mostly deposited in piles in the same place production, causing thereby the risk of contamination of soil and water resources of the region and providing risk to human health. Taken into account the need to find alternative arrangements for phosphogypsum and reduce the impact generated by its contaminants, this study aims to analyze the sensitivity of the leaching rate parameter in the environmental risk evaluation of the application of phosphogypsum in landfills through mathematical modeling, where it is evaluated the concentration of heavy metals and radionuclides in the layer of the soil under the clay layer of the landfill.

  14. Sensitivity analysis of the leaching rate parameter in assessing the environmental risk of phosphogypsum application in sanitary landfills

    International Nuclear Information System (INIS)

    Marchesi, Marcos Vinicius A.; Hama, Naruhiko; Jacomino, Vanusa M.F.; Ladeira, Ana Claudia Q.; Cota, Stela D.S.

    2013-01-01

    The attack with sulfuric acid to phosphate rock produces both phosphoric acid, basic raw material in the manufacture of fertilizers, as a by-product called phosphogypsum. Phosphogypsum is composed mostly of calcium sulfate dihydrated, but may have high levels of impurities from the phosphate rock matrix as a series of natural radionuclides, and heavy metals (e.g. Cd, Zn) and metalloids (e.g. , As and Se). Although it is used for agricultural purposes and more recently in construction, in Brazil the generation rate estimated at six million tons per year is much higher than the amount spent on existing alternatives, and therefore mostly deposited in piles in the same place production, causing thereby the risk of contamination of soil and water resources of the region and providing risk to human health. Taken into account the need to find alternative arrangements for phosphogypsum and reduce the impact generated by its contaminants, this study aims to analyze the sensitivity of the leaching rate parameter in the environmental risk evaluation of the application of phosphogypsum in landfills through mathematical modeling, where it is evaluated the concentration of heavy metals and radionuclides in the layer of the soil under the clay layer of the landfill

  15. Determination of the coefficient of uranium and thorium distribution in phosphogypsum for their use in sanitary landfills

    International Nuclear Information System (INIS)

    Marchesi, Marcos Vinicius A.; Hama, Naruhiko; Jacomino, Vanusa M. F.; Ladeira, Ana Claudia Q.; Cota, Stela D. S.; Nascimento, Marcos Roberto Lopes do; Taddei, Maria Helena

    2013-01-01

    Phosphogypsum is a byproduct from the production of phosphoric acid, and contain radionuclides, heavy metals and metalloids from phosphate rock. It represents a risk to the environment if improperly stored. Because it is composed mainly of dihydrated calcium sulphate, phosphogypsum can be used in anaerobic environments such as those found in landfills to accelerate microbial processes of decomposition of municipal solid waste and thus increase the life of these facilities. One of the options of your application being studied is the use of phosphogypsum replacing the covers of soil/clay in landfills. Besides reducing the demand for soil and clay, this application would be an alternative to disposal of the waste, since the alternatives are not sufficient for more than five million tons produced per year in Brazil. To ensure the safety of this application, the potential environmental impact of contaminants in phosphogypsum should be evaluated. The rate of leaching of contaminants are being studied by determining the coefficient of distribution of the contaminants in the phosphogypsum. Batch tests were performed by mixing different proportions of slurry and phosphogypsum. This work presents the results for the chain of uranium and natural thorium

  16. EFFECT OF SULFATE LOADING RATE AND ORGANIC LOADING RATE ON ANAEROBIC BAFFLED REACTORS USED FOR TREATMENT OF SANITARY LANDFILL LEACHATES

    Directory of Open Access Journals (Sweden)

    O. Burbano-Figueroa

    2015-06-01

    Full Text Available AbstractThis study investigated the effect of organic loading rate (OLR and sulfate loading rate (SLR on landfill leachate treatment by a lab-scale anaerobic baffled reactor (ABR. Landfill leachate contained a concentration of organic matter between 3966 and 5090 mg COD.L-1 and no detectable amounts of sulfate. Reactors were started-up by feeding them with iron-sulfate at a SLR of 0.05 g SO42-.L-1.day-1 (4 weeks. Factorial design and response surface techniques were used to evaluate and optimize the effects of these operating variables on COD removal. ABRs were operated at OLRs ranging from 0.30 up to 6.84 g COD.L-1.day-1 by changes in influent volumetric flow. SO42- was added to the influent at a SRL from 0.06 to 0.13 g SO42-.L-1.day-1. The highest value of COD removal (66% was reached at an OLR of 3.58 g COD.L-1.day-1 and SLR of 0.09 g SO4-2.L-1.day-1 with a COD/SO4-2 ratio of 40. Under these conditions sulfate is mainly used for molecular hydrogen consumption while organic matter is preferentially degraded via methanogesis.

  17. Design of concrete waste basin in Integrated Temporarily Sanitary Landfill (ITSL) in Siosar, Karo Regency, Indonesia on supporting clean environment and sustainable fertilizers for farmers

    Science.gov (United States)

    Ginting, N.; Siahaan, J.; Tarigan, A. P.

    2018-03-01

    A new settlement in Siosar village of Karo Regency has been developed for people whose villages have been completely destroyed by the prolong eruptions of Sinabung. An integrated temporarily sanitary landfill (ITSL) was built there to support the new living environment. The objective of this study is to investigate the organic waste decomposing in order to improve the design of the conventional concrete waste basin installed in the ITSL. The study was last from May until August 2016. The used design was Completely Randomized Design (CRD) in which organic waste was treated using decomposer with five replications in three composter bins. Decomposting process lasted for three weeks. Research parameters were pH, temperature, waste reduction in weight, C/N, and organic fertilizer production(%). The results of waste compost as follows : pH was 9.45, ultimate temperature was 31.6°C, C/N was in the range of 10.5-12.4, waste reduction was 53% and organic fertilizer production was 47%. Based on the decomposting process and the analysis, it is recommended that the conventional concrete waste basin should be divided into three colums and each column would be filled with waste when previous column is fulled. It is predicted that when the third column is fully occupied then the waste in the first column already become a sustainable fertilizer.

  18. Bench scale model studies on sanitary landfill leachate treatment with M. oleifera seed extract and hollow fibre micro-filtration membrane

    Directory of Open Access Journals (Sweden)

    S. A. Muyibi

    2002-10-01

    Full Text Available A laboratory-based study using a Bench Scale model of four unit operations made up of coagulation (using Moringa oleifera seed extract as a coagulant, flocculation, sedimentation and micro-filtration, have been adopted to treat the leachate from Air Hitman Sanitary Landfill at Puchong in Malaysia. M. oleifera dosages of 150 and 175 mg/L had achieved 43.8% Cadmium removal, 21.2% Total Chromium removal, 66.8% Lead removal and 16% Iron removal. It also removed 55.4% of Total Suspended Solids, 10% of Total Dissolved Solids and 24.2% of Volatile Suspended Solids. Micro-filtration hollow fibre membrane decreased the turbidity, total suspended solids, total dissolved solids, volatile suspended solids, and organic matter in the leachate by 98.3%, 96.7%, 20.8%, 36.6% and 21.9% respectively. Overall heavy metals removal after micro-filtration using hollow fibre membrane was 94% for Cadmium, 29.8% for Total Chromium, 73.2% for Lead, and 18.3% for Iron. The results have shown that M. oleifera is a promising natural polymer for removing heavy metals from leachates and may be used as a pre-treatment to eliminate a portion of the toxic heavy metals, which limits the activity of micro organisms in the leachates.

  19. Does a plant for mechanical-biological waste treatment require a sanitary landfill?; Braucht die MBA eine Deponie?

    Energy Technology Data Exchange (ETDEWEB)

    Schulte, Burkart [GVoA mbH und Co. KG, Hille (Germany)

    2012-11-01

    In mechanical-biological waste treatment, an interesting recyclable fraction is dumped in landfill together with other treatment residues. This may be 10-20% depending on the energy content of the initial material. Some operators of mechanical-biological waste treatment plants are currently working on modifying their waste treatment processes. Results so far have shown that this may also reduce the cost. (orig.) [German] Bei der bisherigen Abfallentsorgung mittels einer MBA (mechanisch-biologische Abfallbehandlung) wird immer noch ein interessanter Wertstoffanteil mit dem Deponat auf der Deponie abgelagert. Je nach Qualitaet der Vorbehandlung sind dies alleine vom Energieinhalt des Eingangsmaterials ca. 10-20%. Um auch diesen Anteil zu verwerten, sind aktuell einige MBA-Betreiber dabei, ihre Verfahren entsprechend umzustellen. Erste Ergebnisse zeigen, dass dies auch noch zu Kosteneinsparungen fuehren kann. (orig.)

  20. Remedial investigation work plan for Bear Creek Valley Operable Unit 1 (S-3 Ponds, Boneyard/Burnyard, Oil Landfarm, Sanitary Landfill I, and the Burial Grounds, including Oil Retention Ponds 1 and 2) at the Oak Ridge Y-12 Plant, Oak Ridge, Tennessee. Volume 1, Main text

    International Nuclear Information System (INIS)

    1994-03-01

    This document refers to data concerning the Environmental Restoration Program implemented at the Oak Ridge Y-12 plant. Topics discussed include: Remediation plans for the burial grounds, sanitary landfill I, oil retention ponds, S-3 ponds, and the boneyard/burnyard at Y-12. This document also contains information about the environmental policies regulating the remediation

  1. Environmental characterization foundry sands used in sanitary landfills; Caracterizacao ambiental de areias descartadas de fundicao utilizadas na cobertura de residuos em aterros sanitarios

    Energy Technology Data Exchange (ETDEWEB)

    Domingues, L.G.F.; Ferreira, G.C.S.; Pires, M.S.G.; Teixeira, I.; Carnin, R.; Sarro, W.S., E-mail: lucienegferrari@gmail.com [Universidade Estadual de Campinas (UNICAMP), SP (Brazil)

    2016-07-01

    The national solid waste policy recommends reducing solid waste generation and reusing them in different applications. Preliminary studies show that the foundry sand generated from cast metal parts undercut, has excellent applicability in grain size stabilization of soils for geotechnical functions, and therefore, should not be discarded as waste. This study aimed at environmental characterization of two lots of waste foundry sand (WFS), from different industries, to the particle size stabilization of a clayey soil for use in coverage of solid waste in landfills. The methodology included physicochemical characterization tests (grain size, permeability, XRF and heavy metals) and environmental (NBR 10004: 2004, NBR 10005: 2004, NBR 10006: 20004 and acute toxicity with Vibrio fischeri). The results prove the environmental viability of using these lots of WFS as functional material in the composition of landfills. (author)

  2. Utilization of biogas from sanitary landfill for generation of electrical energy in Sao Paulo: a case study; Aproveitamento do biogas proveniente de aterro sanitario para geracao de energia eletrica em Sao Paulo: estudo de caso

    Energy Technology Data Exchange (ETDEWEB)

    Garcilasso, Vanessa Pecora; Coelho, Suani Teixeira Coelho [Centro Nacional de Referencia em Biomassa (CENBIO), Sao Paulo, SP (Brazil); Velazquez, Silvia Maria Stortini Gonzalez [Universitaria Presbiteriana Mackenzie, Sao Paulo, SP (Brazil)

    2010-07-01

    Utilization of the biogas proceeding from urban solid residues for electricity generation: case study in Sao Paulo. The biogas, generated from organic matter degradation, is composed by a mixture of gases, the main components being carbon dioxide and methane, which is a greenhouse effect gas with global warming potential around 21 times greater when compared to CO{sub 2}. Biogas production is possible from a great variety of organic residues such as urban solid residues, residues from agricultural and livestock activities, swine livestock, sewage mud, among others. The sanitary landfills may count on techniques of capture of the produced biogas and its later burning in flare, where the methane is transformed in CO{sub 2}, minimizing the environmental impact. Besides the opportunity of reducing the environmental damages, biogas can also be used as fuel for generating electricity, thus adding environmental gain and reduction of costs, due to the diminishing of purchase of the energy consumed in the concessionaire. In this context, this article presents the project of utilization of biogas proceeding from urban solid residues for electricity generation and gas illumination, developed by CENBIO. This project is currently in development and the obtained results will provide technical and economic subsidies for its replication. (author)

  3. Methane emissions from sanitary landfills in Italy. Evaluation and forecasting; Le emissioni di metano dalle discariche di rifiuti in Italia: stima e scenari futuri

    Energy Technology Data Exchange (ETDEWEB)

    Colombari, F.; De Lauretis, R.; De Stefanis, P.; Gaudioso, D. [ENEA, Centro Ricerche Casaccia, Rome (Italy). Dipt. Ambiente

    1998-07-01

    The report estimates the methane emissions from landfills by three different methodologies derived from IPCC experiences. A detailed evaluation of solid waste production (MSW) composition is shown in order to update results obtained from old researches. Finally it shows a prediction of MSW production from 1996 to 2011 in different scenarios related to MSW management strategies. [Italian] Il rapporto analizza la stima della quantita' di metano generato dalle discariche di rifiuti utilizzando tre differenti metodologie di calcolo, derivanti dalle conoscenze scientifiche dell'IPCC, dopo aver approfondito la composizione dei rifiuti. Riporta infine per il periodo 1996-2011, la stima della produzione e dello smaltimento dei rifiuti e la predisposizione di diversi scenari futuri di emissione del metano, relativi a differenti scelte all'interno del sistema di gestione dei rifiuti.

  4. Landfill gas from environment to energy

    International Nuclear Information System (INIS)

    Gendebien, A.; Pauwels, M.; Constant, M.; Ledrut-Damanet, M.J.; Nyns, E.J.; Fabry, R.; Ferrero, G.L.; Willumsen, H.C.; Butson, J.

    1992-01-01

    Landfill gas is an alternative source of energy which can be commercially exploited wherever municipal solid wastes are disposed of in sanitary landfills. In this context, it was decided to launch a comprehensive study on the subject of energy valorization of landfill gas. The main topics dealt with in the study, which is supported by a comprehensive literature survey and six detailed case-studies, include; (i) the environmental impact of landfill gas, (ii) the process of landfill gas genesis and the technology of landfill gas control by its exploitation, (iii) the monitoring of landfill gas emissions, (iv) the policies and legal aspects of landfill gas in the European Community and in the world, (v) the estimation of landfill gas potentials and economics of landfill gas control and exploitation, (vi) the status of landfill gas exploitation in the European Community and in the world. (authors). refs., figs., tabs

  5. Detailed test plan on co-disposal of deminumum levels of LLRW and sanitary waste

    International Nuclear Information System (INIS)

    Chian, E.S.K.

    1984-01-01

    The major objectives of this investigation are: (1) to study the attenuation mechanisms for radionuclides (LLRW) in simulated sanitary landfills with and without leachate recycle; and (2) to determine the complexation potential of ligands (viz., sulfides, humic substances) present in the leachate during different stages of landfill stabilization. Since the major emphasis of this research is on containment and isolation of LLRW within a sanitary landfill the following key elements have been incorporated into the design of the simulated pilot-scale sanitary landfills: (1) containment of LLRW within the landfills by placing the municipal refuse and LLRW in polymeric membrane-lined cells (30-mil, HDA, Gundline liner, Gundle, TX) with a leachate collection system; (2) enhancement of stabilization by leachate recycle; and (3) recovery of the gas produced from the sanitary landfills. The proposed research program addresses the fate of LLRW in municipal sanitary landfills thereby, establishing a data base to predict radionuclide pathways in sanitary landfills and to aid in assessing the environmental impacts of codisposal of LLRW within sanitary landfills. The outcome of this study may also serve to alleviate the current concern of unnecessary filling of limited space in existing licensed shallow-land burial sites. 4 figures, 1 table

  6. Simulação e avaliação do desempenho hidrológico da drenagem horizontal de percolado em aterro sanitário Leachate horizontal drainage hydrologic performance evaluation and simulation in sanitary landfill

    Directory of Open Access Journals (Sweden)

    José Capelo Neto

    2005-09-01

    Full Text Available A determinação da quantidade de percolado gerado em aterros sanitários continua sendo uma tarefa difícil, principalmente no semi-árido nordestino onde predominam caracteríticas meteorológicas e geológicas bem peculiares. O programa HELP (avaliação do comportamento hidrológico em aterros sanitários, desenvolvido por Schroder et al (1984, foi utilizado na simulação de várias configurações de drenagem de fundo. Aplicou-se ao modelo, dados meteorológicos e de solos da região onde está o aterro sanitário de Caucaia (ASMOC, a qual é representativa do semi-árido nordestino. Três características da drenagem de fundo foram variadas (configuração da drenagem, inclinação de fundo e adição de uma camada drenante com alta permeabilidade com o objetivo de avaliar a altura da coluna de percolado, a quantidade de percolado infiltrado no solo e o volume coletado para tratamento. Nas trincheiras sem camada drenante, o aumento da inclinação de fundo e a alteração da configuração dos drenos tiveram pouca influência sobre as variáveis estudadas. A adição da camada drenante proporcionou uma redução significativa da altura da coluna e na infiltração de percolado no solo, mostrando que é um componente fundamental para o bom funcionamento do sistema de drenagem horizontal em aterros sanitários.Leachate quantification in sanitary landfills has always been a difficult task for designers. In the semi-arid northeast of Brazil, where meteorological and geological characteristics are very peculiar, this task becomes even more complicated. With the aid of the computer program HELP-Hydrologic Evaluation of Landfill Performance developed by Schroeder et al (1984, and using local meteorological and geological data, various scenarios were simulated altering trench bottom inclination, drainage system configurations, and adding a layer with high hydraulic conductivity. With those changes, leachate head accumulated in the waste, leachate

  7. On the possibility of using tritium as an indicator of surface water entry into underlying horizons

    International Nuclear Information System (INIS)

    Pavlov, V.A.; Romanov, V.V.; Petrukhin, V.A.; Andrievskij, E.I.; Gribanov, O.I.; Igumnov, A.S.; Malykhin, A.P.

    1981-01-01

    Tritium content in the surface water of the central section of Baikal-Amur railway is investigated to estimate sanitary toxicological state and hydrodynamic regime of these waters, as well as the possibility of using tritium as an indicator of contamination of surface waters. It is established that tritium is a convenient indicator of contamination processes of waters from underground sources. Tritium levels in waters of wells investigated correspond to existing sanitary norms [ru

  8. Methodology for environmental diagnosis of sanitary landfills: Data during 2003; Metodologia de diagnostico ambiental de vertederos como herramienta en la planificacion ambiental. Datos obtenidos en el Observatorio sobre Vertederos de residuos de 2003

    Energy Technology Data Exchange (ETDEWEB)

    Uriarte, J.

    2003-07-01

    Lack of data regarding environmental matters in relation to the great majority of MSW landfills throughout Spanish territory makes it difficult to consider them suitable for exploitation or territorial expansion required for different activities demanded by society. The environmental risk of a landfill must be minimised with the help of environmental planning tools. One of these tools is based on the environmental diagnosis and characterisation of the areas affected by the solid waste deposit.. Diagnosis by means of quantifiable environmental indexes helped us in our work to determine the priorities for the environmental control of certain Spanish landfills. This diagnosis was used for creating the Observatory on Solid Waste Landfills, organized by ATEGRUS (Spanish Technical Association for Waste Management) in 2003 and presented at ATEGRUS 30th Annual conference on Controlled Landfills. (Author)

  9. Mathematical modelization of physical process of biogas migration in sanitary landfills of urban solid wastes; Modelizacion matematica del proceso fisico de migracion del biogas en vertederos controlados de R.S.U

    Energy Technology Data Exchange (ETDEWEB)

    Maranon Maison, E.; Sastre Andres, H.; Martin Gonzalez, S.

    1997-09-01

    An analysis of the laws that govern the biogas movements inside the landfill is carried out. The mathematical equations needed to resolve the problem are studied. Then, a model is defined and used to calculate the biogas movements in several situations. The results obtained are contrasted with data from the bibliography and with tests carried out at the La Zoreda, Landfill (Asturias Spain). (Author) 11 refs.

  10. Tritium storage

    International Nuclear Information System (INIS)

    Hircq, B.

    1990-01-01

    This document represents a synthesis relative to tritium storage. After indicating the main storage particularities as regards tritium, storages under gaseous and solid form are after examined before establishing choices as a function of the main criteria. Finally, tritium storage is discussed regarding tritium devices associated to Fusion Reactors and regarding smaller devices [fr

  11. Seagulls control method by falcons in sanitary landfills in Coll Cardus (Spain); Gestion de la poblaciond e gaviotas en el deposito controlado de Coll Cardus mediante el empleo de halcones

    Energy Technology Data Exchange (ETDEWEB)

    AlvarezmBlanco, H.

    2004-07-01

    A seagull control method through falconry in the engineered landfill of HERA-TRATESA in Barcelona is presented. First, the general problem of vectors is approached, followed by seagull monitoring. Previously used means of scaring seagulls are compared to the present one, in which trained hawks are used. The gull's characteristic behaviour, which makes them so difficult to manage, is used as a means of forcing them to categorise the landfill as an uninteresting feeding zone. The different phases of this initiative are commented on. A period of around three weeks is usually enough to change the seagulls' global behaviour. (Author) 9 refs.

  12. Landfilling: Hydrology

    DEFF Research Database (Denmark)

    Kjeldsen, Peter; Beaven, R.

    2011-01-01

    Landfill hydrology deals with the presence and movement of water through a landfill. The main objective in landfill hydrology is usually to predict leachate generation, but the presence and movement of water in a landfill also affect the degradation of the waste, the leaching of pollutants...... and the geotechnical stability of the fill. Understanding landfill hydrology is thus important for many aspects of landfill, in particular siting, design and operation. The objective of this chapter is to give a basic understanding of the hydrology of landfills, and to present ways to estimate leachate quantities...... under specific circumstances. Initially a general water balance equation is defined for a typical landfill, and the different parts of the water balance are discussed. A separate section discusses water flow and the hydrogeology of landfilled wastes and considers the impact of water short...

  13. Application of urban waste water sludge in revegetation of sanitary landfills; Aplicacion de lodos de depuradora procedentes de aguas residuales urbanas en la revegetacion de vertederos de RSU (II)

    Energy Technology Data Exchange (ETDEWEB)

    Ingelmo Sanchez, F.; Garcia Camarero, J.; Morenilla Martinez, J. J.; Bernacer Bonora, I.; Herrero Chamorro, O.; Amores Blasco, S.

    2000-07-01

    The use of forest soil for re vegetating sealed urban landfills is a practice leading to economic and environmental problems. Recently, it has been demonstrated a suitable technique for minimizing soil needs in the re-vegetation of a closed urban landfill which, the layer of fertile soil usually added for plants to settle and develop in such degraded substrate is replaced by a layer of the degraded soil amended with urban anaerobic sewage sludges. In this work we expose the firsts results of a pilot project for the re-vegetation with this procedure of a closed landfill of municipal solid wastes managed by the company Gestion Integral de Residuos in a collaborative research among the Centro de Investigaciones sobre Desertificacion, the Entidad Publica de Saneamiento de Aguas Residuales de la Comunidad Valenciana and the company Depuracion de Aguas del Mediterraneo. The closed landfill has a surface of 2,6 ha and its re-vegetation will be carried out by introducing native plants (annuals, busch and trees) after incorporation into the degraded soil of the anaerobic sewage sludge at the single dose of 60 tn/ha. (Author) 3 refs.

  14. Landfill Methane

    Science.gov (United States)

    Landfill methane (CH4) accounts for approximately 1.3% (0.6 Gt) of global anthropogenic greenhouse gas emissions relative to total emissions from all sectors of about 49 Gt CO2-eq yr-1. For countries with a history of controlled landfilling, landfills can be one of the larger national sources of ant...

  15. Energetic use of biogas from sanitary landfill in Brazil: a technical feasibility study, economic and environmental; Do aproveitamento energetico do biogas em aterros sanitarios no Brasil: um estudo de viabilidade tecnica, economica e ambiental

    Energy Technology Data Exchange (ETDEWEB)

    Abreu, Fabio Viana de [Petroleo Brasileiro S.A. (PETROBRAS), Rio de Janeiro, RJ (Brazil)

    2012-07-01

    Power generation through biogas in landfills is a production of clean and renewable energy in order to minimize the global impacts generated by the burning of municipal solid waste. In this article, the operational conditions of biogas are defined, and analyzed the appropriate areas and minimum flow of biogas, in m{sup 3}/h, to enable this type of project. The most significant environmental contribution of this project is to reduce emissions of greenhouse gases (GHG), by converting the methane into carbon dioxide. According to the Clean Development Mechanism (CDM), called developed countries can buy carbon credits from developing countries to meet their environmental goals. This alternative of raising revenue is one of the objects of this study. Are studied energy conversion technologies, with analysis of the best alternative for the conversion of landfill biogas energy. Comparative studies are presented and the results showed that the generating sets, using internal combustion engines (Otto or Diesel cycles) are more viable both technically and economic bias for energy conversion of landfill gas in Brazil through thermoelectric units.

  16. Avaliação de parâmetros indicadores de poluição por efluente líquido de um aterro sanitário Evaluation of indicative parameters of pollution for liquid effluent of a sanitary landfill

    Directory of Open Access Journals (Sweden)

    Selene de Oliveira

    2004-09-01

    Full Text Available O presente trabalho consistiu em determinar alguns parâmetros, químicos (metais pesados e DQO e físico-químico (pH, indicadores de poluição/contaminação do efluente líquido do aterro sanitário municipal de Botucatu/SP, visando a avaliação da qualidade das águas subterrâneas do Aqüífero Botucatu. Os resultados obtidos na determinação dos parâmetros indicam poluição ambiental por metais pesados: cádmio, chumbo, cromo, níquel e zinco. Conseqüentemente, contaminação do lençol freático por cádmio e chumbo; da solução do solo por cádmio, chumbo e cromo; e da água superficial por níquel. Também, foi realizada uma estimativa de produção do efluente líquido para registrar a necessidade de redimensionamento dos drenos horizontais, observando a necessidade de priorizar estudos que controlem os processos construtivos e operacionais de aterros sanitários eficientes e de baixo custo.The present work consisted in to determine some parameters, chemical (heavy metals and COD and physiochemical (pH, pollution/contamination indicative of the liquid effluent of the municipal sanitary landfill of Botucatu/SP, seeking the evaluation of the quality of groundwater of the Botucatu Aquifer.The results obtained in the determination of the parameters indicate environmental pollution of the heavy metals: cadmium, lead, chromium, nickel and zinc. Consequently, contamination of the water table for cadmium and lead; of the solution of soil for cadmium, lead, and chromium; and of the surface water for nickel. Also, an estimate of production of the liquid effluent was accomplished to register the need of new dimensioning of the horizontal drains, observing the need to prioritize studies to control the constructive and operational processes of efficient sanitary landfill and of low cost.

  17. Desempenho operacional e ambiental de unidades de reciclagem e disposição final de resíduos sólidos domésticos financiadas pelo ICMS Ecológico de Minas Gerais Operational and environmental performance of sanitary landfills and recycling facilities supported by the Ecological ICMS in Minas Gerais State, Brazil

    Directory of Open Access Journals (Sweden)

    José Francisco do Prado Filho

    2007-03-01

    Full Text Available Este estudo avalia sistemas de reciclagem e de disposição de resíduos sólidos domésticos que possuem incentivos fiscais definidos pela Lei Estadual nº 13.803/2000 de Minas Gerais. A pesquisa foi desenvolvida por análise de documentação de licenciamento ambiental de aterros sanitários e usinas de reciclagem e compostagem de resíduos financiados pela referida Lei e por visitas às unidades sanitárias, sendo usados os instrumentos metodológicos da agência ambiental do Estado de São Paulo (CETESB que avaliam as condições de instalação e operação desses tipos de empreendimentos. Do estudo, constatou-se que o incentivo de Minas Gerais, definido pela Lei do ICMS Ecológico, traz importantes benefícios ambientais aos municípios, embora ainda seja reduzido o número dos contemplados por esse fomento à gestão dos resíduos sólidos urbanos. Conclui-se, também, que algumas das unidades estudadas apresentam problemas de natureza ambiental e operacional.This paper reports a qualitative assessment made at the sanitary landfill, recycling centers and composting units sponsored by the State Law No 13.803/2000, Minas Gerais, Brazil. The analyses of all the documentation used for the environmental licensing process as well as field trips to sanitary landfills and domestic recycle/composting unities were performed. The IQC and IQR indexes from the São Paulo State Environmental Agency (CETESB were used as quality assessment tools. It is concluded that this State Law (Ecological ICMS Law has been promoting substantial environmental benefits to the local communities, despite it is still small the number of cities which have been attended by this regulation for solid waste management. On the other hand, it can be noticed that some operational and environmental issues remain to be addressed in the visited facilities.

  18. Tritium conference days; Journees tritium

    Energy Technology Data Exchange (ETDEWEB)

    Garnier-Laplace, J.; Lebaron-Jacobs, L.; Sene, M.; Devin, P.; Chretien, V.; Le Guen, B.; Guetat, Ph.; Baglan, N.; Ansoborlo, E.; Boyer, C.; Masson, M.; Bailly-Du-Bois, P.; Jenkinson, St.; Wakeford, R.; Saintigny, Y.; Romeo, P.H.; Thompson, P.; Leterq, D.; Chastagner, F.; Cortes, P.; Philippe, M.; Paquet, F.; Fournier, M.

    2009-07-01

    This document gathers the slides of the available presentations given during this conference day. Twenty presentations out of 21 are assembled in the document and deal with: 1 - tritium in the environment (J. Garnier-Laplace); 2 - status of knowledge about tritium impact on health (L. Lebaron-Jacobs); 3 - tritium, discrete but present everywhere (M. Sene); 4 - management of tritium effluents from Areva NC La Hague site - related impact and monitoring (P. Devin); 5 - tritium effluents and impact in the vicinity of EDF's power plants (V. Chretien and B. Le Guen); 6 - contribution of CEA-Valduc centre monitoring to the knowledge of atmospheric tritiated water transfers to the different compartments of the environment (P. Guetat); 7 - tritium analysis in environment samples: constraints and means (N. Baglan); 8 - organically-linked tritium: the analyst view (E. Ansoborlo); 9 - study of tritium transfers to plants via OBT/HTO{sub air} and OBT/HTO{sub free} (C. Boyer); 10 - tritium in the British Channel (M. Masson and P. Bailly-Du-Bois); 11 - tritium in British coastal waters (S. Jenkinson); 12 - recent results from epidemiology (R. Wakeford); 13 - effects of tritiated thymidine on hematopoietic stem cells (P.H. Romeo); 14 - tritium management issue in Canada: the point of view from authorities (P. Thompson); 15 - experience feedback of the detritiation process of Valduc centre (D. Leterq); 16 - difficulties linked with tritiated wastes confinement (F. Chastagner); 17 - optimisation of tritium management in the ITER project (P. Cortes); 18 - elements of thought about the management of tritium generated by nuclear facilities (M. Philippe); 19 - CIPR's position about the calculation of doses and risks linked with tritium exposure (F. Paquet); 20 - tritium think tanks (M. Fournier). (J.S.)

  19. Intrinsic bioremediation of landfills interim report

    Energy Technology Data Exchange (ETDEWEB)

    Brigmon, R.L. [Westinghouse Savannah River Company, Aiken, SC (United States); Fliermans, C.B.

    1997-07-14

    Intrinsic bioremediation is a risk management option that relies on natural biological and physical processes to contain the spread of contamination from a source. Evidence is presented in this report that intrinsic bioremediation is occurring at the Sanitary Landfill is fundamental to support incorportion into a Corrective Action Plan (CAP).

  20. Intrinsic bioremediation of landfills interim report

    International Nuclear Information System (INIS)

    Brigmon, R.L.; Fliermans, C.B.

    1997-01-01

    Intrinsic bioremediation is a risk management option that relies on natural biological and physical processes to contain the spread of contamination from a source. Evidence is presented in this report that intrinsic bioremediation is occurring at the Sanitary Landfill is fundamental to support incorportion into a Corrective Action Plan (CAP)

  1. DEP Reported Sanitary Sewer Overflows

    Data.gov (United States)

    Montgomery County of Maryland — Sanitary sewer overflows reported to the Department of Environmental Protection by the Washington Suburban Sanitary Commission or individuals in the County. Update...

  2. Landfill gas

    International Nuclear Information System (INIS)

    Hartnell, Gaynor

    2000-01-01

    Following the UK Government's initiative for stimulating renewable energy through the Non-Fossil Fuel Obligation (NFFO), the UK landfill gas industry has more than trebled in size in just 4 years. As a result, UK companies are now in a strong position to offer their skills and services overseas. Ireland, Greece and Spain also resort heavily to disposal to landfill. Particularly rapid growth of the landfill gas market is expected in the OECD-Pacific and NAFTA areas. The article explains that landfill gas is a methane-rich mixture produced by anaerobic decomposition of organic wastes in landfills: under optimum conditions, up to 500 cubic meters of gas can be obtained from 1 tonne of biodegradable waste. Data on the number and capacity of sites in the UK are given. The Landfill Gas Association runs courses to counteract the skills shortage in the UK, and tailored courses for overseas visitors are planned

  3. Tritium sources

    International Nuclear Information System (INIS)

    Glodic, S.; Boreli, F.

    1993-01-01

    Tritium is the only radioactive isotope of hydrogen. It directly follows the metabolism of water and it can be bound into genetic material, so it is very important to control levels of contamination. In order to define the state of contamination it is necessary to establish 'zero level', i.e. actual global inventory. The importance of tritium contamination monitoring increases with the development of fusion power installations. Different sources of tritium are analyzed and summarized in this paper. (author)

  4. Tritium storage

    International Nuclear Information System (INIS)

    Hircq, B.

    1989-01-01

    A general synthesis about tritium storage is achieved in this paper and a particular attention is given to practical application in the Fusion Technology Program. Tritium, storage under gaseous form and solid form are discussed (characteristics, advantages, disadvantages and equipments). The way of tritium storage is then discussed and a choice established as a function of a logic which takes into account the main working parameters

  5. FY 1999 achievement report on the supporting project to form energy/environmental technology verification project - International joint verification research project. Research on the waste-fueled power system using gases emitted from the sanitary landfill in Samarkand city; 1999 nendo Samarkand shi ni okeru umetate gas wo riyoshita gomi hatsuden system no kenkyu

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2000-03-01

    In Samarkand city, Uzbekistan, solid waste materials are treated in the sanitary landfill. However, requests were made from the Minister of Communal Services for the construction of power system as a part of the effective waste utilization and the study of the integrated waste collection system enabling the construction of a power system. There is only one waste dumping site in Samarkand city. That started to be used in the beginning of the 1970s. That was planned to be closed in 2000, but is now planned to used till 2005. Therefore, it is urgent to reduce the volume of waste. The incineration of waste is the most suitable for it. In the study of a power system by using waste effectively, it is important to efficiently recover the methane gas emitted from the waste dumping site, to study the adoption of the repowering system using the combustion gas of methane gas for increasing the generated output of waste-fueled power generation facilities, and to heighten the low power generation efficiency. This study includes the survey of the waste discharge amount/composition/heating value, collection of the data on waste collection, and sampling/analysis of gases emitted from the dumping site. The paper reported on the proposals. (NEDO)

  6. Tritium trick

    Science.gov (United States)

    Green, W. V.; Zukas, E. G.; Eash, D. T.

    1971-01-01

    Large controlled amounts of helium in uniform concentration in thick samples can be obtained through the radioactive decay of dissolved tritium gas to He3. The term, tritium trick, applies to the case when helium, added by this method, is used to simulate (n,alpha) production of helium in simulated hard flux radiation damage studies.

  7. Desempenho de sistema de tratamento de lixiviado de aterro sanitário com recirculação do efluente Performance of a sanitary landfill leachate treatment system with effluent recirculation

    Directory of Open Access Journals (Sweden)

    Cláudia Lavina Martins

    2010-12-01

    Full Text Available O objetivo deste estudo foi avaliar o desempenho de um sistema de tratamento de lixiviado de aterro sanitário, em escala piloto, formado por três lagoas em série (L1, L2 e L3 seguidas por um filtro de pedras (FP. Foram estudadas três condições operacionais, verificando-se o efeito da recirculação do efluente da L3 para a L1: 0, 50 e 100% da vazão. O sistema absorveu bem as flutuações de cargas, apresentando remoções superiores a 80% para DBO F, 70% para DQO T e 98% para nitrogênio amoniacal. Na lagoa L2 houve nitrificação parcial, com acúmulo de nitritos. Ocorreu presença marcante do gênero Chlamydomonas nas lagoas L2 e L3 fotossintéticas. Observou-se diminuição da toxicidade do lixiviado, com reduções superiores a 95% na saída do sistema. A melhor eficiência de remoção para as três condições operacionais estudadas foi obtida com 100% de recirculação.The objective of this study was to evaluate the performance of a landfill leachate treatment system, at pilot scale, formed by three in series ponds (L1, L2, and L3 followed by a rock filter. Three operational conditions were studied, assessing the effluent recirculation effect from L3 to L1: 0, 50 and 100% of the flow rate. The system assimilated well the load fluctuations, showing removal efficiencies over 80% for BOD F, 70% for COD T and 98% for ammonia. In the L2 pond there was partial nitrification with nitrite accumulation. It was observed an outstanding presence of the Chlamydomonas gender in photosynthetic ponds L2 and L3. A reduction of the toxicity from the landfill leachate was observed, with reduction of over 95% in the system output. The better removal efficiency for the three studied operational conditions was obtained for 100% of recirculation.

  8. Investigation of tritium in groundwater at Site 300

    International Nuclear Information System (INIS)

    Buddemeier, R.W.

    1985-01-01

    In 1984, landfill monitoring wells at Site 300, a Lawrence Livermore National Laboratory (LLNL) explosive test site, revealed the presence of groundwater contaminated with tritium. These tritium levels were in excess of the State of California drinking water standard. A major investigation was initiated that included a search of records concerning tritium use, disposal, and previous analyses, and a survey of tritium levels in soil, vegetation, and water in contaminated and potentially contaminated areas. Over 50 boreholes were drilled for this investigation to characterize the local hydrogeology and tritium distributions, and a network of soil moisture and groundwater monitoring points was installed. This report presents the work completed through the end of September 1985: the records search; records for drilling completed as part of this study; characterization of the geology, hydrology, and tritium distributions in the contaminated area; and an initial assessment of the probable tritium sources, pathways, and migration rates. 19 refs

  9. Investigation of tritium in groundwater at Site 300

    Energy Technology Data Exchange (ETDEWEB)

    Buddemeier, R.W.

    1985-12-30

    In 1984, landfill monitoring wells at Site 300, a Lawrence Livermore National Laboratory (LLNL) explosive test site, revealed the presence of groundwater contaminated with tritium. These tritium levels were in excess of the State of California drinking water standard. A major investigation was initiated that included a search of records concerning tritium use, disposal, and previous analyses, and a survey of tritium levels in soil, vegetation, and water in contaminated and potentially contaminated areas. Over 50 boreholes were drilled for this investigation to characterize the local hydrogeology and tritium distributions, and a network of soil moisture and groundwater monitoring points was installed. This report presents the work completed through the end of September 1985: the records search; records for drilling completed as part of this study; characterization of the geology, hydrology, and tritium distributions in the contaminated area; and an initial assessment of the probable tritium sources, pathways, and migration rates. 19 refs.

  10. Hanford Site Solid Waste Landfill permit application

    International Nuclear Information System (INIS)

    1991-01-01

    Daily activities at the Hanford Site generate sanitary solid waste (nonhazardous and nonradioactive) that is transported to and permanently disposed of at the Hanford Site Solid Waste Landfill. This permit application describes the manner in which the solid Waste Landfill will be operated under Washington State Department of Ecology Minimum Functional Standards for Solid Waste Handling, Washington Administrative Code 173-304. The solid Waste Landfill is owned by the US Department of Energy -- Richland Operations Office and is used for disposal of solid waste generated at the US Department of Energy Hanford Site. The jurisdictional health department's permit application form for the Solid Waste Landfill is provided in Chapter 1.0. Chapter 2.0 provides a description of the Hanford Site and the Solid Waste Landfill and reviews applicable locational, general facility, and landfilling standards. Chapter 3.0 discusses the characteristics and quantity of the waste disposed of in the Solid Waste Landfill. Chapter 4.0 reviews the regional and site geology and hydrology and the groundwater and vadose zone quality beneath the landfill. Chapters 5.0, 6.0, and 7.0 contain the plan of operation, closure plan, and postclosure plan, respectively. The plan of operation describes the routine operation and maintenance of the Solid Waste Landfill, the environmental monitoring program, and the safety and emergency plans. Chapter 5.0 also addresses the operational cover, environmental controls, personnel requirements, inspections, recordkeeping, reporting, and site security. The postclosure plan describes requirements for final cover maintenance and environmental monitoring equipment following final closure. Chapter 8.0 discusses the integration of closure and postclosure activities between the Solid Waste Landfill and adjacent Nonradioactive Dangerous Waste Landfill. 76 refs., 48 figs, 15 tabs

  11. Tritium autoradiography

    International Nuclear Information System (INIS)

    Caskey, G.R. Jr.

    1981-01-01

    Hydrogen distribution and diffusion within many materials may be investigated by autoradiography if the radioactive isotope tritium is used in the study. Tritium is unstable and decays to helium-3 by emission of a low energy (18 keV) beta particle which may be detected photographically. The basic principles of tritium autoradiography will be discussed. Limitations are imposed on the technique by: (1) the low energy of the beta particles; (2) the solubility and diffusivity of hydrogen in materials; and (3) the response of the photographic emulsion to beta particles. These factors control the possible range of application of tritium autoradiography. The technique has been applied successfully to studies of hydrogen solubility and distribution in materials and to studies of hydrogen damage

  12. The biological degradation as an energy option, determination of the effects of the aerobic phase on the subsequent production of biogas in a sanitary landfill; La degradacion biologica como una opcion energetica, determinacion de los efectos de la fase aerobia sobre la subsecuente produccion de biogas en un relleno sanitario

    Energy Technology Data Exchange (ETDEWEB)

    Aguilar Juarez, Oscar [Asesoria de Servicios Ambientales del Bajio (ASSB), (Mexico)

    2010-07-01

    The present work deals with the energy evaluation of biological processes as energy source and is based on works concerning laboratory, pilot and field research. The objective of the research is to integrate the effect of the aerobic phase during the process of degradation of organic residues (basically the organic fraction of domestic residues), where the last aim is the biogas production. The usefulness of the results is reflected in the suitable estimation of the filling of a sanitary landfill considering the composition of the residues deposited and the effects that this management will have on the run-up time of the same and the velocity of biogas production. Finally, integrates a reflection on the intrinsic energy implications of the process and of the biogas yielding, which is evaluated as well as energy source. [Spanish] El presente trabajo trata sobre la valoracion energetica de procesos biologicos como fuente de energia y se basa en trabajos de investigacion a nivel de laboratorio, piloto y de campo. El objetivo de la investigacion es integrar el efecto de la fase aerobia durante el proceso de degradacion de residuos organicos (basicamente la fraccion organica de residuos domesticos), donde el fin ultimo es la produccion de biogas. La utilidad de los resultados se refleja en la estimacion adecuada del llenado de un relleno sanitario considerando la composicion de los residuos ahi depositados y los efectos que tendra esta gestion sobre el tiempo de estabilizacion de los mismos y la velocidad de produccion de biogas. Finalmente, se integra una reflexion sobre las implicaciones energeticas intrinsecas al proceso y del rendimiento de biogas, el cual a su vez es valorizado como fuente de energia.

  13. LANDFILL LEACHATES PRETREATMENT BY OZONATION

    Directory of Open Access Journals (Sweden)

    Jacek Leszczyński

    2016-06-01

    Full Text Available In this paper, the application of ozonation processes for stabilized landfill leachate treatment was investigated. The leachate came from a municipal sanitary landfill located nearby Bielsk Podlaski. The average values of its main parameters were: pH 8.23; COD 870 mgO2/dm3; BOD 90 mgO2/dm3; NH4+ 136.2 mgN/dm3; UV254 absorbance 0.312 and turbidity 14 NTU. The ozone dosages used were in the range of 115.5 to 808.5 mgO3/dm3 of the leachate. The maximum COD, color and UV254 absorbance removal wa.5 mgO3/dm3. After oxidation, the ratio of BOD/COD was increased from 0.1 up to 0.23.

  14. Hanford Site Solid Waste Landfill permit application. Revision 1

    International Nuclear Information System (INIS)

    1993-01-01

    Both nonhazardous and nonradioactive sanitary solid waste are generated at the Hanford Site. This permit application describes the manner in which the Solid Waste Landfill will be operated. A description is provided of the landfill, including applicable locational, general facility, and landfilling standards. The characteristics and quantity of the waste disposed of are discussed. The regional and site geology and hydrology and the groundwater and vadose zone quality beneath the landfill are reviewed. A plan is included of operation, closure, and postclosure. This report addresses the operational cover, environmental controls, personnel requirements, inspections, recordkeeping, reporting, and site security. The integration of closure and postclosure activities between the Solid Waste Landfill and adjacent Nonradioactive Dangerous Waste Landfill is discussed

  15. Application of environmental isotopes to characterize landfill gases and leachate

    International Nuclear Information System (INIS)

    Liu, C.L.; Hackley, K.C.; Baker, J.

    1992-01-01

    Environmental isotopes have been used to help characterize landfill gases and leachate for the purpose of identifying leachate and/or gas contamination in surrounding monitoring wells. Carbon isotopes (C-13/C-12 and C-14), hydrogen isotopes (H-3 and H-2/H-1) and oxygen isotopes (O-18/O-16) were used to characterize methane, carbon dioxide and leachate produced from two municipal landfills in northeastern Illinois. The isotopic results from the landfill-derived gases and leachate are compared to isotopic compositions of groundwater and gases from nearby monitoring wells. C-14 activity of landfill CH 4 is high compared to CH 4 normally found in subsurface sediments. For this study C-14 activities of the landfill methane range from 129--140 PMC. The C-14 of the dissolved inorganic carbon (DIC) of the leachate samples also have relatively high activities, ranging from 126--141 PMC. The δC-13 and δD values for CH 4 from the landfills fall within a range of values representative of microbial methane produced by acetate-fermentation. The δC-13 of the CO 2 and the DIC are very positive, ranging from 8--14 per-thousand for CO 2 and 13--22 per-thousand for DIC. The δO-18 values of the leachates are similar to current meteoric water values, however, two of the leachate samples are significantly enriched in deuterium by approximately 65 per-thousand. Tritium values of the leachate water are generally higher than expected. For one landfill the tritium activity ranges from 227--338 TU, for the second landfill the tritium activity is approximately 1,300 TU. Compared to tritium levels in normal groundwater, these higher tritium values in the leachates indicate that this isotope has the potential to be an effective tracer for detecting leachate migration

  16. Analysis of the organically bound tritium

    International Nuclear Information System (INIS)

    Baglan, N.; Alanic, G.

    2011-01-01

    In environmental samples, tritium is very often combined with the fraction of bulk water accumulated in the sample but also in the form of organically bound tritium. When the tritium is organically bound, 2 forms can coexist: the exchangeable fraction and the non-exchangeable fraction. The analysis of the different forms of tritium present in the sample is necessary to assess the sanitary hazards due to tritium. The total tritium is obtained from the analysis of the water released when the fresh sample is burnt while the organically bound tritium is obtained from the analysis of the water released when the dry extract of the sample is burnt. The measurement of the exchangeable fraction and the non-exchangeable fraction requires an additional stage of labile exchange. The exchangeable fraction is determined from the analysis of the water released during the labile exchange and the non-exchangeable fraction is determined from the water released during the combustion of the dry extract of the labile exchange

  17. Pilot investigations of surface parts of three closed landfills and factors affecting them.

    Science.gov (United States)

    Saarela, Jouko

    2003-05-01

    Aftercare of closed sanitary landfills in a major environmental problem. Rehabilitation of the landfill with vegetation and reducing leachate production are two issues that must be dealt. For this reason, Finnish Environment Institute has conducted several projects on closed landfills. This research aims at determining the physical and chemical properties of the soils at three closed landfills in Helsinki, Finland. Research was conducted to understand the impact by studying the following properties: Chemical, nutrient metal, gamma and radon analysis of surface soils of three closed landfills in Helsinki area.

  18. INPP Landfill

    International Nuclear Information System (INIS)

    Dahlberg, Jan; Bergstroem, Ulla

    2004-06-01

    The objective of this report is to propose the basic design for final disposal of Very Low Level Radioactive Waste (VLLW) produced at the Ignalina Nuclear Power Plant and at other small waste producers in Lithuania. Considering the safety for the environment, as well as the construction costs, it has been decided that the repository will be of a landfill type based on the same design principles as similar authorised facilities in other countries. It has also been decided that the location of the landfill shall be in the vicinity of the Ignalina Nuclear Power Plant (INPP)

  19. Tritium immobilisation

    International Nuclear Information System (INIS)

    Bridger, N.J.

    1982-01-01

    Tritium is immobilised for long term storage by absorption in a hydridable/tritidable material, such as zirconium. A gas permeable container is packed with the material in the form of sponge fragments, rods or tubes, and a gaseous mixture of hydrogen and tritium introduced into the container whilst the container is at a temperature of about 600 deg C or above. Thermal expansion of the material during reaction with the gaseous mixture compacts the material into a coherent body in the container relatively free from finely divided hydride/ tritide material. (author)

  20. Biogas of sanitary fillers

    International Nuclear Information System (INIS)

    Serrano Camacho, Ciro

    2007-01-01

    The author proposes a methodology for the preliminary estimation of the energetic potential and environmental improvement derivates of the implementation of these technologies that allows to make the first estimative of biogas generation of sanitary fillers with base in the results of the simulation of three predictive model: One Mexican, other denominated Scholl-Canyon of North American origin and the designed by the EPA. The three models use different versions and constants for a differential equation of degradation of first degree

  1. ANCLI's conclusions and recommendations made after the ANCLI colloquium 'Tritium, discrete, but present everywhere'

    International Nuclear Information System (INIS)

    Sene, M.

    2009-01-01

    The authors briefly state the conclusions of the colloquium about the presence of tritium in the environment, its sanitary impact, the re-examination of a management based on release, the need to reduce tritium production. The recommendations are also indicated: to continue researches on organically bound tritium, not to allow any release increase as long as effects are not better known. The role of the ANCLI is outlined

  2. Landfill mining: Development of a cost simulation model.

    Science.gov (United States)

    Wolfsberger, Tanja; Pinkel, Michael; Polansek, Stephanie; Sarc, Renato; Hermann, Robert; Pomberger, Roland

    2016-04-01

    Landfill mining permits recovering secondary raw materials from landfills. Whether this purpose is economically feasible, however, is a matter of various aspects. One is the amount of recoverable secondary raw material (like metals) that can be exploited with a profit. Other influences are the costs for excavation, for processing the waste at the landfill site and for paying charges on the secondary disposal of waste. Depending on the objectives of a landfill mining project (like the recovery of a ferrous and/or a calorific fraction) these expenses and revenues are difficult to assess in advance. This situation complicates any previous assessment of the economic feasibility and is the reason why many landfills that might be suitable for landfill mining are continuingly operated as active landfills, generating aftercare costs and leaving potential hazards to later generations. This article presents a newly developed simulation model for landfill mining projects. It permits identifying the quantities and qualities of output flows that can be recovered by mining and by mobile on-site processing of the waste based on treatment equipment selected by the landfill operator. Thus, charges for disposal and expected revenues from secondary raw materials can be assessed. Furthermore, investment, personnel, operation, servicing and insurance costs are assessed and displayed, based on the selected mobile processing procedure and its throughput, among other things. For clarity, the simulation model is described in this article using the example of a real Austrian sanitary landfill. © The Author(s) 2016.

  3. Biogas movements in sanitary landdfills; Movimiento de biogas en rellenos sanitarios

    Energy Technology Data Exchange (ETDEWEB)

    Vidales A, Humberto

    1988-12-31

    This paper shows a model to study the physical and kinetic equations that determine the movement and diffusion of the biogas in sanitary landfills. This model for biogas flow was made in function of pressure, temperature, waste porosity and permeability, due to a diffusion coefficient of biogas determination 6 refs., 4 figs.

  4. Ocorrência de bactérias clinicamente relevantes nos resíduos de serviços de saúde em um aterro sanitário brasileiro e perfil de susceptibilidade a antimicrobianos Occurrence of clinically relevant bacteria in health service waste in a Brazilian sanitary landfill and antimicrobial susceptibility profile

    Directory of Open Access Journals (Sweden)

    Thiago César Nascimento

    2009-08-01

    Full Text Available Os resíduos de serviços de saúde suscitam polêmica quanto a importância para a saúde humana, animal e ambiental. Avaliou-se a ocorrência de bactérias clinicamente relevantes na pilha de resíduos de serviços de saúde em um aterro sanitário e seu perfil de susceptibilidade aos antimicrobianos. Alíquotas de chorume foram processadas para isolamento seletivo de Staphylococcus sp, bastonetes Gram negativos da família Enterobacteriaceae e não fermentadores. Resistência bacteriana a todos os antimicrobianos testados foi observada em todos os grupos microbianos, além de resistência a mais de uma droga. Os resultados permitem sugerir que bactérias viáveis nos resíduos de serviços de saúde representam riscos à saúde humana e animal. Além disso, a ocorrência de linhagens multirresistentes sustenta a hipótese dos resíduos de serviços de saúde atuarem como reservatórios de marcadores de resistência, com impacto ambiental. A falta de legislação regional de segregação, tratamento e destino de resíduos podem expor diferentes populações a riscos de transmissão de doenças infecciosas associadas a microrganismos multirresistentes.Health service waste gives rise to controversy regarding its importance for human, animal and environmental health. Occurrences of clinically relevant bacteria in piles of health service waste in a sanitary landfill and their antimicrobial susceptibility profile were evaluated. Aliquots of leachate were processed for selective isolation of Staphylococcus sp, Gram-negative rods of the Enterobacteriaceae family and non-fermenters. Bacterial resistance to all the antimicrobials tested was observed in all microbial groups, including resistance to more than one drug. The results make it possible to suggest that viable bacteria in health service waste represent risks to human and animal health. Furthermore, occurrences of multiresistant strains support the hypothesis that health service waste acts as a

  5. Avaliação dos níveis de metais pesados em efluente líquido percolado do aterro sanitário de Paranavaí, Estado do Paraná, Brasil = Assessment of heavy metal levels in percolated liquid from sanitary landfill in Paranavaí, Paraná State, Brazil

    Directory of Open Access Journals (Sweden)

    Lucila Akiko Nagashima

    2009-01-01

    Full Text Available O percolado pode conter diversas substâncias químicas com características tóxicas, dentre elas os metais pesados oriundos de vários materiais provenientes de indústrias, atividades agrícolas, laboratórios, hospitais, residências. A contaminação pormetais apresenta amplo espectro de toxicidade que inclui efeitos neurotóxicos, hepatóxicos, nefrotóxicos, teratogênicos, carcinogênicos ou mutagênicos. O objetivo deste trabalho foi aavaliação dos níveis de Cd, Cr, Cu, Mn, Ni, Pb e Zn do percolado gerado no aterro sanitário de Paranavaí - PR. As amostras foram coletadas a partir de setembro de 2006 a julho de 2007, em quatro pontos distintos nas lagoas de tratamento. Para detecção dosmetais utilizou-se o espectrofotômetro de absorção atômica com chama. Os resultados foram comparados com os limites máximos de concentração de metais em efluentes líquidos estabelecidos pela Resolução 397/2008 - Conama (BRASIL, 2008. Verificou-se que os níveis dos metais analisados, com exceção do Pb, estão dentro dos limites permissíveispela legislação ambiental.Percolated liquid may contain several chemical substances with toxic characteristics, among them heavy metals from industrial sources, agricultural activities, laboratories, hospitals and residences. Metal contamination presents a wide array of toxicities, such as neurotoxic, hepatotoxic, nephrotoxic, teratogenic, carcinogenic or mutagenic effects. The objective of this work was to assess the levels of Cd, Cr, Cu, Mn, Ni, Pb, and Zn in percolated liquid produced at the sanitary landfill in Paranavaí. The samples were collected from September of 2006 to July of 2007, at fourdistinct places of the treatment lake. An atomic absorption spectrophotometer with a burner was used to detect the metals. The results were compared with the maximum allowed values for metal concentration present in Resolution 397/2008 – Conama (BRAZIL, 2008.It was verified that the level of analyzed

  6. Sanitary effects of fossil fuels

    International Nuclear Information System (INIS)

    Nifenecker, H.

    2006-01-01

    In this compilation are studied the sanitary effects of fossil fuels, behavioral and environmental sanitary risks. The risks in connection with the production, the transport and the distribution(casting) are also approached for the oil(petroleum), the gas and the coal. Accidents in the home are evoked. The risks due to the atmospheric pollution are seen through the components of the atmospheric pollution as well as the sanitary effects of this pollution. (N.C.)

  7. Removal of COD and Colour from Sanitary Landfill Leachate by ...

    African Journals Online (AJOL)

    flocculation process using FeCl3 as a conventional coagulant and Ca(OH)2 as base-precipitant. The second method involved integration of Fenton's reagent into the coagulation/flocculation process. Concentration of FeCl3 that reduced chemical ...

  8. Garbage Pollution Has a Solution: The Sanitary Landfill.

    Science.gov (United States)

    Andresen, Ruth

    The principle ways in which communities solve the growing problems of solid waste disposal are studied in this set of audio-visual materials prepared for grades 6-12. A 58-frame colored filmstrip, cassette tape narration, and teacher's guide focus upon the Monterey Bay area of California. Topics examined range from types of disposal sites, the…

  9. The new Waste Law: Challenging opportunity for future landfill operation in Indonesia.

    Science.gov (United States)

    Meidiana, Christia; Gamse, Thomas

    2011-01-01

    The Waste Law No. 18/2008 Article 22 and 44 require the local governments to run environmentally sound landfill. Due to the widespread poor quality of waste management in Indonesia, this study aimed to identify the current situation by evaluating three selected landfills based on the ideal conditions of landfill practices, which are used to appraise the capability of local governments to adapt to the law. The results indicated that the local governments have problems of insufficient budget, inadequate equipment, uncollected waste and unplanned future landfill locations. All of the selected landfills were partially controlled landfills with open dumping practices predominating. In such inferior conditions the implementation of sanitary landfill is not necessarily appropriate. The controlled landfill is a more appropriate solution as it offers lower investment and operational costs, makes the selection of a new landfill site unnecessary and can operate with a minimum standard of infrastructure and equipment. The sustainability of future landfill capacity can be maintained by utilizing the old landfill as a profit-oriented landfill by implementing a landfill gas management or a clean development mechanism project. A collection fee system using the pay-as-you-throw principle could increase the waste income thereby financing municipal solid waste management.

  10. Sanitary surveillance and bioethics

    Directory of Open Access Journals (Sweden)

    Volnei Garrafa

    2017-08-01

    Full Text Available Regulatory practices in the field of health surveillance are indispensable. The aim of this study is to show ‒ taking the Brazilian National Surveillance Agency, governing body of sanitary surveillance in Brazil as a reference ‒ that bioethics provides public bodies a series of theoretical tools from the field of applied ethics for the proper exercise and control of these practices. To that end, the work uses two references of bioethics for the development of a comparative and supportive analysis to regulatory activities in the field of health surveillance: the Universal Declaration on Bioethics and Human Rights of Unesco and the theory of intervention bioethics. We conclude that organizations and staff working with regulatory activities can take advantage of the principles and frameworks proposed by bioethics, especially those related to the Declaration and the theory of intervention bioethics, the latter being set by the observation and use of the principles of prudence, precaution, protection and prevention.

  11. Applying of Electrical Imaging Survey (EIS) to Evaluate Leachate Pollution in Underground Area of Informal Landfill

    DEFF Research Database (Denmark)

    Du, Song; Wang, Di; Mou, Zishen

    2014-01-01

    An informal landfill is an open dump that pollutes the underground environment because it lacks an impervious liner. The leakage of such a landfill is unidirectional and thus difficult to directly test. This study uses electrical imaging survey to evaluate the pollution of the underground...... environment of an informal landfill for municipal solid waste in Beijing. We hypothesize that every location has a specific resistivity resulting from the leachate. We use the membership function of fuzzy mathematics to quantitatively represent the pollution of the underground environment in the sanitary...... landfill. The results are consistent with borehole data....

  12. Magmatic tritium

    International Nuclear Information System (INIS)

    Goff, F.; Aams, A.I.; McMurtry, G.M.; Shevenell, L.; Pettit, D.R.; Stimac, J.A.; Werner, C.

    1997-01-01

    This is the final report of a three-year, Laboratory-Directed Research and Development (LDRD) project at the Los Alamos National Laboratory. Detailed geochemical sampling of high-temperature fumaroles, background water, and fresh magmatic products from 14 active volcanoes reveal that they do not produce measurable amounts of tritium ( 3 H) of deep origin ( 2 O). On the other hand, all volcanoes produce mixtures of meteoric and magmatic fluids that contain measurable 3 H from the meteoric end-member. The results show that cold fusion is probably not a significant deep earth process but the samples and data have wide application to a host of other volcanological topics

  13. Landfill is an important atmospheric mercury emission source

    Institute of Scientific and Technical Information of China (English)

    FENG Xinbin; TANG Shunlin; LI Zhonggen; WANG Shaofeng; LIANG Lian

    2004-01-01

    Since municipal wastes contain refuses with high mercury contents, incineration of municipal wastes becomes the major anthropogenic atmospheric mercury emission source. In China, landfills are however the main way to dispose of municipal wastes. Total gaseous mercury (TGM) concentrations in landfill gas of Gaoyan sanitary landfill located in suburb of Guiyang City were monitored using a high temporal resolved automated mercury analyzer, and mono-methylmercury (MMHg) and dimethylmercury (DMHg) concentrations in landfill gas were also measured using GC coupled with the cold vapor atomic fluorescence (CVAFS) method. Meanwhile, the TGM exchange fluxes between exposed waste and air and the soil surface of the landfill and air, were measured using low Hg blank quartz flux chamber coupled with high temporal resolved automated mercury analyzer technique. TGM concentrations in landfill gas from half year filling area averaged out at 665.52±291.25 ng/m3, which is comparable with TGM concentrations from flue gas of a small coal combustion boiler in Guiyang. The average MMHg and DMHg concentrations averaged out at 2.06±1.82 ng/m3 and 9.50±5.18 ng/m3, respectively. It is proven that mercury emission is the predominant process at the surfaces of both exposed wastes and soil of landfill. Landfills are not only TGM emission source, but also methylmercury emission source to the ambient air. There are two ways to emit mercury to the air from landfills, one is with the landfill gas through landfill gas duct, and the other through soil/air exchange. The Hg emission processes from landfills are controlled by meteorological parameters.

  14. Nitrogen Removal from Landfill Leachate by Microalgae

    Science.gov (United States)

    Pereira, Sérgio F. L.; Gonçalves, Ana L.; Moreira, Francisca C.; Silva, Tânia F. C. V.; Vilar, Vítor J. P.; Pires, José C. M.

    2016-01-01

    Landfill leachates result from the degradation of solid residues in sanitary landfills, thus presenting a high variability in terms of composition. Normally, these effluents are characterized by high ammoniacal-nitrogen (N–NH4+) concentrations, high chemical oxygen demands and low phosphorus concentrations. The development of effective treatment strategies becomes difficult, posing a serious problem to the environment. Phycoremediation appears to be a suitable alternative for the treatment of landfill leachates. In this study, the potential of Chlorella vulgaris for biomass production and nutrients (mainly nitrogen and phosphorus) removal from different compositions of a landfill leachate was evaluated. Since microalgae also require phosphorus for their growth, different loads of this nutrient were evaluated, giving the following N:P ratios: 12:1, 23:1 and 35:1. The results have shown that C. vulgaris was able to grow in the different leachate compositions assessed. However, microalgal growth was higher in the cultures presenting the lowest N–NH4+ concentration. In terms of nutrients uptake, an effective removal of N–NH4+ and phosphorus was observed in all the experiments, especially in those supplied with phosphorus. Nevertheless, N–NO3− removal was considered almost negligible. These promising results constitute important findings in the development of a bioremediation technology for the treatment of landfill leachates. PMID:27869676

  15. Tritium dosimetry and standardization

    International Nuclear Information System (INIS)

    Balonov, M.I.

    1983-01-01

    Actual problem of radiation hygiene such as an evaluation of human irradiation hazard due to a contact with tritium compounds both in industrial and public spheres is under discussion. Sources of tritium release to environment are characterized. Methods of tritium radiation monitoring are discussed. Methods of dosimetry of internal human exposure resulted from tritium compounds are developed on the base of modern representations on metbolism and tritium radiobiological effect. A system of standardization of permissible intake of tritium compounds for personnel and persons of population is grounded. Some protection measures are proposed as applied to tritium overdosage

  16. Tritium accountancy

    International Nuclear Information System (INIS)

    Avenhaus, R.; Spannagel, G.

    1995-01-01

    Conventional accountancy means that for a given material balance area and a given interval of time the tritium balance is established so that at the end of that interval of time the book inventory is compared with the measured inventory. In this way, an optimal effectiveness of accountancy is achieved. However, there are still further objectives of accountancy, namely the timely detection of anomalies as well as the localization of anomalies in a major system. It can be shown that each of these objectives can be optimized only at the expense of the others. Recently, Near-Real-Time Accountancy procedures have been studied; their methodological background as well as their merits will be discussed. (orig.)

  17. Municipal solid wastes (RSU) treatment in land filled controlled: Of its sanitary problems to energy production

    International Nuclear Information System (INIS)

    Urzola C, R.A.

    1995-01-01

    Excessive world wastes production generates constant preoccupations with relation to its management. The methods of classic elimination as sanitary landfill controlled as compared to controvertible incineration and gasification plants as well as expectations created in connection with practices of recycling, its are intensive discussions motive between town halls, technical specialists, ecologists and general public. What is certain is that wastes in the last 30 years have been valued economically. Today the wastes are appreciated by certain sectors that begin to monopolize the recycling line because they see an excellent business. All methods of residues elimination produce at same time other wastes. Solid nature wastes generally end in the landfill and semi-liquid waste are dehydrated with same objective. In the present Thesis, without intending to say that the landfill processing will be the better option, is outlined the form of optimizing the utilization of same. It's demonstrated that landfill, furthermore to fulfil its sanitary function, are converted into an energetic alternative with utilization of flammable gas generated in them, something which represents an interesting value added if is converted into source of welfare for social and economically kernels, as happens in peripheries of the sanitary landfill at large Latin American cities. Of other side are considered principal aspects that intervene in methane gas generation and quality and utilization alternatives. Finally it is made emphasis in environmental situation at European and international level about the landfill gases, how is outlined greenhouse effect topic, what are environmental actions for year 2000 and are related some biogas utilization experiences at Europe

  18. Environmental Isotope Characteristics of Landfill Leachates and Gases

    Science.gov (United States)

    Hackley, Keith C.; Liu, Chao-Li; Coleman, D.D.

    1996-01-01

    The isotopic characteristics of municipal landfill leachate and gases (carbon dioxide and methane) are unique relative to the aqueous and gaseous media in most other natural geologic environments. The ??13 C of the CO2 in landfills is significantly enriched in 13C, with values as high as +20??? reported. The ?? 13C and ??D values of the methane fall within a range of values representative of microbial methane produced primarily by the acetate-fermentation process. The ??D of landfill leachate is strongly enriched in deuterium, by approximately 30??? to nearly 60??? relative to local average precipitation values. This deuterium enrichment is undoubtedly due to the extensive production of microbial methane within the limited reservoir of a landfill. The concentration of the radiogenic isotopes, 14C and 3H, are significantly elevated in both landfill leachate and methane. The 14C values range between approximately 120 and 170 pMC and can be explained by the input of organic material that was affected by the increased 14C content of atmospheric CO2 caused by atmospheric testing of nuclear devices. The tritium measured in leachate, however, is often too high to be explained by previous atmospheric levels and must come from material buried within the landfill. The unique isotopic characteristics observed in landfill leachates and gases provide a very useful technique for confirming whether contamination is from a municipal landfill or some other local source.

  19. Characterization and tropical seasonal variation of leachate: results from landfill lysimeter studied.

    Science.gov (United States)

    Rafizul, Islam M; Alamgir, Muhammed

    2012-11-01

    This study aims to characterize the leachate and to investigate the tropical climatic influence on leachate characteristics of lysimeter studies under different seasonal variations at KUET campus, Bangladesh. Three different situations of landfill were considered here as well as both the open dump lysimeter-A having a base liner and sanitary landfill lysimeter-B and C at two different types of cap liner were simulated. The leachate characteristics, leachate generation and climatic influence parameter had been continually monitored since June 2008 to May 2010, these periods cover both the dry and rainy season. The leachate generation had followed the rainfall pattern and the open dump lysimeter-A without top cover was recorded to have highest leachate generation. Moreover, the open dump lysimeter-A had lower total kjeldahl nitrogen (TKN), ammonia nitrogen (NH(4)-N) and TKN load, while both the COD concentration and load was higher compared with sanitary landfill lysimeter-B and C. In addition, sanitary landfill lysimeter-B, not only had lowest leachate generation, but also produces reasonable low COD concentration and load compared with open dump lysimeter-A. Result reveals that lysimeter operational mode had direct effect on leachate quality. Finally, it can be concluded that the knowledge of leachate quality will be useful in planning and providing remedial measures of proper liner system in sanitary landfill design and leachate treatment. Copyright © 2012 Elsevier Ltd. All rights reserved.

  20. Landfill stabilization focus area: Technology summary

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1995-06-01

    Landfills within the DOE Complex as of 1990 are estimated to contain 3 million cubic meters of buried waste. The DOE facilities where the waste is predominantly located are at Hanford, the Savannah River Site (SRS), the Idaho National Engineering Laboratory (INEL), the Los Alamos National Laboratory (LANL), the Oak Ridge Reservation (ORR), the Nevada Test Site (NTS), and the Rocky Flats Plant (RFP). Landfills include buried waste, whether on pads or in trenches, sumps, ponds, pits, cribs, heaps and piles, auger holes, caissons, and sanitary landfills. Approximately half of all DOE buried waste was disposed of before 1970. Disposal regulations at that time permitted the commingling of various types of waste (i.e., transuranic, low-level radioactive, hazardous). As a result, much of the buried waste throughout the DOE Complex is presently believed to be contaminated with both hazardous and radioactive materials. DOE buried waste typically includes transuranic-contaminated radioactive waste (TRU), low-level radioactive waste (LLW), hazardous waste per 40 CFR 26 1, greater-than-class-C waste per CFR 61 55 (GTCC), mixed TRU waste, and mixed LLW. The mission of the Landfill Stabilization Focus Area is to develop, demonstrate, and deliver safer,more cost-effective and efficient technologies which satisfy DOE site needs for the remediation and management of landfills. The LSFA is structured into five technology areas to meet the landfill remediation and management needs across the DOE complex. These technology areas are: assessment, retrieval, treatment, containment, and stabilization. Technical tasks in each of these areas are reviewed.

  1. Landfill stabilization focus area: Technology summary

    International Nuclear Information System (INIS)

    1995-06-01

    Landfills within the DOE Complex as of 1990 are estimated to contain 3 million cubic meters of buried waste. The DOE facilities where the waste is predominantly located are at Hanford, the Savannah River Site (SRS), the Idaho National Engineering Laboratory (INEL), the Los Alamos National Laboratory (LANL), the Oak Ridge Reservation (ORR), the Nevada Test Site (NTS), and the Rocky Flats Plant (RFP). Landfills include buried waste, whether on pads or in trenches, sumps, ponds, pits, cribs, heaps and piles, auger holes, caissons, and sanitary landfills. Approximately half of all DOE buried waste was disposed of before 1970. Disposal regulations at that time permitted the commingling of various types of waste (i.e., transuranic, low-level radioactive, hazardous). As a result, much of the buried waste throughout the DOE Complex is presently believed to be contaminated with both hazardous and radioactive materials. DOE buried waste typically includes transuranic-contaminated radioactive waste (TRU), low-level radioactive waste (LLW), hazardous waste per 40 CFR 26 1, greater-than-class-C waste per CFR 61 55 (GTCC), mixed TRU waste, and mixed LLW. The mission of the Landfill Stabilization Focus Area is to develop, demonstrate, and deliver safer,more cost-effective and efficient technologies which satisfy DOE site needs for the remediation and management of landfills. The LSFA is structured into five technology areas to meet the landfill remediation and management needs across the DOE complex. These technology areas are: assessment, retrieval, treatment, containment, and stabilization. Technical tasks in each of these areas are reviewed

  2. STAR facility tritium accountancy

    International Nuclear Information System (INIS)

    Pawelko, R. J.; Sharpe, J. P.; Denny, B. J.

    2008-01-01

    The Safety and Tritium Applied Research (STAR) facility has been established to provide a laboratory infrastructure for the fusion community to study tritium science associated with the development of safe fusion energy and other technologies. STAR is a radiological facility with an administrative total tritium inventory limit of 1.5 g (14,429 Ci) [1]. Research studies with moderate tritium quantities and various radionuclides are performed in STAR. Successful operation of the STAR facility requires the ability to receive, inventory, store, dispense tritium to experiments, and to dispose of tritiated waste while accurately monitoring the tritium inventory in the facility. This paper describes tritium accountancy in the STAR facility. A primary accountancy instrument is the tritium Storage and Assay System (SAS): a system designed to receive, assay, store, and dispense tritium to experiments. Presented are the methods used to calibrate and operate the SAS. Accountancy processes utilizing the Tritium Cleanup System (TCS), and the Stack Tritium Monitoring System (STMS) are also discussed. Also presented are the equations used to quantify the amount of tritium being received into the facility, transferred to experiments, and removed from the facility. Finally, the STAR tritium accountability database is discussed. (authors)

  3. Water balance modeling for estimation of residence time of water in a full-scale landfill using a data-assimilation approach

    NARCIS (Netherlands)

    Heimovaara, T.J.; Bun, A.; Van Turnhout, A.G.

    2015-01-01

    In order to develop novel approaches for reducing the after-care of Municipal Solid Waste (MSW) sanitary landfills methods are required with which we can quantify the emission potential present in waste bodies. Currently full-scale experiments are being prepared at three Dutch landfills based on

  4. Landfill design in Serbia

    Directory of Open Access Journals (Sweden)

    Karanac Milica

    2015-01-01

    Full Text Available Waste disposal is an important element of integrated waste management. In order to dispose of waste that is free of environmental risk, the proper design of landfills during their construction and/or closure is necessary. The first section of the paper presents the current state of landfills in Serbia, the second deals with problems in project design of landfills, especially in regard to their: a program of waste disposal; b impermeable layer; c leaching collection and treatment; and d gas collection and treatment. Analysis shows that many modern landfills in Serbia do not meet environmental protection requirements, therefore, they need reconstruction. All existing landfills owned by municipalities, as well as illegal dump sites, should be adequately closed. This paper presents the guidelines for successful landfill design which are to serve to meet the requirements and recommendations of Serbian and European regulations. Sound design of landfill technological elements should insure full sustainability of landfills in Serbia.

  5. Leachate generation from landfill in a semi-arid climate: A qualitative and quantitative study from Sousse, Tunisia.

    Science.gov (United States)

    Frikha, Youssef; Fellner, Johann; Zairi, Moncef

    2017-09-01

    Despite initiatives for enhanced recycling and waste utilization, landfill still represents the dominant disposal path for municipal solid waste (MSW). The environmental impacts of landfills depend on several factors, including waste composition, technical barriers, landfill operation and climatic conditions. A profound evaluation of all factors and their impact is necessary in order to evaluate the environmental hazards emanating from landfills. The present paper investigates a sanitary landfill located in a semi-arid climate (Tunisia) and highlights major differences in quantitative and qualitative leachate characteristics compared to landfills situated in moderate climates. Besides the qualitative analysis of leachate samples, a quantitative analysis including the simulation of leachate generation (using the HELP model) has been conducted. The results of the analysis indicate a high load of salts (Cl, Na, inorganic nitrogen) in the leachate compared to other landfills. Furthermore the simulations with HELP model highlight that a major part of the leachate generated originates form the water content of waste.

  6. Oxidative Tritium Decontamination System

    International Nuclear Information System (INIS)

    Gentile, Charles A.; Parker, John J.; Guttadora, Gregory L.; Ciebiera, Lloyd P.

    2002-01-01

    The Princeton Plasma Physics Laboratory, Tritium Systems Group has developed and fabricated an Oxidative Tritium Decontamination System (OTDS), which is designed to reduce tritium surface contamination on various components and items. The system is configured to introduce gaseous ozone into a reaction chamber containing tritiated items that require a reduction in tritium surface contamination. Tritium surface contamination (on components and items in the reaction chamber) is removed by chemically reacting elemental tritium to tritium oxide via oxidation, while purging the reaction chamber effluent to a gas holding tank or negative pressure HVAC system. Implementing specific concentrations of ozone along with catalytic parameters, the system is able to significantly reduce surface tritium contamination on an assortment of expendable and non-expendable items. This paper will present the results of various experimentation involving employment of this system

  7. Tritium activities in Canada

    International Nuclear Information System (INIS)

    Gierszewski, P.

    1995-01-01

    Canadian tritium activites comprise three major interests: utilites, light manufacturers, and fusion. There are 21 operating CANDU reactors in Canada; 19 with Ontario Hydro and one each with Hydro Quebec and New Brunswick Power. There are two light manufacturers, two primary tritium research facilities (at AECL Chalk River and Ontario Hydro Technologies), and a number of industry and universities involved in design, construction, and general support of the other tritium activities. The largest tritum program is in support of the CANDU reactors, which generate tritium in the heavy water as a by-product of normal operation. Currently, there are about 12 kg of tritium locked up in the heavy water coolant and moderator of these reactors. The fusion work is complementary to the light manufacturing, and is concerned with tritium handling for the ITER program. This included design, development and application of technologies related to Isotope Separation, tritium handling, (tritiated) gas separation, tritium-materials interaction, and plasma fueling

  8. The Tritium White Paper

    International Nuclear Information System (INIS)

    2009-01-01

    This publication proposes a synthesis of the activities of two work-groups between May 2008 and April 2010. It reports the ASN's (the French Agency for Nuclear Safety) point of view, describes its activities and actions, and gives some recommendations. It gives a large and detailed overview of the knowledge status on tritium: tritium source inventory, tritium origin, management processes, capture techniques, reduction, tritium metrology, impact on the environment, impacts on human beings

  9. Ozonation of a pretreated landfill leachate: evaluation of recalcitrance removal

    OpenAIRE

    Van Aken, Pieter; Lambert, Nico; Luyten, Jan; Degrève, Jan; Liers, Sven

    2010-01-01

    The sanitary landfill method for the ultimate disposal of solid waste material continues to be widely accepted and used due to its economic advantages. However, water infiltrates through the solid waste and a variety of organic and inorganic pollutants will be dissolved and transported. These leachates may contain large amounts of organic matter, as well as ammonia-nitrogen, heavy metals, chlorinated organic and inorganic salts. The removal of organic material is usual the prerequisite before...

  10. ZEPHYR tritium system

    International Nuclear Information System (INIS)

    Swansiger, W.; Andelfinger, C.; Buchelt, E.; Fink, J.; Sandmann, W.; Stimmelmayr, A.; Wegmann, H.G.; Weichselgartner, H.

    1982-04-01

    The ignition experiment ZEPHYR will need tritium as an essential component of the fuel. The ZEPHYR Tritium Systems are designed as to recycle the fuel directly at the experiment. An amount of tritium, which is significantly below the total throughput, for example 10 5 Ci will be stored in uranium getters and introduced into the torus by a specially designed injection system. The torus vacuum system operates with tritium-tight turbomolecular pumps and multi-stage roots pumps in order to extract and store the spent fuel in intermediate storage tanks at atmospheric pressure. A second high vacuum system, similar in design, serves as to evacuate the huge containments of the neutral injection system. The spent fuel will be purified and subsequently processed by an isotope separation system in which the species D 2 , DT and T 2 will be recovered for further use. This isotope separation will be achieved by a preparative gaschromatographic process. All components of the tritium systems will be installed within gloveboxes which are located in a special tritium handling room. The atmospheres of the gloveboxes and of the tritium rooms are controlled by a tritium monitor system. In the case of a tritium release - during normal operation as well as during an accident - these atmospheres become processed by efficient tritium absorption systems. All ZEPHYR tritium handling systems are designed as to minimize the quantity of tritium released to the environment, so that the stringent German laws on radiological protection are satisfied. (orig.)

  11. TFTR tritium handling concepts

    International Nuclear Information System (INIS)

    Garber, H.J.

    1976-01-01

    The Tokamak Fusion Test Reactor, to be located on the Princeton Forrestal Campus, is expected to operate with 1 to 2.5 MA tritium--deuterium plasmas, with the pulses involving injection of 50 to 150 Ci (5 to 16 mg) of tritium. Attainment of fusion conditions is based on generation of an approximately 1 keV tritium plasma by ohmic heating and conversion to a moderately hot tritium--deuterium ion plasma by injection of a ''preheating'' deuterium neutral beam (40 to 80 keV), followed by injection of a ''reacting'' beam of high energy neutral deuterium (120 to 150 keV). Additionally, compressions accompany the beam injections. Environmental, safety and cost considerations led to the decision to limit the amount of tritium gas on-site to that required for an experiment, maintaining all other tritium in ''solidified'' form. The form of the tritium supply is as uranium tritide, while the spent tritium and other hydrogen isotopes are getter-trapped by zirconium--aluminum alloy. The issues treated include: (1) design concepts for the tritium generator and its purification, dispensing, replenishment, containment, and containment--cleanup systems; (2) features of the spent plasma trapping system, particularly the regenerable absorption cartridges, their integration into the vacuum system, and the handling of non-getterables; (3) tritium permeation through the equipment and the anticipated releases to the environment; (4) overview of the tritium related ventilation systems; and (5) design bases for the facility's tritium clean-up systems

  12. Safe handling of tritium

    International Nuclear Information System (INIS)

    1991-01-01

    The main objective of this publication is to provide practical guidance and recommendations on operational radiation protection aspects related to the safe handling of tritium in laboratories, industrial-scale nuclear facilities such as heavy-water reactors, tritium removal plants and fission fuel reprocessing plants, and facilities for manufacturing commercial tritium-containing devices and radiochemicals. The requirements of nuclear fusion reactors are not addressed specifically, since there is as yet no tritium handling experience with them. However, much of the material covered is expected to be relevant to them as well. Annex III briefly addresses problems in the comparatively small-scale use of tritium at universities, medical research centres and similar establishments. However, the main subject of this publication is the handling of larger quantities of tritium. Operational aspects include designing for tritium safety, safe handling practice, the selection of tritium-compatible materials and equipment, exposure assessment, monitoring, contamination control and the design and use of personal protective equipment. This publication does not address the technologies involved in tritium control and cleanup of effluents, tritium removal, or immobilization and disposal of tritium wastes, nor does it address the environmental behaviour of tritium. Refs, figs and tabs

  13. Tritium conference days

    International Nuclear Information System (INIS)

    Garnier-Laplace, J.; Lebaron-Jacobs, L.; Sene, M.; Devin, P.; Chretien, V.; Le Guen, B.; Guetat, Ph.; Baglan, N.; Ansoborlo, E.; Boyer, C.; Masson, M.; Bailly-Du-Bois, P.; Jenkinson, St.; Wakeford, R.; Saintigny, Y.; Romeo, P.H.; Thompson, P.; Leterq, D.; Chastagner, F.; Cortes, P.; Philippe, M.; Paquet, F.; Fournier, M.

    2009-01-01

    This document gathers the slides of the available presentations given during this conference day. Twenty presentations out of 21 are assembled in the document and deal with: 1 - tritium in the environment (J. Garnier-Laplace); 2 - status of knowledge about tritium impact on health (L. Lebaron-Jacobs); 3 - tritium, discrete but present everywhere (M. Sene); 4 - management of tritium effluents from Areva NC La Hague site - related impact and monitoring (P. Devin); 5 - tritium effluents and impact in the vicinity of EDF's power plants (V. Chretien and B. Le Guen); 6 - contribution of CEA-Valduc centre monitoring to the knowledge of atmospheric tritiated water transfers to the different compartments of the environment (P. Guetat); 7 - tritium analysis in environment samples: constraints and means (N. Baglan); 8 - organically-linked tritium: the analyst view (E. Ansoborlo); 9 - study of tritium transfers to plants via OBT/HTO air and OBT/HTO free (C. Boyer); 10 - tritium in the British Channel (M. Masson and P. Bailly-Du-Bois); 11 - tritium in British coastal waters (S. Jenkinson); 12 - recent results from epidemiology (R. Wakeford); 13 - effects of tritiated thymidine on hematopoietic stem cells (P.H. Romeo); 14 - tritium management issue in Canada: the point of view from authorities (P. Thompson); 15 - experience feedback of the detritiation process of Valduc centre (D. Leterq); 16 - difficulties linked with tritiated wastes confinement (F. Chastagner); 17 - optimisation of tritium management in the ITER project (P. Cortes); 18 - elements of thought about the management of tritium generated by nuclear facilities (M. Philippe); 19 - CIPR's position about the calculation of doses and risks linked with tritium exposure (F. Paquet); 20 - tritium think tanks (M. Fournier). (J.S.)

  14. Landfill gas: development guidelines

    International Nuclear Information System (INIS)

    1996-11-01

    A Guide produced as part of the UK DTI's New and Renewable Energy Programme provides information which forms a framework enabling landfill gas to be exploited fully as a renewable energy resource. The eight chapters cover the resource base of landfill gas in the UK in the wider context, the technology for energy recovery from landfill gas, the utilisation options for landfill gas, the various project development arrangements and their implementation, the assessment of a site's landfill gas resource, the factors which influence the project economies, financing aspects and the management of project liabilities and finally the national waste disposal policy and required consents followed by the overall process for project mobilisation. (UK)

  15. Sources of tritium

    International Nuclear Information System (INIS)

    Phillips, J.E.; Easterly, C.E.

    1980-12-01

    A review of tritium sources is presented. The tritium production and release rates are discussed for light water reactors (LWRs), heavy water reactors (HWRs), high temperature gas cooled reactors (HTGRs), liquid metal fast breeder reactors (LMFBRs), and molten salt breeder reactors (MSBRs). In addition, release rates are discussed for tritium production facilities, fuel reprocessing plants, weapons detonations, and fusion reactors. A discussion of the chemical form of the release is included. The energy producing facilities are ranked in order of increasing tritium production and release. The ranking is: HTGRs, LWRs, LMFBRs, MSBRs, and HWRs. The majority of tritium has been released in the form of tritiated water

  16. Landfill Top Covers

    DEFF Research Database (Denmark)

    Scheutz, Charlotte; Kjeldsen, Peter

    2011-01-01

    The purpose of the final cover of a landfill is to contain the waste and to provide for a physical separation between the waste and the environment for protection of public health. Most landfill covers are designed with the primary goal to reduce or prevent infiltration of precipitation...... into the landfill in order to minimize leachate generation. In addition the cover also has to control the release of gases produced in the landfill so the gas can be ventilated, collected and utilized, or oxidized in situ. The landfill cover should also minimize erosion and support vegetation. Finally the cover...... is landscaped in order to fit into the surrounding area/environment or meet specific plans for the final use of the landfill. To fulfill the above listed requirements landfill covers are often multicomponent systems which are placed directly on top of the waste. The top cover may be placed immediately after...

  17. Tritium pellet injector results

    International Nuclear Information System (INIS)

    Fisher, P.W.; Bauer, M.L.; Baylor, L.R.; Deleanu, L.E.; Fehling, D.T.; Milora, S.L.; Whitson, J.C.

    1988-01-01

    Injection of solid tritium pellets is considered to be the most promising way of fueling fusion reactors. The Tritium Proof-of- Principle (TPOP) experiment has demonstrated the feasibility of forming and accelerating tritium pellets. This injector is based on the pneumatic pipe-gun concept, in which pellets are formed in situ in the barrel and accelerated with high-pressure gas. This injector is ideal for tritium service because there are no moving parts inside the gun and because no excess tritium is required in the pellet production process. Removal of 3 He from tritium to prevent blocking of the cryopumping action by the noncondensible gas has been demonstrated with a cryogenic separator. Pellet velocities of 1280 m/s have been achieved for 4-mm-diam by 4-mm-long cylindrical tritium pellets with hydrogen propellant at 6.96 MPa (1000 psi). 10 refs., 10 figs

  18. Environmental aspects of tritium

    International Nuclear Information System (INIS)

    Quisenberry, D.R.

    1979-01-01

    The potential radiological implications of environmental tritium releases must be determined in order to develop a programme for dealing with the tritium inventory predicted for the nuclear power industry which, though still in its infancy, produces tritium in megacurie quantities annually. Should the development of fusion power generation become a reality, it will create a potential source for large releases of tritium, much of it in the gaseous state. At present about 90% of the tritium produced enters the environment through gaseous and liquid effluents and is deposited in the hydrosphere as tritiated water. Tritium can be assimilated by plants and animals and organically bound, regardless of the exposure pathway. However, there appears to be no concentration factor relative to hydrogen at any level of food chains analysed to date. The body burden, for man, is dependent on the exposure pathway and tissue-bound fractions are primarily the result of organically bound tritium in food. (author)

  19. Waste management in Ukraine: Municipal solid waste landfills and their impact on rural areas

    Directory of Open Access Journals (Sweden)

    Nataliia Makarenko

    2017-03-01

    Full Text Available The article presents the results of a study of the influence of Myronivka municipal solid waste landfill in the surrounding rural areas. It is established that environmentally hazardous situation has generated in the locations of the landfills causes dissatisfaction among the local population. It is shown that incorrect use may be the cause of the deterioration of quality of drinking water, atmospheric air, sanitary and hygienic condition of agricultural soils. It is established that the effect of the landfill extends beyond the sanitary protection zone, therefore there is a need to improve its monitoring system with obligatory consideration of impacts on adjacent rural areas. The size of the normative sanitary-protective zone was specified under the actual level of air pollution and natural factors. It is shown that such a scientific and methodical approach can provide a more objective establishment of the sanitary protection zone. In turn, this will provide an opportunity to take appropriate organizational and managerial decisions on the placement of different objects and prevent the negative impact of landfills on rural areas.

  20. Organically bound tritium

    International Nuclear Information System (INIS)

    Diabate, S.; Strack, S.

    1993-01-01

    Tritium released into the environment may be incorporated into organic matter. Organically bound tritium in that case will show retention times in organisms that are considerably longer than those of tritiated water which has significant consequences on dose estimates. This article reviews the most important processes of organically bound tritium production and transport through food networks. Metabolic reactions in plant and animal organisms with tritiated water as a reaction partner are of great importance in this respect. The most important production process, in quantitative terms, is photosynthesis in green plants. The translocation of organically bound tritium from the leaves to edible parts of crop plants should be considered in models of organically bound tritium behavior. Organically bound tritium enters the human body on several pathways, either from the primary producers (vegetable food) or at a higher tropic level (animal food). Animal experiments have shown that the dose due to ingestion of organically bound tritium can be up to twice as high as a comparable intake of tritiated water in gaseous or liquid form. In the environment, organically bound tritium in plants and animals is often found to have higher specific tritium concentrations than tissue water. This is not due to some tritium enrichment effects but to the fact that no equilibrium conditions are reached under natural conditions. 66 refs

  1. Tritium sampling and measurement

    International Nuclear Information System (INIS)

    Wood, M.J.; McElroy, R.G.; Surette, R.A.; Brown, R.M.

    1993-01-01

    Current methods for sampling and measuring tritium are described. Although the basic techniques have not changed significantly over the last 10 y, there have been several notable improvements in tritium measurement instrumentation. The design and quality of commercial ion-chamber-based and gas-flow-proportional-counter-based tritium monitors for tritium-in-air have improved, an indirect result of fusion-related research in the 1980s. For tritium-in-water analysis, commercial low-level liquid scintillation spectrometers capable of detecting tritium-in-water concentrations as low as 0.65 Bq L-1 for counting times of 500 min are available. The most sensitive method for tritium-in-water analysis is still 3He mass spectrometry. Concentrations as low as 0.35 mBq L-1 can be detected with current equipment. Passive tritium-oxide-in-air samplers are now being used for workplace monitoring and even in some environmental sampling applications. The reliability, convenience, and low cost of passive tritium-oxide-in-air samplers make them attractive options for many monitoring applications. Airflow proportional counters currently under development look promising for measuring tritium-in-air in the presence of high gamma and/or noble gas backgrounds. However, these detectors are currently limited by their poor performance in humidities over 30%. 133 refs

  2. Landfill mining: Resource potential of Austrian landfills--Evaluation and quality assessment of recovered municipal solid waste by chemical analyses.

    Science.gov (United States)

    Wolfsberger, Tanja; Aldrian, Alexia; Sarc, Renato; Hermann, Robert; Höllen, Daniel; Budischowsky, Andreas; Zöscher, Andreas; Ragoßnig, Arne; Pomberger, Roland

    2015-11-01

    Since the need for raw materials in countries undergoing industrialisation (like China) is rising, the availability of metal and fossil fuel energy resources (like ores or coal) has changed in recent years. Landfill sites can contain considerable amounts of recyclables and energy-recoverable materials, therefore, landfill mining is an option for exploiting dumped secondary raw materials, saving primary sources. For the purposes of this article, two sanitary landfill sites have been chosen for obtaining actual data to determine the resource potential of Austrian landfills. To evaluate how pretreating waste before disposal affects the resource potential of landfills, the first landfill site has been selected because it has received untreated waste, whereas mechanically-biologically treated waste was dumped in the second. The scope of this investigation comprised: (1) waste characterisation by sorting analyses of recovered waste; and (2) chemical analyses of specific waste fractions for quality assessment regarding potential energy recovery by using it as solid recovered fuels. The content of eight heavy metals and the net calorific values were determined for the chemical characterisation tests. © The Author(s) 2015.

  3. Effects of a temporary HDPE cover on landfill gas emissions: multiyear evaluation with the static chamber approach at an Italian landfill.

    Science.gov (United States)

    Capaccioni, Bruno; Caramiello, Cristina; Tatàno, Fabio; Viscione, Alessandro

    2011-05-01

    According to the European Landfill Directive 1999/31/EC and the related Italian Legislation ("D. Lgs. No. 36/2003"), monitoring and control procedures of landfill gas emissions, migration and external dispersions are clearly requested. These procedures could be particularly interesting in the operational circumstance of implementing a temporary cover, as for instance permitted by the Italian legislation over worked-out landfill sections, awaiting the evaluation of expected waste settlements. A possible quantitative approach for field measurement and consequential evaluation of landfill CO(2), CH(4) emission rates in pairs consists of the static, non-stationary accumulation chamber technique. At the Italian level, a significant and recent situation of periodical landfill gas emission monitoring is represented by the sanitary landfill for non-hazardous waste of the "Fano" town district, where monitoring campaigns with the static chamber have been annually conducted during the last 5 years (2005-2009). For the entire multiyear monitoring period, the resulting CO(2), CH(4) emission rates varied on the whole up to about 13,100g CO(2) m(-2)d(-1) and 3800 g CH(4) m(-2)d(-1), respectively. The elaboration of these landfill gas emission data collected at the "Fano" case-study site during the monitoring campaigns, presented and discussed in the paper, gives rise to a certain scientific evidence of the possible negative effects derivable from the implementation of a temporary HDPE cover over a worked-out landfill section, notably: the lateral migration and concentration of landfill gas emissions through adjacent, active landfill sections when hydraulically connected; and consequently, the increase of landfill gas flux velocities throughout the reduced overall soil cover surface, giving rise to a flowing through of CH(4) emissions without a significant oxidation. Thus, these circumstances are expected to cause a certain increase of the overall GHG emissions from the given

  4. Avaliação dos níveis de metais pesados em efluente líquido percolado do aterro sanitário de Paranavaí, Estado do Paraná, Brasil - DOI: 10.4025/actascihealthsci.v31i1.1154 Assessment of heavy metal levels in percolated liquid from sanitary landfill in Paranavaí, Paraná State, Brazil - DOI: 10.4025/actascihealthsci.v31i1.1154

    Directory of Open Access Journals (Sweden)

    Cynthia Algayer da Silva

    2009-05-01

    Full Text Available O percolado pode conter diversas substâncias químicas com características tóxicas, dentre elas os metais pesados oriundos de vários materiais provenientes de indústrias, atividades agrícolas, laboratórios, hospitais, residências. A contaminação por metais apresenta amplo espectro de toxicidade que inclui efeitos neurotóxicos, hepatóxicos, nefrotóxicos, teratogênicos, carcinogênicos ou mutagênicos. O objetivo deste trabalho foi a avaliação dos níveis de Cd, Cr, Cu, Mn, Ni, Pb e Zn do percolado gerado no aterro sanitário de Paranavaí - PR. As amostras foram coletadas a partir de setembro de 2006 a julho de 2007, em quatro pontos distintos nas lagoas de tratamento. Para detecção dos metais utilizou-se o espectrofotômetro de absorção atômica com chama. Os resultados foram comparados com os limites máximos de concentração de metais em efluentes líquidos estabelecidos pela Resolução 397/2008 - Conama (BRASIL, 2008. Verificou-se que os níveis dos metais analisados, com exceção do Pb, estão dentro dos limites permissíveis pela legislação ambiental.Percolated liquid may contain several chemical substances with toxic characteristics, among them heavy metals from industrial sources, agricultural activities, laboratories, hospitals and residences. Metal contamination presents a wide array of toxicities, such as neurotoxic, hepatotoxic, nephrotoxic, teratogenic, carcinogenic or mutagenic effects. The objective of this work was to assess the levels of Cd, Cr, Cu, Mn, Ni, Pb, and Zn in percolated liquid produced at the sanitary landfill in Paranavaí. The samples were collected from September of 2006 to July of 2007, at four distinct places of the treatment lake. An atomic absorption spectrophotometer with a burner was used to detect the metals. The results were compared with the maximum allowed values for metal concentration present in Resolution 397/2008 – Conama (BRAZIL, 2008. It was verified that the level of

  5. Confinement and Tritium Stripping Systems for APT Tritium Processing

    Energy Technology Data Exchange (ETDEWEB)

    Hsu, R.H. [Westinghouse Savannah River Company, AIKEN, SC (United States); Heung, L.K.

    1997-10-20

    This report identifies functions and requirements for the tritium process confinement and clean-up system (PCCS) and provides supporting technical information for the selection and design of tritium confinement, clean-up (stripping) and recovery technologies for new tritium processing facilities in the Accelerator for the Production of Tritium (APT). The results of a survey of tritium confinement and clean-up systems for large-scale tritium handling facilities and recommendations for the APT are also presented.

  6. Confinement and Tritium Stripping Systems for APT Tritium Processing

    International Nuclear Information System (INIS)

    Hsu, R.H.; Heung, L.K.

    1997-01-01

    This report identifies functions and requirements for the tritium process confinement and clean-up system (PCCS) and provides supporting technical information for the selection and design of tritium confinement, clean-up (stripping) and recovery technologies for new tritium processing facilities in the Accelerator for the Production of Tritium (APT). The results of a survey of tritium confinement and clean-up systems for large-scale tritium handling facilities and recommendations for the APT are also presented

  7. Environmental tritium in trees

    International Nuclear Information System (INIS)

    Brown, R.M.

    1979-01-01

    The distribution of environmental tritium in the free water and organically bound hydrogen of trees growing in the vicinity of the Chalk River Nuclear Laboratories (CRNL) has been studied. The regional dispersal of HTO in the atmosphere has been observed by surveying the tritium content of leaf moisture. Measurement of the distribution of organically bound tritium in the wood of tree ring sequences has given information on past concentrations of HTO taken up by trees growing in the CRNL Liquid Waste Disposal Area. For samples at background environmental levels, cellulose separation and analysis was done. The pattern of bomb tritium in precipitation of 1955-68 was observed to be preserved in the organically bound tritium of a tree ring sequence. Reactor tritium was discernible in a tree growing at a distance of 10 km from CRNL. These techniques provide convenient means of monitoring dispersal of HTO from nuclear facilities. (author)

  8. Tritium monitoring techniques

    International Nuclear Information System (INIS)

    DeVore, J.R.; Buckner, M.A.

    1996-05-01

    As part of their operations, the U.S. Navy is required to store or maintain operational nuclear weapons on ships and at shore facilities. Since these weapons contain tritium, there are safety implications relevant to the exposure of personnel to tritium. This is particularly important for shipboard operations since these types of environments can make low-level tritium detection difficult. Some of these ships have closed systems, which can result in exposure to tritium at levels that are below normally acceptable levels but could still cause radiation doses that are higher than necessary or could hamper ship operations. This report describes the state of the art in commercial tritium detection and monitoring and recommends approaches for low-level tritium monitoring in these environments

  9. Effluent and sanitary sewer monitors

    International Nuclear Information System (INIS)

    Stanchi, L.; Vasey, M.R.

    1977-03-01

    Two similar instruments that monitor the liquid wastes from the plutonium facility are described. The operation of the two instruments is completely automatic and performs a continuous surveillance in the frame of Nuclear Safeguards. One instrument controls the liquids from the facility and the other checks the sanitary sewer wastes. Both have self-diagnosing capabilities and take automatic actions in case of abnormal occurrences

  10. Historical review of the sanitary filling of Rio Azul and considerations about heavy metals treated in it and the presents in our homes

    International Nuclear Information System (INIS)

    Mora Chinchilla, Rolando; Mora Amador, Raul

    2003-01-01

    A summary has been done on the most outstanding events during the history of Rio Azul sanitary landfill by consultating documents and local newspapers. The historical outline starts in 1972, when the Inter municipal Cooperative Agreement (COCIM) was created, until May 27, 2002, when a warning was issued on the possible harmful effects on health due to technological waste disposal. Likewise, the method for estimating the mass of metals deposited in the landfill is disclosed. In this landfill the mass of metals varies between 70000 and 100000 tm. Finally, some considerations on household chemical products are made and recommendations are presented to improve metal waste management. (Author) [es

  11. Tritium in metals

    International Nuclear Information System (INIS)

    Schober, T.

    1990-01-01

    In this Chapter a review is given of some of the important features of metal tritides as opposed to hydrides and deuterides. After an introduction to the topics of tritium and tritium in metals information will be presented on a variety of metal-tritium systems. Of main interest here are the differences from the classic hydrogen behavior; the so called isotope effect. A second important topic is that of aging effects produced by the accumulation of 3 He in the samples. (orig.)

  12. Tritium sources; Izvori tricijuma

    Energy Technology Data Exchange (ETDEWEB)

    Glodic, S [Institute of Nuclear Sciences VINCA, Belgrade (Yugoslavia); Boreli, F [Elektrotehnicki fakultet, Belgrade (Yugoslavia)

    1993-07-01

    Tritium is the only radioactive isotope of hydrogen. It directly follows the metabolism of water and it can be bound into genetic material, so it is very important to control levels of contamination. In order to define the state of contamination it is necessary to establish 'zero level', i.e. actual global inventory. The importance of tritium contamination monitoring increases with the development of fusion power installations. Different sources of tritium are analyzed and summarized in this paper. (author)

  13. High-pressure tritium

    International Nuclear Information System (INIS)

    Coffin, D.O.

    1976-01-01

    Some solutions to problems of compressing and containing tritium gas to 200 MPa at 700 0 K are discussed. The principal emphasis is on commercial compressors and high-pressure equipment that can be easily modified by the researcher for safe use with tritium. Experience with metal bellows and diaphragm compressors has been favorable. Selection of materials, fittings, and gauges for high-pressure tritium work is also reviewed briefly

  14. Aerobic landfill bioreactor

    Science.gov (United States)

    Hudgins, Mark P; Bessette, Bernard J; March, John C; McComb, Scott T.

    2002-01-01

    The present invention includes a system of decomposing municipal solid waste (MSW) within a landfill by converting the landfill to aerobic degradation in the following manner: (1) injecting air via the landfill leachate collection system (2) injecting air via vertical air injection wells installed within the waste mass; (3) applying leachate to the waste mass using a pressurized drip irrigation system; (4) allowing landfill gases to vent; and (5) adjusting air injection and recirculated leachate to achieve a 40% to 60% moisture level and a temperature between 120.degree. F. and 140.degree. F. in steady state.

  15. Landfill disposal risk assessment

    International Nuclear Information System (INIS)

    Mininni, G.; Passino, R.; Spinosa, L.

    1993-01-01

    Landfill disposal is the most used waste disposal system in Italy, due to its low costs and also to the great opposition of populations towards new incineration plants and the adjustment of the existing ones. Nevertheless, landfills may present many environmental problems as far as leachate and biogas are concerned directly influencing water, air and soil. This paper shows the most important aspects to be considered for a correct evaluation of environmental impacts caused by a landfill of urban wastes. Moreover, detection systems for on site control of pollution phenomena are presented and some measures for an optimal operation of a landfill are suggested

  16. Trends in sustainable landfilling in Malaysia, a developing country.

    Science.gov (United States)

    Fauziah, S H; Agamuthu, P

    2012-07-01

    In Malaysia, landfills are being filled up rapidly due to the current daily generation of approximately 30,000 tonnes of municipal solid waste. This situation creates the crucial need for improved landfilling practices, as sustainable landfilling technology is yet to be achieved here. The objective of this paper is to identify and evaluate the development and trends in landfilling practices in Malaysia. In 1970, the disposal sites in Malaysia were small and prevailing waste disposal practices was mere open-dumping. This network of relatively small dumps, typically located close to population centres, was considered acceptable for a relatively low population of 10 million in Malaysia. In the 1980s, a national programme was developed to manage municipal and industrial wastes more systematically and to reduce adverse environmental impacts. The early 1990s saw the privatization of waste management in many parts of Malaysia, and the establishment of the first sanitary landfills for MSW and an engineered landfill (called 'secure landfill' in Malaysia) for hazardous waste. A public uproar in 2007 due to contamination of a drinking water source from improper landfilling practices led to some significant changes in the government's policy regarding the country's waste management strategy. Parliament passed the Solid Waste and Public Cleansing Management (SWPCM) Act 2007 in August 2007. Even though the Act is yet to be implemented, the government has taken big steps to improve waste management system further. The future of the waste management in Malaysia seems somewhat brighter with a clear waste management policy in place. There is now a foundation upon which to build a sound and sustainble waste management and disposal system in Malaysia.

  17. Implementation of the semi-aerobic landfill system (Fukuoka method) in developing countries: a Malaysia cost analysis.

    Science.gov (United States)

    Chong, Theng Lee; Matsufuji, Yasushi; Hassan, Mohd Nasir

    2005-01-01

    Most of the existing solid waste landfill sites in developing countries are practicing either open dumping or controlled dumping. Proper sanitary landfill concepts are not fully implemented due to technological and financial constraints. Implementation of a fully engineered sanitary landfill is necessary and a more economically feasible landfill design is crucial, particularly for developing countries. This study was carried out by focusing on the economics from the development of a new landfill site within a natural clay area with no cost of synthetic liner up to 10 years after its closure by using the Fukuoka method semi-aerobic landfill system. The findings of the study show that for the development of a 15-ha landfill site in Malaysia with an estimated volume of 2,000,000 m(3), the capital investment required was about US 1,312,895 dollars, or about US 0.84 dollars/tonne of waste. Assuming that the lifespan of the landfill is 20 years, the total cost of operation was about US 11,132,536 dollars or US 7.15 dollars/tonne of waste. The closure cost of the landfill was estimated to be US 1,385,526 dollars or US 0.89 dollars/tonne of waste. Therefore, the total cost required to dispose of a tonne of waste at the semi-aerobic landfill was estimated to be US 8.89 dollars. By considering an average tipping fee of about US 7.89 dollars/tonne of waste in Malaysia in the first year, and an annual increase of 3% to about US 13.84 dollars in year-20, the overall system recorded a positive revenue of US 1,734,749 dollars. This is important information for the effort of privatisation of landfill sites in Malaysia, as well as in other developing countries, in order to secure efficient and effective landfill development and management.

  18. Landfilling: Environmental Issues

    DEFF Research Database (Denmark)

    Christensen, Thomas Højlund; Manfredi, Simone; Kjeldsen, Peter

    2011-01-01

    , the extent and quality of the technical environmental protection measures introduced, the daily operation and the timescale. This chapter describes the main potential environmental impacts from landfills. The modern landfill is able to avoid most of these impacts. However, in the planning and design...

  19. Landfilling: Concepts and Challenges

    DEFF Research Database (Denmark)

    Christensen, Thomas Højlund; Scharff, H.; Hjelmar, O.

    2011-01-01

    Landfilling of waste historically has been the main management route for waste, and in many parts of the world it still is. Landfills have developed from open polluting dumps to modern highly engineered facilities with sophisticated control measures and monitoring routines. However, in spite of all...

  20. Woody plant roots fail to penetrate a clay-lined landfill: Managment implications

    Science.gov (United States)

    Robinson, George R.; Handel, Steven N.

    1995-01-01

    In many locations, regulatory agencies do not permit tree planting above landfills that are sealed with a capping clay, because roots might penetrate the clay barrier and expose landfill contents to leaching. We find, however, no empirical or theoretical basis for this restriction, and instead hypothesize that plant roots of any kind are incapable of penetrating the dense clays used to seal landfills. As a test, we excavated 30 trees and shrubs, of 12 species, growing over a clay-lined municipal sanitary landfill on Staten Island, New York. The landfill had been closed for seven years, and featured a very shallow (10 to 30-cm) soil layer over a 45-cm layer of compacted grey marl (Woodbury series) clay. The test plants had invaded naturally from nearby forests. All plants examined—including trees as tall as 6 m—had extremely shallow root plates, with deformed tap roots that grew entirely above and parallel to the clay layer. Only occasional stubby feeder roots were found in the top 1 cm of clay, and in clay cracks at depths to 6 cm, indicating that the primary impediment to root growth was physical, although both clay and the overlying soil were highly acidic. These results, if confirmed by experimental research should lead to increased options for the end use of many closed sanitary landfills.

  1. The ITER tritium systems

    International Nuclear Information System (INIS)

    Glugla, M.; Antipenkov, A.; Beloglazov, S.; Caldwell-Nichols, C.; Cristescu, I.R.; Cristescu, I.; Day, C.; Doerr, L.; Girard, J.-P.; Tada, E.

    2007-01-01

    ITER is the first fusion machine fully designed for operation with equimolar deuterium-tritium mixtures. The tokamak vessel will be fuelled through gas puffing and pellet injection, and the Neutral Beam heating system will introduce deuterium into the machine. Employing deuterium and tritium as fusion fuel will cause alpha heating of the plasma and will eventually provide energy. Due to the small burn-up fraction in the vacuum vessel a closed deuterium-tritium loop is required, along with all the auxiliary systems necessary for the safe handling of tritium. The ITER inner fuel cycle systems are designed to process considerable and unprecedented deuterium-tritium flow rates with high flexibility and reliability. High decontamination factors for effluent and release streams and low tritium inventories in all systems are needed to minimize chronic and accidental emissions. A multiple barrier concept assures the confinement of tritium within its respective processing components; atmosphere and vent detritiation systems are essential elements in this concept. Not only the interfaces between the primary fuel cycle systems - being procured through different Participant Teams - but also those to confinement systems such as Atmosphere Detritiation or those to fuelling and pumping - again procured through different Participant Teams - and interfaces to buildings are calling for definition and for detailed analysis to assure proper design integration. Considering the complexity of the ITER Tritium Plant configuration management and interface control will be a challenging task

  2. Radionuclide Basics: Tritium

    Science.gov (United States)

    Tritium is a hydrogen atom that has two neutrons in the nucleus and one proton. It is radioactive and behaves like other forms of hydrogen in the environment. Tritium is produced naturally in the upper atmosphere and as a byproduct of nuclear fission.

  3. Biostabilization of landfill waste

    Energy Technology Data Exchange (ETDEWEB)

    Hansen, D.L. [Landfill Service Corp., Apalachin, NY (United States)

    1995-06-01

    In November 1991, the city of Albany, N.Y., together with the principals of Landfill Service Corp. (Apalachin, N.Y.), proposed to demonstrate the successful practice of biostabilized solid waste placement in the newly constructed, double-composite-lined Interim Landfill located in the city of Albany. The small landfill covers just 12 acres and is immediately adjacent to residential neighbors. The benefits of this biostabilization practice include a dramatic improvement in the orderliness of waste placement, with significant reduction of windblown dust and litter. The process also reduces the presence of typical landfill vectors such as flies, crows, seagulls, and rodents. The physically and biologically uniform character of the stabilized waste mass can result in more uniform future landfill settlement and gas production properties. This can allow for more accurate prediction of post-closure conditions and reduction or elimination of remedial costs attendant to post-closure gross differential settlement.

  4. Environmental and Geologic Assessment to Locate a Manual Sanitary Refill in the Mene de Mauroa Church, Venezuela

    Directory of Open Access Journals (Sweden)

    Simón E. Morales-Soto

    2016-05-01

    Full Text Available The inadequate disposal of urban wastes is nowadays an environmental issue having a negative impact on several communities. The objective of this investigation is to select the most adequate place to locate a manual sanitary landfill to dump the solid wastes from the Mene de Mauroa (Venezuela church. A total of 19 variables were subjected to a series of evaluations applying the scale and weight method. This method consists of comparing the variables according to their level of priority. The area with the highest score is to be selected as the most adequate area for the sanitary landfill according to a weighting scale of 5 values for the scoring of each variable.

  5. In-vessel tritium

    International Nuclear Information System (INIS)

    Ueda, Yoshio; Ohya, Kaoru; Ashikawa, Naoko; Ito, Atsushi M.; Kato, Daiji; Kawamura, Gakushi; Takayama, Arimichi; Tomita, Yukihiro; Nakamura, Hiroaki; Ono, Tadayoshi; Kawashima, Hisato; Shimizu, Katsuhiro; Takizuka, Tomonori; Nakano, Tomohide; Nakamura, Makoto; Hoshino, Kazuo; Kenmotsu, Takahiro; Wada, Motoi; Saito, Seiki; Takagi, Ikuji; Tanaka, Yasunori; Tanabe, Tetsuo; Yoshida, Masafumi; Toma, Mitsunori; Hatayama, Akiyoshi; Homma, Yuki; Tolstikhina, Inga Yu.

    2012-01-01

    The in-vessel tritium research is closely related to the plasma-materials interaction. It deals with the edge-plasma-wall interaction, the wall erosion, transport and re-deposition of neutral particles and the effect of neutral particles on the fuel recycling. Since the in-vessel tritium shows a complex nonlinear behavior, there remain many unsolved problems. So far, behaviors of in-vessel tritium have been investigated by two groups A01 and A02. The A01 group performed experiments on accumulation and recovery of tritium in thermonuclear fusion reactors and the A02 group studied theory and simulation on the in-vessel tritium behavior. In the present article, outcomes of the research are reviewed. (author)

  6. Protection against tritium radiations

    International Nuclear Information System (INIS)

    Bal, Georges

    1964-05-01

    This report presents the main characteristics of tritium, describes how it is produced as a natural or as an artificial radio-element. It outlines the hazards related to this material, presents how materials and tools are contaminated and decontaminated. It addresses the issue of permissible maximum limits: factors of assessment of the risk induced by tritium, maximum permissible activity in body water, maximum permissible concentrations in the atmosphere. It describes the measurement of tritium activity: generalities, measurement of gas activity and of tritiated water steam, tritium-induced ionisation in an ionisation chamber, measurement systems using ionisation chambers, discontinuous detection of tritium-containing water in the air, detection of surface contamination [fr

  7. Tritium fuel cycle modeling and tritium breeding analysis for CFETR

    Energy Technology Data Exchange (ETDEWEB)

    Chen, Hongli; Pan, Lei; Lv, Zhongliang; Li, Wei; Zeng, Qin, E-mail: zengqin@ustc.edu.cn

    2016-05-15

    Highlights: • A modified tritium fuel cycle model with more detailed subsystems was developed. • The mean residence time method applied to tritium fuel cycle calculation was updated. • Tritium fuel cycle analysis for CFETR was carried out. - Abstract: Attaining tritium self-sufficiency is a critical goal for fusion reactor operated on the D–T fuel cycle. The tritium fuel cycle models were developed to describe the characteristic parameters of the various elements of the tritium cycle as a tool for evaluating the tritium breeding requirements. In this paper, a modified tritium fuel cycle model with more detailed subsystems and an updated mean residence time calculation method was developed based on ITER tritium model. The tritium inventory in fueling system and in plasma, supposed to be important for part of the initial startup tritium inventory, was considered in the updated mean residence time method. Based on the model, the tritium fuel cycle analysis of CFETR (Chinese Fusion Engineering Testing Reactor) was carried out. The most important two parameters, the minimum initial startup tritium inventory (I{sub m}) and the minimum tritium breeding ratio (TBR{sub req}) were calculated. The tritium inventories in steady state and tritium release of subsystems were obtained.

  8. Tritium breeding in fusion reactors

    International Nuclear Information System (INIS)

    Abdou, M.A.

    1982-10-01

    Key technological problems that influence tritium breeding in fusion blankets are reviewed. The breeding potential of candidate materials is evaluated and compared to the tritium breeding requirements. The sensitivity of tritium breeding to design and nuclear data parameters is reviewed. A framework for an integrated approach to improve tritium breeding prediction is discussed with emphasis on nuclear data requirements

  9. Tritium permeation through iron

    International Nuclear Information System (INIS)

    Hagi, Hideki; Hayashi, Yasunori

    1989-01-01

    An experimental method for measuring diffusion coefficients and permeation rates of tritium in metals around room temperature has been established, and their values in iron have been obtained by using the method. Permeation rates of tritium and hydrogen through iron were measured by the electrochemical method in which a tritiated aqueous solution was used as a cathodic electrolyte. Tritium and hydrogen were introduced from one side of a membrane specimen by cathodic polarization, while at the other side of the specimen the permeating tritium and hydrogen were extracted by potentiostatical ionization. The amount of permeated hydrogen was obtained by integrating the anodic current, and that of tritium was determined by measuring the radioactivity of the electrolyte sampled from the extraction side. Diffusion coefficients of tritium (D T ) and hydrogen (D H ) were determined from the time lag of tritium and hydrogen permeation. D T =9x10 -10 m 2 /s and D H =4x10 -9 m 2 /s at 286 K for annealed iron specimens. These values of D T and D H were compared with the previous data of the diffusion coefficients of hydrogen and deuterium, and the isotope effect in diffusion was discussed. (orig.)

  10. Tritium technology. A Canadian overview

    Energy Technology Data Exchange (ETDEWEB)

    Hemmings, R.L. [Canatom NPM (Canada)

    2002-10-01

    An overview of the various tritium research and operational activities in Canada is presented. These activities encompass tritium processing and recovery, tritium interactions with materials, and tritium health and safety. Many of these on-going activities form a sound basis for the tritium use and handling aspects of the ITER project. Tritium management within the CANDU heavy water reactor, associated detritiation facilities, research and development facilities, and commercial industry and improving the understanding of tritium behaviour in humans and the environment remain the focus of a long-standing Canadian interest in tritium. While there have been changes in the application of this knowledge and experience over time, the operating experience and the supporting research and development continue to provide for improved plant and facility operations, an improved understanding of tritium safety issues, and improved products and tools that facilitate tritium management. (author)

  11. Tritium technology. A Canadian overview

    International Nuclear Information System (INIS)

    Hemmings, R.L.

    2002-01-01

    An overview of the various tritium research and operational activities in Canada is presented. These activities encompass tritium processing and recovery, tritium interactions with materials, and tritium health and safety. Many of these on-going activities form a sound basis for the tritium use and handling aspects of the ITER project. Tritium management within the CANDU heavy water reactor, associated detritiation facilities, research and development facilities, and commercial industry and improving the understanding of tritium behaviour in humans and the environment remain the focus of a long-standing Canadian interest in tritium. While there have been changes in the application of this knowledge and experience over time, the operating experience and the supporting research and development continue to provide for improved plant and facility operations, an improved understanding of tritium safety issues, and improved products and tools that facilitate tritium management. (author)

  12. Metabolism and dosimetry of tritium

    International Nuclear Information System (INIS)

    Hill, R.L.; Johnson, J.R.

    1993-01-01

    This document was prepared as a review of the current knowledge of tritium metabolism and dosimetry. The physical, chemical, and metabolic characteristics of various forms of tritium are presented as they pertain to performing dose assessments for occupational workers and for the general public. For occupational workers, the forms of tritium discussed include tritiated water, elemental tritium gas, skin absorption from elemental tritium gas-contaminated surfaces, organically bound tritium in pump oils, solvents and other organic compounds, metal tritides, and radioluminous paints. For the general public, age-dependent tritium metabolism is reviewed, as well as tritiated water, elemental tritium gas, organically bound tritium, organically bound tritium in food-stuffs, and tritiated methane. 106 refs

  13. 9 CFR 416.4 - Sanitary operations.

    Science.gov (United States)

    2010-01-01

    ... 9 Animals and Animal Products 2 2010-01-01 2010-01-01 false Sanitary operations. 416.4 Section 416... SANITATION § 416.4 Sanitary operations. (a) All food-contact surfaces, including food-contact surfaces of... compounds, sanitizing agents, processing aids, and other chemicals used by an establishment must be safe and...

  14. Experience in handling concentrated tritium

    International Nuclear Information System (INIS)

    Holtslander, W.J.

    1985-12-01

    The notes describe the experience in handling concentrated tritium in the hydrogen form accumulated in the Chalk River Nuclear Laboratories Tritium Laboratory. The techniques of box operation, pumping systems, hydriding and dehydriding operations, and analysis of tritium are discussed. Information on the Chalk River Tritium Extraction Plant is included as a collection of reprints of papers presented at the Dayton Meeting on Tritium Technology, 1985 April 30 - May 2

  15. Problems of anthropogenic tritium limitation

    Directory of Open Access Journals (Sweden)

    Kochetkov О.A.

    2013-12-01

    Full Text Available This article contains the current situation in respect to the environmental concentrations of anthropogenic and natural tritium. There are presented and analyzed domestic standards for НТО of all Radiation Safety Standards (NRB, as well as the regulations analyzed for tritium in drinking water taken in other countries today. This article deals with the experience of limitation of tritium and focuses on the main problem of rationing of tritium — rationing of organically bound tritium.

  16. Complete genome of Pandoraea pnomenusa RB-38, an oxalotrophic bacterium isolated from municipal solid waste landfill site.

    Science.gov (United States)

    Lim, Yan-Lue; Ee, Robson; Yong, Delicia; Tee, Kok-Keng; Yin, Wai-Fong; Chan, Kok-Gan

    2015-11-20

    Pandoraea pnomenusa RB-38 is a bacterium isolated from a former sanitary landfill site. Here, we present the complete genome of P. pnomenusa RB38 in which an oxalate utilization pathway was identified. The genome analysis suggested the potential of this strain as an effective biocontrol agent against oxalate-producing phytopathogens. Copyright © 2015 Elsevier B.V. All rights reserved.

  17. Applicability of anaerobic membrane bioreactors for landfill leachate treatment: Review and opportunity

    Science.gov (United States)

    Abuabdou, Salahaldin M. A.; Bashir, Mohammed J. K.; Aun, Ng Choon; Sethupathi, Sumathi

    2018-04-01

    Sanitary landfilling is nowadays the most common way to eliminate municipal solid wastes (MSW). The resulted landfill leachate is a highly contaminated liquid. Even small quantities of this high-strength leachate can cause serious damage to surface and ground water receptors. Thus, these leachates must be appropriately treated before being discharged into the environment. In the last years, anaerobic membrane bioreactor (AnMBR) technology is being considered as a very attractive alternative for leachate treatment due to the significant advantages. In the last decade, many studies have been conducted in which various types of anaerobic reactors were used in combination with membranes. This paper is a review of the potential of anaerobic membrane bioreactor technology for municipal landfill leachate treatment. A critical review in AnMBR performance interesting landfill leachate in lab scale is also done. In addition, the review discusses the impact of the various factors on both biological and filtration performances of anaerobic membrane bioreactors.

  18. Landfill Site Selection by AHP Based Multi-criteria Decision Making Tool: A Case Study in Kolkata, India

    Science.gov (United States)

    Majumdar, Ankush; Hazra, Tumpa; Dutta, Amit

    2017-09-01

    This work presents a Multi-criteria Decision Making (MCDM) tool to select a landfill site from three candidate sites proposed for Kolkata Municipal Corporation (KMC) area that complies with accessibility, receptor, environment, public acceptability, geological and economic criteria. Analytical Hierarchy Process has been used to solve the MCDM problem. Suitability of the three sites (viz. Natagachi, Gangajoara and Kharamba) as landfills as proposed by KMC has been checked by Landfill Site Sensitivity Index (LSSI) as well as Economic Viability Index (EVI). Land area availability for disposing huge quantity of Municipal Solid Waste for the design period has been checked. Analysis of the studied sites show that they are moderately suitable for landfill facility construction as both LSSI and EVI scores lay between 300 and 750. The proposed approach represents an effective MCDM tool for siting sanitary landfill in growing metropolitan cities of developing countries like India.

  19. Tritium permeation and recovery

    International Nuclear Information System (INIS)

    Bond, R.A.; Hamilton, A.M.

    1987-01-01

    The paper is an appendix to a study of the reactor relevance of the NET design concept. The latter study examines whether the technologies and design principles proposed for NET can be directly extrapolated to a demonstration (DEMO) reactor. In this appendix, tritium transport in the DEMO breeding blanket is considered with emphasis on the permeation rate from the lithium-lead breeder into the coolant. A computational model used to calculate the tritium transport in the breeder blanket is described. Results are reported for the tritium transport in the NET/INTOR type blanket as well as the DEMO blanket in order to provide a comparison. In addition, results are presented for the helium coolant tritium extraction analysis. (U.K.)

  20. Tritium protective clothing

    International Nuclear Information System (INIS)

    Fuller, T.P.; Easterly, C.E.

    1979-06-01

    Occupational exposures to radiation from tritium received at present nuclear facilities and potential exposures at future fusion reactor facilities demonstrate the need for improved protective clothing. Important areas relating to increased protection factors of tritium protective ventilation suits are discussed. These areas include permeation processes of tritium through materials, various tests of film permeability, selection and availability of suit materials, suit designs, and administrative procedures. The phenomenological nature of film permeability calls for more standardized and universal test methods, which would increase the amount of directly useful information on impermeable materials. Improvements in suit designs could be expedited and better communicated to the health physics community by centralizing devlopmental equipment, manpower, and expertise in the field of tritium protection to one or two authoritative institutions

  1. Tritium breeding blanket

    International Nuclear Information System (INIS)

    Smith, D.; Billone, M.; Gohar, Y.; Baker, C.; Mori, S.; Kuroda, T.; Maki, K.; Takatsu, H.; Yoshida, H.; Raffray, A.; Sviatoslavsky, I.; Simbolotti, G.; Shatalov, G.

    1991-01-01

    The terms of reference for ITER provide for incorporation of a tritium breeding blanket with a breeding ratio as close to unity as practical. A breeding blanket is required to assure an adequate supply of tritium to meet the program objectives. Based on specified design criteria, a ceramic breeder concept with water coolant and an austenitic steel structure has been selected as the first option and lithium-lead blanket concept has been chosen as an alternate option. The first wall, blanket, and shield are integrated into a single unit with separate cooling systems. The design makes extensive use of beryllium to enhance the tritium breeding ratio. The design goals with a tritium breeding ratio of 0.8--0.9 have been achieved and the R ampersand D requirements to qualify the design have been identified. 4 refs., 8 figs., 2 tabs

  2. Tritium in plants

    International Nuclear Information System (INIS)

    Vichot, L.; Losset, Y.

    2009-01-01

    The presence of tritium in the environment stems from its natural production by cosmic rays, from the fallout of the nuclear weapon tests between 1953 and 1964, and locally from nuclear industry activities. A part of the tritiated water contained in the foliage of plants is turned into organically bound tritium (OBT) by photosynthesis. The tritium of OBT, that is not exchangeable and then piles up in the plant, can be used as a marker of the past. It has been shown that the quantity of OBT contained in the age-rings of an oak that grew near the CEA center of Valduc was directly correlated with the tritium releases of the center. (A.C.)

  3. Tritium-v. 2

    International Nuclear Information System (INIS)

    1987-01-01

    Several bibliographical references about tritium are shown. The following aspects are presented: properties, analysis, monitoring, dosimetry reactions, labelling, industrial production, radiological protection, applications to science, technology and industry and some processes to obtain the element. (E.G.) [pt

  4. Tritium waste package

    Science.gov (United States)

    Rossmassler, Rich; Ciebiera, Lloyd; Tulipano, Francis J.; Vinson, Sylvester; Walters, R. Thomas

    1995-01-01

    A containment and waste package system for processing and shipping tritium xide waste received from a process gas includes an outer drum and an inner drum containing a disposable molecular sieve bed (DMSB) seated within outer drum. The DMSB includes an inlet diffuser assembly, an outlet diffuser assembly, and a hydrogen catalytic recombiner. The DMSB absorbs tritium oxide from the process gas and converts it to a solid form so that the tritium is contained during shipment to a disposal site. The DMSB is filled with type 4A molecular sieve pellets capable of adsorbing up to 1000 curies of tritium. The recombiner contains a sufficient amount of catalyst to cause any hydrogen add oxygen present in the process gas to recombine to form water vapor, which is then adsorbed onto the DMSB.

  5. Tritium protective clothing

    Energy Technology Data Exchange (ETDEWEB)

    Fuller, T. P.; Easterly, C. E.

    1979-06-01

    Occupational exposures to radiation from tritium received at present nuclear facilities and potential exposures at future fusion reactor facilities demonstrate the need for improved protective clothing. Important areas relating to increased protection factors of tritium protective ventilation suits are discussed. These areas include permeation processes of tritium through materials, various tests of film permeability, selection and availability of suit materials, suit designs, and administrative procedures. The phenomenological nature of film permeability calls for more standardized and universal test methods, which would increase the amount of directly useful information on impermeable materials. Improvements in suit designs could be expedited and better communicated to the health physics community by centralizing devlopmental equipment, manpower, and expertise in the field of tritium protection to one or two authoritative institutions.

  6. Thin film tritium dosimetry

    Science.gov (United States)

    Moran, Paul R.

    1976-01-01

    The present invention provides a method for tritium dosimetry. A dosimeter comprising a thin film of a material having relatively sensitive RITAC-RITAP dosimetry properties is exposed to radiation from tritium, and after the dosimeter has been removed from the source of the radiation, the low energy electron dose deposited in the thin film is determined by radiation-induced, thermally-activated polarization dosimetry techniques.

  7. Management of tritium wastes

    International Nuclear Information System (INIS)

    Kisalu, J.; Mellow, D.G.; Pennington, J.D.; Thompson, H.M.; Wood, E.

    1991-07-01

    This work provides a review of the management of tritium wastes with particular reference to current practice, possible alternatives and to the implications of any alternatives considered. It concludes that reduction in UK emissions from nuclear industry is feasible but at a cost out of all proportion to the reduction in dose commitment achievable. Commercial usage of tritium involves importation at several times the UK nuclear production level although documentation is sparse. (author)

  8. PRODUCTION OF TRITIUM

    Science.gov (United States)

    Jenks, G.H.; Shapiro, E.M.; Elliott, N.; Cannon, C.V.

    1963-02-26

    This invention relates to a process for the production of tritium by subjecting comminuted solid lithium fluoride containing the lithium isotope of atomic mass number 6 to neutron radiation in a self-sustaining neutronic reactor. The lithium fiuoride is heated to above 450 deg C. in an evacuated vacuum-tight container during radiation. Gaseous radiation products are withdrawn and passed through a palladium barrier to recover tritium. (AEC)

  9. Tritium in nuclear power plants

    International Nuclear Information System (INIS)

    Badyaev, V.V.; Egorov, Yu.A.; Sklyarov, V.P.; Stegachev, G.V.

    1981-01-01

    The problem of tritium formation during NPP operation is considered on the basis of available published data. Tritium characteristics are given, sources of the origin of natural and artificial tritium are described. NPP contribution to the total tritium amount in the environment is determined, as well as contribution of each process in the reactor to the quantity of tritium, produced at the NPP. Thermal- and fast-neutron reactions with tritium production are shown, their contribution to the total amount of tritium in a coolant is estimated, taking into account the type of reactor. Data on tritium content in NPP wastes and in the air of working premises are presented. Methods for sampling and sample preparation to measurements as well as the appropriate equipment are considered. Design of the gas-discharge counter of internal filling, used for measuring tritium activity in samples is described [ru

  10. Japanese university program on tritium radiobiology and environmental tritium

    International Nuclear Information System (INIS)

    Okada, Shigefumi

    1989-01-01

    The university program of the tritium study in the Special Research Project of Nuclear Fusion (1980-1989) is now on its 9th year. The study's aim is to assess tritium risk on man and environment for development of Japanese Nuclear Fusion Program. The tritium study begun by establishing various tritium safe-handling devices and methods to protect scientists from tritium contamination. Then, the tritium studies were initiated in three areas: The first was the studies on biological effects of tritiated water, where their RBE values, their modifying factors and mechanisms were investigated. Also, several human monitoring systems for detection of tritium-induced damage were developed. The second was the metabolic studies of tritium, including a daily tritium monitoring system, methods to enhance excretion of tritiated water from body and means to prevent oxidation of tritium gas in the body. The third was the study of environmental tritium. Tritium levels in environmental waters of various types were estimated all-over in Japan and their seasonal or regional variation were analyzed. Last two years, the studies were extended to estimate tritium activities of plants, foods and man in Japan. (author)

  11. Tritium Assay and Dispensing of KEPRI Tritium Lab

    International Nuclear Information System (INIS)

    Sohn, S. H.; Song, K. M.; Lee, S. K.; Lee, K.W.; Ko, B. W.

    2009-01-01

    The Wolsong Tritium Removal Facility(WTRF) has been constructed to reduce tritium levels in the heavy water systems and environmental emissions at the site. The WTRF was designed to process 100 kg/h of heavy water with the overall tritium extraction efficiency of 97% per single pass and to produce ∼700 g of tritium as T2 per year at the feed concentration of 0.37 TBq/kg. The high purity tritium greater than 99% is immobilized as a metal hydride to secure its long term storage. The recovered tritium will be made available for industrial uses and some research applications in the future. Then KEPRI is constructing the tritium lab. to build-up infrastructure to support tritium research activities and to support tritium control and accountability systems for tritium export. This paper describes the initial phases of the tritium application program including the laboratory infrastructure to support the tritium related R and D activities and the tritium controls in Korea

  12. Comparison of tritium production facilities

    International Nuclear Information System (INIS)

    He Kaihui; Huang Jinhua

    2002-01-01

    Detailed investigation and research on the source of tritium, tritium production facilities and their comparison are presented based on the basic information about tritium. The characteristics of three types of proposed tritium production facilities, i.e., fissile type, accelerator production tritium (APT) and fusion type, are presented. APT shows many advantages except its rather high cost; fusion reactors appear to offer improved safety and environmental impacts, in particular, tritium production based on the fusion-based neutron source costs much lower and directly helps the development of fusion energy source

  13. Characterization of landfill leachates and studies on heavy metal removal.

    Science.gov (United States)

    Ceçen, F; Gürsoy, G

    2000-10-01

    This study covers a thorough characterisation of landfill leachates emerging from a sanitary landfill area. The landfill leachates were obtained in the acidic stage of landfill stabilisation. Their organic content was high as reflected by the high BOD5 (5 day biological oxygen demand) and COD (chemical oxygen demand) values. They were also highly polluted in terms of the parameters TKN (total Kjeldahl nitrogen), NH4-N, alkalinity, hardness and heavy metals. Nickel was present in these wastewaters at a significant concentration. With regard to the high heavy metal content of these wastewaters, several physicochemical removal alternatives for the heavy metals Cu, Pb, Zn, Ni, Cd, Cr, Mn and Fe were tested using coagulation, flocculation, precipitation, base addition and aeration. Additionally, COD removal and ammonia stripping were examined. Co-precipitation with either alum or iron salts did not usually lead to significantly higher heavy metal removal than lime alone. The major methods leading to an effective heavy metal removal were aeration and lime addition. Nickel and cadmium seemed to be strongly complexed and were not removed by any method. Also lead removal proved to be difficult. The results are also discussed in terms of compliance with standards.

  14. Do landfills affect the environmental quality of nearby streams?

    Directory of Open Access Journals (Sweden)

    Leandro Schlemmer Brasil

    2017-12-01

    Full Text Available When inappropriately disposed, solid waste may contaminate the soil, water and air, leading to severe negative impacts on biodiversity. The Brazilian National Policy for Solid Waste (PNRS requires municipalities to ensure the environmental quality of landfills. Accordingly, our objective was to evaluate the community of aquatic insects in a stream with stretches downstream and upstream of a sanitary landfill. Our hypothesis was that there will be no differences in insect community between the stretches (downstream and upstream on the basis of the premise that landfills abiding by the PNRS do not cause environmental damage to nearby areas. There was no change in any aspect of the composition of the macroinvertebrate community as a result of the landfill. The only changes observed in the macroinvertebrate communities occurred between the dry and rainy seasons, which were related to the seasonality and consequent changes in the environmental conditions of the water over the year. Our study, although limited, showed primary and pioneering evidence that the PNRS can contribute positively to the conservation of the biotic quality of aquatic environments, further reinforcing the need for immediate implementation of the PNRS throughout the country.

  15. A framework for assessment and characterisation of municipal solid waste landfill leachate: an application to the Turbhe landfill, Navi Mumbai, India.

    Science.gov (United States)

    Mishra, Harshit; Rathod, Merwan; Karmakar, Subhankar; Kumar, Rakesh

    2016-06-01

    Rapid industrialisation, growing population and changing lifestyles are the root causes for the generation of huge amounts of solid waste in developing countries. In India, disposal of municipal solid waste (MSW) through open dumping is the most common waste disposal method. Unfortunately, leachate generation from landfill is high due to the prolonged and prominent monsoon season in India. As leachate generation rate is high in most of the tropical countries, long-term and extensive monitoring efforts are expected to evaluate actual environmental pollution potential due to leachate contamination. However, the leachate characterisation involves a comprehensive process, which has numerous shortcomings and uncertainties possibly due to the complex nature of landfilling process, heterogeneous waste characteristics, widely varying hydrologic conditions and selection of analytes. In order to develop a sustainable MSW management strategy for protecting the surface and ground water resources, particularly from MSW landfill leachate contamination, assessment and characterisation of leachate are necessary. Numerous studies have been conducted in the past to characterise leachate quality from various municipal landfills; unfortunately, none of these propose a framework or protocol. The present study proposes a generic framework for municipal landfill leachate assessment and characterisation. The proposed framework can be applied to design any type of landfill leachate quality monitoring programme and also to facilitate improved leachate treatment activities. A landfill site located at Turbhe, Navi Mumbai, India, which had not been investigated earlier, has been selected as a case study. The proposed framework has been demonstrated on the Turbhe landfill site which is a comparatively new and the only sanitary landfill in Navi Mumbai.

  16. Tritium emissions reduction facility (TERF)

    International Nuclear Information System (INIS)

    Lamberger, P.H.; Hedley, W.H.

    1993-01-01

    Tritium handling operations at Mound include production of tritium-containing devices, evaluation of the stability of tritium devices, tritium recovery and enrichment, tritium process development, and research. In doing this work, gaseous process effluents containing 400,000 to 1,000,000 curies per year of tritium are generated. These gases must be decontaminated before they can be discharged to the atmosphere. They contain tritium as elemental hydrogen, as tritium oxide, and as tritium-containing organic compounds at low concentrations (typically near one ppm). The rate at which these gases is generated is highly variable. Some tritium-containing gas is generated at all times. The systems used at Mound for capturing tritium from process effluents have always been based on the open-quotes oxidize and dryclose quotes concept. They have had the ability to remove tritium, regardless of the form it was in. The current system, with a capacity of 1.0 cubic meter of gas per minute, can effectively remove tritium down to part-per-billion levels

  17. Use of the Geographic Information System and Analytic Hierarchy Process for Municipal Solid Waste Landfill Site Selection: A Case Study of Najafabad, Iran

    Directory of Open Access Journals (Sweden)

    A. Afzali

    2014-03-01

    Full Text Available Following technological advancements and integrated municipal solid waste management in recent decades, various methods such as recycling, biotreatment, thermal treatment, and sanitary landfills have been developed and employed. Creating sanitary landfills is a major strategy in the integrated solid waste management hierarchy. It is cheaper and thus more common than other disposal methods. Selecting a suitable solid waste landfill site can prevent adverse ecological and socioeconomic effects. Landfill site selection requires the analysis of spatial data, regulations, and accepted criteria. The present study aimed to use the geographic information system and the analytic hierarchy process to identify an appropriate landfill site for municipal solid wastes in Najafabad (Isfahan, Iran. Environmental and socioeconomic criteria were evaluated through different information layers in the Boolean and fuzzy logics. The analytical hierarchy process was applied for weighing the fuzzy information layers. Subsequently, two suitable sites were identified by superimposing the maps from the Boolean and fuzzy logics and considering the minimum required landfill area for 20 years. However, proximity of these two sites to Tiran (a nearby city made them undesirable landfill sites for Najafabad. Therefore, due to the existing restrictions in Najafabad, the possibility of creating landfill sites in common with adjacent cities should be further investigated.

  18. Tritium production distribution in the accelerator production of tritium device

    International Nuclear Information System (INIS)

    Kidman, R.B.

    1997-11-01

    Helium-3 ( 3 He) gas is circulated throughout the accelerator production of tritium target/blanket (T/B) assembly to capture neutrons and convert 3 He to tritium. Because 3 He is very expensive, it is important to know the tritium producing effectiveness of 3 He at all points throughout the T/B. The purpose of this paper is to present estimates of the spatial distributions of tritium production, 3 He inventory, and the 3 He FOM

  19. ENHANCED LANDFILL MINING: KONSEP BARU PENGELOLAAN LANDFILL BERKELANJUTAN

    OpenAIRE

    Wahyono, Sri

    2016-01-01

    Enhanced landfill mining (ELFM) adalah konsep baru yang terintegrasi tentang recovery material dan energi pada sebuah landfill yang bermanfaat bagi keberlanjutan pengelolaan material dan pengelolaan landfill. Konsep tersebut mengintegrasikan berbagai teknologi seperti teknologi ekskavasi, teknologi pemilahan, teknologi termal, teknologi transformasi dan daur ulang. Hal tersebut juga terintegrasi dengan aspek non teknis seperti aspek regulasi, market, ekonomi, sosial, dan lingkungan. Konsep EL...

  20. Cold Vacuum Drying facility sanitary sewage collection system design description

    International Nuclear Information System (INIS)

    PITKOFF, C.C.

    1999-01-01

    This document describes the Cold Vacuum Drying Facility (CVDF) sanitary sewage collection system. The sanitary sewage collection system provides collection and storage of effluents and raw sewage from the CVDF to support the cold vacuum drying process. This system is comprised of a sanitary sewage holding tank and pipes for collection and transport of effluents to the sanitary sewage holding tank

  1. Turkey Run Landfill Emissions Dataset

    Data.gov (United States)

    U.S. Environmental Protection Agency — landfill emissions measurements for the Turkey run landfill in Georgia. This dataset is associated with the following publication: De la Cruz, F., R. Green, G....

  2. Field Monitoring of Landfill Gas

    International Nuclear Information System (INIS)

    Silvola, M.; Priha, E.

    2003-01-01

    The Finnish waste legislation requires monitoring of landfill gases. The main goal of this study is to develop instructions for field monitoring of landfill gases to be utilized by consultants and authorities. In the project it was got acquainted with the field analytical methods of landfill gases and instruments of field measurement. It was done various practical field measurements in several landfills. In the studied landfills were observed methane, carbon dioxide and oxygen concentrations and gas forming inside waste embankment in different seasons. It was measured methane emissions that discharged through a landfill surface by a chamber technique. In addition to this it was studied volatile organic compounds (VOC:s), which were liberated in a landfill. It was also studied methane oxidization in cover layers of a landfill. (orig.)

  3. Tritium Systems Test Facility

    International Nuclear Information System (INIS)

    Cafasso, F.A.; Maroni, V.A.; Smith, W.H.; Wilkes, W.R.; Wittenberg, L.J.

    1978-01-01

    This TSTF proposal has two principal objectives. The first objective is to provide by mid-FY 1981 a demonstration of the fuel cycle and tritium containment systems which could be used in a Tokamak Experimental Power Reactor for operation in the mid-1980's. The second objective is to provide a capability for further optimization of tritium fuel cycle and environmental control systems beyond that which is required for the EPR. The scale and flow rates in TSTF are close to those which have been projected for a prototype experimental power reactor (PEPR/ITR) and will permit reliable extrapolation to the conditions found in an EPR. The fuel concentrations will be the same as in an EPR. Demonstrations of individual components of the deuterium-tritium fuel cycle and of monitoring, accountability and containment systems and of a maintenance methodology will be achieved at various times in the FY 1979-80 time span. Subsequent to the individual component demonstrations--which will proceed from tests with hydrogen (and/or deuterium) through tracer levels of tritium to full operational concentrations--a complete test and demonstration of the integrated fuel processing and tritium containment facility will be performed. This will occur near the middle of FY 1981. Two options were considered for the TSTF: (1) The modification of an existing building and (2) the construction of a new facility

  4. Tritium analysis at TFTR

    International Nuclear Information System (INIS)

    Voorhees, D.R.; Rossmassler, R.L.; Zimmer, G.

    1995-01-01

    The tritium analytical system at TFRR is used to determine the purity of tritium bearing gas streams in order to provide inventory and accountability measurements. The system includes a quadrupole mass spectrometer and beta scintillator originally configured at Monsanto Mound Research Laboratory in the late 1970's and early 1980's. The system was commissioned and tested between 1991 and 1992 and is used daily for analysis of calibration standards, incoming tritium shipments, gases evolved from uranium storage beds and measurement of gases returned to gas holding tanks. The low resolution mass spectrometer is enhanced by the use of a metal getter pump to aid in resolving the mass 3 and 4 species. The beta scintillator complements the analysis as it detects tritium bearing species that often are not easily detected by mass spectrometry such as condensable species or hydrocarbons containing tritium. The instruments are controlled by a personal computer with customized software written with a graphical programming system designed for data acquisition and control. A discussion of the instrumentation, control systems, system parameters, procedural methods, algorithms, and operational issues will be presented. Measurements of gas holding tanks and tritiated water waste streams using ion chamber instrumentation are discussed elsewhere

  5. First district sanitary doctor of Katerynoslav

    OpenAIRE

    M.P. Chaban; Z.I. Shevtsova; V.V. Gaponov

    2017-01-01

    The life and professional activity of Vasyl Tymofiiovych Skrylnikov — a famous doctor-hygienist, scientist, and public figure have been represented. V.T. Skrylnikov contributed to the development of sanitary-prophylaxis direction in zemstvo medicine in Katerynoslav province in the second half of the 19th century; he was the first district sanitary doctor in Katerynoslav. The scientist actively studied medical features of natural agents, namely Tymofiivska clay. He successfully worked at Slovi...

  6. Recalcitrance removal of pretreated landfill leachate by ozone-based oxidation processes

    OpenAIRE

    Van Aken, Pieter; Van Eyck, Kwinten; Luyten, Jan; Degrève, Jan; Liers, Sven

    2010-01-01

    The sanitary landfill method for the ultimate disposal of solid waste material continues to be widely accepted and used due to its economic advantages. However, water infiltrates through the solid waste and a variety of organic and inorganic pollutants will be dissolved and transported. These leachates may contain large amounts of organic matter, as well as ammonia-nitrogen, heavy metals, chlorinated organic and inorganic salts. The removal of organic material is usual the prerequisite before...

  7. Tritium - is it underestimated

    International Nuclear Information System (INIS)

    Whitlock, G.D.

    1980-01-01

    Practical experience in the use of the Whitlock Tritium Meter in various laboratories and industrial establishments throughout the world has shown that:-a) Measurements by smear/wipe tests can often be in error by three orders of magnitude or more; b) Sub-visual surface scratches (8μ deep) are radiologically important; c) Volatile forms of tritium exist in 20% to 30% of establishments visited. It is concluded that a) the widespread use of smear/wipe techniques for the assessment of 3 H surface contamination based on the assumption that 10% of removable activity is collected by the smear/wipe should be re-examined and b) tritium surface contamination assessed as 'fixed' can contain volatile fractions with a hazard potential which may be considerably greater than the hazard from removable activity at present covered by maximum permissible level recommendations. (H.K.)

  8. Tritium in HTR systems

    International Nuclear Information System (INIS)

    Steinwarz, W.

    1987-07-01

    Starting from the basis of the radiological properties of tritium, the provisions of present-day radiation protection legislation are discussed in the context of the handling of this radionuclide in HTR plants. Tritium transportation is then followed through from the place of its creation up until the sink, i.e. disposal and/or environmental route, and empirical values obtained in experiments and in plant operation translated into guidelines for plant design and planning. The use of the example of modular HTR plants permits indication that environmental contamination via the 'classical' routes of air and water emissions, and contamination of products, and resulting consumer exposure, are extremely low even on the assumption of extreme conditions. This leads finally to a requirement that the expenditure for implementation of measures for further reduction of tritium activity rates be measured against low radiological effect. (orig.) [de

  9. Atmospheric tritium. Measurement and application

    International Nuclear Information System (INIS)

    Frejaville, Gerard

    1967-02-01

    The possible origins of atmospheric tritium are reviewed and discussed. A description is given of enrichment (electrolysis and thermal diffusion) and counting (gas counters and liquid scintillation counters) processes which can be used for determining atmospheric tritium concentrations. A series of examples illustrates the use of atmospheric tritium for resolving a certain number of hydrological and glaciological problems. (author) [fr

  10. Handling of tritium at TFTR

    International Nuclear Information System (INIS)

    Pierce, C.W.; Howe, H.J.; Yemin, L.; Lind, K.

    1977-01-01

    Some of the engineering approaches taken at TFTR for the tritium control systems are discussed as the requirements being placed on the tritium systems by the operating scenarios of the Tokamak. The tritium control systems presently being designed for TFTR will limit the annual release to the environment to less than 100 curies

  11. Tritium effluent removal system

    International Nuclear Information System (INIS)

    Lamberger, P.H.; Gibbs, G.E.

    1978-01-01

    An air detritiation system has been developed and is in routine use for removing tritium and tritiated compounds from glovebox effluent streams before they are released to the atmosphere. The system is also used, in combination with temporary enclosures, to contain and decontaminate airborne releases resulting from the opening of tritium containment systems during maintenance and repair operations. This detritiation system, which services all the tritium handling areas at Mound Facility, has played an important role in reducing effluents and maintaining them at 2 percent of the level of 8 y ago. The system has a capacity of 1.7 m 3 /min and has operated around the clock for several years. A refrigerated in-line filtration system removes water, mercury, or pump oil and other organics from gaseous waste streams. The filtered waste stream is then heated and passed through two different types of oxidizing beds; the resulting tritiated water is collected on molecular sieve dryer beds. Liquids obtained from regenerating the dryers and from the refrigerated filtration system are collected and transferred to a waste solidification and packaging station. Component redundancy and by-pass capabilities ensure uninterrupted system operation during maintenance. When processing capacity is exceeded, an evacuated storage tank of 45 m 3 is automatically opened to the inlet side of the system. The gaseous effluent from the system is monitored for tritium content and recycled or released directly to the stack. The average release is less than 1 Ci/day. The tritium effluent can be reduced by isotopically swamping the tritium; this is accomplished by adding hydrogen prior to the oxidizer beds, or by adding water to the stream between the two final dryer beds

  12. Restoration of landfill sites

    Energy Technology Data Exchange (ETDEWEB)

    Jones, A K; Chamley, M E

    1986-10-01

    Many excavated quarries are subsequently used for waste disposal operations and frequently imported landfill provides the only means of restoring a former quarry to some beneficial afteruse. Concentrating solely on the final surface cover, this paper sets out some of the principles, which should be considered by those involved in landfill operations to ensure the long term success of restoration schemes. With the emphasis on restoration to agriculture, factors such as availability of cover materials and depths necessary are discussed in terms of requirements to support plant growth, protect clay capping layers and prevent damage to agricultural implements. Soil handling and appropriate after care management are considered. 4 refs.

  13. Development of tritium technology at the Tritium Systems Test Assembly

    International Nuclear Information System (INIS)

    Anderson, J.L.; Bartlit, J.R.

    1982-01-01

    The Tritium Systems Test Assembly (TSTA) at the Los Alamos National Laboratory is dedicated to the development, demonstration, and interfacing of technologies related to the deuterium-tritium fuel cycle for large scale fusion reactor systems starting with the Fusion Engineering Device (FED) or the International Tokamak Reactor (INTOR). This paper briefly describes the fuel cycle and safety systems at TSTA including the Vacuum Facility, Fuel Cleanup, Isotope Separation, Transfer Pumping, Emergency Tritium Cleanup, Tritium Waste Treatment, Tritium Monitoring, Data Acquisition and Control, Emergency Power and Gas Analysis systems. Discussed in further detail is the experimental program proposed for the startup and testing of these systems

  14. Monitoring of tritium

    Science.gov (United States)

    Corbett, James A.; Meacham, Sterling A.

    1981-01-01

    The fluid from a breeder nuclear reactor, which may be the sodium cooling fluid or the helium reactor-cover-gas, or the helium coolant of a gas-cooled reactor passes over the portion of the enclosure of a gaseous discharge device which is permeable to hydrogen and its isotopes. The tritium diffused into the discharge device is radioactive producing beta rays which ionize the gas (argon) in the discharge device. The tritium is monitored by measuring the ionization current produced when the sodium phase and the gas phase of the hydrogen isotopes within the enclosure are in equilibrium.

  15. Tritium in rad waste management

    International Nuclear Information System (INIS)

    Gandhi, P.M.; Ali, S.S.; Mathur, R.K.; Rastogi, R.C.

    1990-01-01

    Radioactive waste arising from PHWR's are invariably contaminated with tritium activity. Their disposal is crucial as it governs the manner and extent of radioactive contamination of human environment. The technique of tritium measurement and its application plays an important role in assessing the safety of the disposal system. Thus, typical applications involving tritium measurements include the evaluation of a site for solid waste burial facility and evaluation of a water body for liquid waste dispersal. Tritium measurement is also required in assessing safe air route dispersal of tritium. (author)

  16. ARIES-I tritium system

    International Nuclear Information System (INIS)

    Sze, D.K.; Tam, S.W.; Billone, M.C.; Hassanein, A.M.; Martin, R.

    1990-09-01

    A key safety concern in a D-T fusion reactor is the tritium inventory. There are three components in a fusion reactor with potentially large inventories, i.e., the blanket, the fuel processing system and the plasma facing components. The ARIES team selected the material combinations, decided the operating conditions and refined the processing systems, with the aiming of minimizing the tritium inventories and leakage. The total tritium inventory for the ARIES-I reactor is only 700 g. This paper discussed the calculations and assumptions we made for the low tritium inventory. We also addressed the uncertainties about the tritium inventory. 13 refs., 2 figs., 3 tabs

  17. Landfill lights Liverpool festival

    Energy Technology Data Exchange (ETDEWEB)

    Matan, E

    1986-12-01

    Plants which generate power from garbage landfill gas with outputs up to 10 MWe now run into hundreds around the world. Projects to produce combined-heat-and-power from such resources are relatively few. At Liverpool, UK, a 1 MWe CHP plant has been operating successfully at the site of a major international garden festival.

  18. Financing landfill gas projects

    International Nuclear Information System (INIS)

    Bull, R.

    1992-01-01

    The problems of financing landfill gas projects in the UK in the last few years are discussed. The approach of the author in setting up a company to finance such projects in the power generation field and a separate company to design and supply turnkey packages is reported. (UK)

  19. Occurrence, characteristics and leakage of polybrominated diphenyl ethers in leachate from municipal solid waste landfills in China

    International Nuclear Information System (INIS)

    Li, Ying; Li, Jinhui; Deng, Chao

    2014-01-01

    Raw leachate samples were collected from various municipal solid waste (MSW) landfills in a densely populated city in North China to measure the levels and compositional patterns of polybrominated diphenyl ethers (PBDEs) in leachate. The total concentration of PBDEs ranged from 4.0 to 351.2 ng/L, with an average of 73.0 ng/L. BDE-209 dominated the congeners in most of the samples, followed by BDE-47 and -99. Higher PBDEs concentrations were found in leachate from younger landfill facilities in the urban area. Pearson correlation analysis implied a potential dependence of the PBDEs level on landfill age, suspended solids and dissolved organic carbon, while the results of principal component analysis (PCA) suggested potential origins and transportation of PBDEs in leachate. The Monte Carlo method was adopted to estimate the annual leakage of PBDEs into the underground environment nationwide, based on two main scenarios: simple landfills with inadequate liner systems and composite-lined landfills with defective geomembranes. -- Highlights: • Levels and congener patterns of PBDEs in landfill leachate from China are measured. • Pollution loading of PBDEs in leachate is identified through comparative analysis. • Leachate properties perform moderate impact on the occurrence of PBDEs. • Both commercial and decomposition origins contribute to lower brominated congeners. • Leakage rate of PBDEs due to inadequate liner is estimated nationwide. -- This paper determined the levels and distribution of PBDEs in MSW landfill leachate and predicted the leakage of PBDEs from sanitary landfills into the underground environment across China

  20. Hydrogeology and historical assessment of a classic sequential-land use landfill site, Illinois, U.S.A.

    Science.gov (United States)

    Booth, Colin J.; Vagt, Peter J.

    1990-05-01

    The Blackwell site in northeastern Illinois was a classic sequential-use project combining land reclamation, a sanitary landfill, and a recreational park. This paper adds a recent assessment of leachate generation and groundwater contamination to the site's unfinished record. Hydrogeological studies show that (1) the landfill sits astride an outwash aquifer and a till mound, which are separated from an underlying dolomite aquifer by a thin, silty till; (2) leachate leaks from the landfill at an estimated average rate between 48 and 78 m3/d; (3) the resultant contaminant plume is virtually stagnant in the till but rapidly diluted in the outwash aquifer, so that no off-site contamination is detected; (4) trace VOC levels in the dolomite probably indicate that contaminants have migrated there from the landfill-derived plume in the outwash. Deviations from the original landfill concepts included elimination of a leachate collection system, increased landfill size, local absence of a clay liner, and partial use of nonclay cover. The hydrogeological setting was unsuitable for the landfill as constructed, indicating the importance of detailed geological consideration in landfill and land-use planning.

  1. Tritium breeding materials

    International Nuclear Information System (INIS)

    Hollenberg, G.W.; Johnson, C.E.; Abdou, M.

    1984-03-01

    Tritium breeding materials are essential to the operation of D-T fusion facilities. Both of the present options - solid ceramic breeding materials and liquid metal materials are reviewed with emphasis not only on their attractive features but also on critical materials issues which must be resolved

  2. Tritium breeding materials

    International Nuclear Information System (INIS)

    Hollenberg, G.W.; Johnson, C.E.; Abdou, M.A.

    1984-01-01

    Tritium breeding materials are essential to the operation of D-T fusion facilities. Both of the present options - solid ceramic breeding materials and liquid metal materials are reviewed with emphasis not only on their attractive features but also on critical materials issues which must be resolved

  3. Properties of tritium and its compounds

    International Nuclear Information System (INIS)

    Belovodskij, L.F.; Gaevoj, V.K.; Grishmanovskij, V.I.

    1985-01-01

    Ways of tritium preparation and different aspects of its application are considered. Physicochemical properties of this isotope and some compounds of it - tritium oxides, lithium, titanium, zirconium, uranium tritides, tritium organic compounds - are discussed. In particular, diffusion of tritium and its oxide through different materials, tritium oxidation processes, decomposition of tritium-containing compounds under the action of self-radiation are considered. Main radiobiological tritium properties are described

  4. Use of tritium and sources

    International Nuclear Information System (INIS)

    Noguchi, Hiroshi

    1997-01-01

    There are many kinds of tritium, sources in the environment. The maximum inventory of them is the nuclear tests, although the atmospheric nuclear test has not been carried out since 1981. So that the inventory originated from them will decrease. By the latest data in 1989, the total amount of released tritium was about 24 PBq/yr by the use of atomic energy in the world. The maximum source was the heavy water moderated reactors, for example, CANDU reactor. In the future, large amount of tritium inventory may be the fusion reactor. The test of JET (Joint European Torus) released about 600 GBq of tritium until March in 1992. 80-90% of them were tritium water (HTO). The amount of tritium released from industries and medicine are limited. Although ITER has a large amount of tritium inventory, the amount of release is seemed not to be larger than other nuclear power facility. (S.Y.)

  5. Tritium transport calculations for the IFMIF Tritium Release Test Module

    Energy Technology Data Exchange (ETDEWEB)

    Freund, Jana, E-mail: jana.freund@kit.edu; Arbeiter, Frederik; Abou-Sena, Ali; Franza, Fabrizio; Kondo, Keitaro

    2014-10-15

    Highlights: • Delivery of material data for the tritium balance in the IFMIF Tritium Release Test Module. • Description of the topological models in TMAP and the adapted fusion-devoted Tritium Permeation Code (FUS-TPC). • Computation of release of tritium from the breeder solid material into the purge gas. • Computation of the loss of tritium over the capsule wall, rig hull, container wall and purge gas return line. - Abstract: The IFMIF Tritium Release Test Module (TRTM) is projected to measure online the tritium release from breeder ceramics and beryllium pebble beds under high energy neutron irradiation. Tritium produced in the pebble bed of TRTM is swept out continuously by a purge gas flow, but can also permeate into the module's metal structures, and can be lost by permeation to the environment. According analyses on the tritium inventory are performed to support IFMIF plant safety studies, and to support the experiment planning. This paper describes the necessary elements for calculation of the tritium transport in the Tritium Release Test Module as follows: (i) applied equations for the tritium balance, (ii) material data from literature and (iii) the topological models and the computation of the five different cases; namely release of tritium from the breeder solid material into the purge gas, loss of tritium over the capsule wall, rig hull, container wall and purge gas return line in detail. The problem of tritium transport in the TRTM has been studied and analyzed by the Tritium Migration Analysis Program (TMAP) and the adapted fusion-devoted Tritium Permeation Code (FUS-TPC). TMAP has been developed at INEEL and now exists in Version 7. FUS-TPC Code was written in MATLAB with the original purpose to study the tritium transport in Helium Cooled Lead Lithium (HCLL) blanket and in a later version the Helium Cooled Pebble Bed (HCPB) blanket by [6] (Franza, 2012). This code has been further modified to be applicable to the TRTM. Results from the

  6. Tritium transport calculations for the IFMIF Tritium Release Test Module

    International Nuclear Information System (INIS)

    Freund, Jana; Arbeiter, Frederik; Abou-Sena, Ali; Franza, Fabrizio; Kondo, Keitaro

    2014-01-01

    Highlights: • Delivery of material data for the tritium balance in the IFMIF Tritium Release Test Module. • Description of the topological models in TMAP and the adapted fusion-devoted Tritium Permeation Code (FUS-TPC). • Computation of release of tritium from the breeder solid material into the purge gas. • Computation of the loss of tritium over the capsule wall, rig hull, container wall and purge gas return line. - Abstract: The IFMIF Tritium Release Test Module (TRTM) is projected to measure online the tritium release from breeder ceramics and beryllium pebble beds under high energy neutron irradiation. Tritium produced in the pebble bed of TRTM is swept out continuously by a purge gas flow, but can also permeate into the module's metal structures, and can be lost by permeation to the environment. According analyses on the tritium inventory are performed to support IFMIF plant safety studies, and to support the experiment planning. This paper describes the necessary elements for calculation of the tritium transport in the Tritium Release Test Module as follows: (i) applied equations for the tritium balance, (ii) material data from literature and (iii) the topological models and the computation of the five different cases; namely release of tritium from the breeder solid material into the purge gas, loss of tritium over the capsule wall, rig hull, container wall and purge gas return line in detail. The problem of tritium transport in the TRTM has been studied and analyzed by the Tritium Migration Analysis Program (TMAP) and the adapted fusion-devoted Tritium Permeation Code (FUS-TPC). TMAP has been developed at INEEL and now exists in Version 7. FUS-TPC Code was written in MATLAB with the original purpose to study the tritium transport in Helium Cooled Lead Lithium (HCLL) blanket and in a later version the Helium Cooled Pebble Bed (HCPB) blanket by [6] (Franza, 2012). This code has been further modified to be applicable to the TRTM. Results from the

  7. Tritium determination in water

    International Nuclear Information System (INIS)

    Gavini, Ricardo M.

    2008-01-01

    An analytical procedure for the determination of tritium in water is described in this paper. The determination is carried out in presence of other radionuclides, such as Fe-55, Ni-63, Mn-54, Zn-65, Co-60, Cd-109, Sr-90, Cs-134 and Cs-137. The method consists in a simple distillation stage prior to measurement by liquid scintillation counting. The samples containing beta and gamma emitters are conditioned with a (NO 3 ) 2 Pb solution and Na(OH) up to pH = 7 - 8. This produces lead hydroxide precipitation that allows fixing volatile elements, which could be transported together with tritium, and may increase the extinction degree of the sample or interfere with the counting process. Special attention must be paid if presence of Fe-55 (E max ∼ 5.95 keV) is suspected as it might not be distinguished from tritium (E max ∼ 18 keV), leading to an overestimation of tritium activity. Different tests were carried to obtain the optimum method conditions, to achieve the purification of the tritium and a pH near to 7 in the distilled. The detection limit (2σ) was 8.0 Bq/l and the distillation performance was 98.3 %. This technique was applied to water samples containing Fe-55 and other gamma radionuclides in 1M hydrochloric acid media in successive Environmental Measurements Laboratory (EML), U.S. Department of Energy (DOE) intercomparison programs. The results obtained were very satisfactory and are presented in this paper. (author)

  8. Vegetation and moisture performance on a Resource Conservation and Recovery Act-equivalent landfill cap at the Hanford site

    International Nuclear Information System (INIS)

    Kemp, C.J.; Sackschewsky, M.R.

    1997-03-01

    Landfills, as defined under the Resource Conservation and Recovery Act of 1976 (RCRA) can receive waste materials from commercial and industrial operations, residences, and other sources. Sanitary landfills that are used to dispose of solid waste require a landfill cover that meets RCRA requirements to prevent leaching of water through buried wastes and to isolate the waste for a period of 30 years. The purpose of a RCRA landfill cover is to 'protect public health, to prevent land, air, and water pollution, and conserve the state's natural, economic, and energy resources' (Washington Administrative Code [WAC] 173-304). The hypothesis of this study were as follows: (1) amending soil nitrogen would enhance perennial grass biomass; (2) the amount of biomass produced by commercially-available wheatgrass species would be similar to bluebunch wheatgrass; and (3) the vegetative biomass, as required by WAC-173-304, would not be produced in a semiarid climate

  9. Survival, reproduction, and recruitment of woody plants after 14 years on a reforested landfill

    Science.gov (United States)

    Robinson, George R.; Handel, Steven N.; Schmalhofer, Victoria R.

    1992-03-01

    With the advent of modern sanitary landfill closure techniques, the opportunity exists for transforming municipal landfills into urban woodlands. While costs of fullscale reforestation are generally prohibitive, a modest planting of clusters of trees and shrubs could initiate or accelerate population expansions and natural plant succession from open field to diverse forest. However, among woody species that have been screened for use on landfills, these ecological potentials have not yet been investigated. We examined a 14-yr-old landfill plantation in New Jersey, USA, established to test tolerance of 19 species of trees and shrubs to landfill environments. We measured survivorship, reproduction, and recruitment within and around the experimental installation. Half of the original 190 plants were present, although survival and growth rates varied widely among species. An additional 752 trees and shrubs had colonized the plantation and its perimeter, as well as 2955 stems of vines. However, the great majority (>95%) of woody plants that had colonized were not progeny of the planted cohort, but instead belonged to 18 invading species, mostly native, bird-dispersed, and associated with intermediate stages of secondary plant succession. Based on this evidence, we recommend that several ecological criteria be applied to choices of woody species for the restoration of municipal landfills and similar degraded sites, in order to maximize rapid and economical establishment of diverse, productive woodlands.

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

    International Nuclear Information System (INIS)

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

    1996-01-01

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

  11. Performance of a mixed-waste landfill amid geologic uncertainty—learning from a case study: Altamont Hills, California, U.S.A.

    Science.gov (United States)

    Taffet, Michael J.; Lamarre, Albert L.; Oberdorfer, June A.

    1991-11-01

    This paper presents a case study that illustrates how geologic factors, which are not always obvious without extensive study, may hamper later landfill performance. The site is Lawrence Livermore National Laboratory (LLNL) site 300. Two unlined landfills, opened in 1958, and 1968, contain small amounts of tritium, uranium-238, lead, and beryllium in a vast proportion of inert materials (gravel, wood, and plastic). Groundwater analyses indicate that tritium at activities up to 600,000 picoCuries per liter (pCi/l) is present in two plumes beneath and adjacent to the landfills within a perched water-bearing zone. The affected water-bearing zone averages 2 m in thickness and occurs within the late Miocene Neroly Formation, which is composed of feldspathic sandstones and siltstones and interbedded claystones and conglomerates. Scanning election microscopy (SEM) analysis indicates that diagenetic clays have occluded the porosity of much of the sandstones. However, abundant fractures appear to provide permeability. Depth to the water table fluctuates greatly beneath the site but averages about 10 m. In the past, following heavy rains, groundwater levels rose into the landfill bottoms and mobilized the tritium. Rapid recharge and rise of water levels appear to have been enhanced by the funnelling of surface water by topography, direct infiltration through fractures and permeable landfill materials, and the low permeability of the geologic materials that comprise the water-bearing zone. These and other hydrogeologic conditions contributed to groundwater contact with landfill materials but were not known before landfill construction. Such information is important for siting landfills in the current regulatory environment. Contaminant transport modeling indicates that even if the perched water-bearing zone were continuous to the site 300 boundary, tritium activities would undergo radioactive decay to background levels by the time the tritiated water could reach the site

  12. A Review on Landfill Management in the Utilization of Plastic Waste as an Alternative Fuel

    Directory of Open Access Journals (Sweden)

    Hidayah Nurul

    2018-01-01

    Full Text Available Wastes from landfills originate from many spheres of life. These are produces as a result of human activities either domestically or industrially. The global plastic production increased over years due to the vast applications of plastics in many sectors. The continuous demand of plastics caused the plastic wastes accumulation in the landfill consumed a lot of spaces that contributed to the environmental. In addition, economic growth and development also increased our demand and dependency on plastics which leads to its accumulation in landfills imposing risk on human health, animals and cause environmental pollution problems such as ground water contamination, sanitary related issues, etc. The management and disposal of plastic waste have become a major concern, especially in developing cities. The idea of waste to energy recovery is one of the promising techniques used for managing the waste of plastic. Hence, this paper aims review at utilizing of plastic as an alternative fuel.

  13. A Review on Landfill Management in the Utilization of Plastic Waste as an Alternative Fuel

    Science.gov (United States)

    Hidayah, Nurul; Syafrudin

    2018-02-01

    Wastes from landfills originate from many spheres of life. These are produces as a result of human activities either domestically or industrially. The global plastic production increased over years due to the vast applications of plastics in many sectors. The continuous demand of plastics caused the plastic wastes accumulation in the landfill consumed a lot of spaces that contributed to the environmental. In addition, economic growth and development also increased our demand and dependency on plastics which leads to its accumulation in landfills imposing risk on human health, animals and cause environmental pollution problems such as ground water contamination, sanitary related issues, etc. The management and disposal of plastic waste have become a major concern, especially in developing cities. The idea of waste to energy recovery is one of the promising techniques used for managing the waste of plastic. Hence, this paper aims review at utilizing of plastic as an alternative fuel.

  14. Landfill Gas | Climate Neutral Research Campuses | NREL

    Science.gov (United States)

    Landfill Gas Landfill Gas For campuses located near an active or recently retired landfill , landfill gas offers an opportunity to derive significant energy from a renewable energy resource. The following links go to sections that describe when and where landfill gas systems may fit into your climate

  15. Tritium in the aquatic environment

    International Nuclear Information System (INIS)

    Blaylock, B.G.; Hoffman, F.O.; Frank, M.L.

    1986-02-01

    Tritium is of environmental importance because it is released from nuclear facilities in relatively large quantities and because it has a half life of 12.26 y. Most of the tritium released into the atmosphere eventually reaches the aqueous environment, where it is rapidly taken up by aquatic organisms. This paper reviews the current literature on tritium in the aquatic environment. Conclusions from the review, which covered studies of algae, aquatic macrophytes, invertebrates, fish, and the food chain, were that aquatic organisms incorporate tritium into their tissue-free water very rapidly and reach concentrations near those of the external medium. The rate at which tritium from tritiated water is incorporated into the organic matter of cells is slower than the rate of its incorporation into the tissue-free water. If organisms consume tritiated food, incorporation of tritium into the organic matter is faster, and a higher tritium concentration is reached than when the organisms are exposed to only tritiated water alone. Incorporation of tritium bound to molecules into the organic matter depends on the chemical form of the ''carrier'' molecule. No evidence was found that biomagnification of tritium occurs at higher trophic levels. Radiation doses from tritium releases to large populations of humans will most likely come from the consumption of contaminated water rather than contaminated aquatic food products

  16. Tritium. Today's and tomorrow's developments

    International Nuclear Information System (INIS)

    Gazal, S.; Amiard, J.C.; Caussade, Bernard; Chenal, Christian; Hubert, Francoise; Sene, Monique

    2010-01-01

    Radioactive hydrogen isotope, tritium is one of the radionuclides which is the most released in the environment during the normal operation of nuclear facilities. The increase of nuclear activities and the development of future generations of reactors, like the EPR and ITER, would lead to a significant increase of tritium effluents in the atmosphere and in the natural waters, thus raising many worries and questions. Aware about the importance of this question, the national association of local information commissions (ANCLI) wished to make a status of the existing knowledge concerning tritium and organized in 2008 a colloquium at Orsay (France) with an inquiring approach. The scientific committee of the ANCLI, renowned for its expertise skills, mobilized several nuclear specialists to carry out this thought. This book represents a comprehensive synthesis of today's knowledge about tritium, about its management and about its impact on the environment and on human health. Based on recent scientific data and on precise examples, it treats of the overall questions raised by this radionuclide: 1 - tritium properties and different sources (natural and anthropic), 2 - the problem of tritiated wastes management; 3 - the bio-availability and bio-kinetics of the different tritium species; 4 - the tritium labelling of environments; 5 - tritium measurement and modeling of its environmental circulation; 6 - tritium radio-toxicity and its biological and health impacts; 7 - the different French and/or international regulations concerning tritium. (J.S.)

  17. Tritium breeders and tritium permeation barrier coatings for fusion reactor

    International Nuclear Information System (INIS)

    Yamawaki, Michio; Kawamura, Hiroshi; Tsuchiya, Kunihiko

    2004-01-01

    A state of R and D of tritium breeders and tritium permeation barrier coatings for fusion reactor is explained. A list of candidate for tritium breeders consists of ceramics containing lithium, for examples, Li 2 O, Li 2 TiO 3 , Li 2 ZrO 3 , Li 4 SiO 4 and LiAlO 2 . The characteristics and form are described. The optimum particle size is from 1 to 10 μm. The production technologies of tritium breeders in the world are stated. Characteristics of ceramics with lithium as tritium breeders are compared. TiC, TiN/TiC, Al 2 O 3 and Cr 2 O 3 -SiO 2 -P 2 O 5 are tritium permeation barrier coating materials. These production methods and evaluation of characteristics are explained. (S.Y.)

  18. Universal tritium transmitter

    International Nuclear Information System (INIS)

    Cordaro, J. V.; Wood, M.

    2008-01-01

    At the Savannah River Site and throughout the National Nuclear Security Agency (NNSA) tritium is measured using Ion or Kanne Chambers. Tritium flowing through an Ion Chamber emits beta particles generating current flow proportional to tritium radioactivity. Currents in the 1 x 10 -15 A to 1 x 10 -6 A are measured. The distance between the Ion Chamber and the electrometer in NNSA facilities can be over 100 feet. Currents greater than a few micro-amperes can be measured with a simple modification. Typical operating voltages of 500 to 1000 Volts and piping designs require that the Ion Chamber be connected to earth ground. This grounding combined with long cable lengths and low currents requires a very specialized preamplifier circuit. In addition, the electrometer must be able to supply 'fail safe' alarm signals which are used to alert personnel of a tritium leak, trigger divert systems preventing tritium releases to the environment and monitor stack emissions as required by the United States federal Government and state governments. Ideally the electrometer would be 'self monitoring'. Self monitoring would reduce the need for constant checks by maintenance personnel. For example at some DOE facilities monthly calibration and alarm checks must be performed to ensure operation. NNSA presently uses commercially available electrometers designed specifically for this critical application. The problems with these commercial units include: ground loops, high background currents, inflexibility and susceptibility to Electromagnetic Interference (EMI) which includes RF and Magnetic fields. Existing commercial electrometers lack the flexibility to accommodate different Ion Chamber designs required by the gas pressure, type of gas and range. Ideally the electrometer could be programmed for any expected gas, range and high voltage output. Commercially available units do not have 'fail safe' self monitoring capability. Electronics used to measure extremely low current must have

  19. First district sanitary doctor of Katerynoslav

    Directory of Open Access Journals (Sweden)

    M.P. Chaban

    2017-02-01

    Full Text Available The life and professional activity of Vasyl Tymofiiovych Skrylnikov — a famous doctor-hygienist, scientist, and public figure have been represented. V.T. Skrylnikov contributed to the development of sanitary-prophylaxis direction in zemstvo medicine in Katerynoslav province in the second half of the 19th century; he was the first district sanitary doctor in Katerynoslav. The scientist actively studied medical features of natural agents, namely Tymofiivska clay. He successfully worked at Sloviansk resort, was the editor of a local newspaper. V.T. Skrylnikov is an author of many works on balneotherapy.

  20. Environmental monitoring for tritium in tritium separation facility

    International Nuclear Information System (INIS)

    Varlam, Carmen; Stefanescu, Ioan; Steflea, Dumitru; Lazar, Roxana Elena

    2001-01-01

    The Cryogenic Pilot is an experimental project in the nuclear energy national research program, which has the aim of developing technologies for tritium and deuterium separation by cryogenic distillation. The experimental installation is located 15 km near the highest city of the area and 1 km near Olt River. An important chemical activity is developed in the area and chemical plants make up almost entire neighborhood of the Experimental Cryogenic Pilot. It is necessary to emphasize this aspect because the hall sewage system of the pilot is connected with the one of other three chemical plants from vicinity. This is the reason why we progressively established elements of an environmental monitoring program well in advance of tritium operation in order to determine baseline levels. The first step was the tritium level monitoring in environmental water and sewage from neighboring industrial activity. In this work, a low background liquid scintillation was used to determine tritium activity concentration according to ISO 9698/1998 standard. We measured drinking water, precipitation, river water, underground water and wastewater. The tritium level was between 10 TU and 27 TU what indicates that there is no source of tritium contamination in the neighborhood of Cryogenic Pilot. In order to determine baseline levels we decided to monitor monthly each location. In this paper it is presented a standard method used for tritium determination in water samples, the precautions needed to achieve reliable results and the evolution of tritium level in different location near the Experimental Pilot for Tritium and Deuterium Cryogenic Separation. (authors)

  1. Environmental monitoring for tritium at tritium separation facility

    International Nuclear Information System (INIS)

    Varlam, C.; Stefanescu, I.; Steflea, D.; Lazar, R.E.

    2001-01-01

    The Cryogenic Pilot is an experimental project in the nuclear energy national research program, which has the aim of developing technologies for tritium and deuterium separation by cryogenic distillation. The experimental installation is located 15 km near the highest city of the area and 1 km near Olt River. An important chemical activity is developed in the area and the Experimental Cryogenic Pilot's, almost the entire neighborhood are chemical plants. It is necessary to emphasize this aspect because the sewerage system is connected with the other three chemical plants from the neighborhood. This is the reason that we progressively established elements of an environmental monitoring program well in advance of tritium operation in order to determine baseline levels. The first step was the tritium level monitoring in environmental water and waste water of industrial activity from neighborhood. In this work, a low background liquid scintillation is used to determine tritium activity concentration according to ISO 9698/1998. We measured drinking water, precipitation, river water, underground water and waste water. The tritium level was between 10 TU and 27 TU that indicates there is no source of tritium contamination in the neighborhood of Cryogenic Pilot. In order to determine baseline levels we decide to monitories monthly each location. In this paper a standard method is presented which it is used for tritium determination in water sample, the precautions needed in order to achieve reliable results, and the evolution of tritium level in different location near the Experimental Pilot Tritium and Deuterium Cryogenic Separation.(author)

  2. Landfill Mining of Shredder Residues

    DEFF Research Database (Denmark)

    Hansen, Jette Bjerre; Hyks, Jiri; Shabeer Ahmed, Nassera

    In Denmark, shredder residues (SR) are classified as hazardous waste and until January 2012 the all SR were landfilled. It is estimated that more than 1.8 million tons of SR have been landfilled in mono cells. This paper describes investigations conducted at two Danish landfills. SR were excavated...... from the landfills and size fractionated in order to recover potential resources such as metal and energy and to reduce the amounts of SR left for re-landfilling. Based on the results it is estimated that 60-70% of the SR excavated could be recovered in terms of materials or energy. Only a fraction...... with particle size less than 5 mm needs to be re-landfilled at least until suitable techniques are available for recovery of materials with small particle sizes....

  3. Tritium concentration monitor

    International Nuclear Information System (INIS)

    Shono, Kosuke.

    1991-01-01

    A device for measuring the concentration of tritium in gaseous wastes in a power plant and a nuclear fuel reprocessing plant is reduced in the size and improved in performance. The device of the present invention pressurizes a sampling gas and cools it to a dew point. Water content in the sampling gas cooled to the dew point is condensated and recovered to a fine tube-like water content recovering container. The concentration of the recovered condensates is measured by a tritium density analyzer. With such procedures, since the specimen is pressurized, the dew point can be elevated. Accordingly, the size of the cooling device can be decreased, enabling to contribute to the reduction of the size of the entire device. Further, since the water content recovering device is formed as a fine tube, the area of contact between the specimen gas and the liquid condensated water can be reduced. Accordingly, evaporation of the liquid condensates can be prevented. (I.S.)

  4. Inventory of tritium concentration of waters in the Manche department; Inventaire des concentrations en tritium des eaux du Departement de La Manche

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2007-07-01

    For the inventory of water tritium concentration in the Manche department, it is the complementarity that animated the work opened during year 2001. To answer to a commune sensitivity such water quality, particularly drinking water at tap, the A.C.R.O. laboratory brought its know how to make and its technical means in the area of tritium analysis and the general council brought its know how to make and its logistics means in matter of sanitary control. This collaboration has allowed to supply an indication on the tritium content of the distribution waters of thirty of the most important cities of the department. Then, it allowed to inform on the radiological situation (in relation with the tritium presence) of coast waters and principal rivers waters. More than 160 controls have been realised between the months of march 2001 and february 2002. Only the tritium under the shape of tritiated water has been measured. The measures have been made by liquid scintillation according to the regulatory agreement. (N.C.)

  5. Phytoremediation of landfill leachate

    International Nuclear Information System (INIS)

    Jones, D.L.; Williamson, K.L.; Owen, A.G.

    2006-01-01

    Leachate emissions from landfill sites are of concern, primarily due to their toxic impact when released unchecked into the environment, and the potential for landfill sites to generate leachate for many hundreds of years following closure. Consequently, economically and environmentally sustainable disposal options are a priority in waste management. One potential option is the use of soil-plant based remediation schemes. In many cases, using either trees (including short rotation coppice) or grassland, phytoremediation of leachate has been successful. However, there are a significant number of examples where phytoremediation has failed. Typically, this failure can be ascribed to excessive leachate application and poor management due to a fundamental lack of understanding of the plant-soil system. On balance, with careful management, phytoremediation can be viewed as a sustainable, cost effective and environmentally sound option which is capable of treating 250 m 3 ha -1 yr -1 . However, these schemes have a requirement for large land areas and must be capable of responding to changes in leachate quality and quantity, problems of scheme establishment and maintenance, continual environmental monitoring and seasonal patterns of plant growth. Although the fundamental underpinning science is well understood, further work is required to create long-term predictive remediation models, full environmental impact assessments, a complete life-cycle analysis and economic analyses for a wide range of landfill scenarios

  6. Phytoremediation of landfill leachate.

    Science.gov (United States)

    Jones, D L; Williamson, K L; Owen, A G

    2006-01-01

    Leachate emissions from landfill sites are of concern, primarily due to their toxic impact when released unchecked into the environment, and the potential for landfill sites to generate leachate for many hundreds of years following closure. Consequently, economically and environmentally sustainable disposal options are a priority in waste management. One potential option is the use of soil-plant based remediation schemes. In many cases, using either trees (including short rotation coppice) or grassland, phytoremediation of leachate has been successful. However, there are a significant number of examples where phytoremediation has failed. Typically, this failure can be ascribed to excessive leachate application and poor management due to a fundamental lack of understanding of the plant-soil system. On balance, with careful management, phytoremediation can be viewed as a sustainable, cost effective and environmentally sound option which is capable of treating 250m(3)ha(-1)yr(-1). However, these schemes have a requirement for large land areas and must be capable of responding to changes in leachate quality and quantity, problems of scheme establishment and maintenance, continual environmental monitoring and seasonal patterns of plant growth. Although the fundamental underpinning science is well understood, further work is required to create long-term predictive remediation models, full environmental impact assessments, a complete life-cycle analysis and economic analyses for a wide range of landfill scenarios.

  7. Metabolism of organically bound tritium

    International Nuclear Information System (INIS)

    Travis, C.C.

    1984-01-01

    The classic methodology for estimating dose to man from environmental tritium ignores the fact that organically bound tritium in foodstuffs may be directly assimilated in the bound compartment of tissues without previous oxidation. We propose a four-compartment model consisting of a free body water compartment, two organic compartments, and a small, rapidly metabolizing compartment. The utility of this model lies in the ability to input organically bound tritium in foodstuffs directly into the organic compartments of the model. We found that organically bound tritium in foodstuffs can increase cumulative total body dose by a factor of 1.7 to 4.5 times the free body water dose alone, depending on the bound-to-loose ratio of tritium in the diet. Model predictions are compared with empirical measurements of tritium in human urine and tissue samples, and appear to be in close agreement. 10 references, 4 figures, 3 tables

  8. A prototype wearable tritium monitor

    International Nuclear Information System (INIS)

    Surette, R. A.; Dubeau, J.

    2008-01-01

    Sudden unexpected changes in tritium-in-air concentrations in workplace air can result in significant unplanned exposures. Although fixed area monitors are used to monitor areas where there is a potential for elevated tritium in air concentrations, they do not monitor personnel air space and may require some time for acute tritium releases to be detected. There is a need for a small instrument that will quickly alert staff of changing tritium hazards. A moderately sensitive tritium instrument that workers could wear would bring attention to any rise in tritium levels that were above predetermined limits and help in assessing the potential hazard therefore minimizing absorbed dose. Hand-held instruments currently available can be used but require the assistance of a fellow worker or restrict the user to using only one hand to perform some duties. (authors)

  9. Effects of tritium in elastomers

    International Nuclear Information System (INIS)

    Zapp, P.E.

    1982-01-01

    Elastomers are used as flange gaskets in the piping system of the Savannah River Plant tritium facilities. A number of elastomers is being examined to identify those compounds more radiation-resistant than the currently specified Buna-N rubber and to study the mechanism of tritium radiation damage. Radiation resistance is evaluated by compression set tests on specimens exposed to about 1 atm tritium for several months. Initial results show that ethylene-propylene rubber and three fluoroelastomers are superior to Buna-N. Off-gassing measurements and autoradiography show that retained surface absorption of tritium varies by more than an order of magnitude among the different elastomer compounds. Therefore, tritium solubility and/or exchange may have a role in addition to that of chemical structure in the damage process. Ongoing studies of the mechanism of radiation damage include: (1) tritium absorption kinetics, (2) mass spectroscopy of radiolytic products, and (3) infrared spectroscopy

  10. Tritium Storage Material

    International Nuclear Information System (INIS)

    Cowgill, Donald F.; Luo, Weifang; Smugeresky, John E.; Robinson, David B.; Fares, Stephen James; Ong, Markus D.; Arslan, Ilke; Tran, Kim L.; McCarty, Kevin F.; Sartor, George B.; Stewart, Kenneth D.; Clift, W. Miles

    2008-01-01

    Nano-structured palladium is examined as a tritium storage material with the potential to release beta-decay-generated helium at the generation rate, thereby mitigating the aging effects produced by enlarging He bubbles. Helium retention in proposed structures is modeled by adapting the Sandia Bubble Evolution model to nano-dimensional material. The model shows that even with ligament dimensions of 6-12 nm, elevated temperatures will be required for low He retention. Two nanomaterial synthesis pathways were explored: de-alloying and surfactant templating. For de-alloying, PdAg alloys with piranha etchants appeared likely to generate the desired morphology with some additional development effort. Nano-structured 50 nm Pd particles with 2-3 nm pores were successfully produced by surfactant templating using PdCl salts and an oligo(ethylene oxide) hexadecyl ether surfactant. Tests were performed on this material to investigate processes for removing residual pore fluids and to examine the thermal stability of pores. A tritium manifold was fabricated to measure the early He release behavior of this and Pd black material and is installed in the Tritium Science Station glove box at LLNL. Pressure-composition isotherms and particle sizes of a commercial Pd black were measured.

  11. Toxicity of tritium

    International Nuclear Information System (INIS)

    Dobson, R.L.

    1979-01-01

    Among radionuclides of importance in atomic energy, 3 H has relatively low toxicity. The main health and environmental worry is the possibility that significant biological effects may follow from protracted exposure to low concentrations in water. To examine this possible hazard and measure toxicity at low tritium concentrations, chronic exposure studies were done on mice and monkeys. During vulnerable developmental periods animals were exposed to 3 HOH, and mice were exposed also to 60 Co gamma irradiation and energy-related chemical agents. The biological endpoint measured was the irreversible loss of female germ cells. Effects from tritium were observed at surprisingly low concentrations where 3 H was found more damaging than previously thought. Comparisons between tritium and gamma radiation showed the relative biological effectiveness (RBE) to be greater than 1 and to reach approximately 3 at very low exposures. For perspective, other comparisons were made: between radiation and chemical agents, which revealed parallels in action on germ cells, and between pre- and postnatal exposure, which warn of possible special hazard to the fetus from both classes of energy-related byproducts

  12. Biological effects of tritium

    International Nuclear Information System (INIS)

    Nieto, M.

    1985-01-01

    The aim of this project is to study the thermal effects on proliferation activity in the intestinal epithelium of the goldfish acclimated at different temperatures (stationary state). The cell division occurs only at certain phases of the circadian cycle when the proliferative activity is synchronized or trained by an environmental factor such as light-dark cycle. Another aspect of the project is the study of the biological effects, non-stochastic, on cell kinetics in animals chronically exposed to low dose rates or tritium and gamma rays from 60 CO, used as a standard radiation. The influence on the accumulated dose per cell and cycle cell in function of the duration of the cell cycle at different acclimation temperatures should be considered. To calculate the risk of tritium contamination from nuclear power plants (radiation exposure), the organic tissue-bond is of decisive importance due to the long turnover of the organic tissue-bond in organisms favouring transport of tritium to other organisms of the ecosystem and to man. (author)

  13. Tritium removal and retention device

    International Nuclear Information System (INIS)

    Boyle, R.F.; Durigon, D.D.

    1980-01-01

    A device is provided for removing and retaining tritium from a gaseous medium, and also a method of manufacturing the device. The device, consists of an inner core of zirconium alloy, preferably Zircaloy-4, and an outer adherent layer of nickel which acts as a selective and protective window for passage of tritium. The tritium then reacts with or is absorbed by the zirconium alloy, and is retained until such time as it is desirable to remove it during reprocessing. (auth)

  14. An overview of tritium production

    International Nuclear Information System (INIS)

    He Kaihui; Huang Jinghua; Feng Kaiming

    2002-01-01

    The characteristics of three types of proposed tritium production facilities, fissile type, accelerator production tritium (APT), and fusion type, are presented. The fissile reactors, especially commercial light water reactor, use comparatively mature technology and are designed to meet current safety and environmental guidelines. Conversely, APT shows many advantages except its rather high cost, while fusion reactors appear to offer improved safety and environmental impact, in particular, tritium production based on the fusion-based neutron source. However, its cost keeps unknown

  15. Tritium safety issues for TFCX

    International Nuclear Information System (INIS)

    Reilly, H.J.; Piet, S.J.; Merrill, B.J.

    1985-01-01

    Estimated tritium releases from the Tokamak Fusion Core Experiment are compared to the expected limits. A reaction kinetics model is described that predicts the conversion of tritium to the oxide form in free space. An analysis of the required capacity of the Emergency Tritium Cleanup System is also presented. The conclusions of this work are expected to be applicable to other experimental fusion devices that are now being considered

  16. Tritium behavior in ITER beryllium

    International Nuclear Information System (INIS)

    Longhurst, G.R.

    1990-10-01

    The beryllium neutron multiplier in the ITER breeding blanket will generate tritium through transmutations. That tritium constitutes a safety hazard. Experiments evaluating tritium storage and release mechanisms have shown that most of the tritium comes out in a burst during thermal ramping. A small fraction of retained tritium is released by thermally activated processes. Analysis of recent experimental data shows that most of the tritium resides in helium bubbles. That tritium is released when the bubbles undergo swelling sufficient to develop porosity that connects with the surface. That appears to occur when swelling reaches about 10--15%. Other tritium appears to be stored chemically at oxide inclusions, probably as Be(OT) 2 . That component is released by thermal activation. There is considerable variation in published values for tritium diffusion through the beryllium and solubility in it. Data from experiments using highly irradiated beryllium from the Idaho National Engineering Laboratory showed diffusivity generally in line with the most commonly accepted values for fully dense material. Lower density material, planned for use in the ITER blanket may have very short diffusion times because of the open structure. The beryllium multiplier of the ITER breeding blanket was analyzed for tritium release characteristics using temperature and helium production figures at the midplane generated in support of the ITER Summer Workshop, 1990 in Garching. Ordinary operation, either in Physics or Technology phases, should not result in the release of tritium trapped in the helium bubbles. Temperature excursions above 600 degree C result in large-scale release of that tritium. 29 refs., 10 figs., 3 tabs

  17. Tritium inventory tracking and management

    International Nuclear Information System (INIS)

    Eichenberg, T.W.; Klein, A.C.

    1990-01-01

    This investigation has identified a number of useful applications of the analysis of the tracking and management of the tritium inventory in the various subsystems and components in a DT fusion reactor system. Due to the large amounts of tritium that will need to be circulated within such a plant, and the hazards of dealing with the tritium an electricity generating utility may not wish to also be in the tritium production and supply business on a full time basis. Possible scenarios for system operation have been presented, including options with zero net increase in tritium inventory, annual maintenance and blanket replacement, rapid increases in tritium creation for the production of additional tritium supplies for new plant startup, and failures in certain system components. It has been found that the value of the tritium breeding ratio required to stabilize the storage inventory depends strongly on the value and nature of other system characteristics. The real operation of a DT fusion reactor power plant will include maintenance and blanket replacement shutdowns which will affect the operation of the tritium handling system. It was also found that only modest increases in the tritium breeding ratio are needed in order to produce sufficient extra tritium for the startup of new reactors in less than two years. Thus, the continuous operation of a reactor system with a high tritium breeding ratio in order to have sufficient supplies for other plants is not necessary. Lastly, the overall operation and reliability of the power plant is greatly affected by failures in the fuel cleanup and plasma exhaust systems

  18. Tritium monitor and collection system

    Science.gov (United States)

    Bourne, G.L.; Meikrantz, D.H.; Ely, W.E.; Tuggle, D.G.; Grafwallner, E.G.; Wickham, K.L.; Maltrud, H.R.; Baker, J.D.

    1992-01-14

    This system measures tritium on-line and collects tritium from a flowing inert gas stream. It separates the tritium from other non-hydrogen isotope contaminating gases, whether radioactive or not. The collecting portion of the system is constructed of various zirconium alloys called getters. These alloys adsorb tritium in any of its forms at one temperature and at a higher temperature release it as a gas. The system consists of four on-line getters and heaters, two ion chamber detectors, two collection getters, and two guard getters. When the incoming gas stream is valved through the on-line getters, 99.9% of it is adsorbed and the remainder continues to the guard getter where traces of tritium not collected earlier are adsorbed. The inert gas stream then exits the system to the decay chamber. Once the on-line getter has collected tritium for a predetermined time, it is valved off and the next on-line getter is valved on. Simultaneously, the first getter is heated and a pure helium purge is employed to carry the tritium from the getter. The tritium loaded gas stream is then routed through an ion chamber which measures the tritium activity. The ion chamber effluent passes through a collection getter that readsorbs the tritium and is removable from the system once it is loaded and is then replaced with a clean getter. Prior to removal of the collection getter, the system switches to a parallel collection getter. The effluent from the collection getter passes through a guard getter to remove traces of tritium prior to exiting the system. The tritium loaded collection getter, once removed, is analyzed by liquid scintillation techniques. The entire sequence is under computer control except for the removal and analysis of the collection getter. 7 figs.

  19. Tritium accounting for PHWR plants

    International Nuclear Information System (INIS)

    Nair, P.S.; Duraisamy, S.

    2012-01-01

    Tritium, the radioactive isotope of hydrogen, is produced as a byproduct of the nuclear reactions in the nuclear power plants. In a Pressurized Heavy Water Reactor (PHWR) tritium activity is produced in the Heat Transport and Moderator systems due to neutron activation of deuterium in heavy water used in these systems. Tritium activity build up occurs in some of the water systems in the PHWR plants through pick up from the plant atmosphere, inadvertent D 2 O ingress from other systems or transfer during processes. The tritium, produced by the neutron induced reactions in different systems in the reactor undergoes multiple processes such as escape through leaks, storage, transfer to external locations, decay, evaporation and diffusion and discharge though waste streams. Change of location of tritium inventory takes place during intentional transfer of heavy water, both reactor grade and downgraded, from one system to another. Tritium accounting is the application of accounting techniques to maintain knowledge of the tritium inventory present in different systems of a facility and to construct activity balances to detect any discrepancy in the physical inventories. It involves identification of all the tritium hold ups, transfers and storages as well as measurement of tritium inventories in various compartments, decay corrections, environmental release estimations and evaluation of activity generation during the accounting period. This paper describes a methodology for creating tritium inventory balance based on periodic physical inventory taking, tritium build up, decay and release estimations. Tritium accounting in the PHWR plants can prove to be an effective regulatory tool to monitor its loss as well as unaccounted release to the environment. (author)

  20. Mixed Waste Landfill Integrated Demonstration

    International Nuclear Information System (INIS)

    1994-02-01

    The mission of the Mixed Waste Landfill Integrated Demonstration (MWLID) is to demonstrate, in contaminated sites, new technologies for clean-up of chemical and mixed waste landfills that are representative of many sites throughout the DOE Complex and the nation. When implemented, these new technologies promise to characterize and remediate the contaminated landfill sites across the country that resulted from past waste disposal practices. Characterization and remediation technologies are aimed at making clean-up less expensive, safer, and more effective than current techniques. This will be done by emphasizing in-situ technologies. Most important, MWLID's success will be shared with other Federal, state, and local governments, and private companies that face the important task of waste site remediation. MWLID will demonstrate technologies at two existing landfills. Sandia National Laboratories' Chemical Waste Landfill received hazardous (chemical) waste from the Laboratory from 1962 to 1985, and the Mixed-Waste Landfill received hazardous and radioactive wastes (mixed wastes) over a twenty-nine year period (1959-1988) from various Sandia nuclear research programs. Both landfills are now closed. Originally, however, the sites were selected because of Albuquerque's and climate and the thick layer of alluvial deposits that overlay groundwater approximately 480 feet below the landfills. This thick layer of ''dry'' soils, gravel, and clays promised to be a natural barrier between the landfills and groundwater

  1. [Sanitary education of workers of bakeries and pastry enterprises].

    Science.gov (United States)

    Krasil'shchikov, M I; Nemets, M G; Novikova, O V; Gavrilenko, E V; Osipova, E M; Osinova, T I

    2000-01-01

    The paper presents experience with sanitary education of workers from food industrial enterprises. The study revealed a number of disadvantages of the methodological aspect of sanitary education of these workers. A sanitary education programme has been worked out for workers engaged in food and food processing industries (production of bread, baked goods, and confectionery) and approved by the State Sanitary and Epidemiological Surveillance Department), Ministry of Health of Russia on March 1999.

  2. Tritium-assisted fusion breeders

    International Nuclear Information System (INIS)

    Greenspan, E.; Miley, G.H.

    1983-08-01

    This report undertakes a preliminary assessment of the prospects of tritium-assisted D-D fuel cycle fusion breeders. Two well documented fusion power reactor designs - the STARFIRE (D-T fuel cycle) and the WILDCAT (Cat-D fuel cycle) tokamaks - are converted into fusion breeders by replacing the fusion electric blankets with 233 U producing fission suppressed blankets; changing the Cat-D fuel cycle mode of operation by one of the several tritium-assisted D-D-based modes of operation considered; adjusting the reactor power level; and modifying the resulting plant cost to account for the design changes. Three sources of tritium are considered for assisting the D-D fuel cycle: tritium produced in the blankets from lithium or from 3 He and tritium produced in the client fission reactors. The D-D-based fusion breeders using tritium assistance are found to be the most promising economically, especially the Tritium Catalyzed Deuterium mode of operation in which the 3 He exhausted from the plasma is converted, by neutron capture in the blanket, into tritium which is in turn fed back to the plasma. The number of fission reactors of equal thermal power supported by Tritium Catalyzed Deuterium fusion breeders is about 50% higher than that of D-T fusion breeders, and the profitability is found to be slightly lower than that of the D-T fusion breeders

  3. TFTR tritium operations lessons learned

    International Nuclear Information System (INIS)

    Gentile, C.A.; Raftopoulos, S.; LaMarche, P.

    1996-01-01

    The Tokamak Fusion Test Reactor which is the progenitor for full D-T operating tokamaks has successfully processed > 81 grams of tritium in a safe and efficient fashion. Many of the fundamental operational techniques associated with the safe movement of tritium through the TFTR facility were developed over the course of many years of DOE tritium facilities (LANL, LLNL, SRS, Mound). In the mid 1980's The Tritium Systems Test Assembly (TSTA) at LANL began reporting operational techniques for the safe handling of tritium, and became a major conduit for the transfer of safe tritium handling technology from DOE weapons laboratories to non-weapon facilities. TFTR has built on many of the TSTA operational techniques and has had the opportunity of performing and enhancing these techniques at America's first operational D-T fusion reactor. This paper will discuss negative pressure employing 'elephant trunks' in the control and mitigation of tritium contamination at the TFTR facility, and the interaction between contaminated line operations and Δ pressure control. In addition the strategy employed in managing the movement of tritium through TFTR while maintaining an active tritium inventory of < 50,000 Ci will be discussed. 5 refs

  4. The Health Risk Assessment of Pb and Cr leachated from fly ash monolith landfill

    International Nuclear Information System (INIS)

    Hung, Ming-Lung; Wu, Sheng-Yao; Chen, Yen-Chuan; Shih, Hsiu-Ching; Yu, Yue-Hwa; Ma, Hwong-wen

    2009-01-01

    As of 2004, nearly two hundred thousand tons of fly ash monoliths are created each year in Taiwan to confine heavy metals for reducing the leaching quantity by precipitation. However, due to abnormal monolith fracture, poorly liner quality or exceeding usage over designed landfill capacity, serious groundwater pollution of the landfills has been reported. This research focuses on Pb and Cr leaching from monolithic landfill to assess the risk of groundwater pollution in the vicinity. The methodology combines water budget simulations using HELP model with fate and risk simulations using MMSOILS model for 5 kinds of landfill structures and 2 types of leaching models, and calculates the risk distribution over 400 grids in the down gradient direction of groundwater. The results demonstrated that the worst liner quality will cause the largest risk and the most significant exposure pathway is groundwater intake, which accounted for 98% of the total risk. Comparing Pb and Cr concentrations in the groundwater with the drinking water standards, only 14.25% of the total grids are found to be under 0.05 mg/L of Pb, and over 96.5% of the total grids are in the safety range of Cr. It indicates that Pb leaching from fly ash monolithic landfills may cause serious health risks. Without consideration of the parameters uncertainty, the cancer and noncancer risk of Pb with the sanitary landfill method was 4.23E-07 and 0.63, respectively, both under acceptable levels. However, by considering the parameters uncertainty, the non-carcinogenic risk of Pb became 1.43, exceeding the acceptable level. Only under the sealed landfill method was the hazard quotient below 1. It is important to use at least the sealed landfill for fly ash monoliths containing lead to effectively reduce health risks.

  5. 21 CFR 129.35 - Sanitary facilities.

    Science.gov (United States)

    2010-04-01

    ... HUMAN CONSUMPTION PROCESSING AND BOTTLING OF BOTTLED DRINKING WATER Buildings and Facilities § 129.35... is not considered water of a safe, sanitary quality as required for use in bottled water by paragraph... comply with bottled water quality standards (§ 165.110(b) of this chapter) and section 402(a)(1) and (a...

  6. [Sanitary-hygienic assessment of microbial biofertilizer].

    Science.gov (United States)

    Arkhipchenko, N A; Akhtemava, G A; Lebedeva, T V; Voronina, A A; Makhan'kova, T I; Pavlova, M M; Shteĭntsaĭg, T A

    1991-10-01

    Biological treatment of sewage from pig-breeding complexes allowed to produce microbial biomass and primary sediments. The mixture of these components (1:1) after rendering harmless and drying out become the high effective biofertilizer. The results of chronic experiment on sanitary status of soil (microbial and helminthological indexes) under this biofertilizer usage are discussed, and the harmlessness of it is demonstrated.

  7. 21 CFR 1210.14 - Sanitary inspection of plants.

    Science.gov (United States)

    2010-04-01

    ... 21 Food and Drugs 8 2010-04-01 2010-04-01 false Sanitary inspection of plants. 1210.14 Section... FEDERAL IMPORT MILK ACT Inspection and Testing § 1210.14 Sanitary inspection of plants. The sanitary conditions of any plant handling milk or cream any part of which is to be shipped or transported into the...

  8. 21 CFR 1210.11 - Sanitary inspection of dairy farms.

    Science.gov (United States)

    2010-04-01

    ... 21 Food and Drugs 8 2010-04-01 2010-04-01 false Sanitary inspection of dairy farms. 1210.11... UNDER THE FEDERAL IMPORT MILK ACT Inspection and Testing § 1210.11 Sanitary inspection of dairy farms. The sanitary conditions of any dairy farm producing milk or cream to be shipped or transported into...

  9. 25 CFR 700.55 - Decent, safe, and sanitary dwelling.

    Science.gov (United States)

    2010-04-01

    ... 25 Indians 2 2010-04-01 2010-04-01 false Decent, safe, and sanitary dwelling. 700.55 Section 700... PROCEDURES General Policies and Instructions Definitions § 700.55 Decent, safe, and sanitary dwelling. (a) General. The term decent, safe, and sanitary dwelling means a dwelling which— (1) Meets applicable federal...

  10. Overview of tritium fast-fission yields

    International Nuclear Information System (INIS)

    Tanner, J.E.

    1981-03-01

    Tritium production rates are very important to the development of fast reactors because tritium may be produced at a greater rate in fast reactors than in light water reactors. This report focuses on tritium production and does not evaluate the transport and eventual release of the tritium in a fast reactor system. However, if an order-of-magnitude increase in fast fission yields for tritium is confirmed, fission will become the dominant production source of tritium in fast reactors

  11. Technology developments for improved tritium management

    International Nuclear Information System (INIS)

    Miller, J.M.; Spagnolo, D.A.

    1994-06-01

    Tritium technology developments have been an integral part of the advancement of CANDU reactor technology. An understanding of tritium behaviour within the heavy-water systems has led to improvements in tritium recovery processes, tritium measurement techniques and overall tritium control. Detritiation technology has been put in place as part of heavy water and tritium management practices. The advances made in these technologies are summarized. (author). 20 refs., 5 figs

  12. Landfill Gas Energy Project Data and Landfill Technical Data

    Science.gov (United States)

    This page provides data from the LMOP Database for U.S. landfills and LFG energy projects in Excel files, a map of project and candidate landfill counts by state, project profiles for a select group of projects, and information about Project Expo sites.

  13. The Importance of Landfill Gas Policy Measures

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2009-07-01

    The purpose of this document is to identify and examine global policies, measures, and incentives that appear to be stimulating LFG use. As certain countries have made great advances in LFGE development through effective policies, the intention of this report is to use information from the IEA's Global Renewable Energy and Energy Efficiency Measures and Policies Databases to identify and discuss policies. By consolidating this information and categorising it according to policy type, the attributes that are most appealing or applicable to the circumstances of a particular country or area -- technology demonstration, financial incentives, awareness campaigns, etc. -- are more easily identified. The report begins with background information on LFG and sanitary landfill practices, including a discussion of regional disparities, followed by a description of LFG mitigation technologies. Barriers to LFGE projects are then outlined. An explanation of the importance and effectiveness of policy measures leads into a discussion of types and examples of measures that are being used to overcome these barriers and encourage LFGE development. The report concludes with lessons learned, recommendations for further study, and resources where more information can be found.

  14. Tritium sorption by cement and subsequent release

    International Nuclear Information System (INIS)

    Ono, F.; Tanaka, S.; Yamawaki, M.

    1994-01-01

    In a fusion reactor or tritium handling facilities, contamination of concrete by tritium and subsequent release from it to the reactor or experimental rooms is a matter of problem for safety control of tritium and management of operational environment. In order to evaluate these tritium behavior, interaction of tritiated water with concrete or cement should be clarified. In the present study, HTO sorption and subsequent release from cement were studied by combining various experimental methods. From the basic studies on tritium-cement interactions, it has become possible to evaluate tritium uptake by cement or concrete and subsequent tritium release behavior as well as tritium removing methods from them

  15. Landfill gas management in Canada

    International Nuclear Information System (INIS)

    David, A.

    1997-01-01

    Landfill gas produced from solid waste landfills is one of the most significant sources of anthropogenic methane in Canada. Methane, a potent greenhouse gas, is 24.5 times more powerful than carbon dioxide by weight in terms of global climate change. Landfill gas recovery plays an important role in Canada's commitment to stabilize greenhouse gas emissions at 1990 levels by the year 2000 under the United Nations Framework Convention on Climate Change. Landfill gas is a potentially harmful emission that can be converted into a reliable environmentally-sustainable energy source used to generate electricity, fuel industries and heat buildings. The recovery and utilization of landfill gas is a win-win situation which makes good sense from local, regional and global perspectives. It provides the benefits of (1) reducing the release of greenhouse gases that contribute to global warming; (2) limiting odors; (3) controlling damage to vegetation; (4) reducing risks from explosions, fires and asphyxiation; (5) converting a harmful emission into a reliable energy source; and (6) creating a potential source of revenue and profit. Canadian landfills generate about 1 million tons of methane every year; the equivalent energy of 9 million barrels of oil (eight oil super tankers), or enough energy to meet the annual heating needs of more than half a million Canadian homes. Currently, twenty-seven facilities recover and combust roughly 25% of the methane generated by Canadian landfills producing about 3.2 PJ (10 15 Joules) of energy including 80 MW of electricity and direct fuel for nearby facilities (e.g., cement plants, gypsum board manufacturers, recycling facilities, greenhouses). This paper reviews landfill gas characteristics; environmental, health and safety impacts; landfill gas management in Canada; the costs of landfill gas recovery and utilization systems; and on-going projects on landfill gas utilization and flaring

  16. JET experiments with tritium and deuterium–tritium mixtures

    NARCIS (Netherlands)

    Horton, L.; Batistoni, P.; Boyer, H.; Challis, C.; Ciric, D.; Donne, A. J. H.; Eriksson, L. G.; Garcia, J.; Garzotti, L.; Gee, S.; Hobirk, J.; Joffrin, E.; Jones, T.; King, D. B.; Knipe, S.; Litaudon, X.; Matthews, G. F.; Monakhov, I.; Murari, A.; Nunes, I.; Riccardo, V.; Sips, A. C. C.; Warren, R.; Weisen, H.; Zastrow, K. D.

    2016-01-01

    Extensive preparations are now underway for an experiment in the Joint European Torus (JET) using tritium and deuterium–tritium mixtures. The goals of this experiment are described as well as the progress that has been made in developing plasma operational scenarios and physics reference pulses for

  17. Tritium contaminated waste management at the tritium systems test assembly

    International Nuclear Information System (INIS)

    Jalbert, R.A.; Carlson, R.V.

    1987-01-01

    The Tritium Systems Test Assembly (TSTA) at Los Alamos continues to move toward full operation of an integrated, full-sized, computer-controlled fusion fuel processing loop. Concurrent nonloop experiments further the development of advanced tritium technologies and handling methods. Since tritium operations began in June 1984, tritium contaminated wastes have been produced at TSTA that are roughly typical in kind and amount of those to be produced by tritium fueling operations at fusion reactors. Methods of managing these wastes are described, including information on some methods of decontamination so that equipment can be reused. Data are given on the kinds and amounts of wastes and the general level of contamination. Also included are data on environmental emissions and doses to personnel that have resulted from TSTA operations. Particular problems in waste managements are discussed

  18. Landfill Construction and Capacity Expansion

    NARCIS (Netherlands)

    Andre, F.J.; Cerda, E.

    2003-01-01

    We study the optimal capacity and lifetime of landfills taking into account their sequential nature.Such an optimal capacity is characterized by the so-called Optimal Capacity Condition.Particular versions of this condition are obtained for two alternative settings: first, if all the landfills are

  19. Tritium transport and control in the FED

    International Nuclear Information System (INIS)

    Rogers, M.L.

    1981-01-01

    The tritium systems for the FED have three primary purposes. The first is to provide tritium and deuterium fuel for the reactor. This fuel can be new tritium or deuterium delivered to the plant site, or recycled DT from the reactor that must be processed before it can be recycled. The second purpose of the FED tritium systems is to provide state-of-the-art tritium handling to limit worker radiation exposure and to minimize tritium losses to the environment. The final major objective of the FED tritium systems is to provide an integrated system test of the tritium handling technology necessary to support the fusion reactor program. Every effort is being made to incorporate available information from the Tritium System Test Assembly (TSTA) at Los Alamos National Laboratory, the Tokamak Fusion Test Reactor (TFTR) tritium systems, and the tritium handling information generated within DOE for the past 20 years

  20. Ontario Hydro diversifies into tritium

    International Nuclear Information System (INIS)

    Anon.

    1983-01-01

    A report is given on a plant which is to be built at the Darlington Candu reactor site in Canada for the extraction of tritium from heavy water. As tritium is used as a fuel in fusion research the market for it is expected to grow. The design of the system is outlined with the help of a flow diagram. (U.K.)

  1. Tritium containment in fusion facilities

    International Nuclear Information System (INIS)

    Anderson, J.L.

    1978-01-01

    The key environmental control systems that have been identified and are being developed are listed. A brief description of each of the following systems is given: primary process materials, permeation barriers, secondary containment, tritium waste treatment, emergency tritium cleanup, maintenance procedures, and tertiary containment

  2. Tritium accountancy in fusion systems

    Energy Technology Data Exchange (ETDEWEB)

    Klein, J.E.; Clark, E.A.; Harvel, C.D.; Farmer, D.A.; Tovo, L.L.; Poore, A.S. [Savannah River National Laboratory, Aiken, SC (United States); Moore, M.L. [Savannah River Nuclear Solutions, Aiken, SC (United States)

    2015-03-15

    The US Department of Energy (DOE) has clearly defined requirements for nuclear material control and accountability (MCA) of tritium whereas the International Atomic Energy Agency (IAEA) does not since tritium is not a fissile material. MCA requirements are expected for tritium fusion machines and will be dictated by the host country or regulatory body where the machine is operated. Material Balance Areas (MBA) are defined to aid in the tracking and reporting of nuclear material movements and inventories. Material sub-accounts (MSA) are established along with key measurement points (KMP) to further subdivide a MBA to localize and minimize uncertainties in the inventory difference (ID) calculations for tritium accountancy. Fusion systems try to minimize tritium inventory which may require continuous movement of material through the MSA. The ability of making meaningful measurements of these material transfers is described in terms of establishing the MSA structure to perform and reconcile ID calculations. For fusion machines, changes to the traditional ID equation will be discussed which includes breeding, burn-up, and retention of tritium in the fusion device. The concept of 'net' tritium quantities consumed or lost in fusion devices is described in terms of inventory taking strategies and how it is used to track the accumulation of tritium in components or fusion machines. (authors)

  3. The tritium operations experience on TFTR

    International Nuclear Information System (INIS)

    Halle, A. von; Anderson, J.L.; Gentile, C.; Grisham, L.; Hosea, J.; Kamperschroer, J.; LaMarche, P.; Oldaker, M.; Nagy, A.; Raftopoulos, S.; Stevenson, T.

    1995-01-01

    The Tokamak Fusion Test Reactor (TFTR) tritium gas system is administratively limited to 5 grams of tritium and provides the feedstock gas for the neutral beam and torus injection systems. Tritium operations on TFTR began with leak checking of gas handling systems, qualification of the gas injection systems, and high power plasma operations using trace amounts of tritium in deuterium feedstock gas. Full tritium operation commenced with four highly diagnosed neutral beam pulses into a beamline calorimeter to verify planned tritium beam operating routines and to demonstrate the deuterium to tritium beam isotope exchange. Since that time, TFTR has successfully operated each of the twelve neutral beam ion sources in tritium during hundreds of tritium beam pulses and torus gas injections. This paper describes the TFTR tritium gas handling systems and TFTR tritium operations of the gas injection systems and the neutral beam ion sources. Tritium accounting and accountability is discussed, including tritium retention issues of the torus limiters and beam impinged surfaces of the beamline components. Also included is tritium beam velocity analysis that compares the neutral beam extracted ion species composition for deuterium and tritium and that determines the extent of beam isotope exchange on subsequent deuterium and tritium beam pulses. The required modifications to TFTR operating routines to meet the U.S. Department of Energy regulations for a low hazard nuclear facility and the problems encountered during initial tritium operations are described. (orig.)

  4. The tritium operations experience on TFTR

    International Nuclear Information System (INIS)

    von Halle, A.; Gentile, C.

    1994-01-01

    The Tokamak Fusion Test Reactor (TFTR) tritium gas system is administratively limited to 5 grains of tritium and provides the feedstock gas for the neutral beam and torus injection systems. Tritium operations on TFTR began with leak checking of gas handling systems, qualification of the gas injection systems, and high power plasma operations using using trace amounts of tritium in deuterium feedstock gas. Full tritium operation commenced with four highly diagnosed neutral beam pulses into a beamline calorimeter to verify planned tritium beam operating routines and to demonstrate the deuterium to tritium beam isotope exchange. Since that time, TFTR has successfully operated each of the twelve neutral beam ion sources in tritium during hundreds of tritium beam pulses and torus gas injections. This paper describes- the TFTR tritium gas handling systems and TFTR tritium operations of the gas injection systems and the neutral beam ion sources. Tritium accounting and accountability is discussed, including tritium retention issues of the torus limiters and beam impinged surfaces of the beamline components. Also included is tritium beam velocity analysis that compares the neutral beam extracted ion species composition for deuterium and tritium and that determines the extent of beam isotope exchange on subsequent deuterium and tritium beam pulses. The required modifications to TFTR operating routines to meet the US Department of Energy regulations for a low hazard nuclear facility and the problems encountered during initial tritium operations are described

  5. Organic halogens in landfill leachates

    DEFF Research Database (Denmark)

    Grøn, C.; Christensen, J. B.; Jensen, Dorthe Lærke

    2000-01-01

    Using a group parameter, total organic halogens (TOX), high TOX concentrations were found in leachates and leachate contaminated groundwaters at two Danish mixed sanitary and hazardous waste sites. With commonly used screening procedures for organic contaminants, the individual halogenated organi...

  6. Tritium in the food chain

    International Nuclear Information System (INIS)

    Koenig, L.A.

    1988-01-01

    Tritium is a hydrogen isotope taking part in the global hydrogen cycle as well as in all metabolic processes. The resultant problems with respect to the food chain are summarized briefly with emphasis on 'organically bound tritium'. However, only a small number of the numerous publications on this topic can be taken into consideration. Publications describing experiments under defined conditions are reported, thus allowing a semiempirical interpretation to be made. Tritium activity measurements of food grown in the vicinity of the Karlsruhe Nuclear Research Center have been carried out. A list of the results is given. A dose assessment is performed under simplifying assumptions. Even when the organically bound tritium is taken into account, a radiation exposure of less than 1% of that of K-40 is obtained under these conditions. To avoid misinterpretation, the specific activity (Bq H-3/g H) of water-bound and organically bound tritium has to be considered separately. (orig.) [de

  7. Tritium metabolism in rat tissues

    International Nuclear Information System (INIS)

    Takeda, H.

    1982-01-01

    As part of a series of studies designed to evaluate the relative radiotoxicity of various tritiated compounds, metabolism of tritium in rat tissues was studied after administration of tritiated water, leucine, thymidine, and glucose. The distribution and retention of tritium varied widely, depending on the chemical compound administered. Tritium introduced as tritiated water behaved essentially as body water and became uniformly distributed among the tissues. However, tritium administered as organic compounds resulted in relatively high incorporation into tissue constituents other than water, and its distribution differed among the various tissues. Moreover, the excretion rate of tritium from tissues was slower for tritiated organic compounds than for tritiated water. Administrationof tritiated organic compounds results in higher radiation doses to the tissues than does administration of tritiated water. Among the tritiated compounds examined, for equal radioactivity administered, leucine gave the highest radiation dose, followed in turn by thymidine, glucose, and water. (author)

  8. Tritium behaviour in higher plants

    International Nuclear Information System (INIS)

    Guenot, J.

    1984-05-01

    Vine grapes and potato seedlings have been exposed in situ to tritiated water vapor and 14 C labeled carbon dioxide. Leaves sampling was done during and after the exposition. Measurements allowed to distinguish the three forms of tritium in leaves, i.e. tissue free water tritium (TFWT) and organically bound tritium (OBT), in exchangeable position or not. The results lead to a description of the dynamical behaviour of tritium between these three compartments. It has been shown that 20% of organically bound hydrogen is readily exchangeable thus being in permanent isotopic equilibium with tissue free water. Moreover, the activity of nonexchangeable OBT appears to be strongly related to the organic 14 C, which shows that photosynthesis is responsible of tritium incorporation in organic nonexchangeable position, and occurs with a 20% discrimination in favor of protium. In contrast with the other two compartments, this fixation is almost irreversible, which is a fact of importance from a radiological point of view [fr

  9. Tritium practices past and present

    International Nuclear Information System (INIS)

    Gede, V.P.; Gildea, P.D.

    1980-01-01

    History of the production and use of tritium, as well as handling techniques, are reviewed. Handling techniques first used at Lawrence Livermore National Laboratory made use of glass vacuum systems and relatively crude ion chambers for monitoring airborne activity. The first use of inert atmosphere glove boxes demonstrated that uptake through the skin could be a serious personnel exposure problem. Growing environmental concerns in the early 1970's resulted in the implementation by the Atomic Energy Commission of a new criteria to limit atmospheric tritium releases to levels as low as practicable. An important result of the new criteria was the development of containment and recovery systems to capture tritium rather than vent it to the atmosphere. The Sandia National Laboratories, Livermore, Tritium Research Laboratory containment and decontamination systems are presented as a typical example of this technology. The application of computers to control systems is expected to provide the greatest potential for change in future tritium handling practices

  10. Alternative landfill cover technology demonstration at Kaneohe Marine Corps Base Hawaii

    International Nuclear Information System (INIS)

    Karr, L.A.; Harre, B.; Hakonson, T.E.

    1997-01-01

    Surface covers to control water infiltration to waste buried in landfills will be the remediation alternative of choice for most hazardous and sanitary landfills operated by the Department of Defense. Although surface covers are the least expensive method of remediation for landfills, they can still be expensive solutions. Conventional wisdom suggests that landfill capping technology is well developed as evidenced by the availability of EPA guidance for designing and constructing what has become known as the open-quotes RCRA Capclose quotes. In practice, however, very little testing of the RCRA cap, or any other design, has been done to evaluate how effective these designs are in limiting infiltration of water into waste. This paper describes a low cost alternative to the open-quotes RCRA Capclose quotes that is being evaluated at Marine Corps Base Hawaii (MCBH) Kaneohe Bay. This study uses an innovative, simple and inexpensive concept to manipulate the fate of water falling on a landfill. The infiltration of water through the cap will be controlled by combining the evaporative forces of vegetation to remove soil water, with engineered structures that limit infiltration of precipitation into the soil. This approach relies on diverting enough of the annual precipitation to runoff, so that the water that does infiltrate into the soil can easily be removed by evapotranspiration

  11. [Sanitary control of food in Mexico city].

    Science.gov (United States)

    Sartí-Gutiérrez, E J; Parrilla-Cerrillo, C; Vázquez-Barojas, S; Kawashima-Hashimoto, L; Farías-Rodríguez, A; García-Juárez, C

    1989-01-01

    This work was undertaken as to avoid health risks to tourism in the "XIIth Soccer World Cup, Mexico 86". The above project was carried out through proper quality control of foods, drinking water as well as a definite care of personal hygiene of all those involved in the catering business (132 restaurants were included). The mentioned report informs only of the work of the National Public Health Laboratory in the Sanitary Epidemiological Program. The following products were analyzed: 133 water samples, 272 animated and nonliving surfaces, and 399 foods. Twenty seven percent of water samples were rejected, as well as 85% of the different surfaces and 60% of the food samples. High counts of mesophilic aerobics, followed by coliforms, S. aureus and Salmonella sp., were the principal specimens encountered. Therefore, it was suggested the permanent development of a sanitary epidemiological program.

  12. Photoproduction of tritium

    International Nuclear Information System (INIS)

    Becker, J.A.; Anderson, J.D.; Weiss, M.S.

    1995-01-01

    3 H (Tritium) is required for maintenance of nuclear weapons in the stockpile. The National Defense need for 3 H was historically met by the Savannah River Facility. This facility is no longer safe for operation. 3 H decays with a mean lifetime τ = 17.8 y, and therefore new methods of 3 H production are required to meet US military requirements. Irradiation of 7 Li by low-energy photons produces tritium ( 3 H) via the photodisintegration process. Waste heat from the 7 Li target can be extracted and used for the direct generation of electricity. Other advantages include: negligible residual radioactivity, simple target technology, small low-energy electron accelerators for bremsstrahlung production (the photon source), developed liquid metal technology, modularity, simple extraction of 3 H from a recirculating 7 Li target, abundant supply of 7 Li, and straightforward target-accelerator-bremsstrahlung converter interface. A schematic plant characterized by very low risk is described, and a figure-of-merit is obtained

  13. Tritium-surface interactions

    International Nuclear Information System (INIS)

    Kirkaldy, J.S.

    1983-06-01

    The report deals broadly with tritium-surface interactions as they relate to a fusion power reactor enterprise, viz., the vacuum chamber, first wall, peripherals, pumping, fuel recycling, isotope separation, repair and maintenance, decontamination and safety. The main emphasis is on plasma-surface interactions and the selection of materials for fusion chamber duty. A comprehensive review of the international (particularly U.S.) research and development is presented based upon a literature review (about 1 000 reports and papers) and upon visits to key laboratories, Sandia, Albuquerque, Sandia, Livermore and EGβG Idaho. An inventory of Canadian expertise and facilities for RβD on tritium-surface interactions is also presented. A number of proposals are made for the direction of an optimal Canadian RβD program, emphasizing the importance of building on strength in both the technological and fundamental areas. A compendium of specific projects and project areas is presented dealing primarily with plasma-wall interactions and permeation, anti-permeation materials and surfaces and health, safety and environmental considerations. Potential areas of industrial spinoff are identified

  14. Methane emissions from MBT landfills

    Energy Technology Data Exchange (ETDEWEB)

    Heyer, K.-U., E-mail: heyer@ifas-hamburg.de; Hupe, K.; Stegmann, R.

    2013-09-15

    Highlights: • Compilation of methane generation potential of mechanical biological treated (MBT) municipal solid waste. • Impacts and kinetics of landfill gas production of MBT landfills, approach with differentiated half-lives. • Methane oxidation in the waste itself and in soil covers. • Estimation of methane emissions from MBT landfills in Germany. - Abstract: Within the scope of an investigation for the German Federal Environment Agency (“Umweltbundesamt”), the basics for the estimation of the methane emissions from the landfilling of mechanically and biologically treated waste (MBT) were developed. For this purpose, topical research including monitoring results regarding the gas balance at MBT landfills was evaluated. For waste treated to the required German standards, a methane formation potential of approximately 18–24 m{sup 3} CH{sub 4}/t of total dry solids may be expected. Monitoring results from MBT landfills show that a three-phase model with differentiated half-lives describes the degradation kinetics in the best way. This is due to the fact that during the first years of disposal, the anaerobic degradation processes still proceed relatively intensively. In addition in the long term (decades), a residual gas production at a low level is still to be expected. Most of the soils used in recultivation layer systems at German landfills show a relatively high methane oxidation capacity up to 5 l CH{sub 4}/(m{sup 2} h). However, measurements at MBT disposal sites indicate that the majority of the landfill gas (in particular at non-covered areas), leaves the landfill body via preferred gas emission zones (hot spots) without significant methane oxidation. Therefore, rather low methane oxidation factors are recommended for open and temporarily covered MBT landfills. Higher methane oxidation rates can be achieved when the soil/recultivation layer is adequately designed and operated. Based on the elaborated default values, the First Order Decay (FOD

  15. Appendices for Fort George G. Meade Active Sanitary Landfill and Clean Fill Dump Remedial Investigation Report

    Science.gov (United States)

    1992-12-01

    3O VLYqq Time: P7 /0 Well Condition.: Well Diameter (inches): L4 U Odor (describe): Sounding Method: tW L= . . Measurement Reference: ’TOC Pv Stick... acca (f:):~ (=in)-__ --- 13.10 L AP Siium i=; ’are: _______________ Commane n ds Cbserwvuic-n: ______________________ 507 31 ,;IL 3: iL8.15 ’a~~l !o

  16. Life Cycle Comparison of Waste-to-Energy to Sanitary Landfill

    Science.gov (United States)

    Life cycle assessment (LCA) can be used to evaluate the environmental footprint of products, processes, and services. An LCA allows decision makers to compare products and processes through systematic evaluation of supply chains. Also known as a “cradle-to-grave” approach, LCA ev...

  17. Hanford 200 area (sanitary) waste water system

    International Nuclear Information System (INIS)

    Danch, D.A.; Gay, A.E.

    1994-09-01

    The US Department of Energy (DOE) Hanford Site is located in southeastern Washington State. The Hanford Site is approximately 1,450 sq. km (560 sq. mi) of semiarid land set aside for activities of the DOE. The reactor fuel processing and waste management facilities are located in the 200 Areas. Over the last 50 years at Hanford dicard of hazardous and sanitary waste water has resulted in billions of liters of waste water discharged to the ground. As part of the TPA, discharges of hazardous waste water to the ground and waters of Washington State are to be eliminated in 1995. Currently sanitary waste water from the 200 Area Plateau is handled with on-site septic tank and subsurface disposal systems, many of which were constructed in the 1940s and most do not meet current standards. Features unique to the proposed new sanitary waste water handling systems include: (1) cost effective operation of the treatment system as evaporative lagoons with state-of-the-art liner systems, and (2) routing collection lines to avoid historic contamination zones. The paper focuses on the challenges met in planning and designing the collection system

  18. Torus evacuation and tritium handling on NET

    International Nuclear Information System (INIS)

    Dinner, P.; Chazalon, M.; Iseli, M.

    1986-08-01

    The use of tritium as a fuel affects the design of many systems, as well as requiring several new systems not needed on non DT-burning Tokamaks. This paper summarizes: major tritium process interconnections, tritium flows and inventories; primary requirements, preferred design alternatives, and related development issues; design philosophy for tritium and primary vacuum systems. 14 refs

  19. Contribution to the tritium continental effect

    International Nuclear Information System (INIS)

    Lewis, R.R.; Froehlich, K.; Hebert, D.

    1987-01-01

    The results of tritium measurements of atmospheric water vapour and precipitation samples for 1982 and 1983 are presented. The data were used to establish a simple model describing the tritium continental effect taking into account re-evaporation of tritium from the continental land surfaces and man-made tritium. (author)

  20. Contribution to the tritium continental effect

    International Nuclear Information System (INIS)

    Lewis, R.R.; Froehlich, K.; Hebert, D.

    1987-01-01

    The results of tritium measurements of atmospheric water vapour and precipitation samples for 1982 and 1983 are presented. The data were used to establish a simple model describing the tritium continental effect taking into account re-evaporation of tritium from the continental land surfaces. Some comments on man made tritium are given. (author)

  1. Overview of the tritium system of Ignitor

    International Nuclear Information System (INIS)

    Rizzello, C.; Tosti, S.

    2008-01-01

    Among the recent design activities of the Ignitor program, the analysis of the tritium system has been carried out with the aim to describe the main equipments and the operations needed for supplying the deuterium-tritium mixtures and recovering the plasma exhaust. In fact, the tritium system of Ignitor provides for injecting deuterium-tritium mixtures into the vacuum chamber in order to sustain the fusion reaction: furthermore, it generally manages and controls the tritium and the tritiated materials of the machine fuel cycle. Main functions consist of tritium storage and delivery, tritium injection, tritium recovery from plasma exhaust, treatment of the tritiated wastes, detritiation of the contaminated atmospheres, tritium analysis and accountability. In this work an analysis of the designed tritium system of Ignitor is summarized

  2. Tritium, biography of an element

    International Nuclear Information System (INIS)

    Keller, C.

    1980-01-01

    Tritium is the lightest radioactive atom, an isotope of hydrogen. In science it has many uses, particularly for marking organic molecules in order to find out about biochemical and medical processes. But also the traces of tritium contained in rain or sea water are used for investigations; they range from establishing the vintage of old wines to ascertaining sea water mixtures. Tritium will become important in large-scale technology if it should become possible to construct fusion reactors, since it is one of the fuels. (orig.) [de

  3. Tritium monitor for fusion reactors

    Energy Technology Data Exchange (ETDEWEB)

    Jalbert, R.A.

    1982-08-01

    This report describes the design, operation, and performance of a flow-through ion-chamber instrument designed to measure tritium concentrations in air containing /sup 13/N, /sup 16/N, and /sup 41/Ar produced by neutrons generated by D-T fusion devices. The instrument employs a chamber assembly consisting of two coaxial ionization chambers. The inner chamber is the flow-through measuring chamber and the outer chamber is used for current subtraction. A thin wall common to both chambers is opaque to the tritium betas. Currents produced in the two chambers by higher energy radiation are automatically subtracted, leaving only the current due to tritium.

  4. The organically bound tritium: an analyst vision

    International Nuclear Information System (INIS)

    Ansoborlo, E.; Baglan, N.

    2009-01-01

    The authors report the work of a work group on tritium analysis. They recall the different physical forms of tritium: gas (HT, hydrogen-tritium), water vapour (HTO or tritiated water) or methane (CH3T), but also in organic compounds (OBT, organically bound tritium) which are either exchangeable or non-exchangeable. They evoke measurement techniques and methods, notably to determine the tritium volume activity. They discuss the possibilities to analyse and distinguish exchangeable and non-exchangeable OBTs

  5. Tritium monitoring at the Sandia Tritium Research Laboratory

    International Nuclear Information System (INIS)

    Devlin, T.K.

    1978-10-01

    Sandia Laboratories at Livermore, California, is presently beginning operation of a Tritium Research Laboratory (TRL). The laboratory incorporates containment and cleanup facilities such that any unscheduled tritium release is captured rather than vented to the atmosphere. A sophisticated tritium monitoring system is in use at the TRL to protect operating personnel and the environment, as well as ensure the safe and effective operation of the TRL decontamination systems. Each monitoring system has, in addition to a local display, a display in a centralized control room which, when coupled room which, when coupled with the TRL control computer, automatically provides an immediate assessment of the status of the entire facility. The computer controls a complex alarm array status of the entire facility. The computer controls a complex alarm array and integrates and records all operational and unscheduled tritium releases

  6. 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.

  7. JET experiments with tritium and deuterium–tritium mixtures

    Energy Technology Data Exchange (ETDEWEB)

    Horton, Lorne, E-mail: Lorne.Horton@jet.uk [JET Exploitation Unit, Culham Science Centre, Abingdon OX14 3DB (United Kingdom); European Commission, B-1049 Brussels (Belgium); EUROfusion Consortium, JET, Culham Science Centre, Abingdon OX14 3DB (United Kingdom); Batistoni, P. [Unità Tecnica Fusione - ENEA C. R. Frascati - via E. Fermi 45, Frascati (Roma), 00044, Frascati (Italy); EUROfusion Consortium, JET, Culham Science Centre, Abingdon OX14 3DB (United Kingdom); Boyer, H.; Challis, C.; Ćirić, D. [CCFE, Culham Science Centre, Abingdon OX14 3DB, Oxon (United Kingdom); EUROfusion Consortium, JET, Culham Science Centre, Abingdon OX14 3DB (United Kingdom); Donné, A.J.H. [EUROfusion Programme Management Unit, Culham Science Centre, Abingdon OX14 3DB (United Kingdom); FOM Institute DIFFER, PO Box 1207, NL-3430 BE Nieuwegein (Netherlands); EUROfusion Consortium, JET, Culham Science Centre, Abingdon OX14 3DB (United Kingdom); Eriksson, L.-G. [European Commission, B-1049 Brussels (Belgium); EUROfusion Consortium, JET, Culham Science Centre, Abingdon OX14 3DB (United Kingdom); Garcia, J. [CEA, IRFM, F-13108 Saint Paul Lez Durance (France); EUROfusion Consortium, JET, Culham Science Centre, Abingdon OX14 3DB (United Kingdom); Garzotti, L.; Gee, S. [CCFE, Culham Science Centre, Abingdon OX14 3DB, Oxon (United Kingdom); EUROfusion Consortium, JET, Culham Science Centre, Abingdon OX14 3DB (United Kingdom); Hobirk, J. [Max-Planck-Institut für Plasmaphysik, D-85748 Garching (Germany); EUROfusion Consortium, JET, Culham Science Centre, Abingdon OX14 3DB (United Kingdom); Joffrin, E. [CEA, IRFM, F-13108 Saint Paul Lez Durance (France); EUROfusion Consortium, JET, Culham Science Centre, Abingdon OX14 3DB (United Kingdom); and others

    2016-11-01

    Highlights: • JET is preparing for a series of experiments with tritium and deuterium–tritium mixtures. • Physics objectives include integrated demonstration of ITER operating scenarios, isotope and alpha physics. • Technology objectives include neutronics code validation, material studies and safety investigations. • Strong emphasis on gaining experience in operation of a nuclear tokamak and training scientists and engineers for ITER. - Abstract: Extensive preparations are now underway for an experiment in the Joint European Torus (JET) using tritium and deuterium–tritium mixtures. The goals of this experiment are described as well as the progress that has been made in developing plasma operational scenarios and physics reference pulses for use in deuterium–tritium and full tritium plasmas. At present, the high performance plasmas to be tested with tritium are based on either a conventional ELMy H-mode at high plasma current and magnetic field (operation at up to 4 MA and 4 T is being prepared) or the so-called improved H-mode or hybrid regime of operation in which high normalised plasma pressure at somewhat reduced plasma current results in enhanced energy confinement. Both of these regimes are being re-developed in conjunction with JET's ITER-like Wall (ILW) of beryllium and tungsten. The influence of the ILW on plasma operation and performance has been substantial. Considerable progress has been made on optimising performance with the all-metal wall. Indeed, operation at the (normalised) ITER reference confinement and pressure has been re-established in JET albeit not yet at high current. In parallel with the physics development, extensive technical preparations are being made to operate JET with tritium. The state and scope of these preparations is reviewed, including the work being done on the safety case for DT operation and on upgrading machine infrastructure and diagnostics. A specific example of the latter is the planned calibration at

  8. Thought experiment with tritium

    International Nuclear Information System (INIS)

    Anderson, H.F.; Everhart, J.L.; Hobrock, D.L.; Seabaugh, P.W.

    1995-01-01

    An experiment is proposed in which a minimum of thirty (30) grams of tritium is packaged as lithium tritide in a steel container weighing several kilograms. After decontamination of the outside surface, calorimetry measurements would be made, and the unit would be weighed very accurately. After several decades, the calorimeter and weight measurements would be repeated. If the weight measurements could be made with the required accuracy, it would be possible to correlate the observed change in mass with the total energy emitted (calculated from the mean energy measured by calorimetry) over the time interval. If successful, this experiment would, in the opinion of the authors, be the first laboratory experiment to directly verify the equivalency of mass and energy. 4 refs., 2 figs., 3 tabs

  9. Quantification of leachate discharged to groundwater using the water balance method and the hydrologic evaluation of landfill performance (HELP) model.

    Science.gov (United States)

    Alslaibi, Tamer M; Abustan, Ismail; Mogheir, Yunes K; Afifi, Samir

    2013-01-01

    Landfills are a source of groundwater pollution in Gaza Strip. This study focused on Deir Al Balah landfill, which is a unique sanitary landfill site in Gaza Strip (i.e., it has a lining system and a leachate recirculation system). The objective of this article is to assess the generated leachate quantity and percolation to the groundwater aquifer at a specific site, using the approaches of (i) the hydrologic evaluation of landfill performance model (HELP) and (ii) the water balance method (WBM). The results show that when using the HELP model, the average volume of leachate discharged from Deir Al Balah landfill during the period 1997 to 2007 was around, 6800 m3/year. Meanwhile, the average volume of leachate percolated through the clay layer was 550 m3/year, which represents around 8% of the generated leachate. Meanwhile, the WBM indicated that the average volume of leachate discharged from Deir Al Balah landfill during the same period was around 7660 m3/year--about half of which comes from the moisture content of the waste, while the remainder comes from the infiltration of precipitation and re-circulated leachate. Therefore, the estimated quantity of leachate to groundwater by these two methods was very close. However, compared with the measured leachate quantity, these results were overestimated and indicated a dangerous threat to the groundwater aquifer, as there was no separation between municipal, hazardous and industrial wastes, in the area.

  10. Tritium containment of controlled thermonuclear fusion reactor

    International Nuclear Information System (INIS)

    Tanaka, Yoshihisa; Tsukumo, Kiyohiko; Suzuki, Tatsushi

    1979-01-01

    It is well known that tritium is used as the fuel for nuclear fusion reactors. The neutrons produced by the nuclear fusion reaction of deuterium and tritium react with lithium in blankets, and tritium is produced. The blankets reproduce the tritium consumed in the D-T reaction. Tritium circulates through the main cooling system and the fuel supply and evacuation system, and is accumulated. Tritium is a radioactive substance emitting β-ray with 12.6 year half-life, and harmful to human bodies. It is an isotope of hydrogen, and apt to diffuse and leak. Especially at high temperature, it permeates through materials, therefore it is important to evaluate the release of tritium into environment, to treat leaked tritium to reduce its release, and to select the method of containing tritium. The permeability of tritium and its solubility in structural materials are discussed. The typical blanket-cooling systems of nuclear fusion reactors are shown, and the tungsten coating of steam generator tubes and tritium recovery system are adopted for reducing tritium leak. In case of the Tokamak type reactor of JAERI, the tritium recovery system is installed, in which the tritium gas produced in blankets is converted to tritium steam with a Pd-Pt catalytic oxidation tower, and it is dehydrated and eliminated with a molecular sieve tower, then purified and recovered. (Kako, I.)

  11. Development of Automated Monitoring and Management System of Municipal Solid Waste Landfill Based on the Industrial OMRON Controller

    Science.gov (United States)

    Kostarev, S. N.; Sereda, T. G.

    2018-01-01

    The application of the programmable logic integrated circuits (PLC) for creating the software and hardware complexes of the medium complexity is an economically sound solution. The application of the OMRON controller to solve the monitoring and management tasks of safety of the municipal solid waste (MSW) landfill with the use of technology of the filtrate recirculation and the landfill maps irrigation is shown in the article. The article contains the technical solution connected with the implementation of the 2162059RU invention patent for the municipal solid waste landfill management in the Kurgan region of Russia. The calculation of maps and ponds was made with consideration of the limited sanitary and protection zone. The GRUNDFOS dosing and reactor equipment was proposed to use in the project.

  12. Landfill gas: planning and regulation

    International Nuclear Information System (INIS)

    Nealon, T.

    1991-01-01

    There is no legislation in the UK that relates directly to landfill gas. However, various pieces of legislation do exist which control all aspects of landfill and therefore, indirectly, landfill gas. This legislation includes Planning Acts, The Control of Pollution Act, Health and Safety at Work Acts, and Public Health Acts, and affects landfill gas throughout the life of the site - from planning stage to long after the last load has been deposited and restoration has been carried out. Responsibility for ensuring compliance with these various Acts lies with a variety of Authorities, including Plannning Authorities, Waste Disposal Authorities, and Environmental Health Authorities. Responsibility for actual compliance with the Acts lies with the operator, for active sites, and the landowner in the case of closed sites. (author)

  13. Biogeochemistry of landfill leachate plumes

    DEFF Research Database (Denmark)

    Christensen, Thomas Højlund; Kjeldsen, Peter; Bjerg, Poul Løgstrup

    2001-01-01

    are relatively narrow and do not in terms of width exceed the width of the landfill. The concept of redox zones being present in the plume has been confirmed by the reported composition of the leachate contaminated groundwater at several landfills and constitutes an important framework for understanding...... the behavior of the contaminants in the plume as the leachate migrates away from the landfill. Diverse microbial communities have been identified in leachate plumes and are believed to be responsible for the redox processes. Dissolved organic C in the leachate, although it appears to be only slowly degradable...... to be subject to anaerobic oxidation, but the mechanisms are not yet understood. Heavy metals do not seem to constitute a significant pollution problem at landfills, partly because the heavy metal concentrations in the leachate often are low, and partly because of strong attenuation by sorption...

  14. Landfill Gas Energy Benefits Calculator

    Science.gov (United States)

    This page contains the LFG Energy Benefits Calculator to estimate direct, avoided, and total greenhouse gas reductions, as well as environmental and energy benefits, for a landfill gas energy project.

  15. Tritium transport around nuclear facilities

    International Nuclear Information System (INIS)

    Murphy, C.E. Jr.; Sweet, C.W.

    1981-01-01

    The transport and cycling of tritium around nuclear facilities is reviewed with special emphasis on studies at the Savannah River Laboratory, Aiken, South Carolina. These studies have shown that the rate of deposition from the atmosphere, the site of deposition, and the subsequent cycling are strongly influenced by the compound with which the tritium is associated. Tritiated hydrogen is largely deposited in the soil, while tritiated water is deposited in the greatest quantity in the vegetation. Tritiated hydrogen is converted in the soil to tritiated water that leaves the soil slowly, through drainage and transpiration. Tritiated water deposited directly to the vegetation leaves the vegetation more rapidly after exposure. Only a small part of the tritium entering the vegetation becomes bound in organic molecules. However, it appears tht the existence of soil organic compounds with tritium concentrations greater than the equilibrium concentration in the associated water can be explained by direct metabolism of tritiated hydrogen in vegetation

  16. TFTR tritium inventory accountability system

    International Nuclear Information System (INIS)

    Saville, C.; Ascione, G.; Elwood, S.; Nagy, A.; Raftopoulos, S.; Rossmassler, R.; Stencel, J.; Voorhees, D.; Tilson, C.

    1995-01-01

    This paper discusses the program, PPPL (Princeton Plasma Physics Laboratory) Material Control and Accountability Plan, that has been implemented to track US Department of Energy's tritium and all other accountable source material. Specifically, this paper details the methods used to measure tritium in various systems at the Tokamak Fusion Test Reactor; resolve inventory differences; perform inventory by difference inside the Tokamak; process and measure plasma exhaust and other effluent gas streams; process, measure and ship scrap or waste tritium on molecular sieve beds; and detail organizational structure of the Material Control and Accountability group. In addition, this paper describes a Unix-based computerized software system developed at PPPL to account for all tritium movements throughout the facility. 5 refs., 2 figs

  17. Tritium management for fusion reactors

    International Nuclear Information System (INIS)

    Rouyer, J.L.; Djerassi, H.

    1985-01-01

    To determine a waste management strategy, one has to identify first the wastes (quantities, activities, etc.), then to define options, and to compare these options by appropriate criteria and evaluations. Two European Associations are working together, i.e., Studsvik and CEA, on waste treatment and tritium problems. A contribution to fusion specific tritiated waste management strategy is presented. It is demonstrated that the best strategy is to retain tritium (outgas and recover, or immobilize it) so that residual tritium releases are kept to a minimum. For that, wastes are identified, actual regulations are described and judged inadequate without amendments for fusion problems. Appropriate criteria are defined. Options for treatment and disposal of tritiated wastes are proposed and evaluated. A tritium recovery solution is described

  18. Radiotoxicity of tritium in mammals

    International Nuclear Information System (INIS)

    Silini, G.; Metalli, P.; Vulpis, G.

    1972-12-01

    Basic data relative to tritium, its physicochemical behaviour in environment, its major sources of contamination and its metabolism through the mammalian organisms are reviewed. After considering the radiotoxicity of tritium particularly at the cellular and whole-body level the conclusion is drawn that the major uncertainties regard the fraction of tritium incorporated into the nuclei of some tissues. This fraction is eliminated very slowly and is capable of modifying the genetic structures of the nucleus. A more refined analysis of radiobiological phenomena and a better knowledge of the dose effect relationship should permit the extrapolation of the data to the low doses of tritium contamination. This extrapolation is of great interest in the field of public health for the elaboration of the relevant radioprotection standards

  19. Tritium transport around nuclear faciliteis

    International Nuclear Information System (INIS)

    Murphy, C.E. Jr.; Sweet, C.W.

    1982-01-01

    The transport and cycling of tritium around nuclear facilities is reviewed with special emphasis on studies at the Savannah River Laboratory, Aiken, South Carolina. These studies have shown that the rate of deposition from the atmosphere, the site of deposition, and the subsequent cycling are strongly influenced by the compound with which the tritium is associated. Tritiated hydrogen is largely deposited in the soil, while tritiated water is deposited in the greatest quantity in the vegetation. Tritiated hydrogen is converted in the soil to tritiated water that leaves the soil slowly, through drainage and transpiration. Tritiated water deposited directly to the vegetation leaves the vegetation more rapidly after exposure. Only a small part of the tritium entering the vegetation becomes bound in organic molecules. However, it appears that the existence of soil organic compounds with tritium concentrations greater than the equilibrium concentration in the associated water can be explained by direct metabolism of tritiated hydrogen in vegetation. (J.P.N.)

  20. Tritium in fusion reactor components

    International Nuclear Information System (INIS)

    Watson, J.S.; Fisher, P.W.; Talbot, J.B.

    1980-01-01

    When tritium is used in a fusion energy experiment or reactor, several implications affect and usually restrict the design and operation of the system and involve questions of containment, inventory, and radiation damage. Containment is expected to be particularly important both for high-temperature components and for those components that are prone to require frequent maintenance. Inventory is currently of major significance in cases where safety and environmental considerations limit the experiments to very low levels of tritium. Fewer inventory restrictions are expected as fusion experiments are placed in more-remote locations and as the fusion community gains experience with the use of tritium. However, the advent of power-producing experiments with high-duty cycle will again lead to serious difficulties based principally on tritium availability; cyclic operations with significant regeneration times are the principal problems

  1. [Prophylactic requirements for sanitary and epidemiological surveillance in dentistry].

    Science.gov (United States)

    Kaplan, B M; Maksimenko, L V; Fedotova, N N; Gololobova, T V; Konovalov, O E

    2009-01-01

    The paper outlines the requirements for sanitary-and-epidemiological surveillance to prevent dental diseases. The investigations pose tasks to medical prevention centers to solve the problems in tooth prophylaxis, such as organizational-and-methodological, sanitary-and-educational, health-improving, and others. The sanitary-and-hygienic requirements for therapeutic-and-prophylactic dental facilities are defined. A procedure for keeping a management protocol for the prevention of tooth diseases is described.

  2. Sanitary effects of fossil fuels; Effets sanitaires des combustibles fossiles

    Energy Technology Data Exchange (ETDEWEB)

    Nifenecker, H. [Centre National de la Recherche Scientifique (IN2P3/CNRS), 38 - Grenoble (France)

    2006-07-01

    In this compilation are studied the sanitary effects of fossil fuels, behavioral and environmental sanitary risks. The risks in connection with the production, the transport and the distribution(casting) are also approached for the oil(petroleum), the gas and the coal. Accidents in the home are evoked. The risks due to the atmospheric pollution are seen through the components of the atmospheric pollution as well as the sanitary effects of this pollution. (N.C.)

  3. Tritium control and accountability instructions

    International Nuclear Information System (INIS)

    Wall, W.R.; Cruz, S.L.

    1985-08-01

    This instruction describes the tritium accountability procedures practiced by the Tritium Research Laboratory, at Sandia National Laboratories, Livermore. The accountability procedures are based upon the Sandia National Laboratories, Livermore, Nuclear Materials Operations Manual, SAND83-8036. The Nuclear Materials Operations Manual describes accountability techniques which are in compliance with the Department of Energy 5630 series Orders, Code of Federal Regulations, and Sandia National Laboratories Instructions

  4. Tritium pellet injector for TFTR

    International Nuclear Information System (INIS)

    Gouge, M.J.; Baylor, L.R.; Cole, M.J.; Combs, S.K.; Dyer, G.R.; Fehling, D.T.; Fisher, P.W.; Foust, C.R.; Langley, R.A.; Milora, S.L.; Qualls, A.L.; Wilgen, J.B.; Schmidt, G.L.; Barnes, G.W.; Persing, R.G.

    1992-01-01

    The tritium pellet injector (TPI) for the Tokamak Fusion Test Reactor (TFTR) will provide a tritium pellet fueling capability with pellet speeds in the 1- to 3-km/s range for the TFTR deuterium-tritium (D-T) phase. The existing TFTR deuterium pellet injector (DPI) has been modified at Oak Ridge National Laboratory (ORNL) to provide a four-shot, tritium-compatible, pipe-gun configuration with three upgraded single-stage pneumatic guns and a two-stage light gas gun driver. The TPI was designed to provide pellets ranging from 3.3 to 4.5 mm in diameter in arbitrarily programmable firing sequences at speeds up to approximately 1.5 km/s for the three single-stage drivers and 2.5 to 3 km/s for the two-stage driver. Injector operation is controlled by a programmable logic controller. The new pipe-gun injector assembly was installed in the modified DPI guard vacuum box, and modifications were made to the internals of the DPI vacuum injection line, including a new pellet diagnostics package. Assembly of these modified parts with existing DPI components was then completed, and the TPI was tested at ORNL with deuterium pellet. Results of the limited testing program at ORNL are described. The TPI is being installed on TFTR to support the D-D run period in 1992. In 1993, the tritium pellet injector will be retrofitted with a D-T fuel manifold and secondary tritium containment systems and integrated into TFTR tritium processing systems to provide full tritium pellet capability

  5. Tritium control and accountability instructions

    International Nuclear Information System (INIS)

    Wall, W.R.

    1981-03-01

    This instruction describes the tritium accountability procedures practiced by the Tritium Research Laboratory, Building 968 at Sandia National Laboratories, Livermore. The accountability procedures are based upon the Sandia National Laboratories, Livermore, Nuclear Materials Operations Manual, SAND78-8018. The Nuclear Materials Operations Manual describes accountability techniques which are in compliance with the Department of Energy Manual, Code of Federal Regulations, and Sandia National Laboratories Instructions

  6. Design and test about de tritium system to filling tritium glove box

    International Nuclear Information System (INIS)

    Lei, Jiarong; Du, Yang; Yang, Yong

    2008-01-01

    In order to deal tritium permeated from inflating tritium system at the scene of inflating tritium, dealing waste tritium gas system was designed according to demand and action of dealing waste tritium gas from inflating tritium, and the data of character and volume about appliance of catalyst reaction and drying agent was calculated. Through the test at the scene of inflating tritium, it is result that dealing waste tritium gas system's efficiency reaches above 85% average in circulatory system, so that it can be used in practice extensively. (author)

  7. Landfill gas management facilities design guidelines

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2010-03-15

    In British Columbia, municipal solid waste landfills generate over 1000 tonnes of methane per year; landfill gas management facilities are required to improve the environmental performance of solid waste landfills. The aim of this document, developed by the British Columbia Ministry of the Environment, is to provide guidance for the design, installation, and operation of landfill gas management facilities to address odor and pollutant emissions issues and also address health and safety issues. A review of technical experience and best practices in landfill gas management facilities was carried out, as was as a review of existing regulations related to landfill gas management all over the world. This paper provides useful information to landfill owners, operators, and other professionals for the design of landfill gas management facilities which meet the requirements of landfill gas management regulations.

  8. Separation of Tritium from Wastewater

    International Nuclear Information System (INIS)

    JEPPSON, D.W.

    2000-01-01

    A proprietary tritium loading bed developed by Molecular Separations, Inc (MSI) has been shown to selectively load tritiated water as waters of hydration at near ambient temperatures. Tests conducted with a 126 (micro)C 1 tritium/liter water standard mixture showed reductions to 25 (micro)C 1 /L utilizing two, 2-meter long columns in series. Demonstration tests with Hanford Site wastewater samples indicate an approximate tritium concentration reduction from 0.3 (micro)C 1 /L to 0.07 (micro)C 1 /L for a series of two, 2-meter long stationary column beds Further reduction to less than 0.02 (micro)C 1 /L, the current drinking water maximum contaminant level (MCL), is projected with additional bed media in series. Tritium can be removed from the loaded beds with a modest temperature increase and the beds can be reused Results of initial tests are presented and a moving bed process for treating large quantities of wastewaters is proposed. The moving bed separation process appears promising to treat existing large quantities of wastewater at various US Department of Energy (DOE) sites. The enriched tritium stream can be grouted for waste disposition. The separations system has also been shown to reduce tritium concentrations in nuclear reactor cooling water to levels that allow reuse. Energy requirements to reconstitute the loading beds and waste disposal costs for this process appear modest

  9. Tritium research activities in Korea

    Energy Technology Data Exchange (ETDEWEB)

    Jung, Ki Jung, E-mail: kjjung@nfri.re.kr [National Fusion Research Institute, Yusung-gu, Daejeon 305-333 (Korea, Republic of); Yun, Sei-Hun, E-mail: shyun@nfri.re.kr [National Fusion Research Institute, Yusung-gu, Daejeon 305-333 (Korea, Republic of); Chang, Min Ho; Kang, Hyun-Goo; Chung, Dongyou; Cho, Seungyon; Lee, Hyeon Gon [National Fusion Research Institute, Yusung-gu, Daejeon 305-333 (Korea, Republic of); Chung, Hongsuk; Choi, Woo-Seok [Korea Atomic Energy Research Institute, Yusung-gu, Daejeon 305-353 (Korea, Republic of); Song, Kyu-Min; Moon, Chang-Bae [Korea Hydro & Nuclear Power Central Research Institute, Yusung-gu, Daejeon 305-343 (Korea, Republic of); Lee, Euy Soo [Dongguk University, Jung-gu, Seoul, 100-715 (Korea, Republic of); Cho, Jungho; Kim, Dong-Sun [Kongju National University, Cheonan, Chungnam, 330-717 (Korea, Republic of); Moon, Hung-Man [Daesung Industrial Gases Co., Ltd., Danwon-gu, Ansan-si, Gyeonggi-do, 425-090 (Korea, Republic of); Noh, Seung Jeong [Dankook University, Suji-gu, Yongin-si, Gyeonggi-do, 448-701 (Korea, Republic of); Ju, Hyunchul [Inha University, Nam-gu, Incheon, 402-751 (Korea, Republic of); Hong, Tae-Whan [Korea National University of Transportation, Chungju, Chungbuk, 380-702 (Korea, Republic of)

    2016-12-15

    Highlights: • NFRI, KAERI and KHNP CRI are major leading group for the ITER tritium SDS design; studying engineering, simulation of hydride bed, risk analysis (on safety, HAZOP), basic study, control logic & sequential operation, and others. KHNP has WTRF which gives favorable experiences for collaboration researchers. • Supplementary research partners: Five Universities (Dongguk University and POSTECH, Inha University, Dankook University, Korea National Transport University, and Kongju National University) and one industrial company (Daesung Industrial Gases Co., Ltd.); studying on basic and engineering, programming & simulation on the various topics for ITER tritium SDS, TEP, ISS, ADS, and etc. - Abstract: Major progress in tritium research in the Republic of Korea began when Korea became responsible for ITER tritium Storage and Delivery System (SDS) procurement package which is part of the ITER Fuel Cycle. To deliver the tritium SDS package, a variety of research institutes, universities and industry have respectively taken roles and responsibilities in developing technologies that have led to significant progress. This paper presents the current work and status of tritium related technological research and development (R&D) in Korea and introduces future R&D plans in the area of fuel cycle systems for fusion power generation.

  10. Sanitary hot water; Eau chaude sanitaire

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2004-07-01

    Cegibat, the information-recommendation agency of Gaz de France for building engineering professionals, has organized this conference meeting on sanitary hot water to present the solutions proposed by Gaz de France to meet its clients requirements in terms of water quality, comfort, energy conservation and respect of the environment: quantitative aspects of the hot water needs, qualitative aspects, presentation of the Dolce Vita offer for residential buildings, gas water heaters and boilers, combined solar-thermal/natural gas solutions, key-specifications of hot water distribution systems, testimony: implementation of a gas hot water reservoir and two accumulation boilers in an apartment building for young workers. (J.S.)

  11. Florence Nightingale and the India sanitary reforms.

    Science.gov (United States)

    Hays, J C

    1989-09-01

    After the Crimean War, Florence Nightingale persisted in researching the health conditions of British troops throughout the Empire. Undaunted by geographic limitations, she surveyed and publicized data that documented the mismanagement of living conditions and health care among the occupational forces on the Indian continent. Nightingale proposed widespread changes in the reporting of military health status and biostatistics, in sanitary engineering, and in self-care activities. With dogged persistence, she continued to gather follow-up data to measure the changing health status of soldiers in a land she never saw.

  12. Tritium concentrations in tree ring cellulose

    International Nuclear Information System (INIS)

    Kaji, Toshio; Momoshima, Noriyuki; Takashima, Yoshimasa.

    1989-01-01

    Measurements of tritium (tissue bound tritium; TBT) concentration in tree rings are presented and discussed. Such measurement is expected to provide a useful means of estimating the tritium level in the environment in the past. The concentration of tritium bound in the tissue (TBT) in a tree ring considered to reflect the environmental tritium level in the area at the time of the formation of the ring, while the concentration of tritium in the free water in the tissue represents the current environmental tritium level. First, tritium concentration in tree ring cellulose sampled from a cedar tree grown in a typical environment in Fukuoka Prefecture is compared with the tritium concentration in precipitation in Tokyo. Results show that the year-to-year variations in the tritium concentration in the tree rings agree well with those in precipitation. The maximum concentration, which occurred in 1963, is attibuted to atmospheric nuclear testing which was performed frequently during the 1961 - 1963 period. Measurement is also made of the tritium concentration in tree ring cellulose sampled from a pine tree grown near the Isotope Center of Kyushu University (Fukuoka). Results indicate that the background level is higher probably due to the release of tritium from the facilities around the pine tree. Thus, measurement of tritium in tree ring cellulose clearly shows the year-to-year variation in the tritium concentration in the atmosphere. (N.K.)

  13. Exploration for tritium-free water

    International Nuclear Information System (INIS)

    Hussain, S.D.

    1982-10-01

    Tritium-free water is generally required in large quantities for the preparation of laboratory tritium standards as well as blanks which are used to determine background count rate in the measurement of low level tritium concentrations in water samples by liquid scintillation counting method. In order to meet the requirements of tritium-free water and save the recurring expenditure on its import from abroad, exploration for locating its source in the country was undertaken. Water samples collected from a few possible sources were analysed precisely for their tritium content at the International Atomic Energy Agency, Vienna, Austria and a source of tritium-free water was determined. (authors)

  14. Tritium problems in fusion reactor systems

    International Nuclear Information System (INIS)

    Hickman, R.G.

    1975-01-01

    A brief introduction is given to the role tritium will play in the development of fusion power. The biological and worldwide environmental behavior of tritium is reviewed. The tritium problems expected in fusion power reactors are outlined. A few thoughts on tritium permeation and recent results for tritium cleanup and CT 4 accumulation are presented. Problems involving the recovery of tritium from the breeding blanket in fusion power reactors are also considered, including the possible effect of impurities in lithium blankets and the use of lithium as a regenerable getter pump. (auth)

  15. Quantification of landfill methane using modified Intergovernmental Panel on Climate Change's waste model and error function analysis.

    Science.gov (United States)

    Govindan, Siva Shangari; Agamuthu, P

    2014-10-01

    Waste management can be regarded as a cross-cutting environmental 'mega-issue'. Sound waste management practices support the provision of basic needs for general health, such as clean air, clean water and safe supply of food. In addition, climate change mitigation efforts can be achieved through reduction of greenhouse gas emissions from waste management operations, such as landfills. Landfills generate landfill gas, especially methane, as a result of anaerobic degradation of the degradable components of municipal solid waste. Evaluating the mode of generation and collection of landfill gas has posted a challenge over time. Scientifically, landfill gas generation rates are presently estimated using numerical models. In this study the Intergovernmental Panel on Climate Change's Waste Model is used to estimate the methane generated from a Malaysian sanitary landfill. Key parameters of the model, which are the decay rate and degradable organic carbon, are analysed in two different approaches; the bulk waste approach and waste composition approach. The model is later validated using error function analysis and optimum decay rate, and degradable organic carbon for both approaches were also obtained. The best fitting values for the bulk waste approach are a decay rate of 0.08 y(-1) and degradable organic carbon value of 0.12; and for the waste composition approach the decay rate was found to be 0.09 y(-1) and degradable organic carbon value of 0.08. From this validation exercise, the estimated error was reduced by 81% and 69% for the bulk waste and waste composition approach, respectively. In conclusion, this type of modelling could constitute a sensible starting point for landfills to introduce careful planning for efficient gas recovery in individual landfills. © The Author(s) 2014.

  16. Yolo County's Accelerated Anaerobic and Aerobic Composting (Full-Scale Controlled Landfill Bioreactor) Project

    Science.gov (United States)

    Yazdani, R.; Kieffer, J.; Akau, H.; Augenstein, D.

    2002-12-01

    Sanitary landfilling is the dominant method of solid waste disposal in the United States, accounting for about 217 million tons of waste annually (U.S. EPA, 1997) and has more than doubled since 1960. In spite of increasing rates of reuse and recycling, population and economic growth will continue to render landfilling as an important and necessary component of solid waste management. Yolo County Department of Planning and Public Works, Division of Integrated Waste Management is demonstrating a new landfill technology called Bioreactor Landfill to better manage solid waste. In a Bioreactor Landfill, controlled quantities of liquid (leachate, groundwater, gray-water, etc.) are added and recirculated to increase the moisture content of the waste and improve waste decomposition. As demonstrated in a small-scale demonstration project at the Yolo County Central Landfill in 1995, this process significantly increases the biodegradation rate of waste and thus decreases the waste stabilization and composting time (5 to 10 years) relative to what would occur within a conventional landfill (30 to 50 years or more). When waste decomposes anaerobically (in absence of oxygen), it produces landfill gas (biogas). Biogas is primarily a mixture of methane, a potent greenhouse gas, carbon dioxide, and small amounts of Volatile Organic Compounds (VOC's) which can be recovered for electricity or other uses. Other benefits of a bioreactor landfill composting operation include increased landfill waste settlement which increases in landfill capacity and life, improved leachate chemistry, possible reduction of landfill post-closure management time, opportunity to explore decomposed waste for landfill mining, and abatement of greenhouse gases through highly efficient methane capture over a much shorter period of time than is typical of waste management through conventional landfilling. This project also investigates the aerobic decomposition of waste of 13,000 tons of waste (2.5 acre) for

  17. Landfill to Learning Facility

    Science.gov (United States)

    Venner, Laura

    2008-05-01

    Engaging "K-to-Gray” audiences (children, families, and older adults) in scientific exploration and discovery is the main goal of the NJMC Center for Environmental and Scientific Education and the William D. McDowell Observatory located in Lyndhurst, NJ. Perched atop a closed and reclaimed municipal solid waste landfill, our new LEED - certified building (certification pending) and William D. McDowell observatory will bring hands-on scientific experiences to the 25,000 students and 3,000 adults that visit our site from the NY/NJ region each year. Our programs adhere to the New Jersey Core Curriculum Content Standards and are modified for accessibility for the underserved communities that visit us, specifically those individuals that have mobility, sensory, and/or cognitive ability differences. The programs are conducted in a classroom setting and are designed to nourish the individual's inquisitive nature and provide an opportunity to function as a scientist by, making observations, performing experiments and recording data. We have an $850,000, three year NSF grant that targets adults with disabilities and older adults with age related limitations in vision, hearing, cognition and/or mobility. From dip netting in the marsh to astronomical investigation of the cosmos, the MEC/CESE remains committed to reaching the largest audience possible and leaving them with a truly exceptional scientific experience that serves to educate and inspire.

  18. Monitoring and modeling of long-term settlements of an experimental landfill in Brazil.

    Science.gov (United States)

    Simões, Gustavo Ferreira; Catapreta, Cícero Antônio Antunes

    2013-02-01

    Settlement evaluation in sanitary landfills is a complex process, due to the waste heterogeneity, time-varying properties and influencing factors and mechanisms, such as mechanical compression due to load application and creep, and physical-chemical and biological processes caused by the wastes decomposition. Many empirical models for the analysis of long-term settlement in landfills are reported in the literature. This paper presents the results of a settlement monitoring program carried out during 6 years in Belo Horizonte experimental landfill. Different sets of field data were used to calibrate three long-term settlement prediction models (rheological, hyperbolic and composite). The parameters obtained in the calibration were used to predict the settlements and to compare with actual field data. During the monitoring period of 6 years, significant vertical strains were observed (of up to 31%) in relation to the initial height of the experimental landfill. The results for the long-term settlement prediction obtained by the hyperbolic and rheological models significantly underestimate the settlements, regardless the period of data used in the calibration. The best fits were obtained with the composite model, except when 1 year field data were used in the calibration. The results of the composite model indicate settlements stabilization at larger times and with larger final settlements when compared to the hyperbolic and rheological models. Copyright © 2012 Elsevier Ltd. All rights reserved.

  19. Leachate Characterization from a Closed Landfill in Air Hitam, Puchong, Malaysia

    International Nuclear Information System (INIS)

    Nur Fatin Dahlia Mat Salleh; Ku Halim Ku Hamid

    2013-01-01

    Leachate, wastewater that was collected from landfill is known to have pungent smell and may impose serious harm to human health and the environment. Air Hitam, Puchong Sanitary Landfill has stopped its land filling operation since December 2006 and is under post-closure maintenance stages. After several years of stopping its operation, a landfill will still produce leachate hence it needs constant monitoring and maintenance. The main aim of this paper was to characterize leachate produced from Air Hitam, Puchong Closed Landfill, according to several important parameters: pH, temperature, chemical oxygen demand (COD), ammoniacal nitrogen (NH 4 -N), total organic carbon (TOC), total solids, volatile organic acids (VOA) and heavy metals content, to determine its suitability in producing methane by identifying its phase. Leachate samples were drawn weekly for a period of 3 months from three different ponds, untreated raw leachate pond 1 and treated leachate pond 2 and 3. Results obtained showed that the average values were around 25 degree Celsius, average pH 8, highest COD reading was 5,248 mg/L, TOC highest at 6,797 mg/L, VOA highest at 1,424 mg/L and ammoniacal content of 3.10 mg/L the highest. (author)

  20. GIS-based approach for optimized siting of municipal solid waste landfill

    International Nuclear Information System (INIS)

    Sumathi, V.R.; Natesan, Usha; Sarkar, Chinmoy

    2008-01-01

    The exponential rise in the urban population of the developing countries in the past few decades and the resulting accelerated urbanization phenomenon has brought to the fore the necessity to develop environmentally sustainable and efficient waste management systems. Sanitary landfill constitutes one of the primary methods of municipal solid waste disposal. Optimized siting decisions have gained considerable importance in order to ensure minimum damage to the various environmental sub-components as well as reduce the stigma associated with the residents living in its vicinity, thereby enhancing the overall sustainability associated with the life cycle of a landfill. This paper addresses the siting of a new landfill using a multi-criteria decision analysis (MCDA) and overlay analysis using a geographic information system (GIS). The proposed system can accommodate new information on the landfill site selection by updating its knowledge base. Several factors are considered in the siting process including geology, water supply resources, land use, sensitive sites, air quality and groundwater quality. Weightings were assigned to each criterion depending upon their relative importance and ratings in accordance with the relative magnitude of impact. The results from testing the system using different sites show the effectiveness of the system in the selection process

  1. Impact of landfill leachate on the groundwater quality: A case study in Egypt

    Directory of Open Access Journals (Sweden)

    Magda M. Abd El-Salam

    2015-07-01

    Full Text Available Alexandria Governorate contracted an international company in the field of municipal solid waste management for the collection, transport and disposal of municipal solid waste. Construction and operation of the sanitary landfill sites were also included in the contract for the safe final disposal of solid waste. To evaluate the environmental impacts associated with solid waste landfilling, leachate and groundwater quality near the landfills were analyzed. The results of physico-chemical analyses of leachate confirmed that its characteristics were highly variable with severe contamination of organics, salts and heavy metals. The BOD5/COD ratio (0.69 indicated that the leachate was biodegradable and un-stabilized. It was also found that groundwater in the vicinity of the landfills did not have severe contamination, although certain parameters exceeded the WHO and EPA limits. These parameters included conductivity, total dissolved solids, chlorides, sulfates, Mn and Fe. The results suggested the need for adjusting factors enhancing anaerobic biodegradation that lead to leachate stabilization in addition to continuous monitoring of the groundwater and leachate treatment processes.

  2. Planning for the closure of uncontrolled landfills in Turkey to reduce environmental impacts.

    Science.gov (United States)

    Ergene Şentürk, Didar; Alp, Emre

    2016-11-01

    Landfilling is the most preferred solid waste disposal method in Turkey owing to both economic and technical reasons. However, beside the sanitary landfills there are also hundreds of uncontrolled waste sites located throughout Turkey, which are often left either abandoned or burning. Because there is a lack of legislative guidelines governing the closure and rehabilitation of these dumpsites, the municipalities that are responsible for waste management do not initiate the proactive strategies required for the closure of these sites. In this study, a method based on a multi-criteria analysis is conducted for different dumpsites in Turkey to evaluate the level of negative impacts on the environment. This method is based on the use of environmental indices for a quantitative assessment of the landfills, such as environmental interaction between the source and the receptors, environmental values of the receptors, and operational conditions. It was possible to assess the robustness of the proposed methodology since the pre- and post-groundwater quality monitoring data was available from the study sites that were closed and rehabilitated in 2014. The results of this study show that the method based on a multi-criteria analysis is an effective tool while in the preliminary planning stages of closure and rehabilitation activities of uncontrolled waste landfills. © The Author(s) 2016.

  3. Studies on chemical phenomena of high concentration tritium water and organic compounds of tritium from viewpoint of the tritium confinement

    International Nuclear Information System (INIS)

    Yamanishi, Toshihiko; Hayashi, Takumi; Iwai, Yasunori; Isobe, Kanetsugu; Hara, Masanori; Sugiyama, Takahiko; Okuno, Kenji

    2009-01-01

    As a part of the grant-in-aid for scientific research on priority areas entitled 'frontiers of tritium researches toward fusion reactors', coordinated two research programs on chemical phenomena of high concentration tritium water and organic compounds of tritium from view point of the tritium confinement have been conducted by the C01 team. The results are summarized as follows: (1) Chemical effects of the high concentration tritium water on stainless steels as structural materials of fusion reactors were investigated. Basic data on tritium behaviors at the metal-water interface and corrosion of metal in tritium water were obtained. (2) Development of the tritium confinement and extraction system for the circulating cooling water in the fusion reactor was studied. Improvement was obtained in the performance of a chemical exchange column and catalysts as major components of the water processing system. (J.P.N.)

  4. 30 CFR 71.501 - Sanitary toilet facilities; maintenance.

    Science.gov (United States)

    2010-07-01

    ... Section 71.501 Mineral Resources MINE SAFETY AND HEALTH ADMINISTRATION, DEPARTMENT OF LABOR COAL MINE SAFETY AND HEALTH MANDATORY HEALTH STANDARDS-SURFACE COAL MINES AND SURFACE WORK AREAS OF UNDERGROUND COAL MINES Sanitary Toilet Facilities at Surface Worksites of Surface Coal Mines § 71.501 Sanitary...

  5. Estimated release from the saltstone landfill effect of landfill caps and landfill-cap/monolith-liner combinations

    International Nuclear Information System (INIS)

    Wilhite, E.L.

    1985-01-01

    The effect of capping the entire saltstone landfill is dependent on the effectiveness of the clay cap in preventing infiltration. A cap that is 99% effective will reduce releases from the saltstone landfill by a factor of 7.7. Several combinations of landfill design alterations will result in meeting ground water standards

  6. Landfill aeration for emission control before and during landfill mining.

    Science.gov (United States)

    Raga, Roberto; Cossu, Raffaello; Heerenklage, Joern; Pivato, Alberto; Ritzkowski, Marco

    2015-12-01

    The landfill of Modena, in northern Italy, is now crossed by the new high velocity railway line connecting Milan and Bologna. Waste was completely removed from a part of the landfill and a trench for the train line was built. With the aim of facilitating excavation and further disposal of the material extracted, suitable measures were defined. In order to prevent undesired emissions into the excavation area, the aerobic in situ stabilisation by means of the Airflow technology took place before and during the Landfill Mining. Specific project features involved the pneumatic leachate extraction from the aeration wells (to keep the leachate table low inside the landfill and increase the volume of waste available for air migration) and the controlled moisture addition into a limited zone, for a preliminary evaluation of the effects on process enhancement. Waste and leachate were periodically sampled in the landfill during the aeration before the excavation, for quality assessment over time; the evolution of biogas composition in the landfill body and in the extraction system for different plant set-ups during the project was monitored, with specific focus on uncontrolled migration into the excavation area. Waste biological stability significantly increased during the aeration (waste respiration index dropped to 33% of the initial value after six months). Leachate head decreased from 4 to 1.5m; leachate recirculation tests proved the beneficial effects of moisture addition on temperature control, without hampering waste aerobization. Proper management of the aeration plant enabled the minimization of uncontrolled biogas emissions into the excavation area. Copyright © 2015 Elsevier Ltd. All rights reserved.

  7. Turkey Point tritium. Progress report

    International Nuclear Information System (INIS)

    Ostlund, H.G.; Dorsey, H.G.

    1976-01-01

    In 1972-73 the Florida Power and Light Company (FPL) began operation of two nuclear reactors at Turkey Point on lower Biscayne Bay. One radioactive by-product resulting from the operation of the nuclear reactors, tritium, provides a unique opportunity to study transport and exchange processes on a local scale. Since the isotope in the form of water is not removed from the liquid effluent, it is discharged to the cooling canal system. By studying its residence time in the canal and the pathways by which it leaves the canals, knowledge of evaporative process, groundwater movement, and bay exchange with the ocean can be obtained. Preliminary results obtained from measurement of tritium levels, both in the canal system and in the surrounding environment are discussed. Waters in lower Biscayne Bay and Card and Barnes Sounds receive only a small portion of the total tritium produced by the nuclear plant. The dominating tritium loss most likely is through evaporation from the canals. The capability of measuring extremely low HTO levels allows the determination of the evaporation rate experimentally by measuring the tritium levels of air after having passed over the canals

  8. Tritium Management Loop Design Status

    Energy Technology Data Exchange (ETDEWEB)

    Rader, Jordan D. [ORNL; Felde, David K. [ORNL; McFarlane, Joanna [ORNL; Greenwood, Michael Scott [ORNL; Qualls, A L. [ORNL; Calderoni, Pattrick [Idaho National Laboratory (INL)

    2017-12-01

    This report summarizes physical, chemical, and engineering analyses that have been done to support the development of a test loop to study tritium migration in 2LiF-BeF2 salts. The loop will operate under turbulent flow and a schematic of the apparatus has been used to develop a model in Mathcad to suggest flow parameters that should be targeted in loop operation. The introduction of tritium into the loop has been discussed as well as various means to capture or divert the tritium from egress through a test assembly. Permeation was calculated starting with a Modelica model for a transport through a nickel window into a vacuum, and modifying it for a FLiBe system with an argon sweep gas on the downstream side of the permeation interface. Results suggest that tritium removal with a simple tubular permeation device will occur readily. Although this system is idealized, it suggests that rapid measurement capability in the loop may be necessary to study and understand tritium removal from the system.

  9. An assembly of tritium production experiment

    International Nuclear Information System (INIS)

    Abe, Toshihiko

    1981-01-01

    An assembly for tritium production experiment, i.e. Tritium Extraction System (TREX) constructed as a small scale test facility for tritium production, and Tritium Removal System (TRS) attached to TREX, and the preliminary results of the experiments with them are described. The radiological safety of the process and operation is also an important consideration. Lithium-aluminum alloy was selected as the most promising target material. The following matters are involved in the scope of production technology: the selection of a target material and target preparation, reactor irradiation, the construction of a facility for the extraction of tritium from the irradiated target, the establishment of the optimum conditions of extraction, the purification, collection and storage of tritium, and the inspection of the product. The tritium production experiment at JAERI is yet on the initial stage; the development is to be continued with the stepwise increase of the scale of tritium production. (J.P.N.)

  10. Tritium in the environment. Knowledge synthesis

    International Nuclear Information System (INIS)

    2009-01-01

    This report first presents the nuclear and physical-chemical properties of tritium and addresses the notions of bioaccumulation, bio-magnification and remanence. It describes and comments the natural and anthropic origins of tritium (natural production, quantities released in the environment in France by nuclear tests, nuclear plants, nuclear fuel processing plants, research centres). It describes how tritium is measured as a free element (sampling, liquid scintillation, proportional counting, enrichment method) or linked to organic matter (combustion, oxidation, helium-3-based measurement). It discusses tritium concentrations noticed in different parts of the environment (soils, continental waters, sea). It describes how tritium is transferred to ecosystems (transfer of atmospheric tritium to ground ecosystems, and to soft water ecosystems). It discusses existing models which describe the behaviour of tritium in ecosystems. It finally describes and comments toxic effects of tritium on living ground and aquatic organisms

  11. Recommended radiological controls for tritium operations

    International Nuclear Information System (INIS)

    Mansfield, G.

    1992-01-01

    This informal report presents recommendations for an adequate radiological protection program for tritium operations. Topics include hazards analysis, facility design, personnel protection equipment, training, operational procedures, radiation monitoring, to include surface and airborne tritium contamination, and program management

  12. Corrective Action Investigation Plan for Corrective Action Unit 5: Landfills, Nevada Test Site, Nevada (Rev. No.: 0) includes Record of Technical Change No. 1 (dated 9/17/2002)

    Energy Technology Data Exchange (ETDEWEB)

    IT Corporation, Las Vegas, NV

    2002-05-28

    This Corrective Action Investigation Plan contains the U.S. Department of Energy, National Nuclear Security Administration Nevada Operations Office's approach to collect the data necessary to evaluate corrective action alternatives appropriate for the closure of Corrective Action Unit (CAU) 5 under the Federal Facility Agreement and Consent Order. Corrective Action Unit 5 consists of eight Corrective Action Sites (CASs): 05-15-01, Sanitary Landfill; 05-16-01, Landfill; 06-08-01, Landfill; 06-15-02, Sanitary Landfill; 06-15-03, Sanitary Landfill; 12-15-01, Sanitary Landfill; 20-15-01, Landfill; 23-15-03, Disposal Site. Located between Areas 5, 6, 12, 20, and 23 of the Nevada Test Site (NTS), CAU 5 consists of unlined landfills used in support of disposal operations between 1952 and 1992. Large volumes of solid waste were produced from the projects which used the CAU 5 landfills. Waste disposed in these landfills may be present without appropriate controls (i.e., use restrictions, adequate cover) and hazardous and/or radioactive constituents may be present at concentrations and locations that could potentially pose a threat to human health and/or the environment. During the 1992 to 1995 time frame, the NTS was used for various research and development projects including nuclear weapons testing. Instead of managing solid waste at one or two disposal sites, the practice on the NTS was to dispose of solid waste in the vicinity of the project. A review of historical documentation, process knowledge, personal interviews, and inferred activities associated with this CAU identified the following as potential contaminants of concern: volatile organic compounds, semivolatile organic compounds, polychlorinated biphenyls, pesticides, petroleum hydrocarbons (diesel- and gasoline-range organics), Resource Conservation and Recovery Act Metals, plus nickel and zinc. A two-phase approach has been selected to collect information and generate data to satisfy needed resolution

  13. Astronomy on a Landfill

    Science.gov (United States)

    Venner, Laura

    2008-09-01

    Engaging "K-to-Gray” audiences (children, families, and older adults) in astronomical activities is one of the main goals of the NJMC Center for Environmental and Scientific Education and the William D. McDowell Observatory located in Lyndhurst, NJ. Perched atop a closed and reclaimed municipal solid waste landfill, our new LEED - certified building (certification pending) and William D. McDowell observatory will assist in bringing the goals of IYA 2009 to the approximately 25,000 students and 15,000 adults that visit our site from the NY/NJ region each year. Diversifying our traditional environmental science offerings, we have incorporated astronomy into our repertoire with "The Sun Through Time” module, which includes storytelling, cultural astronomy, telescope anatomy, and other activities that are based on the electromagnetic spectrum and our current knowledge of the sun. These lessons have also been modified to bring astronomy to underserved communities, specifically those individuals that have dexterity or cognitive ability differences. The program is conducted in a classroom setting and is designed to meet New Jersey Core Curriculum Content Standards. With the installation of our new 20” telescope, students and amateur astronomers will be given the opportunity to perform rudimentary research. In addition, a program is in development that will allow individuals to measure local sky brightness and understand the effects of light pollution on astronomical viewing. Teaching astronomy in an urban setting presents many challenges. All individuals, regardless of ability level or location, should be given the opportunity to be exposed to the wonders of the universe and the MEC/CESE has been successful in providing those opportunities.

  14. Tritium in metals: Techniques of preparation

    International Nuclear Information System (INIS)

    Laesser, R.; Klatt, K.H.; Mecking, P.; Wenzl, H.

    1982-08-01

    In order to study the behavior of tritium in metals, an all metal apparatus has been built for the safe handling of 100 mg of tritium. Samples of palladium, vanadium, niobium, and tantalum were loaded with tritium, deuterium or hydrogen. Some details of the phase diagrams could be established by DTA and by measurement of the lattice parameters. The diffusion of tritium in V, Nb, and Ta was studied with the Gorsky-effect. (TWO)

  15. Tritium decontamination of machine components and walls

    International Nuclear Information System (INIS)

    Hircq, B.; Wong, K.Y.; Jalbert, R.A.; Shmayda, W.T.

    1991-01-01

    Tritium decontamination techniques for machine components and their application at tritium handling facilities are reviewed. These include commonly used methods such as vacuuming, purging, thermal desorption and isotopic exchange as well as less common methods such as chemical/electrochemical etching, plasma discharge cleaning, and destructive methods. Problems associated with tritium contamination of walls and use of protective coatings are reviewed. Tritium decontamination considerations at fusion facilities are discussed

  16. Environmental upgrading of a landfill

    International Nuclear Information System (INIS)

    Agostinetto, V.; Vendrame, G.

    1999-01-01

    This article refers to an experimental study concerning the vegetative upgrading of a closed-down landfill (once used for industrial waste disposal). The aim was to check the possibility of reconstructing or aiding the natural growth of a vegetation in keeping with the surrounding area, in a tried environment such as that of landfills. The original idea contained in the approved project - which meant to generically upgrade the territory by planting species belonging to the grassy layer, shrubs and trees - has, with time, undergone some changes. On the basis of both the knowledge acquired during management and of a more accurate analysis of the territory, the experiment was preferred to aim at finding out which were the species, both continental and Mediterranean, able to gradually adjust to the surrounding landscape, leaving to natural selection the task to decide which species were more suitable to the upgrading of closed-down landfills, and which planting technique was more effective [it

  17. [To the 90th anniversary of State Sanitary Epidemiologic Service Formation in Russian Federation].

    Science.gov (United States)

    Beliaev, E N; Podunova, L G

    2012-01-01

    State Educational Institution of Higher Professional Training of the Ministry of Health Care and Social Development Foundation of Russian Sanitary Epidemiologic Service dates back to September, 15, 1922, when a Decree on Sanitary Institutions of the Republic was signed. Afterwards the institutions of Sanitary Epidemiologic Service were improved: foundation of State Sanitary Inspectorate (1933-1951), approval of new concept of the Service and intensification of State Sanitary Inspectorate (1951-1991), foundation of State Sanitary Epidemiologic Service, centralization of management and financing of the Service, formation of Sanitary Epidemiologic Legislation (1991-2004), further restructurization of Sanitary Epidemiologic Service in accordance with administrative changes in Russia (2004 until now).

  18. Survey of landfill gas generation potential

    International Nuclear Information System (INIS)

    Gauntlett, W.D.

    1992-09-01

    This project identifies all the landfill sites in each of the 50 states capable of producing 750,000 SCFD of mixed landfill gas for a period of at least 10 years. The study identified 749 landfill sites nationally, with an aggregate gas production rate sufficient to fuel approximately 6000 MW of fuel cell power plants

  19. METHANE PHYTOREMEDIATION BY VEGETATIVE LANDFILL COVER SYSTEMS

    Science.gov (United States)

    Landfill gas, consisting of methane and other gases, is produced from organic compounds degrading in landfills, contributes to global climate change, is toxic to various types of vegetation, and may pose a combustion hazard at higher concentrations. New landfills are required to ...

  20. LANDFILL BIOREACTOR PERFORMANCE, SECOND INTERIM REPORT

    Science.gov (United States)

    A bioreactor landfill is a landfill that is operated in a manner that is expected to increase the rate and extent of waste decomposition, gas generation, and settlement compared to a traditional landfill. This Second Interim Report was prepared to provide an interpretation of fie...

  1. Tritium calorimeter setup and operation

    CERN Document Server

    Rodgers, D E

    2002-01-01

    The LBNL tritium calorimeter is a stable instrument capable of measuring tritium with a sensitivity of 25 Ci. Measurement times range from 8-hr to 7-days depending on the thermal conductivity and mass of the material being measured. The instrument allows accurate tritium measurements without requiring that the sample be opened and subsampled, thus reducing personnel exposure and radioactive waste generation. The sensitivity limit is primarily due to response shifts caused by temperature fluctuation in the water bath. The fluctuations are most likely a combination of insufficient insulation from ambient air and precision limitations in the temperature controller. The sensitivity could probably be reduced to below 5 Ci if the following improvements were made: (1) Extend the external insulation to cover the entire bath and increase the top insulation. (2) Improve the seal between the air space above the bath and the outside air to reduce evaporation. This will limit the response drift as the water level drops. (...

  2. Polymeric media for tritium fixation

    International Nuclear Information System (INIS)

    Franz, J.A.; Burger, L.L.

    1975-01-01

    The synthesis and leach testing of several polymeric media for tritium fixation are presented. Tritiated bakelite, poly(acrylonitrile) and polystyrene successfully fixed tritium. Tritium leach rates at the tracer level appear to be negligible. Advantages and disadvantages of the processes are discussed, and further bench-scale investigations underway are reported. Rough cost estimates are presented for the different media and are compared with alternate approaches such as deep-well injection and long-term tank storage. Polymeric media costs are high compared to deep-well storage and are of the same order of magnitude per liter of water as for isotopic enrichment. With this limitation, polymeric media can be economically feasible only for highly concentrated tritiated wastes. It is recommended that the bakelite and polystyrene processes be examined on a larger scale to permit more accurate cost analysis and process design. (auth)

  3. Tritium processing using metal hydrides

    International Nuclear Information System (INIS)

    Mallett, M.W.

    1986-01-01

    E.I. duPont de Nemours and Company is commissioned by the US Department of Energy to operate the Savannah River Plant and Laboratory. The primary purpose of the plant is to produce radioactive materials for national defense. In keeping with current technology, new processes for the production of tritium are being developed. Three main objectives of this new technology are to ease the processing of, ease the storage of, and to reduce the operating costs of the tritium production facility. Research has indicated that the use of metal hydrides offers a viable solution towards satisfying these objectives. The Hydrogen and Fuels Technology Division has the responsibility to conduct research in support of the tritium production process. Metal hydride technology and its use in the storage and transportation of hydrogen will be reviewed

  4. Implanted-tritium permeation experiments

    International Nuclear Information System (INIS)

    Longhurst, G.R.; Holland, D.F.; Casper, L.A.; Hsu, P.Y.; Miller, L.G.; Schmunk, R.E.; Watts, K.D.; Wilson, C.J.; Kershner, C.J.; Rogers, M.L.

    1982-04-01

    In fusion reactors, charge exchange neutral atoms of tritium coming from the plasma will be implanted into the first wall and other interior structures. EG and G Idaho is conducting two experiments to determine the magnitude of permeation into the coolant streams and the retention of tritium in those structures. One experiment uses an ion gun to implant deuterium. The ion gun will permit measurements to be made for a variety of implantation energies and fluxes. The second experiment utilizes a fission reactor to generate a tritium implantation flux by the 3 He(n,p) 3 H reaction. This experiment will simulate the fusion reactor radiation environment. We also plan to verify a supporting analytical code development program, in progress, by these experiments

  5. Tritium emissions from a detritiation facility

    International Nuclear Information System (INIS)

    Rodrigo, L.; El-Behairy, O.; Boniface, H.; Hotrum, C.; McCrimmon, K.

    2010-01-01

    Tritium is produced in heavy-water reactors through neutron capture by the deuterium atom. Annual production of tritium in a CANDU reactor is typically 52-74 TBq/MW(e). Some CANDU reactor operators have implemented detritiation technology to reduce both tritium emissions and dose to workers and the public from reactor operations. However, tritium removal facilities also have the potential to emit both elemental tritium and tritiated water vapor during operation. Authorized releases to the environment, in Canada, are governed by Derived Release Limits (DRLs). DRLs represent an estimate of a release that could result in a dose of 1 mSv to an exposed member of the public. For the Darlington Nuclear Generating Station, the DRLs for airborne elemental tritium and tritiated water emissions are ~15.6 PBq/week and ~825 TBq/week respectively. The actual tritium emissions from Darlington Tritium Removal Facility (DTRF) are below 0.1% of the DRL for elemental tritium and below 0.2% of the DRL for tritiated water vapor. As part of an ongoing effort to further reduce tritium emissions from the DTRF, we have undertaken a review and assessment of the systems design, operating performance, and tritium control methods in effect at the DTRF on tritium emissions. This paper discusses the results of this study. (author)

  6. Tritium inventory prediction in a CANDU plant

    International Nuclear Information System (INIS)

    Song, M.J.; Son, S.H.; Jang, C.H.

    1995-01-01

    The flow of tritium in a CANDU nuclear power plant was modeled to predict tritium activity build-up. Predictions were generally in good agreement with field measurements for the period 1983--1994. Fractional contributions of coolant and moderator systems to the environmental tritium release were calculated by least square analysis using field data from the Wolsong plant. From the analysis, it was found that: (1) about 94% of tritiated heavy water loss came from the coolant system; (2) however, about 64% of environmental tritium release came from the moderator system. Predictions of environmental tritium release were also in good agreement with field data from a few other CANDU plants. The model was used to calculate future tritium build-up and environmental tritium release at Wolsong site, Korea, where one unit is operating and three more units are under construction. The model predicts the tritium inventory at Wolsong site to increase steadily until it reaches the maximum of 66.3 MCi in the year 2026. The model also predicts the tritium release rate to reach a maximum of 79 KCi/yr in the year 2012. To reduce the tritium inventory at Wolsong site, construction of a tritium removal facility (TRF) is under consideration. The maximum needed TRF capacity of 8.7 MCi/yr was calculated to maintain tritium concentration effectively in CANDU reactors

  7. Tritium oxidation and exchange: preliminary studies

    International Nuclear Information System (INIS)

    Phillips, J.E.; Easterly, C.E.

    1978-05-01

    The radiological hazard resulting from an exposure to either tritium oxide or tritium gas is discussed and the factors contributing to the hazard are presented. From the discussion it appears that an exposure to tritium oxide vapor is 10 4 to 10 5 times more hazardous than exposure to tritium gas. Present and future sources of tritium are briefly considered and indicate that most of the tritium has been and is being released as tritium oxide. The likelihood of gaseous releases, however, is expected to increase in the future, calling to task the present general release assumption that 100% of all tritium released is as oxide. Accurate evaluation of the hazards from a gaseous release will require a knowledge of the conversion rate of tritium gas to tritium oxide. An experiment for determining the conversion rate of tritium gas to tritium oxide is presented along with some preliminary data. The conversion rates obtained for low initial concentrations (10 -4 to 10 -1 mCi/ml) indicate the conversion may proceed more rapidly than would be expected from an extrapolation of previous data taken at higher concentrations

  8. Bioassay guideline 2: guidelines for tritium bioassay

    International Nuclear Information System (INIS)

    1983-01-01

    This guideline is one of a series under preparation by the Federal-Provincial Working Group on Bioassay and In Vivo Monitoring Criteria. In this report tritium compounds have been grouped into four categories for the purpose of calculating Annual Limits on Intake and Investigation Levels: tritium gas, tritiated water, tritium-labelled compounds and nucleic acid precursors

  9. 10 CFR 30.55 - Tritium reports.

    Science.gov (United States)

    2010-01-01

    ... 10 Energy 1 2010-01-01 2010-01-01 false Tritium reports. 30.55 Section 30.55 Energy NUCLEAR..., Inspections, Tests, and Reports § 30.55 Tritium reports. (a)-(b) [Reserved] (c) Except as specified in paragraph (d) of this section, each licensee who is authorized to possess tritium shall report promptly to...

  10. Toxicity and dosimetry of tritium

    International Nuclear Information System (INIS)

    Myers, D.K.; Johnson, J.R.

    1991-01-01

    Tritium doses to the general public are very low (currently about 0.2 μSv per year). Radiation doses from tritium to members of the public living in the vicinity of a CANDU power station are higher but rarely exceed 20 μSv per year or 1% of normal exposures to radiation from all natural sources, but doses to some radiation workers can approach ten mSv per year. The relative biological effectiveness (RBE) of tritium beta rays varies appreciably depending upon the biological endpoint. Observed RBE values at low doses and low dose-rates are usually about 2 to 3 when tritium beta rays are compared to 60 Co gamma rays but are closer to 1 than to 2 when compared to 200 kVp X-rays. This conclusion is supported by microdosimetric considerations of the quality of tritium beta rays, 60 Co gamma rays and X-rays. Since X-rays have traditionally been accepted as reference radiation by the International Commission on Radiological Protection, it seems reasonable that the quality factor (Q) assigned to tritium beta rays should be close to one. Recommended procedures in Canada for estimation of effective dose equivalents from exposures to HTO and HT assume that Q = 1 and that body water represents 67% of the mass of soft tissue; they take into account conversions of HTO to appear to be reasonable for radiation protection purposes when the source of exposure is HTO or HT, but will not be adequate for exposures to other tritiated compounds. (modified author abstract) (137 refs., 11 figs., 12 tabs.)

  11. Water radiological sanitary control of Veracruz State

    International Nuclear Information System (INIS)

    Carreon G, E.; Vazquez C, J. A.; Aguilar P, M. del C.; Parissi C, A.

    2014-10-01

    This work is carried out in Veracruz State covering over 11 jurisdictions of the State (Panuco, Tuxpan, Poza Rica, Martinez de la Torre, Xalapa, Cordoba, Orizaba, Veracruz, Cosamaloapan, San Andres Tuxtla and Coatzacoalcos). The sampling was realized in a period from 2009 to 2013 analyzing home drinking water, supply sources and wells, the sampling was done by the sanitary checkers of different jurisdictions with approved methods and the methodology was validated at the State Laboratory of Public Health. 1637 samples were analyzed by counting equipment Tennelec Canberra series 5 and a gas supply system P-10 with calibration curves for alpha and gross beta. The results of measurements ranging from 0.07 to 0.25 Bq/L in the activity concentration gross alpha annual average, an gross beta were from 0.12 to 0.17 Bq/L in the activity concentration gross beta annual average, and with a concentration range of alpha activity up to 0.62 and a minimum 0.02, and the concentration of beta activity of a maximum value 1.54 and a minimum 0.02, taking also as resulted in five years of analysis only 1.16% of the analyzed samples (19 samples) showed a value of alpha activity concentration above the minimum detectable concentration and 62.43% (1022 samples) of the analyzed samples showed a value of beta activity concentration above the minimum detectable concentration, is also clear that the results of the sanitary jurisdictions of Panuco and Tuxpan not have corresponding activity values for the years 2009, 2011-2013 except 2010. We can conclude that the regular measurements of alpha and gross beta activity in water are invaluable for timely detection of radioactive contamination. (Author)

  12. The INEL Tritium Research Facility

    International Nuclear Information System (INIS)

    Longhurst, G.R.

    1990-01-01

    The Tritium Research Facility (TRF) at the Idaho National Engineering Laboratory (INEL) is a small, multi-user facility dedicated to research into processes and phenomena associated with interaction of hydrogen isotopes with other materials. Focusing on bench-scale experiments, the main objectives include resolution of issues related to tritium safety in fusion reactors and the science and technology pertinent to some of those issues. In this report the TRF and many of its capabilities will be described. Work presently or recently underway there will be discussed, and the implications of that work to the development of fusion energy systems will be considered. (orig.)

  13. The INEL Tritium Research Facility

    Energy Technology Data Exchange (ETDEWEB)

    Longhurst, G.R. (Idaho National Engineering Lab., Idaho Falls (USA))

    1990-06-01

    The Tritium Research Facility (TRF) at the Idaho National Engineering Laboratory (INEL) is a small, multi-user facility dedicated to research into processes and phenomena associated with interaction of hydrogen isotopes with other materials. Focusing on bench-scale experiments, the main objectives include resolution of issues related to tritium safety in fusion reactors and the science and technology pertinent to some of those issues. In this report the TRF and many of its capabilities will be described. Work presently or recently underway there will be discussed, and the implications of that work to the development of fusion energy systems will be considered. (orig.).

  14. Tritium turnover in succulent plants

    International Nuclear Information System (INIS)

    Krishnamoorthy, T.M.; Gogate, S.S.; Soman, S.D.

    1977-01-01

    Measurements of turnover rates for tissue free water tritium (TFWT) and tissue bound tritium (TBT) were carried out in three succulent plants, Opuntia sp., E. Trigona and E. Mili using tritiated water as tracer. The estimated half-times were 52, 57.5 and 80 days for TFWT and 212, 318 and 132 days for TBT in the stems of the above plants respectively. Opuntia sp. showed significant incorporation of TBT, 10% of TFWT on weight basis, while the other two plants showed lesser incorporation, 2-3% of TFWT. However, the leaves of E. Mili indicated the same level of fixation of TBT as the stem of Opuntia sp. (author)

  15. Tritium processing in JT-60U

    International Nuclear Information System (INIS)

    Miya, Naoyuki; Masaki, Kei

    1997-01-01

    Tritium retention analysis and tritium concentration measurement have been made during the large Tokamak JT-60U deuterium operations. This work has been carried out to evaluate the tritium retention for graphite tiles inside the vacuum vessel and tritium release characteristics in the tritium cleanup operations. JT-60U has carried out D-D experiments since July 1991. In the deuterium operations during the first two years, about 1.7 x 10 19 D-D fusion neutrons were produced by D (d, p) T reactions in plasma, which are expected to produce ∼31 GBq of tritium. The tritium produced is evacuated by a pumping system. A part of tritium is, however, trapped in the graphite tiles. Several sample tiles were removed from the vessel and the retained tritium Distribution in the tiles was measured using a liquid scintillator. The results of poloidal distribution showed that the tritium concentration in the divertor tiles was higher than that in the first wall tiles and it peaked in the tiles between two strike points of divertor magnetic lines. Tritium concentration in the exhaust gas from the vessel have also been measured with an ion chamber during the tritium cleanup operations with hydrogen divertor discharges and He-GDC. Total of recovered tritium during the cleanup operations was ∼ 7% of that generated. The results of these measurements showed that the tritium of 16-23 GBq still remained in the graphite tiles, which corresponded to about 50-70% of the tritium generated in plasma. The vessel is ventilated during the in-vessel maintenance works, then the atmosphere is always kept lower than the legal concentration guide level of 0.7 Bq/cm 3 for radiation work permit requirements. (author)

  16. Tritium monitoring in environment at ICIT Tritium Separation Facility

    International Nuclear Information System (INIS)

    Varlam, Carmen; Stefanescu, I.; Vagner, Irina; Faurescu, I.; Toma, A.; Dulama, C.; Dobrin, R.

    2008-01-01

    Full text: The Cryogenic Pilot is an experimental project developed within the national nuclear energy research program, which is designed to develop the required technologies for tritium and deuterium separation by cryogenic distillation of heavy water. The process used in this installation is based on a combination between liquid-phase catalytic exchange (LPCE) and cryogenic distillation. Basically, there are two ways that the Cryogenic Pilot could interact with the environment: by direct atmospheric release and through the sewage system. This experimental installation is located 15 km near the region biggest city and in the vicinity - about 1 km, of Olt River. It must be specified that in the investigated area there is an increased chemical activity; almost the entire Experimental Cryogenic Pilot's neighborhood is full of active chemical installations. This aspect is really essential for our study because the sewerage system is connected with the other three chemical plants from the neighborhood. For that reason we progressively established elements of an environmental monitoring program well in advance of tritium operation in order to determine baseline levels. The first step was the tritium level monitoring in environmental water and wastewater of industrial activity from neighborhood. In order to establish the base level of tritium concentration in the environment around the nuclear facilities, we investigated the sample preparation treatment for different types of samples: onion, green beams, grass, apple, garden lettuce, tomato, cabbage, strawberry and grapes. We used azeotropic distillation of all types of samples, the carrier solvent being toluene from different Romanian providers. All measurements for the determination of environmental tritium concentration were performed using liquid scintillation counting (LSC), with the Quantulus 1220 spectrometer. (authors)

  17. Automation system for tritium contaminated surface monitoring

    International Nuclear Information System (INIS)

    Culcer, Mihai; Iliescu, Mariana; Curuia, Marian; Raceanu, Mircea; Enache, Adrian; Stefanescu, Ioan; Ducu, Catalin; Malinovschi, Viorel

    2005-01-01

    The low energy of betas makes tritium difficult to detect. However, there are several methods used in tritium detection, such as liquid scintillation and ionization chambers. Tritium on or near a surface can be also detected using proportional counter and, recently, solid state devices. The paper presents our results in the design and achievement of a surface tritium monitor using a PIN photodiode as a solid state charged particle detector to count betas emitted from the surface. That method allows continuous, real-time and non-destructively measuring of tritium. (authors)

  18. Tritium compatibility of alumina and Fosterite

    Energy Technology Data Exchange (ETDEWEB)

    Coffin, D.O.

    1979-09-01

    Many pressure measurements are required to control processing of the fuel gases associated with fusion power reactors. Since most pressure transducers respond to changes in pressure sensitive electrical parameters, insulators will be required to withstand chronic exposures to concentrated tritium. For this investigation samples of alumina and Fosterite were exposed to concentrated tritium gas for 11 weeks. Gas phase impurities were then analyzed for clues that would indicate decomposition of the exposed materials. The only gaseous impurity resulting from these tritium exposures was tritio-methane, which is always produced when tritium is stored in stainless steel containers. There was no evidence that either alumina or Fosterite decomposed in the presence of tritium.

  19. Management of tritium at nuclear facilities

    International Nuclear Information System (INIS)

    1984-01-01

    This report presents extending summaries of the works of the participants to an IAEA co-ordinated research programme, ''Handling Tritium - bearing effluents and wastes''. The subjects covered include production of tritium in nuclear power plants (mainly heavy water and light water reactors), as well as at reprocessing plants; removal and enrichment of tritium at nuclear facilities; conditioning methods and characteristics of immobilized tritium of low and high concentration; some potential methods of storage and disposal of tritium. In addition to the conclusions of this three-years work, possible activities in the field are recommended

  20. Study on tritium recovery from breeder materials

    International Nuclear Information System (INIS)

    Moriyama, H.; Moritani, K.

    1997-01-01

    For the development of fusion reactor blanket systems, some of the key issues on the tritium recovery performance of solid and liquid breeder materials were studied. In the case of solid breeder materials, a special attention was focussed on the effects of irradiation on the tritium recovery performance, and tritium release experiments, luminescence measurements of irradiation defects and modeling studies were systematically performed. For liquid breeder materials, tritium recovery experiments from molten salt and liquid lithium were performed, and the technical feasibility of tritium recovery methods was discussed. (author)

  1. Landfilling of waste incineration residues

    DEFF Research Database (Denmark)

    Christensen, Thomas Højlund; Astrup, Thomas; Cai, Zuansi

    2002-01-01

    Residues from waste incineration are bottom ashes and air-pollution-control (APC) residues including fly ashes. The leaching of heavy metals and salts from the ashes is substantial and a wide spectrum of leaching tests and corresponding criteria have been introduced to regulate the landfilling...

  2. Landfill gas powers brick production

    International Nuclear Information System (INIS)

    CADDET UK National Team.

    1997-01-01

    Marshalls plc produce high-quality facing bricks using tunnel kilns at the company's Stairfoot Brickworks site, in the UK. The company extracts clay from the adjacent quarries, which are subsequently filled with domestic waste. In 1981 Marshalls decided to exploit the landfill gas (LFG) resource 'on its doorstep'. (author)

  3. Impermeable layers in landfill design

    Directory of Open Access Journals (Sweden)

    Karanac Milica

    2013-01-01

    Full Text Available Landfills are complex systems which could potentially contaminate the environment. It should be prevented by providing impermeability during the landfill design. In that aim related regulations should be followed and adequate materials that provide impermeability should be used. The first part of the paper presents review of the current regulations, interpretations, and recommendations from U.S., EU and Republic of Serbia. Knowing that the Serbian regulation should fully follow related European Directive, in analyses some inadequate formulations and terms were observed related to the Directive Annex I, 3.2. Request of the Regulation that deals with the bottom of the landfill leakage is formulated differently than in Directive as well. Mentioned problems enable some design solutions which are not among the best available techniques. In the second part the paper presents comparative analysis of possible alternatives in impermeable layer design, both for the bottom and landfill cover. Some materials like clay, CCL, GCL might not be able to satisfy prescribed requirements. The longest lifetime and the lowest coefficient of permeability, as well as excellent mechanical, chemical and thermal stability, show the mixture of sand, bentonite and polymers (PEBSM. [Projekat Ministarstva nauke Republike Srbije, br. TR 34009

  4. Use of the landfill water pollution index (LWPI) for groundwater quality assessment near the landfill sites.

    Science.gov (United States)

    Talalaj, Izabela A; Biedka, Pawel

    2016-12-01

    The purpose of the paper is to assess the groundwater quality near the landfill sites using landfill water pollution index (LWPI). In order to investigate the scale of groundwater contamination, three landfills (E, H and S) in different stages of their operation were taken into analysis. Samples of groundwater in the vicinity of studied landfills were collected four times each year in the period from 2004 to 2014. A total of over 300 groundwater samples were analysed for pH, EC, PAH, TOC, Cr, Hg, Zn, Pb, Cd, Cu, as required by the UE legal acts for landfill monitoring system. The calculated values of the LWPI allowed the quantification of the overall water quality near the landfill sites. The obtained results indicated that the most negative impact on groundwater quality is observed near the old Landfill H. Improper location of piezometer at the Landfill S favoured infiltration of run-off from road pavement into the soil-water environment. Deep deposition of the groundwater level at Landfill S area reduced the landfill impact on the water quality. Conducted analyses revealed that the LWPI can be used for evaluation of water pollution near a landfill, for assessment of the variability of water pollution with time and for comparison of water quality from different piezometers, landfills or time periods. The applied WQI (Water Quality Index) can also be an important information tool for landfill policy makers and the public about the groundwater pollution threat from landfill.

  5. Weapons engineering tritium facility overview

    Energy Technology Data Exchange (ETDEWEB)

    Najera, Larry [Los Alamos National Laboratory

    2011-01-20

    Materials provide an overview of the Weapons Engineering Tritium Facility (WETF) as introductory material for January 2011 visit to SRS. Purpose of the visit is to discuss Safety Basis, Conduct of Engineering, and Conduct of Operations. WETF general description and general GTS program capabilities are presented in an unclassified format.

  6. Generation of gaseous tritium standards

    International Nuclear Information System (INIS)

    Hohorst, F.A.

    1994-09-01

    The determination of aqueous and non-aqueous tritium in gaseous samples is one type of determination often requested of radioanalytical laboratories. This determination can be made by introducing the sample as a gas into a sampling train containing two silica gel beds separated by.a catalytic oxidizer bed. The first bed traps tritiated water. The sample then passes into and through the oxidizer bed where non-aqueous tritium containing species are oxidized to water and other products of combustion. The second silica gel bed then traps the newly formed tritiated water. Subsequently, silica gel is removed to plastic bottles, deionized water is added, and the mixture is permitted to equilibrate. The tritium content of the equilibrium mixture is then determined by conventional liquid scintillation counting (LSC). For many years, the moisture content of inert, gaseous samples has been determined using monitors which quantitatively electrolyze the moisture present after that moisture has been absorbed by phosphorous pentoxide or other absorbents. The electrochemical reaction is quantitative and definitive, and the energy consumed during electrolysis forms the basis of the continuous display of the moisture present. This report discusses the experimental evaluation of such a monitor as the basis for a technique for conversion of small quantities of SRMs of tritiated water ( 3 HOH) into gaseous tritium standards ( 3 HH)

  7. Tritium-labelled abscisic acid

    International Nuclear Information System (INIS)

    Pluciennik, H.; Michalski, L.

    1991-01-01

    A simple method for the preparation of biologically active abscisic acid (growth inhibiting plant hormone) labelled with tritium is described. The product obtained has a specific radioactivity of 1.12 GBq mmol -1 : the yield is about 60% as compared to the initial amount of the substance used. (author) 7 refs.; 2 figs

  8. Tritium Level in Romanian Precipitation

    Energy Technology Data Exchange (ETDEWEB)

    Varlam, C.; Stefanescu, I.; Faurescu, I.; Bogdan, D.; Soare, A. [Institute for Cryogenic and Isotope Technologies, Rm. Valcea (Romania); Duliu, O. G. [Faculty of Physics, University of Bucharest, Magurele (Romania)

    2013-07-15

    Romania is one of the countries that has no station included in GNIP (Global Network of Isotopes in Precipitation) on its territory. This paper presents results regarding the tritium concentration in precipitation for the period 1999-2009. The precipitation fell at the Institute for cryogenic and Isotope technologies (geographical coordinates: altitude 237 m, latitude 45{sup o}02'07' N, longitude 24{sup o}17'03' E) an was collected both individually and as a composite average of each month. It was individually measured and the average was calculated and compared with the tritium concentration measured in the composite sample. tritium concentration levels ranged from 9.9 {+-} 2.1 TU for 2004 and 13.7 {+-} 2.2 TU for 2009. Comparing the arithmetic mean values with the weighted mean for the period of observation, it was noticed that the higher absolute values of the weighted means were constant. It was found that for the calculated monthly average for the period of observation (1999-2009), the months with the maximum tritium concentration are the same as the months with the maximum amount of precipitation. This behaviour is typical for the monitored location. (author)

  9. Tritium transport analysis for CFETR WCSB blanket

    Energy Technology Data Exchange (ETDEWEB)

    Zhao, Pinghui, E-mail: phzhao@mail.ustc.edu.cn; Yang, Wanli; Li, Yuanjie; Ge, Zhihao; Nie, Xingchen; Gao, Zhongping

    2017-01-15

    Highlights: • A simplified tritium transport model for CFETR WCSB blanket was developed. • Tritium transport process in CFETR WCSB blanket was analyzed. • Sensitivity analyses of tritium transport parameters were carried out. - Abstract: Water Cooled Solid Breeder (WCSB) blanket was put forward as one of the breeding blanket candidate schemes for Chinese Fusion Engineering Test Reactor (CFETR). In this study, a simplified tritium transport model was developed. Based on the conceptual engineering design, neutronics and thermal-hydraulic analyses of CFETR WCSB blanket, tritium transport process was analyzed. The results show that high tritium concentration and inventory exist in primary water loop and total tritium losses exceed CFETR limits under current conditions. Conducted were sensitivity analyses of influential parameters, including tritium source, temperature, flow-rate capacity and surface condition. Tritium performance of WCSB blanket can be significantly improved under a smaller tritium impinging rate, a larger flow-rate capacity or a better surface condition. This work provides valuable reference for the enhancement of tritium transport behavior in CFETR WCSB blanket.

  10. Tritium behavior intentionally released in the room

    International Nuclear Information System (INIS)

    Kobayashi, K.; Hayashi, T.; Iwai, Y.; Yamanishi, T.; Willms, R. S.; Carlson, R. V.

    2008-01-01

    To construct a fusion reactor with high safety and acceptability, it is necessary to establish and to ensure tritium safe handling technology. Tritium should be well-controlled not to be released to the environment excessively and to prevent workers from excess exposure. It is especially important to grasp tritium behavior in the final confinement area, such as the room and/or building. In order to obtain data for actual tritium behavior in a room and/or building, a series of intentional Tritium Release Experiments (TREs) were planned and carried out within a radiologically controlled area (main cell) at Tritium System Test Assembly (TSTA) in Los Alamos National Laboratory (LANL) under US-JAPAN collaboration program. These experiments were carried out three times. In these experiments, influence of a difference in the tritium release point and the amount of hydrogen isotope for the initial tritium behavior in the room were suggested. Tritium was released into the main cell at TSTA/LANL. The released tritium reached a uniform concentration about 30 - 40 minutes in all the experiments. The influence of the release point and the amount of hydrogen isotope were not found to be important in these experiments. The experimental results for the initial tritium behavior in the room were also simulated well by the modified three-dimensional eddy flow analysis code FLOW-3D. (authors)

  11. Tritium migration in nuclear desalination plants

    International Nuclear Information System (INIS)

    Muralev, E.D.

    2003-01-01

    Tritium transport, as one of important items of radiation safety assessment, should be taken into consideration before construction of a Nuclear Desalination Plant (NDP). The influence of tritium internal exposition to the human body is very dangerous because of 3 H associations with water molecules. The problem of tritium in nuclear engineering is connected to its high penetration ability (through fuel element cans and other construction materials of a reactor), with the difficulty of extracting tritium from process liquids and gases. Sources of tritium generation in NDP are: nuclear fuel, boron in control rods, and deuterium in heat carrier. Tritium passes easily through the walls of a reactor vessel, intermediate heat exchangers, steam generators and other technological equipment, through the walls of heat carrier pipelines. The release of tritium and its transport could be assessed, using mathematical models, based on the assumption that steady state equilibrium has been attained between the sources of tritium, produced water and release to the environment. Analysis of the model shows the tritium concentration dependence in potable water on design features of NDP. The calculations obtained and analysis results for NDP with BN-350 reactor give good convergence. According to the available data, tritium concentration in potable water is less than the statutory maximum concentration limit. The design of a NDP requires elaboration of technical solutions, capable of minimising the release of tritium to potable water produced. (author)

  12. Storage and Assay of Tritium in STAR

    International Nuclear Information System (INIS)

    Longhurst, Glen R.; Anderl, Robert A.; Pawelko, Robert J.; Stoots, Carl J.

    2005-01-01

    The Safety and Tritium Applied Research (STAR) facility at the Idaho National Engineering and Environmental Laboratory (INEEL) is currently being commissioned to investigate tritium-related safety questions for fusion and other technologies. The tritium inventory for the STAR facility will be maintained below 1.5 g to avoid the need for STAR to be classified as a Category 3 nuclear facility. A key capability in successful operation of the STAR facility is the ability to receive, inventory, and dispense tritium to the various experiments underway there. The system central to that function is the Tritium Storage and Assay System (SAS).The SAS has four major functions: (1) receiving and holding tritium, (2) assaying, (3) dispensing, and (4) purifying hydrogen isotopes from non-hydrogen species.This paper describes the design and operation of the STAR SAS and the procedures used for tritium accountancy in the STAR facility

  13. Tritium pellet injection sequences for TFTR

    International Nuclear Information System (INIS)

    Houlberg, W.A.; Milora, S.L.; Attenberger, S.E.; Singer, C.E.; Schmidt, G.L.

    1983-01-01

    Tritium pellet injection into neutral deuterium, beam heated deuterium plasmas in the Tokamak Fusion Test Reactor (TFTR) is shown to be an attractive means of (1) minimizing tritium use per tritium discharge and over a sequence of tritium discharges; (2) greatly reducing the tritium load in the walls, limiters, getters, and cryopanels; (3) maintaining or improving instantaneous neutron production (Q); (4) reducing or eliminating deuterium-tritium (D-T) neutron production in non-optimized discharges; and (5) generally adding flexibility to the experimental sequences leading to optimal Q operation. Transport analyses of both compression and full-bore TFTR plasmas are used to support the above observations and to provide the basis for a proposed eight-pellet gas gun injector for the 1986 tritium experiments

  14. Imaging of tritium implanted into graphite

    International Nuclear Information System (INIS)

    Malinowski, M.E.; Causey, R.A.

    1988-01-01

    The extensive use of graphite in plasma-facing surfaces of tokamaks such as the Tokamak Fusion Test Reactor, which has planned tritium discharges, makes two-dimensional tritium detection techniques important in helping to determine torus tritium inventories. We have performed experiments in which highly oriented pyrolytic graphite (HOPG) samples were first tritium implanted with fluences of ∼10 16 T/cm 2 at energies approx. 0 C resulted in no discernible motion of tritium along the basal plane, but did show that significant desorption of the implanted tritium occurred. The current results indicate that tritium in quantities of 10 12 T/cm 2 in tritiated components could be readily detected by imaging at lower magnifications

  15. Calculation of tritium release from reactor's stack

    International Nuclear Information System (INIS)

    Akhadi, M.

    1996-01-01

    Method for calculation of tritium release from nuclear to environment has been discussed. Part of gas effluent contain tritium in form of HTO vapor released from reactor's stack was sampled using silica-gel. The silica-gel was put in the water to withdraw HTO vapor absorbed by silica-gel. Tritium concentration in the water was measured by liquid scintillation counter of Aloka LSC-703. Tritium concentration in the gas effluent and total release of tritium from reactor's stack during certain interval time were calculated using simple mathematic formula. This method has examined for calculation of tritium release from JRR-3M's stack of JAERI, Japan. From the calculation it was obtained the value of tritium release as much as 4.63 x 10 11 Bq during one month. (author)

  16. Tritium systems test assembly stabilization

    International Nuclear Information System (INIS)

    Jasen, William G.; Michelotti, Roy A.; Anast, Kurt R.; Tesch, Charles

    2004-01-01

    The Tritium Systems Test Assembly (TSTA) was a facility dedicated to tritium technology Research and Development (R and D) primarily for future fusion power reactors. The facility was conceived in mid 1970's, operations commenced in early 1980's, stabilization and deactivation began in 2000 and were completed in 2003. The facility will remain in a Surveillance and Maintenance (S and M) mode until the Department of Energy (DOE) funds demolition of the facility, tentatively in 2009. A safe and stable end state was achieved by the TSTA Facility Stabilization Project (TFSP) in anticipation of long term S and M. At the start of the stabilization project, with an inventory of approximately 140 grams of tritium, the facility was designated a Hazard Category (HC) 2 Non-Reactor Nuclear facility as defined by US Department of Energy standard DOE-STD-1027-92 (1997). The TSTA facility comprises a laboratory area, supporting rooms, offices and associated laboratory space that included more than 20 major tritium handling systems. The project's focus was to reduce the tritium inventory by removing bulk tritium, tritiated water wastes, and tritium-contaminated high-inventory components. Any equipment that remained in the facility was stabilized in place. All of the gloveboxes and piping were rendered inoperative and vented to atmosphere. All equipment, and inventoried tritium contamination, remaining in the facility was left in a safe-and-stable state. The project used the End Points process as defined by the DOE Office of Environmental Management (web page http://www.em.doe.- gov/deact/epman.htmtlo) document and define the end state required for the stabilization of TSTA Facility. The End Points process added structure that was beneficial through virtually all phases of the project. At completion of the facility stabilization project the residual tritium inventory was approximately 3,000 curies, considerably less than the 1.6-gram threshold for a HC 3 facility. TSTA is now

  17. Emissions from the Bena Landfill

    Science.gov (United States)

    Schafer, C.; Blake, D. R.; Hughes, S.

    2016-12-01

    In 2013, Americans generated 254 million tons of municipal solid waste (MSW). The gas generated from the decomposition of MSW is composed of approximately 50% methane, 50% carbon dioxide, and a small proportion of non-methane organic compounds (NMOCs). NMOCs constitute less than 1% of landfill emissions, but they can have a disproportionate environmental impact as they are highly reactive ozone precursors. During the 2016 Student Airborne Research Program (SARP), whole air samples were collected at the Bena landfill outside of Bakersfield, CA and throughout Bakersfield and analyzed using gas chromatography in order to quantify NMOC emissions. This area was determined to have elevated concentrations of benzene, trichloroethylene, and tetrachloroethylene, all of which are categorized by the EPA as hazardous to human health. Benzene was found to have a concentration of 145 ± 4 pptv, four times higher than the background levels in Bakersfield (36 ± 1 pptv). Trichloroethylene and tetrachloroethylene had concentrations of 18 ± 1 pptv and 31 ± 1 pptv which were 18 and 10 times greater than background concentrations, respectively. In addition, hydroxyl radical reactivity (ROH) was calculated to determine the potential for tropospheric ozone formation. The total ROH of the landfill was 7.5 ± 0.2 s-1 compared to total background ROH of 1.0 ± 0.1 s-1 . NMOCs only made up 0.6% of total emissions, but accounted for 67% of total ROH.These results can help to shape future landfill emission policies by highlighting the importance of NMOCs in addition to methane. More research is needed to investigate the ozone forming potential of these compounds at landfills across the country.

  18. Tritium issues in plasma wall interactions

    International Nuclear Information System (INIS)

    Tanabe, T.

    2009-01-01

    In order to establish a D-T fusion reactor as an energy source, it is not enough to have a DT burning plasma, and economical conversion of fusion energy to electricity and/or heat, a large enough margin of tritium breeding and tritium safety must be simultaneously achieved. In particular, handling of huge amount of tritium needs a significant effort to ensure that the radiation dose of radiological workers and of the public is below the limits specified by the International Commission on Radiological Protection. For the safety reasons, tritium in a reactor will be limited to only a few kg orders in weight, with radioactivity up to 10 17 Bq. Since public exposure to tritium is regulated at a level as tiny as a few Bq/cm 2 , tritium must be strictly confined in a reactor system with accountancy of an order of pg (pico-gram). Generally qualitative analysis with the accuracy of more than 3 orders of magnitude is hardly possible. We are facing to lots of safety concerns in the handling of huge amounts of radioactive tritium as a fuel and to be bred in a blanket. In addition, tritium resources are very limited. Not only for the safety reason but also for the saving of tritium resources, tritium retention in a reactor must be kept as small as possible. In the present tokamaks, however, hydrogen retention is significantly large, i.e. more than 20% of fueled hydrogen is continuously piled up in the vacuum vessel, which must not be allowed in a reactor. After the introduction of tritium as a hydrogen radioisotope, this lecture will present tritium issues in plasma wall interactions, in particular, fueling, retention and recovering, considering the handling of large amounts of tritium, i.e. confinement, leakage, contamination, permeation, regulations and tritium accountancy. Progress in overcoming such problems will be also presented. This document is made of the slides of the presentation. (author)

  19. Methane production from food waste leachate in laboratory-scale simulated landfill.

    Science.gov (United States)

    Behera, Shishir Kumar; Park, Jun Mo; Kim, Kyeong Ho; Park, Hung-Suck

    2010-01-01

    Due to the prohibition of food waste landfilling in Korea from 2005 and the subsequent ban on the marine disposal of organic sludge, including leachate generated from food waste recycling facilities from 2012, it is urgent to develop an innovative and sustainable disposal strategy that is eco-friendly, yet economically beneficial. In this study, methane production from food waste leachate (FWL) in landfill sites with landfill gas recovery facilities was evaluated in simulated landfill reactors (lysimeters) for a period of 90 d with four different inoculum-substrate ratios (ISRs) on volatile solid (VS) basis. Simultaneous biochemical methane potential batch experiments were also conducted at the same ISRs for 30 d to compare CH(4) yield obtained from lysimeter studies. Under the experimental conditions, a maximum CH(4) yield of 0.272 and 0.294 L/g VS was obtained in the batch and lysimeter studies, respectively, at ISR of 1:1. The biodegradability of FWL in batch and lysimeter experiments at ISR of 1:1 was 64% and 69%, respectively. The calculated data using the modified Gompertz equation for the cumulative CH(4) production showed good agreement with the experimental result obtained from lysimeter study. Based on the results obtained from this study, field-scale pilot test is required to re-evaluate the existing sanitary landfills with efficient leachate collection and gas recovery facilities as engineered bioreactors to treat non-hazardous liquid organic wastes for energy recovery with optimum utilization of facilities. 2010 Elsevier Ltd. All rights reserved.

  20. Sanitary-epidemiologic service in Perm region: 95th anniversary (dedicated to Russian Sanitary-epidemiologic service

    Directory of Open Access Journals (Sweden)

    V.G. Kostarev

    2017-09-01

    Full Text Available The paper outlines the first stages of sanitary activities development in Perm region. We highlight the fact that it was Perm where I.I. Molessson, the first official sanitary inspector in Russia, worked. Here one of the first sanitary inspection of a whole region was performed and "Perm sanitary bulletin" was first published. It was in Perm, where the first sanitary office was established in 1890, and in 1898 the first bacteriological laboratory was organized. Bodies and institutions of Rospotrebnadzor in Perm region are known to be founded on September 15, 1922, when a Decree by Russian People's Commissars Council "On the Republic's sanitary bodies" was issued. A sanitary-hygienic faculty of Perm Medical Institute was set up in 1931 and it gave grounds for preparing qualified sanitary inspectors for state sanitary authorities. We described basic tasks which were tackled by sanitary inspectors during the Great Patriotic War and just after it. Rospotrebnadzor activities are proved to make for substantial improvements of sanitary-epidemiologic situation in the region. Currently more than 95 % of population are provided with drinking water which fully corresponds to the sanitary legislation requirements. We note constant improvements in catering objects quality and we also see that a quantity of food samples taken at such objects which don't correspond to hygienic standards remains stably low. A share of working places deviating from hygienic standards as per noise, vibration, and illumination, has reduced. Medical examinations are now available to 97.9 % of workers functioning under hazardous (dangerous working conditions. The lowest occupa-tional morbidity level over the last few years was registered in Perm region in 2016. The Service was among the first in the country to transfer to result-oriented budgeting and risk-oriented surveillance model. Organizational structure is constantly being developed; new legal, economic and organizational

  1. Analysis on tritium permeation in tritium storage bed with gas flowing calorimetry

    Energy Technology Data Exchange (ETDEWEB)

    Nakamura, Hirofumi; Hayashi, Takumi; Suzuki, Takumi; Nishi, Masataka [Japan Atomic Energy Research Inst., Naka Fusion Research Establishment, Department of Fusion Engineering Research, Naka, Ibaraki (Japan); Yoshida, Hiroshi [Japan Atomic Energy Research Inst., Naka Fusion Research Establishment, ITER-Joint Centeral Team, Naka, Ibaraki (Japan)

    2000-10-01

    Tritium permeation amount in a tritium storage bed with gas flowing calorimetric was evaluated under a condition of new operation mode for International Thermonuclear Experimental Reactor (ITER). As a result, tritium permeation under the new operation mode was estimated to be about twice of that under the practical operation mode. This result show that it would be regardless in a view point of material control of tritium, however, it was suggested to be required additional tritium removal or evacuate system in a view points of safety control or performance of accountability or thermal insulating of the tritium storage bed. (author)

  2. Tritium transport studies with use of the ISEP NPA during tritium trace experimental campaign on JET

    International Nuclear Information System (INIS)

    Mironov, M I; Afanasyev, V I; Murari, A; Santala, M; Beaumont, P

    2010-01-01

    The neutral particle analyzer (NPA) known as ISEP (Ion SEParator) was applied to measure the tritium neutral flux during the tritium trace experiment (TTE) on JET. The energy dependence (in the 5-28 keV energy range) of the tritium neutral flux rise time after a short ∼100 ms tritium gas puff into deuterium plasmas has been observed for the first time. The dependence has been interpreted as being due to the penetration of the tritium ions from the plasma boundary into the core and has been used for the calculation of the tritium diffusion coefficient and convective velocity values.

  3. Tritium confinement in a new tritium processing facility at the Savannah River Site

    International Nuclear Information System (INIS)

    Heung, L.K.; Owen, J.H.; Hsu, R.H.; Hashinger, R.F.; Ward, D.E.; Bandola, P.E.

    1991-01-01

    A new tritium processing facility, named the Replacement Tritium Facility (RTF), has been completed and is being prepared for startup at the Savannah River Site (SRS). The RTF has the capability to recover, purify and separate hydrogen isotopes from recycled gas containers. A multilayered confinement system is designed to reduce tritium losses to the environment. This confinement system is expected to confine and recover any tritium that might escape the process equipment, and to maintain the tritium concentration in the nitrogen glovebox atmosphere to less than 10 -2 μCi/cc tritium

  4. Factors associated with sanitary conditions of food and drinking ...

    African Journals Online (AJOL)

    Introduction: Food borne illness has been a global challenge and it persisted as a ... an absence of sanitary facilities for waste management was major cause. ... inspection on the establishments to promote and ensure proper hygiene and ...

  5. Simulated evapotranspiration from a landfill irrigated with landfill leachate

    International Nuclear Information System (INIS)

    Aronsson, P.

    1996-01-01

    Evapotranspiration from a landfill area, irrigated with leachate water, was simulated with the SOIL model. Three different types of vegetation (bare soil, grass ley, and willow) were used both with and without irrigation. The highest simulated evapotranspiration (604 mm) during the growing season was found from an irrigated willow stand with a high interception capacity. The lowest evapotranspiration (164 mm) was found from the bare soil. The relatively high evapotranspiration from the willow was probably caused by the high LAI (Leaf Area Index) and the low aerodynamic resistance within the willow stand. The results indicate that it is possible to reduce most of the leakage water from a landfill by irrigation of willow stands. 9 refs, 4 figs, 1 tab

  6. Imaging and characterization of heterogeneous landfills using geophysical methods

    NARCIS (Netherlands)

    Konstantaki, L.A.

    2016-01-01

    Nowadays many countries use landfilling for the management of their waste or for treating old landfills. Emissions from landfills can be harmful to the environment and to human health, making the stabilization of landfills a priority for the landfill communities. Estimation of the emission potential

  7. Reductive dechlorination of chlorinated solvents in landfills

    International Nuclear Information System (INIS)

    Wang, J.Y.; Wu, C.

    2002-01-01

    The use of landfills as an in situ biological treatment system represents an alternative for source area remediation with a significant cost saving. The specific objective of this research is to investigate the intrinsic bioattenuation capacity of the landfill ecosystem for chlorinated aliphatic hydrocarbons (CAHs). The research was conducted in two complementary systems: simulated landfill bioreactors and batch degradation experiment in serum bottles. Refuse samples excavated from a landfill were tested in laboratory bioreactors designed and operated to facilitate refuse decomposition under landfilling conditions. Each bioreactor was operated with leachate recirculation and gas collection. Target CAHs, tetrachloroethene (PCE) and trichloroethene (TCE), were added to selected reactors and maintained at 20 μM each in leachate to simulate the effect of long-term exposure of refuse microorganisms to CAHs on the degradation potential of these chemicals in landfills. At two different stages of refuse decomposition, active refuse decomposition representing young landfills and maturation phase representing aged landfills, anaerobic microbial cultures were derived from selected bioreactors and tested in serum bottles for their abilities to biodegrade target CAHs. Results of this study suggest that landfills have an intrinsic reductive dechlorination capacity for PCE and TCE. The decomposition of refuse, a source of complex organics, enhances reductive dechlorination by the refuse cultures tested in this study. In addition, the test results suggest that it may be possible to develop engineering strategies to promote both CAHs degradation and refuse decomposition in landfills. (author)

  8. Comparison of the sanitary effects of energy chains. Methodological aspects

    International Nuclear Information System (INIS)

    Fagnani, F.

    1979-01-01

    Beyond technical and economical matters, the development of an industrial technology involves more or less numerous indirect consequences. From this viewpoint, the author analysis the methodological problems raised in evaluating the sanitary and ecological problems of the different energy-producing lines and considers successively the matter of technical interdependences, protection and safety regulations and selection of sites, classification of risks and measuring problems in relation to sanitary effects [fr

  9. Landfill reduction experience in The Netherlands.

    Science.gov (United States)

    Scharff, Heijo

    2014-11-01

    Modern waste legislation aims at resource efficiency and landfill reduction. This paper analyses more than 20 years of landfill reduction in the Netherlands. The combination of landfill regulations, landfill tax and landfill bans resulted in the desired landfill reduction, but also had negative effects. A fierce competition developed over the remaining waste to be landfilled. In 2013 the Dutch landfill industry generated €40 million of annual revenue, had €58 million annual costs and therefore incurred an annual loss of €18 million. It is not an attractive option to prematurely end business. There is a risk that Dutch landfill operators will not be able to fulfil the financial obligations for closure and aftercare. Contrary to the polluter pays principle the burden may end up with society. EU regulations prohibiting export of waste for disposal are in place. Strong differentials in landfill tax rate between nations have nevertheless resulted in transboundary shipment of waste and in non-compliance with the self-sufficiency and proximity principles. During the transformation from a disposal society to a recycling society, it is important to carefully plan required capacity and to guide the reorganisation of the landfill sector. At some point, it is no longer profitable to provide landfill services. It may be necessary for public organisations or the state to take responsibility for the continued operation of a 'safety net' in waste management. Regulations have created a financial incentive to pass on the burden of monitoring and controlling the impact of waste to future generations. To prevent this, it is necessary to revise regulations on aftercare and create incentives to actively stabilise landfills. Copyright © 2014 Elsevier Ltd. All rights reserved.

  10. Tritium sorption by cement and subsequent release

    International Nuclear Information System (INIS)

    Ono, F.; Yamawaki, M.

    1995-01-01

    In a fusion reactor or tritium-handling facilities, contamination of concrete by tritium and subsequent release from it to the reator or experimental room is a matter of problem for safe control of tritium and management of operational environment. In order to evaluate this tritium behavior, interaction of tritiated water with concrete or cement should be clarified. In the present study, HTO sorption and subsequent release from cement were experimentally studied.(1)Sorption experiments were conducted using columns packed with cement particles of different sizes. From the analysis of the breakthrough curve, tritium diffusivity in macropores and microparticles were evaluated.(2)From the short-term tritium release experiments, effective desorption rate constants were evaluated and the effects of temperature and moisture were studied.(3)In the long-term tritium release experiments to 6000h, the tritium release mechanism was found to be composed of three kinds of water: initially from capillary water, and in the second stage from gel water and from the water in the cement crystal.(4)Tritium release behavior by heat treatment to 800 C was studied. A high temperature above 600 C was required for the tritium trapped in the crystal water to be released. (orig.)

  11. The LLNL portable tritium processing system

    International Nuclear Information System (INIS)

    Anon.

    1995-01-01

    The end of the Cold War significantly reduced the need for facilities to handle radioactive materials for the US nuclear weapons program. The LLNL Tritium Facility was among those slated for decommissioning. The plans for the facility have since been reversed, and it remains open. Nevertheless, in the early 1990s, the cleanup (the Tritium Inventory Removal Project) was undertaken. However, removing the inventory of tritium within the facility and cleaning up any pockets of high-level residual contamination required that we design a system adequate to the task and meeting today's stringent standards of worker and environmental protection. In collaboration with Sandia National Laboratory and EG ampersand G Mound Applied Technologies, we fabricated a three-module Portable Tritium Processing System (PTPS) that meets current glovebox standards, is operated from a portable console, and is movable from laboratory to laboratory for performing the basic tritium processing operations: pumping and gas transfer, gas analysis, and gas-phase tritium scrubbing. The Tritium Inventory Removal Project is now in its final year, and the portable system continues to be the workhorse. To meet a strong demand for tritium services, the LLNL Tritium Facility will be reconfigured to provide state-of-the-art tritium and radioactive decontamination research and development. The PTPS will play a key role in this new facility

  12. The Chalk River Tritium Extraction Plant

    International Nuclear Information System (INIS)

    Holtslander, W.J.; Harrison, T.E.; Spagnolo, D.A.

    1990-01-01

    The Chalk River Tritium Extraction Plant for removal of tritium from heavy water is described. Tritium is present in the heavy water from research reactors in the form of DTO at a concentration in the range of 1-35 Ci/kg. It is removed by a combination of catalytic exchange to transfer the tritium from DTO to DT, followed by cryogenic distillation to separate and concentrate the tritium to T 2 . The tritium product is reacted with titanium and packaged for transportation and storage as titanium tritide. The plant processes heavy water at a rate of 25 kg/h and removes 80% of the tritium and 90% of the protium per pass. Catalytic exchange is carried out in the liquid phase using a proprietary wetproofed catalyst. The plant serves two roles in the Canadian fusion program: it produces pure tritium for use in fusion research and development, and it demonstrates on an industrial scale many of the tritium technologies that are common to the tritium systems in fusion reactors (author)

  13. The Chalk River Tritium Extraction Plant

    Energy Technology Data Exchange (ETDEWEB)

    Holtslander, W J; Harrison, T E; Spagnolo, D A

    1990-07-01

    The Chalk River Tritium Extraction Plant for removal of tritium from heavy water is described. Tritium is present in the heavy water from research reactors in the form of DTO at a concentration in the range of 1-35 Ci/kg. It is removed by a combination of catalytic exchange to transfer the tritium from DTO to DT, followed by cryogenic distillation to separate and concentrate the tritium to T{sub 2}. The tritium product is reacted with titanium and packaged for transportation and storage as titanium tritide. The plant processes heavy water at a rate of 25 kg/h and removes 80% of the tritium and 90% of the protium per pass. Catalytic exchange is carried out in the liquid phase using a proprietary wetproofed catalyst. The plant serves two roles in the Canadian fusion program: it produces pure tritium for use in fusion research and development, and it demonstrates on an industrial scale many of the tritium technologies that are common to the tritium systems in fusion reactors (author)

  14. Estimation of Biological Effects of Tritium.

    Science.gov (United States)

    Umata, Toshiyuki

    2017-01-01

    Nuclear fusion technology is expected to create new energy in the future. However, nuclear fusion requires a large amount of tritium as a fuel, leading to concern about the exposure of radiation workers to tritium beta radiation. Furthermore, countermeasures for tritium-polluted water produced in decommissioning of the reactor at Fukushima Daiichi Nuclear Power Station may potentially cause health problems in radiation workers. Although, internal exposure to tritium at a low dose/low dose rate can be assumed, biological effect of tritium exposure is not negligible, because tritiated water (HTO) intake to the body via the mouth/inhalation/skin would lead to homogeneous distribution throughout the whole body. Furthermore, organically-bound tritium (OBT) stays in the body as parts of the molecules that comprise living organisms resulting in long-term exposure, and the chemical form of tritium should be considered. To evaluate the biological effect of tritium, the effect should be compared with that of other radiation types. Many studies have examined the relative biological effectiveness (RBE) of tritium. Hence, we report the RBE, which was obtained with radiation carcinogenesis classified as a stochastic effect, and serves as a reference for cancer risk. We also introduce the outline of the tritium experiment and the principle of a recently developed animal experimental system using transgenic mouse to detect the biological influence of radiation exposure at a low dose/low dose rate.

  15. Tritium inventories and tritium safety design principles for the fuel cycle of ITER

    International Nuclear Information System (INIS)

    Cristescu, I.R.; Cristescu, I.; Doerr, L.; Glugla, M.; Murdoch, D.

    2007-01-01

    Within the tritium plant of ITER a total inventory of about 2-3 kg will be necessary to operate the machine in the DT phase. During plasma operation, tritium will be distributed in the different sub-systems of the fuel cycle. A tool for tritium inventory evaluation within each sub-system of the fuel cycle is important with respect to both the process of licensing ITER and also for operation. It is very likely that measurements of total tritium inventories may not be possible for all sub-systems; however, tritium accounting may be achieved by modelling its hold-up within each sub-system and by validating these models in real-time against the monitored flows and tritium streams between the sub-systems. To get reliable results, an accurate dynamic modelling of the tritium content in each sub-system is necessary. A dynamic model (TRIMO) for tritium inventory calculation reflecting the design of each fuel cycle sub-systems was developed. The amount of tritium needed for ITER operation has a direct impact on the tritium inventories within the fuel cycle sub-systems. As ITER will function in pulses, the main characteristics that influence the rapid tritium recovery from the fuel cycle as necessary for refuelling are discussed. The confinement of tritium within the respective sub-systems of the fuel cycle is one of the most important safety objectives. The design of the deuterium/tritium fuel cycle of ITER includes a multiple barrier concept for the confinement of tritium. The buildings are equipped with a vent detritiation system and re-circulation type room atmosphere detritiation systems, required for tritium confinement barrier during possible tritium spillage events. Complementarily to the atmosphere detritiation systems, in ITER a water detritiation system for tritium recovery from various sources will also be operated

  16. The tritium content of precipitation and groundwater at Yola, Nigeria ...

    African Journals Online (AJOL)

    Tritium is a radioactive isotope of hydrogen which occurs in precipitation. In groundwater studies tritium measurements give information on the time of recharge to the system; the tritium content of precipitation being used to estimate the input of tritium to the groundwater system. At Yola, the tritium ontents in precipitation and ...

  17. Tritium in Exit Signs | RadTown USA | US EPA

    Science.gov (United States)

    2017-08-07

    Many exit signs contain tritium to light the sign without batteries or electricity. Using tritium in exit signs allows the sign to remain lit if the power goes out. Tritium is most dangerous when it is inhaled or swallowed. Never tamper with a tritium exit sign. If a tritium exit sign is broken, leave the area immediately and notify the building maintenance staff.

  18. Simulation of tritium behavior after intended tritium release in ventilated room

    International Nuclear Information System (INIS)

    Iwai, Yasunori; Hayashi, Takumi; Yamanishi, Toshihiko; Kobayashi, Kazuhiro; Nishi, Masataka

    2001-01-01

    At the Tritium Process Laboratory (TPL) at the Japan Atomic Energy Research Institute (JAERI), Caisson Assembly for Tritium Safety study (CATS) with 12 m 3 of large airtight vessel (Caisson) was fabricated for confirmation and enhancement of fusion reactor safety to estimate tritium behavior in the case where a tritium leak event should happen. One of the principal objectives of the present studies is the establishment of simulation method to predict the tritium behavior after the tritium leak event should happen in a ventilated room. The RNG model was found to be valid for eddy flow calculation in the 50 m 3 /h ventilated Caisson with acceptable engineering precision. The calculated initial and removal tritium concentration histories after intended tritium release were consistent with the experimental observations in the 50 m 3 /h ventilated Caisson. It is found that the flow near a wall plays an important role for the tritium transport in the ventilated room. On the other hand, tritium behavior intentionally released in the 3,000 m 3 of tritium handling room was investigated experimentally under a US-Japan collaboration. The tritium concentration history calculated with the same method was consistent with the experimental observations, which proves that the present developed method can be applied to the actual scale of tritium handling room. (author)

  19. Behaviour of tritium in the environment

    International Nuclear Information System (INIS)

    1979-01-01

    Full text: There is considerable interest in the behaviour of radionuclides of global character that may be released to the environment through the development of nuclear power. Tritium is of particular interest due to its direct incorporation into water and organic tissue. Although there has been a large decrease (more than ten times) in tritium concentration since the stopping of nuclear weapons tests in the atmosphere, the construction in the near future of many water reactors and in the far future of fusion reactors could increase the present levels. Progress has been made during recent years in the assessment of tritium distribution, in detection methods and in biological studies While several meetings have given scientists an opportunity to present papers on tritium, no specific symposium on this topic has been organized by the IAEA since 1961. Thus the purpose of the meeting was to review recent advances and to report on the practical aspects of tritium utilization and monitoring. The symposium was jointly organized with OECD/NEA, in co-operation with the US Department of Energy and the Lawrence Livermore Laboratory. Papers were presented on distribution of tritium, evaluation of future discharges, measurement of tritium, tritium in the aquatic environment, tritium in the terrestrial environment, tritium in man and monitoring of tritium Very interesting papers were given on distribution of tritium and participants got a good idea of the circulation of this radionuclide Some new data were provided on tritium pollution from luminous compounds and we learnt that the tritium release of the Swiss luminous compounds industry is of the same order of magnitude as the tritium release of Windscale. Projections indicate that, in the USA, the total quantity of tritium contained in discarded digital watches will be equal, approximately ten years in the future, to the release of nuclear power reactors Whereas nuclear reactor discharges are controlled there is no control

  20. Landfill reduction experience in The Netherlands

    International Nuclear Information System (INIS)

    Scharff, Heijo

    2014-01-01

    Highlights: • ‘Zero waste’ initiatives never consider risks, side effects or experience of achieved low levels of landfill. • This paper provides insight into what works and what not. • Where strong gradients in regulations and tax occur between countries, waste will find its way to landfills across borders. • Strong landfill reduction can create a fierce competition over the remaining waste to be landfilled resulting in losses. • At some point a public organisation should take responsibility for the operation of a ‘safety net’ in waste management. - Abstract: Modern waste legislation aims at resource efficiency and landfill reduction. This paper analyses more than 20 years of landfill reduction in the Netherlands. The combination of landfill regulations, landfill tax and landfill bans resulted in the desired landfill reduction, but also had negative effects. A fierce competition developed over the remaining waste to be landfilled. In 2013 the Dutch landfill industry generated €40 million of annual revenue, had €58 million annual costs and therefore incurred an annual loss of €18 million. It is not an attractive option to prematurely end business. There is a risk that Dutch landfill operators will not be able to fulfil the financial obligations for closure and aftercare. Contrary to the polluter pays principle the burden may end up with society. EU regulations prohibiting export of waste for disposal are in place. Strong differentials in landfill tax rate between nations have nevertheless resulted in transboundary shipment of waste and in non-compliance with the self-sufficiency and proximity principles. During the transformation from a disposal society to a recycling society, it is important to carefully plan required capacity and to guide the reorganisation of the landfill sector. At some point, it is no longer profitable to provide landfill services. It may be necessary for public organisations or the state to take responsibility for the

  1. Landfill reduction experience in The Netherlands

    Energy Technology Data Exchange (ETDEWEB)

    Scharff, Heijo, E-mail: h.scharff@afvalzorg.nl

    2014-11-15

    Highlights: • ‘Zero waste’ initiatives never consider risks, side effects or experience of achieved low levels of landfill. • This paper provides insight into what works and what not. • Where strong gradients in regulations and tax occur between countries, waste will find its way to landfills across borders. • Strong landfill reduction can create a fierce competition over the remaining waste to be landfilled resulting in losses. • At some point a public organisation should take responsibility for the operation of a ‘safety net’ in waste management. - Abstract: Modern waste legislation aims at resource efficiency and landfill reduction. This paper analyses more than 20 years of landfill reduction in the Netherlands. The combination of landfill regulations, landfill tax and landfill bans resulted in the desired landfill reduction, but also had negative effects. A fierce competition developed over the remaining waste to be landfilled. In 2013 the Dutch landfill industry generated €40 million of annual revenue, had €58 million annual costs and therefore incurred an annual loss of €18 million. It is not an attractive option to prematurely end business. There is a risk that Dutch landfill operators will not be able to fulfil the financial obligations for closure and aftercare. Contrary to the polluter pays principle the burden may end up with society. EU regulations prohibiting export of waste for disposal are in place. Strong differentials in landfill tax rate between nations have nevertheless resulted in transboundary shipment of waste and in non-compliance with the self-sufficiency and proximity principles. During the transformation from a disposal society to a recycling society, it is important to carefully plan required capacity and to guide the reorganisation of the landfill sector. At some point, it is no longer profitable to provide landfill services. It may be necessary for public organisations or the state to take responsibility for the

  2. Geosynthetic applications in landfill design

    International Nuclear Information System (INIS)

    Alshunnar, I.S.; Afifi, S.S.; Tiseo, B.

    1996-01-01

    Landfills are designed to contain waste and to provide protection against discharges of leachate into the environment. Main components of a landfill include a liner system, a leachate collection system, and a cover system. Traditional designs have typically incorporated clay soils for containment and sands with embedded piping for leachate collection. As a result of recent advances in design, geosynthetic materials are now widely used for components. While these materials present cost and feasibility advantages, they also pose significant challenges in stability evaluations, handing during installation, and quality assurance. This paper presents an overview of applications of geosynthetics in design and construction, including: Advantages, disadvantages, design criteria, possible economic benefits of various systems, and related construction considerations. 2 figs., 1 tab

  3. Coupling biofiltration process and electrocoagulation using magnesium-based anode for the treatment of landfill leachate.

    Science.gov (United States)

    Oumar, Dia; Patrick, Drogui; Gerardo, Buelna; Rino, Dubé; Ihsen, Ben Salah

    2016-10-01

    In this research paper, a combination of biofiltration (BF) and electrocoagulation (EC) processes was used for the treatment of sanitary landfill leachate. Landfill leachate is often characterized by the presence of refractory organic compounds (BOD/COD < 0.13). BF process was used as secondary treatment to remove effectively ammonia nitrogen (N-NH4 removal of 94%), BOD (94% removed), turbidity (95% removed) and phosphorus (more than 98% removed). Subsequently, EC process using magnesium-based anode was used as tertiary treatment. The best performances of COD and color removal from landfill leachate were obtained by applying a current density of 10 mA/cm(2) through 30 min of treatment. The COD removal reached 53%, whereas 85% of color removal was recorded. It has been proved that the alkalinity had a negative effect on COD removal during EC treatment. COD removal efficiencies of 52%, 41% and 27% were recorded in the presence of 1.0, 2.0 and 3.0 g/L of sodium bicarbonate (NaHCO3), respectively. Hydroxide ions produced at the cathode electrode reacted with the bicarbonate ions to form carbonates. The presence of bicarbonates in solution hampered the increase in pH, so that the precipitation of magnesium hydroxides could not take place to effectively remove organic pollutants. Copyright © 2016 Elsevier Ltd. All rights reserved.

  4. Treatability of stabilize landfill leachate by using pressmud ash as an adsorbent

    Science.gov (United States)

    Azme, N. N. Mohd; Murshed, M. F.

    2018-04-01

    Leachate is a liquid produced from the landfill that contains high concentration of heavy metals, chemicals and nutrient loading. The treatability of these contaminants are complicated since the current treatment technology are costly and site specific. Therefore, this study was conducted to evaluate the treatability of stabilized landfill leachate by using waste (pressmud ash) as an absorbent. Pressmud ash was prepared by burning at different temperature from 100 to 700 degree Celsius and test at 24 hours shaking time, pH 8, and 4000 rpm. Leachate samples were collected from municipal solid waste (MSW) Pulau Burung Sanitary Landfill (PBSL) and were analyzed for heavy metal, COD, ammonia and colour. This study was performed in two phases i) leachate characteristic, ii) treatability assessment by using pressmud ash. Pressmud was sampled from the sugar mill, Malaysian Sugar Manufacturing (MSM) Sdn Bhd, Seberang Perai, Pulau Pinang. The pressmud with 400°C are highly potential material with a low cost which can be a good adsorbent was capable reducing efficiencies of COD (60.76%), ammonia (64.37%) and colour (35.78%) from real wastewater leachate. Pressmud showed good sorption capability. Surface modification with burning greatly enhanced the reducing efficiency of sugar waste based adsorbent with adsorption efficiency.

  5. Quantification of methane emissions from danish landfills

    DEFF Research Database (Denmark)

    Scheutz, Charlotte; Mønster, Jacob; Kjeldsen, Peter

    2013-01-01

    Whole-landfill methane emission was quantified using a tracer technique that combines controlled tracer gas release from the landfill with time-resolved concentration measurements downwind of the landfill using a mobile high-resolution analytical instrument. Methane emissions from 13 Danish...... landfills varied between 2.6 and 60.8 kg CH4 h–1. The highest methane emission was measured at the largest (in terms of disposed waste amounts) of the 13 landfills, whereas the lowest methane emissions (2.6-6.1 kgCH4 h–1) were measured at the older and smaller landfills. At two of the sites, which had gas...... collection, emission measurements showed that the gas collection systems only collected between 30-50% of the methane produced (assuming that the produced methane equalled the sum of the emitted methane and the collected methane). Significant methane emissions were observed from disposed shredder waste...

  6. Landfilling: Bottom Lining and Leachate Collection

    DEFF Research Database (Denmark)

    Christensen, Thomas Højlund; Manfredi, Simone; Kjeldsen, Peter

    2011-01-01

    from entering the groundwater or surface water. The bottom lining system should cover the full footprint area of the landfill, including both the relatively flat bottom and the sideslopes in the case of an excavated configuration. This prevents the lateral migration of leachate from within the landfill...... triple) liners, are extremely effective in preventing leachate from entering into the environment. In addition, the risk of polluting the groundwater at a landfill by any leakage of leachate depends on several factors related to siting of the landfill: distance to the water table, distance to surface...... water bodies, and the properties of the soil beneath the landfill. In addition to the lining and drainage systems described in this chapter, the siting and hydrogeology of the landfill site (Chapter 10.12) and the top cover (Chapter 10.9) are also part of the barrier system, contributing to reducing...

  7. Landfill gas in the Dutch perspective

    International Nuclear Information System (INIS)

    Scheepers, M.J.J.

    1991-01-01

    Until 1986 landfill gas had a considerable value because of the relative high energy prices. It appeared also that landfill gas was formed in large quantities. However after the collapse of the energy prices in 1986 many new landfill gas projects were delayed or stopped. Recently, the gas emissions on landfills have attracted attention again, but now because of various environmental aspects. With respect to landfill management a well controlled gas extraction seems to be necessary. Utilisation of the gas is still favourable for economic reasons and because of energy savings. The Dutch policy for the next ten years will be reduction of the amount of waste by prevention and recycling. The organic fraction of the municipal solid waste (refuse from vegetables, fruit and garden), obtained by separation in households, will be composted. The other part will be burnt in incinerators. Only the remaining inert refuse will be deposited on landfills. (author)

  8. Development of a tritium monitor combined with an electrochemical tritium pump using a proton conducting oxide

    Energy Technology Data Exchange (ETDEWEB)

    Tanaka, M. [National Institute for Fusion Science, Toki, Gifu (Japan); Sugiyama, T. [Nagoya University, Fro-cho, Chikusa-ku, Nagoya (Japan)

    2015-03-15

    The detection of low level tritium is one of the key issues for tritium management in tritium handling facilities. Such a detection can be performed by tritium monitors based on proton conducting oxide technique. We tested a tritium monitoring system composed of a commercial proportional counter combined with an electrochemical hydrogen pump equipped with CaZr{sub 0.9}In{sub 0.1}O{sub 3-α} as proton conducting oxide. The hydrogen pump operated at 973 K under electrolysis conditions using tritiated water vapor (HTO). The proton conducting oxide extracts tritium molecules (HT) from HTO and tritium concentration is measured by the proportional counter. The advantage of the proposed tritium monitoring system is that it is able to convert HTO into molecular hydrogen.

  9. In-pile test of tritium release from tritium breeding materials (VOM-21H experiment)

    International Nuclear Information System (INIS)

    Kurasawa, Toshimasa; Takeshita, Hidefumi; Watanabe, Hitoshi; Yoshida, Hiroshi.

    1986-10-01

    Material development and blanket design of lithium-based ceramics such as lithium oxide, lithium aluminate, lithium silicate and lithium zirconate have been performed in Japan, United State of America and Europian Communities. Lithium oxide is a most attractive candidate for tritium breeding materials because of its high lithium density, high thermal conductivity and good tritium release performance. This work has been done to clarify the characteristics of tritium release and recovery from Li 2 O by means of in-situ tritium release measurement. The effects of temperature and sweep gas composition on the tritium release were investigated in this VOM-21H Experiment. Good measurement of tritium release was achieved but there were uncertainties in reproduciblity of data. The experimental results show that the role of surface adsorption/desorption makes a significant contribution to the tritium release and tritium inventory. Also, it is necessary to define the rate limiting process either diffusion or surface adsorption/desorption. (author)

  10. Tritium labelled steroids, preparation process and application to synthesis of tritium labelled estrane derivatives

    International Nuclear Information System (INIS)

    1978-01-01

    Process for preparing new steroids labelled with tritium in 6.7 and comprising in 3 a blocked ketonic group as ketal, thioketal or derivatives. Application of these products to the synthesis of tritium labelled estrane derivatives [fr

  11. Organization of setting-up sanitary pass-control regime and sanitary treatment of injured persons in case of radiation accidents

    International Nuclear Information System (INIS)

    Korostin, A.S.; Klochkov, V.N.; Yatsenko, V.N.

    1995-01-01

    The main aim of sanitary pass-control regime is to prevent propagation of radioactive contamination outside the area of emergency-rescue works and guarantee of sanitary treatment of all persons having radioactive contamination. The paper has studied the questions of organization of sanitary pass-control regime, arrangement of sanitary treatment of the injured persons and rendering first aid in case of radioactive contamination of wounds. 5 refs

  12. Radiological training for tritium facilities

    International Nuclear Information System (INIS)

    1996-12-01

    This program management guide describes a recommended implementation standard for core training as outlined in the DOE Radiological Control Manual (RCM). The standard is to assist those individuals, both within DOE and Managing and Operating contractors, identified as having responsibility for implementing the core training recommended by the RCM. This training may also be given to radiological workers using tritium to assist in meeting their job specific training requirements of 10 CFR 835

  13. Radiological training for tritium facilities

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1996-12-01

    This program management guide describes a recommended implementation standard for core training as outlined in the DOE Radiological Control Manual (RCM). The standard is to assist those individuals, both within DOE and Managing and Operating contractors, identified as having responsibility for implementing the core training recommended by the RCM. This training may also be given to radiological workers using tritium to assist in meeting their job specific training requirements of 10 CFR 835.

  14. Polyfluoroalkyl compounds in landfill leachates

    International Nuclear Information System (INIS)

    Busch, Jan; Ahrens, Lutz; Sturm, Renate; Ebinghaus, Ralf

    2010-01-01

    Polyfluoroalkyl compounds (PFCs) are widely used in industry and consumer products. These products could end up finally in landfills where their leachates are a potential source for PFCs into the aqueous environment. In this study, samples of untreated and treated leachate from 22 landfill sites in Germany were analysed for 43 PFCs. ΣPFC concentrations ranged from 31 to 12,819 ng/L in untreated leachate and 4-8060 ng/L in treated leachate. The dominating compounds in untreated leachate were perfluorobutanoic acid (PFBA) (mean contribution 27%) and perfluorobutane sulfonate (PFBS) (24%). The discharge of PFCs into the aqueous environment depended on the cleaning treatment systems. Membrane treatments (reverse osmosis and nanofiltrations) and activated carbon released lower concentrations of PFCs into the environment than cleaning systems using wet air oxidation or only biological treatment. The mass flows of ΣPFCs into the aqueous environment ranged between 0.08 and 956 mg/day. - The first comprehensive survey of polyfluoroalkyl compounds (PFCs) in landfill leachates.

  15. Landfill covers for dry environments

    International Nuclear Information System (INIS)

    Dwyer, S.F.

    1996-01-01

    A large-scale landfill cover field test is currently underway at Sandia National Laboratories in Albuquerque, New Mexico. It is intended to compare and document the performance of alternative landfill cover technologies of various costs and complexities for interim stabilization and/or final closure of landfills in arid and semi-arid environments. Test plots of traditional designs recommended by the US Environmental Protection Agency for both RCRA Subtitle open-quote C close-quote and open-quote D close-quote regulated facilities have been constructed side-by-side with the alternative covers and will serve as baselines for comparison to these alternative covers. The alternative covers were designed specifically for dry environments. The covers will be tested under both ambient and stressed conditions. All covers have been instrumented to measure water balance variables and soil temperature. An on-site weather station records all pertinent climatological data. A key to acceptance of an alternative environmental technology is seeking regulatory acceptance and eventual permitting. The lack of acceptance by regulatory agencies is a significant barrier to development and implementation of innovative cover technologies. Much of the effort on this demonstration has been toward gaining regulatory and public acceptance

  16. Tritium environmental transport studies at TFTR

    International Nuclear Information System (INIS)

    Ritter, P.D.; Dolan, T.J.; Longhurst, G.R.

    1993-01-01

    Environmental tritium concentrations will be measured near the Tokamak Fusion Test Reactor (TFTR) to help validate dynamic models of tritium transport in the environment. For model validation the database must contain sequential measurements of tritium concentrations in key environmental compartments. Since complete containment of tritium is an operational goal, the supplementary monitoring program should be able to glean useful data from an unscheduled acute release. Portable air samplers will be used to take samples automatically every 4 hours for a weak after an acute release, thus obtaining the time resolution needed for code validation. Samples of soil, vegetation, and foodstuffs will be gathered daily at the same locations as the active air monitors. The database may help validate the plant/soil/air part of tritium transport models and enhance environmental tritium transport understanding for the International Thermonuclear Experimental Reactor (ITER)

  17. Tritium environmental transport studies at TFTR

    Science.gov (United States)

    Ritter, P. D.; Dolan, T. J.; Longhurst, G. R.

    1993-06-01

    Environmental tritium concentrations will be measured near the Tokamak Fusion Test Reactor (TFTR) to help validate dynamic models of tritium transport in the environment. For model validation the database must contain sequential measurements of tritium concentrations in key environmental compartments. Since complete containment of tritium is an operational goal, the supplementary monitoring program should be able to glean useful data from an unscheduled acute release. Portable air samplers will be used to take samples automatically every 4 hours for a week after an acute release, thus obtaining the time resolution needed for code validation. Samples of soil, vegetation, and foodstuffs will be gathered daily at the same locations as the active air monitors. The database may help validate the plant/soil/air part of tritium transport models and enhance environmental tritium transport understanding for the International Thermonuclear Experimental Reactor (ITER).

  18. Purification of tritium-free water

    International Nuclear Information System (INIS)

    Hussain, S.D.

    1982-10-01

    Ground water which has been out of contact with the atmosphere for a long time as compared to the half life of tritium (12.43 years) does not contain any measureable amount of tritium. Such water is called tritium-free water. It may contain dissolved and suspended impurities and has to be purified before it can be used for the preparation of blanks and standards required in the routine measurement of low level tritium in water samples. The purification of tritium-free water by distillation in a closed system has been described. The quality of processed tritium-free water was precisely checked at International Atomic Energy Agency (IAEA) Vienna and found satisfactory. (authors)

  19. Modeling tritium transport in the environment

    International Nuclear Information System (INIS)

    Murphy, C.E. Jr.

    1986-01-01

    A model of tritium transport in the environment near an atmospheric source of tritium is presented in the general context of modeling material cycling in ecosystems. The model was developed to test hypotheses about the process involved in tritium cycling. The temporal and spatial scales of the model were picked to allow comparison to environmental monitoring data collected in the vicinity of the Savannah River Plant. Initial simulations with the model showed good agreement with monitoring data, including atmospheric and vegetation tritium concentrations. The model can also simulate values of tritium in vegetation organic matter if the key parameter distributing the source of organic hydrogen is varied to fit the data. However, because of the lack of independent conformation of the distribution parameter, there is still uncertainty about the role of organic movement of tritium in the food chain, and its effect on the dose to man

  20. Tritium Removal from Carbon Plasma Facing Components

    International Nuclear Information System (INIS)

    Skinner, C.H.; Coad, J.P.; Federici, G.

    2003-01-01

    Tritium removal is a major unsolved development task for next-step devices with carbon plasma-facing components. The 2-3 order of magnitude increase in duty cycle and associated tritium accumulation rate in a next-step tokamak will place unprecedented demands on tritium removal technology. The associated technical risk can be mitigated only if suitable removal techniques are demonstrated on tokamaks before the construction of a next-step device. This article reviews the history of codeposition, the tritium experience of TFTR (Tokamak Fusion Test Reactor) and JET (Joint European Torus) and the tritium removal rate required to support ITER's planned operational schedule. The merits and shortcomings of various tritium removal techniques are discussed with particular emphasis on oxidation and laser surface heating

  1. Comparison of Tritium Component Failure Rate Data

    International Nuclear Information System (INIS)

    Lee C. Cadwallader

    2004-01-01

    Published failure rate values from the US Tritium Systems Test Assembly, the Japanese Tritium Process Laboratory, the German Tritium Laboratory Karlsruhe, and the Joint European Torus Active Gas Handling System have been compared. This comparison is on a limited set of components, but there is a good variety of data sets in the comparison. The data compared reasonably well. The most reasonable failure rate values are recommended for use on next generation tritium handling system components, such as those in the tritium plant systems for the International Thermonuclear Experimental Reactor and the tritium fuel systems of inertial fusion facilities, such as the US National Ignition Facility. These data and the comparison results are also shared with the International Energy Agency cooperative task on fusion component failure rate data

  2. History of 232-F, tritium extraction processing

    International Nuclear Information System (INIS)

    Blackburn, G.W.

    1994-08-01

    In 1950 the Atomic Energy Commission authorized the Savannah River Project principally for the production of tritium and plutonium-239 for use in thermonuclear weapons. 232-F was built as an interim facility in 1953--1954, at a cost of $3.9M. Tritium extraction operations began in October, 1955, after the reactor and separations startups. In July, 1957 a larger tritium facility began operation in 232-H. In 1958 the capacity of 232-H was doubled. Also, in 1957 a new task was assigned to Savannah River, the loading of tritium into reservoirs that would be actual components of thermonuclear weapons. This report describes the history of 232-F, the process for tritium extraction, and the lessons learned over the years that were eventually incorporated into the new Replacement Tritium Facility

  3. Effects of interfering constituents on tritium smears

    International Nuclear Information System (INIS)

    Levi, G.D. Jr.; Cheeks, K.E.

    1993-01-01

    Tritium smears are performed by Health Protection Operations (HPO) to assess transferable contamination on work place surfaces, materials for movement outside Radiologically Controlled Areas (RCA), and product containers being shipped between facilities. Historically, gas proportional counters were used to detect transferable tritium contamination collected by smearing. Because tritium is a low-energy beta emitter, gas proportional counters do not provide the sensitivity or the counting efficiency to accurately measure the tritium activity on the smear. Liquid Scintillation Counters (LSC) provide greater counting efficiency for the low-energy beta particles along with greater reliability and reproducibility compared to gas flow proportional counters. The purpose of this technical evaluation was to determine the effects of interfering constituents such as filters, dirt and oil on the counting efficiency and tritium recoveries of tritium smears by LSC

  4. Experiments on tritium behavior in beryllium, (2)

    International Nuclear Information System (INIS)

    Ishitsuka, Etsuo; Kawamura, Hiroshi; Nakata, Hirokatsu; Sugai, Hiroyuki; Tanase, Masakazu.

    1990-02-01

    Beryllium has been used as the neutron reflector of material testing reactor and as the neutron multiplier for the fusion reactor lately. To study the tritium behavior in beryllium, we conducted the experiments, i.e., tritium release by recoil or diffusion by using the hot-pressed beryllium which had been produced both tritium and helium by neutron irradiation. From our experiments, we found that (1) amount of tritium production per one cycle irradiation (lasting 22 days) of JMTR is 10 mCi/g, (2) amount of tritium per surface area of hot-pressed beryllium released by recoil is 4 μCi/cm 2 , (3) diffusion coefficient of tritium in a temperature range of 800 ∼1180degC can be expressed with the following equation; D = 8.7 x 10 4 exp(-2.9x10 5 /R/T) cm 2 /s. (author)

  5. Regulating tritium in drinking water

    International Nuclear Information System (INIS)

    Fluke, R.

    1994-01-01

    This article incorporates an article by E. Koehl from an internal Ontario Hydro publication, and a letter from the Joint Committee of Health and Safety of the Royal Society of Canada and the Canadian Academy of Engineering, submitted to the Ontario Minister of the Environment and Energy. The Advisory Committee on Environmental Standards had recommended that the limit for tritium in Ontario drinking water be reduced from 40,000 to 100 Bq/L, with a further reduction to 20 in five years. Some facts and figures are adduced to show that the effect of tritium in drinking water in Ontario is negligible compared to the effect of background radiation. The risk from tritium to the people of Ontario is undetectably small, and the attempt to estimate this risk by linear extrapolation is extremely dubious. Regulation entails social and economic costs, and the government ought to ensure that the benefits exceed the costs. The costs translate into nothing less than wasted opportunity to save lives in other ways. 3 refs

  6. Tritium management in fusion reactors

    International Nuclear Information System (INIS)

    Galloway, T.R.

    1978-05-01

    This is a review paper covering the key environmental and safety issues and how they have been handled in the various magnetic and inertial confinement concepts and reference designs. The issues treated include: tritium accident analyses, tritium process control, occupational safety, HTO formation rate from the gas-phase, disposal of tritium contaminated wastes, and environmental impact--each covering the Joint European Tokamak (J.E.T. experiment), Tokamak Fusion Test Reactor (TFTR), Russian T-20, The Next Step (TNS) designs by Westinghouse/ORNL and General Atomic/ANL, the ANL and ORNL EPR's, the G.A. Doublet Demonstration Reactor, the Italian Fintor-D and the ORNL Demo Studies. There are also the following full scale plant reference designs: UWMAK-III, LASL's Theta Pinch Reactor Design (RTPR), Mirror Fusion Reactor (MFR), Tandem Mirror Reactor (TMR), and the Mirror Hybrid Reactor (MHR). There are four laser device breakeven experiments, SHIVA-NOVA, LLL reference designs, ORNL Laser Fusion power plant, the German ''Saturn,'' and LLL's Laser Fusion EPR I and II

  7. Refurbishing tritium contaminated ion sources

    International Nuclear Information System (INIS)

    Wright, K.E.; Carnevale, R.H.; McCormack, B.E.; Stevenson, T.; Halle, A. von

    1995-01-01

    Extended tritium experimentation on TFTR has necessitated refurbishing Neutral Beam Long Pulse Ion Sources (LPIS) which developed operational difficulties, both in the TFTR Test Cell and later, in the NB Source Refurbishment Shop. Shipping contaminated sources off-site for repair was not permissible from a transport and safety perspective. Therefore, the NB source repair facility was upgraded by relocating fixtures, tooling, test apparatus, and three-axis coordinate measuring equipment; purchasing and fabricating fume hoods; installing exhaust vents; and providing a controlled negative pressure environment in the source degreaser/decon area. Appropriate air flow monitors, pressure indicators, tritium detectors and safety alarms were also included. The effectiveness of various decontamination methods was explored while the activation was monitored. Procedures and methods were developed to permit complete disassembly and rebuild of an ion source while continuously exhausting the internal volume to the TFTR Stack to avoid concentrations of tritium from outgassing and minimize personnel exposure. This paper presents upgrades made to the LPIS repair facility, various repair tasks performed, and discusses the effectiveness of the decontamination processes utilized

  8. Tritium production in fusion reactors

    International Nuclear Information System (INIS)

    Roth, E.

    1981-08-01

    The present analyses on the possibilities of extracting tritium from the liquid and solid fusion reactor blankets show up many problems. A consistent ensemble of materials and devices for extracting the heat and the tritium has not yet been integrated in a fusion reactor blanket project. The dimensioning of the many pipes required for shifting the tritium can only be done very approximately and the volume taken up by the blanket is difficult to evaluate, etc. The utilization of present data leads to over-dimensioning the installations by prudence and perhaps rejecting the best solutions. In order to measure the parameters of the most promising materials, work must be carried out on well defined samples and not only determine the base physical-chemical coefficients, such as thermal conductivity, scattering coefficients, Sievert parameters, but also the kinetic parameters conventional in chemical engineering, such as the hourly space rates of degassing. It is also necessary to perform long duration experiments under radiation and at operating temperatures, or above, in order to study the ageing of the bodies employed [fr

  9. Tritium calorimeter setup and operation

    International Nuclear Information System (INIS)

    Rodgers, David E.

    2002-01-01

    The LBNL tritium calorimeter is a stable instrument capable of measuring tritium with a sensitivity of 25 Ci. Measurement times range from 8-hr to 7-days depending on the thermal conductivity and mass of the material being measured. The instrument allows accurate tritium measurements without requiring that the sample be opened and subsampled, thus reducing personnel exposure and radioactive waste generation. The sensitivity limit is primarily due to response shifts caused by temperature fluctuation in the water bath. The fluctuations are most likely a combination of insufficient insulation from ambient air and precision limitations in the temperature controller. The sensitivity could probably be reduced to below 5 Ci if the following improvements were made: (1) Extend the external insulation to cover the entire bath and increase the top insulation. (2) Improve the seal between the air space above the bath and the outside air to reduce evaporation. This will limit the response drift as the water level drops. (3) Install an improved temperature controller, preferably with a built in chiller, capable of temperature control to ±0.001 C

  10. Comparison Of Four Landfill Gas Models Using Data From Four Danish Landfills

    DEFF Research Database (Denmark)

    Mønster, Jacob G.; Mou, Zishen; Kjeldsen, Peter

    2011-01-01

    Data about type and quantity of waste disposed in four Danish landfills was collected and used on four different landfill gas generation models. This was done to compare the output data in order to evaluate the performance of the four landfill gas models when used on Danish waste types...

  11. Tritium radioluminescent devices, Health and Safety Manual

    Energy Technology Data Exchange (ETDEWEB)

    Traub, R.J.; Jensen, G.A.

    1995-06-01

    This document consolidates available information on the properties of tritium, including its environmental chemistry, its health physics, and safe practices in using tritium-activated RL lighting. It also summarizes relevant government regulations on RL lighting. Chapters are divided into a single-column part, which provides an overview of the topic for readers simply requiring guidance on the safety of tritium RL lighting, and a dual-column part for readers requiring more technical and detailed information.

  12. Overview of light sources powered by tritium

    International Nuclear Information System (INIS)

    Wu Jian; Lei Jiarong; Liu Wenke

    2012-01-01

    Due to their long lifespan and stable intensity, light sources initiated by tritium instead of electricity or batteries are suitable for low level lighting applications. Therefore, tritium-based radioluminescent (RL) light sources are widely used in both military and civil applications. However, traditional tritium lights with the gas tube structure have several shortcomings: (1) the phosphors are opaque; (2) the glass tube is fragile and easily broken; and (3) the beta kinetic energy is attenuated due to the sorption by the gas; etc. As a result, further application of the tritium lights is limited. In this paper, the lighting mechanism and radiation safety of tritium-based RL light sources are briefly reviewed. Besides, the history and prospects of the development of tritium-based RL light source are discussed. Due to their long lifespan and stable intensity, light sources initiated by tritium instead of electricity or batteries are suitable for low level lighting applications. Therefore, tritium- based radioluminescent (RL) light sources are widely used in both military and civil applications. However, traditional tritium lights with the gas tube structure have several short- comings: (1) the phosphors are opaque; (2) the glass tube is fragile and easily broken; and (3) the beta kinetic energy is attenuated due to the sorption by the gas; etc. As a result, further application of the tritium lights is limited. In this paper, the lighting mechanism and radiation safety of tritium-based RL, light sources are briefly reviewed. Besides, the history and prospects of the development of tritium-based RL light source are discussed. (authors)

  13. Degradation of elastomers by tritium beta radiation

    International Nuclear Information System (INIS)

    Zapp, P.E.; Tuer, G.L. Jr.

    1984-01-01

    Based on its tritium radiation resistance, ethylene propylene rubber has been selected as a candidate for replacement of nitrile rubber in the SRP tritium facilities. A specification for flange gasket material has been developed for ethylene propylene such that its mechanical properties are similar to those of nitrile rubber. In-process testing of ethylene propylene and nitrile gaskets will be conducted in the tritium facilities under identical exposure conditions

  14. Tritium radioluminescent devices, Health and Safety Manual

    International Nuclear Information System (INIS)

    Traub, R.J.; Jensen, G.A.

    1995-06-01

    This document consolidates available information on the properties of tritium, including its environmental chemistry, its health physics, and safe practices in using tritium-activated RL lighting. It also summarizes relevant government regulations on RL lighting. Chapters are divided into a single-column part, which provides an overview of the topic for readers simply requiring guidance on the safety of tritium RL lighting, and a dual-column part for readers requiring more technical and detailed information

  15. Effluent Treatment Facility tritium emissions monitoring

    International Nuclear Information System (INIS)

    Dunn, D.L.

    1991-01-01

    An Environmental Protection Agency (EPA) approved sampling and analysis protocol was developed and executed to verify atmospheric emissions compliance for the new Savannah River Site (SRS) F/H area Effluent Treatment Facility. Sampling equipment was fabricated, installed, and tested at stack monitoring points for filtrable particulate radionuclides, radioactive iodine, and tritium. The only detectable anthropogenic radionuclides released from Effluent Treatment Facility stacks during monitoring were iodine-129 and tritium oxide. This paper only examines the collection and analysis of tritium oxide

  16. The movement of tritium in ecological systems

    International Nuclear Information System (INIS)

    Polevoy, Y; Laichter, Y.

    1988-11-01

    This literature survey summarizes the interaction of tritium gas and tritiated water with various components of the ecological system. The intake of tritium gas and tritiated water in plants and soil is described as well as the location of the highest measurable concentration. This information may serve as a basis for risk assessment from tritium to man through the food chain and enables effective tracing of its concentration in the environment. (author)

  17. Tritium monitoring equipments for animal experiment facilities

    International Nuclear Information System (INIS)

    Sato, Hiroo

    1980-01-01

    Animal experiment facilities using tritium are described with reference to laws and regulations concerning radiological safety. Usual breeding facilities and surrounding conditions at non-radioactive animal experiments are summarized on feasible and effective designs of tritium monitors. Characteristics and desirable arrangements of various kinds of tritium monitors such as ionization chambers, proportional counters and liquid scintillation detectors are discussed from the standpoint of monitoring for room, glove-box, stack, liquid waste and personnel. (J.P.N.)

  18. Congenital anomalies and proximity to landfill sites.

    LENUS (Irish Health Repository)

    Boyle, E

    2004-01-01

    The occurrence of congenital anomalies in proximity to municipal landfill sites in the Eastern Region (counties Dublin, Kildare, Wicklow) was examined by small area (district electoral division), distance and clustering tendancies in relation to 83 landfills, five of which were major sites. The study included 2136 cases of congenital anomaly, 37,487 births and 1423 controls between 1986 and 1990. For the more populous areas of the region 50% of the population lived within 2-3 km of a landfill and within 4-5 km for more rural areas. In the area-level analysis, the standardised prevalence ratios, empirical and full Bayesian modelling, and Kulldorff\\'s spatial scan statistic found no association between the residential area of cases and location of landfills. In the case control analysis, the mean distance of cases and controls from the nearest landfill was similar. The odds ratios of cases compared to controls for increasing distances from all landfills and major landfills showed no significant difference from the baseline value of 1. The kernel and K methods showed no tendency of cases to cluster in relationship to landfills. In conclusion, congenital anomalies were not found to occur more commonly in proximity to municipal landfills.

  19. Evaluating operational vacuum for landfill biogas extraction.

    Science.gov (United States)

    Fabbricino, Massimiliano

    2007-01-01

    This manuscript proposes a practical methodology for estimating the operational vacuum for landfill biogas extraction from municipal landfills. The procedure is based on two sub-models which simulate landfill gas production from organic waste decomposition and distribution of gas pressure and gas movement induced by suction at a blower station. The two models are coupled in a single mass balance equation, obtaining a relationship between the operational vacuum and the amount of landfill gas that can be extracted from an assigned system of vertical wells. To better illustrate the procedure, it is applied to a case study, where a good agreement between simulated and measured data, within +/- 30%, is obtained.

  20. Movement of unlined landfill under preloading surcharge.

    Science.gov (United States)

    Al-Yaqout, Anwar F; Hamoda, Mohamed F

    2007-01-01

    As organic solid waste is decomposed in a landfill and mass is lost due to gas and leachate formation, the landfill settles. Settlement of a landfill interferes with the rehabilitation and subsequent use of the landfill site after closure. This study examined the soil/solid waste movement at the Al-Qurain landfill in Kuwait after 15 years of closure as plans are underway for redevelopment of the landfill site that occupies about a km(2) with an average depth of 8-15m. Field experiments were conducted for 6 mo to measure soil/solid waste movement and water behavior within the landfill using two settlement plates with a level survey access, Casagrande-type piezometers, pneumatic piezometers, and magnetic probe extensometers. Previous results obtained indicated that biological decomposition of refuse continued after closure of the landfill site. The subsurface water rise enhanced the biological activities, which resulted in the production of increasing quantities of landfill gas. The refuse fill materials recorded a high movement rate under the imposed preloading as a result of an increase in the stress state. Up to 55% of the total movement was observed during the first 2 weeks of fill placement and increased to 80% within the first month of the 6-mo preloading test. Pneumatic piezometers showed an increase in water head, which is attributed to the developed pressure of gases escaping during the preloading period.