WorldWideScience

Sample records for waste dump project

  1. Dumping of radioactive waste in the Artic Seas - The International Arctic Seas Assessment Project (IASAP)

    International Nuclear Information System (INIS)

    Linsley, G.S.; Sjoeblom, K.L.

    1994-01-01

    The IAEA has initiated the International Arctic Seas Assessment Project (IASAP) to address the widespread concern over the possible health and environmental impacts of the dumped radioactive wastes in the shallow waters the Arctic seas. The work is being carried out as part of IAEA responsibilities to the London Convention 1972. It is envisaged that the project will last for four years and be run by the IAEA in co-operation with the Norwegian and Russian Governments and with the involvement, through the IAEA, of experts from relevant IAEA member states. The project is aimed at producing an assessment of the potential radiological implications of the dumping and at addressing the question of possible remedial measures. At the same time, it is intended to provide a focus for the reporting of national research and assessment work and a mechanism for encouraging international co-operation and collaboration

  2. A hybrid of QFD and AHP-TOPSIS for Durg dumping waste projects

    Directory of Open Access Journals (Sweden)

    Rituraj Chandrakar

    2018-06-01

    Full Text Available Generation of solid waste is the integral consequence of civilization and its management is stand-ing as a big challenge in front of state government at present time. Municipal solid waste in Durg-Bhilai is littered with improper places due to lack of understanding about the scientific im-portance of garbage and its consequences. Our foremost concern is the selection of appropriate dumping area nearby Durg-Bhilai (C.G. and for the selection of appropriate dumping area, a multi criteria decision making technique is used. This paper attempts to evaluate 4 dumping areas based on 5 criteria. Analytical hierarchy process (AHP is used to determine the weighs for each criterion and quality function deployment (QFD is also implemented. The results indicate that Potiyakala was the best dumping site nearby Durg-Bhilai area.

  3. Sea dumping of hazardous wastes

    International Nuclear Information System (INIS)

    Thomas, J.

    1980-01-01

    From 1967 until 1976 ca. 45,000 t of weak radioactive wastes had been dumped into the sea during several actions under the supervision of the NEA. The requirements to be deduced from the experiences with regard to marine areas, packaging and transports of the wastes are described. Up to now the possibilities of the sea dumping of strong radioactive wastes has been just discussed. The natural removal of the decay heat by sea water would be advantageous but the problem of water-proof packagings for the period of 1000 years have not been solved yet. (orig.) [de

  4. Solid waste dumping site suitability analysis using geographic ...

    African Journals Online (AJOL)

    Solid waste dumping is a serious problem in the urban areas because most solid wastes are not dumped in the suitable areas. Bahir Dar Town has the problem of solid waste dumping site identification. The main objective of this study was to select potential areas for suitable solid waste dumping sites for Bahir Dar Town, ...

  5. Conversion of waste dump into a recreation and leisure park

    International Nuclear Information System (INIS)

    Petit, E.; Martens, P.N.

    1997-01-01

    In a two year strategy-project Aachen University investigated possibilities for postmining activities for a German coal mine. All research work was based on existing infrastructure and mine related potentials. One of the potentials is the waste dump with a height of 90 m above surface and 40 ha in size. This paper deals with the idea of converting the dump into a recreation and leisure park with greater than regional significance. 3 refs., 4 figs

  6. Source, transport and dumping of radioactive waste

    International Nuclear Information System (INIS)

    1980-03-01

    The results of an examination into the problems of radioactive waste are presented, in particular the sources, transport and dumping and the policy considerations in favour of specific methods. The theoretical background of radioactive waste is described, including the physical and chemical, ecological, medical and legal aspects. The practical aspects of radioactive waste in the Netherlands are considered, including the sources, the packaging and transport and dumping in the Atlantic Ocean. The politics and policies involved in this process are outlined. (C.F.)

  7. High slope waste dumps – a proven possibility

    Directory of Open Access Journals (Sweden)

    Igor Svrkota

    2013-11-01

    Full Text Available This paper is an overview of dumping operations on High Slope Waste Dump at Veliki Krivelj open pit copper mine, RTB Bor, Serbia. The High Slope Waste Dump in Bor is the highest single slope waste dump in the world with the slope height of 405 m. The paper gives the basics and limitations of the designed dumping technology, the redesigned technology, gives an overview of the 13 year long operation and gathered experiences and addresses the main issues of dumping operations in high slope conditions as well as the present condition of the High Slope Waste Dump.

  8. Slope Stability Analysis of Waste Dump in Sandstone Open Pit Osielec

    Science.gov (United States)

    Adamczyk, Justyna; Cała, Marek; Flisiak, Jerzy; Kolano, Malwina; Kowalski, Michał

    2013-03-01

    This paper presents the slope stability analysis for the current as well as projected (final) geometry of waste dump Sandstone Open Pit "Osielec". For the stability analysis six sections were selected. Then, the final geometry of the waste dump was designed and the stability analysis was conducted. On the basis of the analysis results the opportunities to improve the stability of the object were identified. The next issue addressed in the paper was to determine the proportion of the mixture containing mining and processing wastes, for which the waste dump remains stable. Stability calculations were carried out using Janbu method, which belongs to the limit equilibrium methods.

  9. Risks from proposed nuclear waste dump unacceptable

    International Nuclear Information System (INIS)

    Veevers, John

    1999-01-01

    The author has a critical look at the proposal by Pangea Resources Australia Pty Ltd (PARPL) to establish in Australia a permanent underground disposal site for radioactive waste from around the world. In his opinion, the inevitable risk in the proposal stems from the magnitudes: 250,000 tonnes of enormously dangerous RADwaste in the northern hemisphere 20,000 km from its destined dump in Australia, where it must remain intact for at least 10,000 years. These magnitudes - of tonnage, lethality, distance of transport, and time - entail great inherent risk. He also argue that the job of the Australian scientists is to apply due diligence to PARPL proposal

  10. Northwest Russia and the Dumping of Radioactive Waste: The London Convention Implemented

    Energy Technology Data Exchange (ETDEWEB)

    Stokke, Olav Schram

    1997-12-31

    The `Polar Oceans and the Law of the Sea Project`, POLOS, is a three-year international research project in international law and international relations. This report is one of the publications under POLOS. The subject is the Soviet dumping of radioactive waste in the Barents and Kara Seas. The most intensely radioactive waste is a number of submarine reactors still containing high-level spent fuel. Some of this dumping violated Soviet commitments to the 1972 London Convention on the Prevention of Marine Pollution by Dumping of Wastes and Other Matter, and this is the starting point of the report. The discussion focuses on how international regimes may affect the domestic implementation in member states, that is, how international agreements can be converted into behavioural adaptation on the part of target groups. Soviet and later Russian management of nuclear waste in the north has been significantly influenced by regulations and programmes generated under international dumping instruments. These international programmes have been supported by the active participation of the Navy itself in the belief that they would lead to transfer of technology and financial resources to Russia from the West. Inspection of military nuclear waste management is largely left to the Northern Fleet. As for monitoring, measurements were for a long time not taken near the dumping sites. As for regulations, the Northern Fleet continued dumping long into the 1990s without permission. Regarding compliance stimulation, foreign support has helped the Northern Fleet avoid dumping. 113 refs.

  11. Guidelines for sea dumping packages of radioactive waste. Revised version.

    International Nuclear Information System (INIS)

    Anon.

    1979-04-01

    The purpose of these Guidelines is to establish general requirements and provide practical information for the design and manufacture of packages for sea dumping of radioactive waste, in accordance with the terms of the OECD Council Decision establishing a Multilateral Consultation and Surveillance Mechanism for Sea Dumping of Radioactive Waste. These Guidelines are in compliance with the IAEA Revised Definition and Recommendations of 1978, for applying the London Dumping Convention to radioactive waste, and are intended for application under the responsibility of the appropriate national authorities of countries participating in the NEA Mechanism

  12. A model of pyritic oxidation in waste rock dumps

    International Nuclear Information System (INIS)

    Davis, G.B.; Ritchie, A.I.M.

    1983-01-01

    The oxidation of pyrite can lead to high acid levels and high concentrations of trace metals in the water that runs off and percolates through pyritic material. This is the situation at the abandoned uranium mine at Rum Jungle in the Northern Territory of Australia, where pyritic oxidation in the waste rock dumps resulting from open cut mining of the uranium orebody has led to pollution of the nearby East Branch of the Finniss River, with trace metals such as copper, manganese and zinc. Mathematical equations are formulated which describe a model of pyritic oxidation within a waste rock dump, where it is assumed that oxygen transport is the rate limiting step in the oxidation process and that oxygen is transported by gaseous diffusion through the pore space of the dump, followed by diffusion into oxidation sites within the particles that comprise the dump. The equations have been solved numerically assuming values for such parameters as porosity, sulphur density and oxygen diffusion coefficients which are applicable to the waste rock dumps at Rum Jungle. An approximate solution to the equations is also presented. Calculations of the heat source distribution and the total SO 4 production rate are presented for both single size particles and for a range of particle sizes in the dump. The usefulness of the approximate solution, and of calculations based on single size particles in the dump in assessing the effectiveness of strategies to reduce pollution from such waste rock dumps are discussed

  13. Effects on the environment of the dumping of nuclear wastes

    International Nuclear Information System (INIS)

    1990-07-01

    Nationally and internationally accepted procedures and technologies are available for the safe handling and disposal of radioactive wastes. Authorized waste disposal practices are designed to ensure that there will be no significant impacts on man and his environment. 'Dumping' of nuclear wastes may result in the elimination of one or more of the multibarriers of protection inherent in an effective radioactive waste management system, thereby increasing the risk of radiological exposure to man and his environment. Quantitative assessments of the degree of environmental contamination and of the resulting hazards to man depend on the specific conditions surrounding the 'uncontrolled disposal' of radioactive waste. These include the nature and activity level of the waste, the physical form of the waste, the package that the waste is contained in and the characteristics of the dumping site. Depending on the scenario envisaged, the consequences of 'uncontrolled disposal' could vary from being insignificant to a situation where there is a significant hazard to an exposed population group. International transactions involving nuclear wastes are taking place between countries on the basis of bilateral agreements and under strict regulatory supervision so that radioactive wastes are transferred safely from one controlled area to another. Such transactions may increase in the future with increased international co-operation in sharing common waste repositories. No evidence exists that confirms that transboundary dumping of radioactive waste has occurred. Investigation of alleged dumping of radioactive wastes by the International Atomic Energy Agency has revealed that the 'suspect wastes' did not contain radioactive material. 2 tabs

  14. Radiation protection with regard to sea dumping of radioactive waste

    International Nuclear Information System (INIS)

    Sanderse, R.W.; Worst, J.

    1980-01-01

    The Netherlands Energy Research Foundation (ECN) has been dumping into the Atlantic Ocean radioactive waste cast into concrete since 1965. In the report the Health Physics problems with regard to the transport and dumping of the radioactive waste are discussed. In particular to the following points has been paid attention: tasks and working methods of the radiation protection service, dose evaluation for the people involved by two different kinds of dumping methods, doses received by the personal involved, some contamination problems caused by leaking drums. (orig.) [de

  15. Practice and assessment of sea dumping of radioactive wastes

    International Nuclear Information System (INIS)

    Templeton, W.L.; Bewers, J.M.

    1985-08-01

    This paper discusses the practice and assessment of the ocean dumping of low-level radioactive wastes. It describes the international and multilateral regulatory framework, the sources, composition, packaging and rate of dumping and, in particular, the recent radiological assessment of the only operational disposal site in the northeast Atlantic. The paper concludes with a discussion of future ocean disposal practices for radioactive wastes, and the application of the approach to the dumping of non-radioactive contaminants in the ocean. 39 refs., 1 fig., 4 tabs

  16. The IAEA's responsibilities in connection with the dumping at sea of radioactive wastes

    International Nuclear Information System (INIS)

    Ha Vinh Phuong

    1983-01-01

    In the context of IAEA's responsibilities regarding the sea dumping of radioactive wastes, this paper reviews international laws of relevance to sea dumping of wastes, and examines IAEA's role under the London Dumping Convention. The paper also describes the OECD/NEA Multilateral Consultation and Surveillance Mechanism on radioactive waste sea dumping operations. (NEA) [fr

  17. Geoelectrical Evaluation of Waste Dump Sites at Warri and its ...

    African Journals Online (AJOL)

    The existing waste dump sites in Delta State were investigated without soil disturbance by using the vertical electrical sounding (VES).The soil overlying the aquifer at Ovwian-Aladja dump site has resistively values, 11.84-85.50 Ohm-m, thicknesses,21.10-31.83m and at depths less than 1m, while at Warri it has resistively ...

  18. Recultivation of mining waste dumps in the Ruhr area, Germany

    International Nuclear Information System (INIS)

    Schulz, D.

    1996-01-01

    In 1993 Ruhrkohle AG produced 41.9 million tons of coal and 19.1 million m 3 of mining waste. Of this, 0.7 million m 3 were used underground as stowing material, 4.7 million m 3 was used commercially, while the remaining 13.7 million m 3 required dumping. Efforts related to the use and disposal of the material up to now dumped are concentrating on applying technical methods to reduce the production of waste underground, on opening up new markets of this material, on utilization of mining waste as a building material, and on low-environmental-impact dumping. Since the late 1970s, the mining waste heaps in the Ruhr mining region have been conceived and designed as landscape structures, i.e. they are integrated into the landscape by means of careful planning and design, and are immediately planted with vegetation. 9 refs., 5 figs

  19. Particulate Matter and Noise Impact Studies of Waste Rock Dump ...

    African Journals Online (AJOL)

    Adansi Gold Company Limited identified an economically viable gold deposit at Nkran in the Amansie West District of Ghana. Mining of this deposit requires the disposal of waste rock materials at a proposed waste rock dump near Nkran and Koninase communities. Since particulates and noise emissions from the ...

  20. Waste Dump Closure and Cost Estimates at AngloGold Ashanti ...

    African Journals Online (AJOL)

    Michael

    2017-12-02

    Dec 2, 2017 ... 2University of Mines and Technology, P.O. Box 237, Tarkwa, Ghana ... The mine has closure plans for the waste dumps and the closure activity ... incur additional cost, it was advised that the mine should execute the closure and reclamation plan without delay. .... Progressively rehabilitate the project area.

  1. Dumping convention

    International Nuclear Information System (INIS)

    Roche, P.

    1992-01-01

    Sea dumping of radioactive waste has, since 1983, been precluded under a moratorium established by the London Dumping Convention. Pressure from the nuclear industry to allow ocean dumping of nuclear waste is reported in this article. (author)

  2. The waste bin: nuclear waste dumping and storage in the Pacific

    International Nuclear Information System (INIS)

    Branch, J.B.

    1984-01-01

    Relatively small amounts of nuclear waste have been stored on Pacific islands and dumped into the Pacific Ocean since 1945. Governments of Pacific countries possessing nuclear power plants are presently seeking permanent waste storage and disposal solutions at Pacific sites including subseabed emplacement of high-level nuclear wastes and ocean dumping of low-level wastes. This article examines these plans and the response of Pacific islanders in their development of policies and international strategies to ban the proposed dumping on a regional basis. Island governments are preparing for a Regional Convention during which a treaty concerned with radioactive waste storage and disposal will be signed. (Author)

  3. International Surveillance Mechanism for Sea Dumping of Radioactive Waste

    Science.gov (United States)

    OECD Observer, 1977

    1977-01-01

    The OECD consultation and surveillance mechanism is discussed in detail in this article. Four phases are identified and examined: (1) Notification, (2) Consultation, (3) Supervision, (4) Post-operation. This system is designed to provide the safest possible conditions for sea dumping of radioactive wastes. (MA)

  4. Solid waste dumping site suitability analysis using geographic ...

    African Journals Online (AJOL)

    Solid waste dumping site suitability analysis using geographic information system (GIS) and remote sensing for Bahir Dar Town, North Western Ethiopia. ... The PDF file you selected should load here if your Web browser has a PDF reader plug-in installed (for example, a recent version of Adobe Acrobat Reader).

  5. Acid Mine Drainage Potential of the Coral Snake Waste Dump ...

    African Journals Online (AJOL)

    This paper assessed the Acid Mine Drainage (AMD) potential of the Coral Snake Waste Dump located close to the Enkansu and Kaw streams in Obuasi. Ten water and fifty rock samples were analysed for physico-chemical parameters. Acid Base Accounting (ABA) determinations using static methods were employed to ...

  6. The problem with coal-waste dumps inventory in Upper Silesian Coal Basin

    Science.gov (United States)

    Abramowicz, Anna; Chybiorz, Ryszard

    2017-04-01

    Coal-waste dumps are the side effect of coal mining, which has lasted in Poland for 250 years. They have negative influence on the landscape and the environment, and pollute soil, vegetation and groundwater. Their number, size and shape is changing over time, as new wastes have been produced and deposited changing their shape and enlarging their size. Moreover deposited wastes, especially overburned, are exploited for example road construction, also causing the shape and size change up to disappearing. Many databases and inventory systems were created in order to control these hazards, but some disadvantages prevent reliable statistics. Three representative databases were analyzed according to their structure and type of waste dumps description, classification and visualization. The main problem is correct classification of dumps in terms of their name and type. An additional difficulty is the accurate quantitative description (area and capacity). A complex database was created as a result of comparison, verification of the information contained in existing databases and its supplementation based on separate documentation. A variability analysis of coal-waste dumps over time is also included. The project has been financed from the funds of the Leading National Research Centre (KNOW) received by the Centre for Polar Studies for the period 2014-2018.

  7. Reconstruction of the inner structure of small scale mining waste dumps by combining GPR and ERTdata.

    Science.gov (United States)

    Kniess, Rudolf; Martin, Tina

    2015-04-01

    Two abandoned small waste dumps in the west of the Harz mountains (Germany) were analysed using ground penetrating radar (GPR) and electrical resistivity tomography (ERT). Aim of the project (ROBEHA, funded by the German Federal Ministry of Education and Research (033R105)) is the assessment of the recycling potential of the mining residues taking into account environmental risks of reworking the dump site. One task of the geophysical prospection is the investigation of the inner structure of the mining dump. This is important for the estimation of the approximate volume of potentially reusable mining deposits within the waste dump. The two investigated dump sites are different in age and therefore differ in their structure. The older residues (mining dumps. The resistivities of the dumped material differ from the bedrock resistivities at both sites. The GPR measurements show near surface layer boundaries down to 3 - 4 m. In consecutive campaigns 100 MHz and 200 MHz antennas were used. The GPR results (layer boundaries) were included into the ERT inversion algorithm to enable more precise and stable resistivity models. This needs some special preprocessing steps. The 3D-Position of every electrode from ERT measurement and the GPR antenna position on the surface require an accuracy of less than 1cm. At some points, the layer boundaries and radar wave velocities can be calibrated with borehole stratigraphic data from a mineralogical drilling campaign. This is important for a precise time-depth conversion of reflectors from GPR measurement. This reflectors were taken from radargram and have been adopted as resistivity boundary in the start model of the geoelectric inversion algorithm.

  8. Dumping of radioactive waste in the Barents and Kara seas

    International Nuclear Information System (INIS)

    Salbu, B.; Christensen, G.C.

    1995-01-01

    To evaluate the level of radioactive contamination in the Kara Sea and to assess short- and long-term consequences of dumped radioactive waste, joint Russian-Norwegian expeditions have been performed annually since 1992. Results from the 1992 joint expedition to the Kara Sea demonstrated very low concentrations of radionuclides in waters and sediments. Contributions from different sources: global fallout, river transport, marine transport of discharges from European reprocessing plants and of fallout from Chernobyl, could be identified. From the expeditions in 1993 and 1994 to three bays at Novaya Zemlya, local contamination in the Stepovogo and the Abrosimov bays due to leakage from the dumped radioactive waste could be confirmed. Results from the 1994 expedition will be published in 1995. The levels of radioactivity in the Kara Sea are, however, very low and represent at present an extremely low impact on man and the marine ecosystem. (Author)

  9. Ocean dumping of low-level radioactive wastes

    International Nuclear Information System (INIS)

    Templeton, W.L.

    1982-10-01

    Scientific bases, developed internationally over the last 20 years, to control and restrict to acceptable levels the resultant radiation doses that potentially could occur from the dumping of low-level radioactive wastes in the deep oceans were presented. The author concluded that present evaluations of the disposal of radioactive wastes into the oceans, coastal and deep ocean, indicate that these are being conducted within the ICRP recommended dose limits. However, there are presently no international institutions or mechanisms to deal with the long-term radiation exposure at low-levels to large numbers of people on a regional basis if not a global level. Recommendations were made to deal with these aspects through the established mechanisms of NEA/OECD and the London Dumping Convention, in cooperation with ICRP, UNSCEAR and the IAEA

  10. Biological reduction of dust nuisance on power station waste dumps

    Energy Technology Data Exchange (ETDEWEB)

    Kozel, J

    1978-01-01

    The results of pot trials and succeeding field trials carried out in 1966-72 to find out the best method of reclamationand stabilishing the fly ash and cinder waste dump at the Melnik power station are summarised. The material consists mainly of fine particles with a size range of less than 1 micron to 0.16 mm in diam., and creates a source of blown dust in dry weather. Treatment of the waste material before sowing grass and legume species, the species tested, sowing rates, applied fertilizers, irrigation and treatment of the resulting swards are discussed. The most suitable species were Festuca rubra, F. ovina, perennial ryegrass and Italian ryegrass; the cost of stabilising the dump was lowest with Italian ryegrass. (In English)

  11. Environmental assessment methodologies for sea dumping of radioactive wastes

    International Nuclear Information System (INIS)

    1983-09-01

    The IAEA and the IMO, in cooperation with the United Nations Environment Programme (UNEP), jointly convened a Technical Committee to provide guidance to national authorities. This document contains the results of the Technical Committee Meeting in Vienna, August - September 1982 and constitutes guidance to the Contracting Parties to the LDC Convention on the nature and content of the environmental assessment required for permit applications for sea dumping of radioactive wastes

  12. Assessment of the mercury emissions from burning mining waste dumps

    Directory of Open Access Journals (Sweden)

    Barbara Białecka

    2016-04-01

    occur and to which the environment and local inhabitants can be exposed, it is important to define the size of the emission of mercury compounds from these objects. Despite the potential threats so far no measurements of mercury concentration which would a llow quantifying this phenomenon have been done. The analyses presented in this article fill this gap. Additionally, initial calculation of annual mercury emissions from burning coal mining waste dumps in Poland is presented.

  13. Modelling of the radiological impact of radioactive waste dumping in the Arctic Seas. Report of the Modelling and Assessment Working Group of the International Arctic Seas Assessment Project (IASAP)

    International Nuclear Information System (INIS)

    2003-01-01

    The work is summarized carried out by the Modelling and Assessment Working Group in 1994-1996. The Modelling and Assessment Working Group was established within the framework of the International Arctic Seas Assessment Project (IASAP) launched by the IAEA in 1993 with the objectives of modelling the environmental dispersal and transport of nuclides to be potentially released from the dumped objects and of assessing the associated radiological impact on man and biota. Models were developed to model the dispersal of the pollutants and for the assessment of the radiological consequences of the releases from the dumped wastes in the Arctic. The results of the model intercomparison exercise were used as a basis on which to evaluate the estimate of concentration fields when detailed source term scenarios were used and also to assess the uncertainties in ensuing dose calculations. The descriptions and modelling work was divided into three main phases: description of the area, collection of relevant and necessary information; extension to and development of predictive models including an extensive model inter-comparison and finally prediction of radiological impact, used in the evaluation of the need and options for remediation

  14. Environmental assessment methodologies for sea dumping of radioactive wastes

    International Nuclear Information System (INIS)

    1984-01-01

    This document, which describes the content of an environmental assessment report, will assist national authorities to meet their obligations under the London Dumping Convention (LDC, 1972) by initiating those steps which are to be undertaken to ensure that ''the procedure to be followed and the nature of such reports shall be agreed by the parties in consultation'' (Article VI. 4). In the context of sea disposal of radioactive wastes, environmental assessments are taken to mean those evaluations which are undertaken to assist in the decision-making processes used by national authorities to determine: 1) How the option of sea disposal compares environmentally, technically, socially and economically with other disposal options (this constitutes the comparison with land-based alternatives); and 2) Whether the impact of a proposed sea disposal option is acceptable (this requires a detailed evaluation of the proposed operation including site selection, quantities and types of waste to be dumped, operational requirements and calculation of radiological and other risks). The term ''environmental assessment'' in these respects is deemed to include both the evaluation of the impact of sea dumping and the document that describes this evaluation

  15. Modeling acid mine drainage in waste rock dumps

    Energy Technology Data Exchange (ETDEWEB)

    Lefebvre, R. [INRS, Quebec (Canada)

    1995-03-01

    Acid mine drainage (AMD) results from the oxidation of sulfides present in mine wastes. The acidity generated by these reactions creates conditions under which metals can be leached and represent a threat for surface and ground waters. Even though leachate collection and neutralization are used to treat the problem, the industry is looking for methods to predict and prevent the generation of AMD at new sites and control methods for sites already producing AMD. Waste rock dumps are generally very large accumulations of barren rocks extracted from open pits to access ore bodies. These rocks contain sulfides, most commonly pyrite, and often generate AMD at rates much higher than in mine tailings which are fine grained by-products of milling operations. Numerous coupled physical processes are involved in AMD production in waste rocks. Sulfide oxidation reactions are strongly exothermic and temperatures beyond 70{degrees}C have been measured in some dumps. That heat is transfered by conduction and fluid advection. Dumps have thick partly saturated zones through which gases flow under thermal gradients and water infiltrates. Oxygen is required by the oxidation reactions and is supplied by diffusion and advection. The reaction products are carried in solution in very concentrated leachates. Numerical modeling of AMD aims to (1) provide a better understanding of the physical processes involved in AMD, (2) allow the integration of available waste rock characterization data, (3) indicate new data or studies which are required to fill the gaps in our quantitative understanding of AMD processes, and (4) supply a tool for the prediction of AMD production, taking into account the impact of control methods. These objectives can only be met through sustained research efforts. This study is part of a wider research effort which as been on-going at La Mine Doyon since 1991.

  16. Sea dumping of radioactive wastes. Part 3: Dumping practice and radioecology

    International Nuclear Information System (INIS)

    Krejsa, P.

    1983-04-01

    Sea dumping of low level radioactive waste is a disposal method practised by a number of states, controlled by OECD/NEA. It makes use of the capacity of the oceans to dilute the radionuclides to levels acceptable concerning resulting dose burdens. For the determination of release rates some oceanographic model have been developed, describing the physical behaviour of the released radionuclides. It is not to be assumed that a complete mathematical description of the involved processes can be made. Too many parameters are dependent and varying as there is the chemical behaviour of different valence states, complexing agents, distribution patterns etc. But it can be seen that the existing description methods allow the adequate modelling of the short and the long term behaviour of the radionuclides. The use of pessimistic assumptions for distribution and reconcentration is sufficient to consider uncertainties of the model. Therefore the arguments of Greenpeace, kindly submitted by this organisation for this study, show no open question, which has not been considered on the sea dumping procedures under surveillance of the OECD/NEA. (Author)

  17. Dumping of low-level radioactive waste in the deep ocean

    International Nuclear Information System (INIS)

    Templeton, W.L.

    1980-01-01

    Two international agreements relate to the dumping of packaged radioactive waste into the oceans - the Convention on the Prevention of Marine Pollution by Dumping Wastes and Other Matter of 1972 (London Convention) and the Multilateral Consultation and Surveillance Mechanism for Sea Dumping of Radioactive Waste of 1977 under the Organization for Economic Co-operation and Development (OECD). The International Atomic Energy Agency was given the responsibility to define high-level radioactive wastes which are unsuitable for dumping in the oceans and to make recommendations for the dumping of other radioactive wastes. A revised Definition and Recommendations was submitted and accepted by the London Convention. This paper reviews the technical basis for the Definition and describes how it has been applied to the radiological assessment of the only operational dumping site in the North East Atlantic

  18. Radioactive waste dumping at sea: causes for concern

    International Nuclear Information System (INIS)

    Alton, D.; Atkinson, N.; Barrett, H.A.

    The dumping of various low-level radioactive wastes at sea has been carried out for many years and has been accepted as a satisfactory means of disposal by national and international regulatory authorities. There are, however, grounds for concern from an environmental standpoint which centre around two particular issues: the likely extent of mobilisation of an increasing radioactive inventory over time and the likely effects of such radioactivity if and when it should make contact with living organisms. The subject is discussed under the headings: mobilisation; effects on the marine environment; physical and biological considerations; future exploitation of the oceans (for food, minerals); and the effects of radiation. (author)

  19. A programme for exposure and epidemiological surveillance of populations living in the vicinity of industrial waste dumps in France

    International Nuclear Information System (INIS)

    Cardis, E.; Hours, M.; Fabry, J.

    1991-01-01

    Following the environmental contamination at the industrial waste site of Montchain, the government of France has resolved to sponsor a programme for monitoring the impact of industrial waste dumps on the environment and on the health of neighbouring populations. The epidemiological approach is generally limited in its power to quantify risks and even to identify hazards because of: 1. the usual lack of information on the identify and level of toxic substances in the dump itself, on the exposures of individuals in the vicinity and therefore on the diseases and symptoms to be studied; 2. the relatively small size of the populations 'at risk' of exposure. The proposed solution is to carry out a systematic - prospective - surveillance of specific exposures in, and around, every industrial waste site in activity in France. The surveillance will be tailored to each dump. This will yield much needed information on the distribution and temporal pattern of exposures in the population. Risk projection models can then be applied and ranges of risk estimates derived in order that public authorities can make decisions on the operation of the dump. A health risk information campaign will be set up. A prospective epidemiologic study of dump workers, involving exposure monitoring, and biological and clinical follow-up, will also be set up. Subsequently, and depending on the agents and levels of exposure identified at individual dumps, epidemiologic surveillance of high risk groups (pregnant women, children) and biological monitoring of a subsample of the population may be set up

  20. Coal Mining Spoil Heap Management as urban solid waste dump; Utilizacion de Escombreras de Carbon como Vertedero Controlado de Residuos Solidos Urbanos

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2000-07-01

    In the coordinated project DISPOSAL OF SOLID RESIDUES FROM COAL it is included the project Coal Mining Spoil Heap Management as Urban Solid Waste Dump. The main target of this project consisted of determining the viability of using coal mining spoil heaps, as controlled dubbish dump of urban solid wastes. The working plan to achieve this objective was composed of the following stages: 1. Urban solid wastes characterization. 2. Methodology to be followed for the selection of coal mining spoil heaps as controlled dump of urban solid wastes. 2.1 Classification and preliminary assessment of the possibility of using spoil heaps as urban solid waste dumps (APT/NON APT). 2.2 Realization of geological, geotechnical, hydrogeological and environmental studies applied to the spoil heaps classified as APT. 2.3 Analysis of the compatibility of the mining activity with the urban solid wastes dumped on the spoil heap. 2.4 Analysis of the use of coal mining wastes in the rubbish dump operative life. 3. Extraction of conclusions. The works were focused in the Leon province. As result of the researches we obtained the following results and conclusions: In the areas studied, only two emplacements are optima to dump urban solid wastes; spoil heap n. 13. Roguera Mine (Cinera-Matallana) and the open pit mine n. 4, Las Chaviadas, in Villablino. The active spoil heap use as controlled rubbish dump can cause, if not managed adequately, several coperating and occupational problems to the mine and to the company that manages the urban solid wastes. The abandoned spoil heap utilisation is difficult due to the problems that would arise when conditioning the site to be use as rubbish dump. The use of abandoned open pit mines, as controlled rubbish dump is feasible if geological, geotechnical, hydrogeological and environmental studies support it. It's possible the use of the coal mining wastes in the different operatives phases of the controlled rubbish dump. The evaluation methodology

  1. Coal Mining Spoil Heap Management as urban solid waste dump; Utilizacion de Escombreras de Carbon como Vertedero Controlado de Residuos Solidos Urbanos

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2000-07-01

    In the coordinated project DISPOSAL OF SOLID RESIDUES FROM COAL it is included the project Coal Mining Spoil Heap Management as Urban Solid Waste Dump. The main target of this project consisted of determining the viability of using coal mining spoil heaps, as controlled dubbish dump of urban solid wastes. The working plan to achieve this objective was composed of the following stages: 1. Urban solid wastes characterization. 2. Methodology to be followed for the selection of coal mining spoil heaps as controlled dump of urban solid wastes. 2.1 Classification and preliminary assessment of the possibility of using spoil heaps as urban solid waste dumps (APT/NON APT). 2.2 Realization of geological, geotechnical, hydrogeological and environmental studies applied to the spoil heaps classified as APT. 2.3 Analysis of the compatibility of the mining activity with the urban solid wastes dumped on the spoil heap. 2.4 Analysis of the use of coal mining wastes in the rubbish dump operative life. 3. Extraction of conclusions. The works were focused in the Leon province. As result of the researches we obtained the following results and conclusions: In the areas studied, only two emplacements are optima to dump urban solid wastes; spoil heap n. 13. Roguera Mine (Cinera-Matallana) and the open pit mine n. 4, Las Chaviadas, in Villablino. The active spoil heap use as controlled rubbish dump can cause, if not managed adequately, several coperating and occupational problems to the mine and to the company that manages the urban solid wastes. The abandoned spoil heap utilisation is difficult due to the problems that would arise when conditioning the site to be use as rubbish dump. The use of abandoned open pit mines, as controlled rubbish dump is feasible if geological, geotechnical, hydrogeological and environmental studies support it. It's possible the use of the coal mining wastes in the different operatives phases of the controlled rubbish dump. The evaluation methodology developed

  2. Global dumping ground: The international traffic in hazardous waste

    International Nuclear Information System (INIS)

    Moyers, B.

    1993-01-01

    This book is based on the PBS's television documentary. It vividly describes the forces that encourage the USA and other industrialized nations to condone the disposal of industrial and domestic hazardous wastes in other countries. Often conducted illegally, this disposal affects the unsuspecting people of less developed nations, many of whom have less stringent environmental laws and regulations. The book also portrays the ill effects of this dumping on the health and environment and convey and important messages: something must be done to get the public involved in repairing a serious global problem and even small measures, illustrated in the book, are a good start. However, the book fails to confront the question of how the public wants the government to be involved

  3. Preliminary studies on trace element contamination in dumping sites of municipal wastes in India and Vietnam

    Science.gov (United States)

    Agusa, T.; Kunito, T.; Nakashima, E.; Minh, T. B.; Tanabe, S.; Subramanian, A.; Viet, P. H.

    2003-05-01

    The disposal of wastes in dumping sites has increasingly caused concem about adverse health effects on the populations living nearby. However, no investigation has been conducted yet on contamination in dumping sites of municipal wastes in Asian developing countries. In this study, concentrations of 11 trace elements (V, Cr, Mn, Co, Cu, Zn, Mo, Ag, Cd, Sb and Pb) were detennined in scalp hair from the population living nearby and in soil from dumping sites and control sites of India and Vietnam. Soil samples in dumping site in India showed significantly higher concentrations of some trace elements than soils in control site, whereas this trend was not notable in Vietnam. This is probably due to the fact that the wastes were covered with the soil in the dumping site of Vietnam. Cadmium concentrations in some hair samples of people living near dumping site in India and Vietnam exceeded the level associated with learning disorder in children. Levels of most of the trace elements in hair were significantly higher in dumping site than those in control site in India and Vietnam, suggesting direct or indirect exposure to those elements from dumping wastes. To our knowledge, this is the first study of trace element contamination in dumping sites in India and Vietnam.

  4. Soil contamination by brominated flame retardants in open waste dumping sites in Asian developing countries.

    Science.gov (United States)

    Eguchi, Akifimi; Isobe, Tomohiko; Ramu, Karri; Tue, Nguyen Minh; Sudaryanto, Agus; Devanathan, Gnanasekaran; Viet, Pham Hung; Tana, Rouch Seang; Takahashi, Shin; Subramanian, Annamalai; Tanabe, Shinsuke

    2013-03-01

    In Asian developing countries, large amounts of municipal wastes are dumped into open dumping sites each day without adequate management. This practice may cause several adverse environmental consequences and increase health risks to local communities. These dumping sites are contaminated with many chemicals including brominated flame retardants (BFRs) such as polybrominated diphenyl ethers (PBDEs) and hexabromocyclododecanes (HBCDs). BFRs may be released into the environment through production processes and through the disposal of plastics and electronic wastes that contain them. The purpose of this study was to elucidate the status of BFR pollution in municipal waste dumping sites in Asian developing countries. Soil samples were collected from six open waste dumping sites and five reference sites in Cambodia, India, Indonesia, Malaysia, and Vietnam from 1999 to 2007. The results suggest that PBDEs are the dominant contaminants in the dumping sites in Asian developing countries, whereas HBCD contamination remains low. Concentrations of PBDEs and HBCDs ranged from ND to 180 μg/kg dry wt and ND to 1.4 μg/kg dry wt, respectively, in the reference sites and from 0.20 to 430 μg/kg dry wt and ND to 2.5 μg/kg dry wt, respectively, in the dumping sites. Contamination levels of PBDEs in Asian municipal dumping sites were comparable with those reported from electronic waste dismantling areas in Pearl River delta, China. Copyright © 2012 Elsevier Ltd. All rights reserved.

  5. Establishment of a multilateral consultation and surveillance mechanism for sea dumping of radioactive waste

    International Nuclear Information System (INIS)

    Strohl, Pierre.

    1977-01-01

    International regulations on dumping of radioactive waste which until only recently were limited to general principles, have developed significantly during the past years, while radioactive waste sea, dumping operations were being undertaken during the same period under the sponsorship of the OECD Nuclear Energy Agency. The latter, in implementation of the London Convention and the IAEA Recommendations, has established a mechanism whose purpose is to place under international control radioactive waste sea dumping operations to ensure that all necessary steps are taken to avoid marine pollution. This paper analyses the technical and legal aspects of the mechanism. (NEA) [fr

  6. An Engineering Model for Prediction of Waste Incineration in a Dump Combustor

    National Research Council Canada - National Science Library

    Arunajatesan, S

    1997-01-01

    An engineering model that can be used to obtain predictions of axial distributions of temperature and species concentrations in complex flows has been formulated and applied to waste incineration in a dump combustor...

  7. Environmental Impact and Remediation of Uranium Tailings and Waste Rock Dumps at Mailuu-Suu in Kyrgyzstan

    International Nuclear Information System (INIS)

    Kunze, C.; Walter, U.; Wagner, F.; Schmidt, P.; Barnekow, U.; Gruber, A.

    2011-01-01

    This paper describes the environmental situation in the former uranium mining and milling region of Mailuu-Suu (Kyrgyzstan), the approach to environmental remediation of the waste facilities (tailings ponds and waste dumps) and the results achieved so far. It starts with an outline of the history of the environmental remediation project which has received international attention and is seen as a pilot project for further remediation activities of former uranium mining and milling sites in the region. Apart from technical aspects, the paper draws conclusions with respect to the administrative environment, institutional capacity building and the local availability of resources needed to successfully implement a complex remediation project. (author)

  8. Open dumping of municipal solid waste and its hazardous impacts on soil and vegetation diversity at waste dumping sites of Islamabad city

    Directory of Open Access Journals (Sweden)

    Syeda Maria Ali

    2014-01-01

    Full Text Available Deteriorating soil quality and decrease in vegetation abundance are grave consequences of open waste dumping which have resulted in growing public concern. The focus of this study is to assess the contribution of open waste dumping in soil contamination and its effect on plant diversity in one of the renowned green cities of Pakistan. Surface soil samples (n = 12 + 12 were collected from both the open waste dumping areas allocated by Capital Development Authority (CDA and sub- sectors of H-belt of Islamabad city (representative of control site. The diversity of vegetation was studied at both sampling sites. Significant modifications were observed in the soil properties of the dumping sites. Soils at the disposal sites showed high pH, TDS and EC regime in comparison to control sites. Various heavy metal concentrations i.e., Lead (Pb, Copper (Cu, Nickel (Ni, Chromium (Cr and Zinc (Zn were also found to be higher at the dumping sites except for Cadmium (Cd which had a higher value in control site. A similar trend was observed in plant diversity. Control sites showed diversified variety of plants i.e., 44 plant species while this number reduced to only 32 plant species at the disposal sites. This is attributed to changes in soil characteristics at disposal sites and in its vicinity areas.

  9. Distribution and Speciation of Mercury in Mine Waste Dumps

    Czech Academy of Sciences Publication Activity Database

    Hojdová, Maria; Navrátil, Tomáš; Rohovec, Jan

    2008-01-01

    Roč. 80, č. 3 (2008), s. 237-241 ISSN 0007-4861 R&D Projects: GA AV ČR(CZ) KJB300130615 Institutional research plan: CEZ:AV0Z30130516 Keywords : mercury * mine waste * mercury speciation * thermo-desorption analysis Subject RIV: DD - Geochemistry Impact factor: 0.609, year: 2008

  10. Report on R and D work on radioactive waste management and dumping of chemical-toxic wastes sponsored by the BMFT in the second half of 1991

    International Nuclear Information System (INIS)

    1992-05-01

    On behalf of the Federal Minister of Research and Technology, the Kernforschungszentrum Karlsruhe has undertaken the projekt management of the R and D programme sector of waste management, subdivided into the programmes decommissioning and nuclear fuel cycle, and ultimate disposal of dangerous wastes. Ultimate disposal of dangerous wastes is understood to be the ultimate disposal of radioactive wastes and the dumping of chemical-toxic wastes. The progress report documents its programme sector of waste management. Its main part contains the formalized interim reports (as of 31.12.1991) on all projects attended by the manager of the waste management project, arranged according to promotion marks (letter C in the promotion mark stands for chemical-toxic, E for ultimate disposal, S for decommisioning, W for reprocessing, and U - for historical reasons - for university project). (orig./BBR) [de

  11. Preliminary study of the pozzolanic activity of dumped mine wastes obtained from the North Bohemian Basin in the Czech Republic

    Czech Academy of Sciences Publication Activity Database

    Sotiriadis, Konstantinos; Šašek, Petr; Ševčík, Radek; Schmidt, P.; Řehoř, M.; Viani, Alberto

    2017-01-01

    Roč. 23, č. 1 (2017), s. 64-69 ISSN 1392-1320 R&D Projects: GA MŠk(CZ) LO1219 Keywords : pozzolanic activity * dumped mine wastes * lime mortars * thermal analysis Subject RIV: JJ - Other Materials OBOR OECD: Materials engineering Impact factor: 0.393, year: 2016 https://www.exeley.com/materials_science/doi/10.5755/j01.ms.23.1.14864

  12. Ranking criteria for assessment of municipal solid waste dumping sites

    Directory of Open Access Journals (Sweden)

    Mahmood Khalid

    2017-03-01

    Full Text Available Priority wise channelization of resources is the key to successful environmental management, especially when funds are limited. The study in hand has successfully developed an algorithmic criterion to compare hazardous effects of Municipal Solid Waste (MSW dumping sites quantitatively. It is a Multi Criteria Analysis (MCA that has made use of the scaling function to normalize the data values, Analytical Hierarchy Process (AHP for assigning weights to input parameters showing their relevant importance, and Weighted Linear Combination (WLC for aggregating the normalized scores. Input parameters have been divided into three classes namely Resident’s Concerns, Groundwater Vulnerability and Surface Facilities. Remote Sensing data and GIS analysis were used to prepare most of the input data. To elaborate the idea, four dumpsites have been chosen as case study, namely Old-FSD, New-FSD, Saggian and Mahmood Booti. The comparison has been made first at class levels and then class scores have been aggregated into environmental normalized index for environmental impact ranking. The hierarchy of goodness found for the selected sites is New-FSD > Old-FSD > Mahmood Booti > Saggian with comparative scores of goodness to environment as 36.67, 28.43, 21.26 and 13.63 respectively. Flexibility of proposed model to adjust any number of classes and parameters in one class will be very helpful for developing world where availability of data is the biggest hurdle in research based environmental sustainability planning. The model can be run even without purchasing satellite data and GIS software, with little inaccuracy, using imagery and measurement tools provided by Google Earth.

  13. Radioactive-waste ocean dumping will have negligible enviromental impact

    International Nuclear Information System (INIS)

    Anon.

    1976-01-01

    This draft report is the result of extensive studies based on the best available information in the field of oceanography, marine radiobiology and health physics. On various basic considerations, assessment was undertaken, and the following conclusion was reached. The quantity of radioactivity to be dumped at one time is assumed to be 500 Ci in the case of test dumping, and 10 5 Ci/year in the case of full-scale dumping. The conditions required for the dumping sea area are that the bottom water flow and upwelling amount are limited, and that the sea bottom is flat. The horizontal dispersion coefficient of 10 7 cm 2 /sec and the vertical dispersion coefficient of 2 x 10 2 cm 2 /sec are assumed. It is assumed that the radionuclides in the disposed package would leached out as soon as it reaches the sea bottom, and would not show any physicochemical behavior. Typycal radionuclides are classified into 5 groups in terms of their half lives, and their estimated concentrations at 1 km depth are tabulated. The maximum level of individual dose and the magnitude of population dose were assessed on the fishermen working in the dumping sea area, and the adults, children and infants who were expected to receive higher dose on account of the larger intake of fish products than average. The dose level given with the dose assessment model and various panamentors under the dumping conditions is much lower than natural radiation and the permissible level recommended by ICRP. (Kobatake, H.)

  14. Reclamation of landfills and dumps of municipal solid waste in a energy efficient waste management system: methodology and practice

    Science.gov (United States)

    Orlova, Tatyana; Melnichuk, Aleksandr; Klimenko, Kseniya; Vitvitskaya, Valentina; Popovych, Valentina; Dunaieva, Ielizaveta; Terleev, Vitaly; Nikonorov, Aleksandr; Togo, Issa; Volkova, Yulia; Mirschel, Wilfried; Garmanov, Vitaly

    2017-10-01

    The article considers the methodological and practical aspects of reclamation of landfills and dumps of municipal solid waste in a waste management system. The general tendencies of system development in the context of elements of the international concept of waste hierarchy are analyzed. Statistics of the formation and burial of domestic waste indicate a strategic non-alternative to the rejection of landfill technologies in favor of environmentally, energy efficient and economically expedient ways of utilization of municipal waste as a world trend. Practical approaches to the study of territories on which there are dumps and landfills are considered to justify the design solutions for reclamation.

  15. Influence of coal ash and slag dumping on dump waste waters of the Kostolac power plants (Serbia)

    Energy Technology Data Exchange (ETDEWEB)

    Popovic, A.; Djinovic, J. [University of Belgrade, Belgrade (Serbia)

    2006-10-01

    The content of selected trace and major elements in the river water used for transport, as well as in the subcategories of the waste waters (overflow and drainage) were analyzed in order to establish the influence of transport and dumping of coal ash and slag from the 'Kostolac A' and 'Kostolac B' power plants located 100 km from Belgrade (Serbia). It was found that during transport of coal ash and slag to the dump, the water used for transport becomes enriched with manganese, nickel, zinc, chromium, vanadium, titanium, cobalt, arsenic, aluminum, and silicon, while more calcium, iron, cadmium, and lead are adsorbed by the ash and slag than is released from them. There is also an equilibrium between the release and adsorption processes of copper and magnesium during transport. The vertical penetration of the water used for transport results in a release of calcium, magnesium, manganese, and cadmium to the environment, while iron, nickel, zinc, chromium, copper, lead, vanadium, titanium, cobalt, and arsenic are adsorbed by the fractions of coal ash and slag in the dump.

  16. Feathered Detectives : Real-Time GPS Tracking of Scavenging Gulls Pinpoints Illegal Waste Dumping

    NARCIS (Netherlands)

    Navarro, J.; Grémillet, D.; Afán, I.; Ramírez, F.; Bouten, W.; Forero, M.G.

    2016-01-01

    Urban waste impacts human and environmental health, and waste management has become one of the major challenges of humanity. Concurrently with new directives due to manage this human by-product, illegal dumping has become one of the most lucrative activities of organized crime. Beyond economic

  17. Convention on the Prevention of Marine Pollution by Dumping of Wastes and Other Matter

    International Nuclear Information System (INIS)

    1974-01-01

    The Convention on the Prevention of Marine Pollution by Dumping of Wastes and Other Matter was drawn up at the Inter-Governmental Conference on the Dumping of Wastes at Sea, held in London from 30 October to 10 November 1972. The Governments of Mexico, the Union of Soviet Socialist Republics, the United Kingdom of Great Britain and Northern Ireland and the United States of America are the Depository Governments for instruments of ratification of, and accession to, the Convention, pursuant to Articles XVII and XVIII respectively

  18. Nuclear waste dumping in the oceans: Has the Cold War taught us anything?

    International Nuclear Information System (INIS)

    Moody-O'Grady, K.

    1995-01-01

    The United States and other international actors have relied without much success on traditional approaches to contain environmental damage done to our oceans by Russian dumping of nuclear waste. Our arms control experience suggests that on-site inspection is successful in situations where there is a lack of information or a lack of trust. Using on-site inspection to gather information and bolster trust could ameliorate the problem of Russian dumping of radioactive wastes into the ocean, so long as the political and financial costs of on-site inspection do not prove to be prohibitively high

  19. Convention on the Prevention of Marine Pollution by Dumping of Wastes and Other Matter

    International Nuclear Information System (INIS)

    1974-01-01

    The Convention on the Prevention of Marine Pollution by Dumping of Wastes and Other Matter was drawn up at the Inter-Governmental Conference on the Dumping of Wastes at Sea, held in London from 30 October to 10 November 1972. The Governments of Mexico, the Union of Soviet Socialist Republics, the United Kingdom of Great Britain and Northern Ireland and the United States of America are the Depository Governments for instruments of ratification of, and accession to, the Convention, pursuant to Articles XVII and XVIII respectively [es

  20. Mathematical Analysis of Malfunctions Caused by Seepage Water to the Republic Radioactive Waste Dump in Mochovce

    Directory of Open Access Journals (Sweden)

    Jozef Kuzma

    2007-01-01

    Full Text Available The storage of radioactive waste and the problem of assuring the low and medium radioactive waste is an actual interdisciplinary problem. An important factor influencing on a complex approach to solving these problems is also a creation of suitable technical conditions for its long-term storage. In this article we mathematically analyze an influence of the break covering and its effect on the long-term stability and reliable serviceability of the Republic radioactive waste dump in Mochovce.

  1. Mechanical characterization of municipal solid waste from two waste dumps at Delhi, India.

    Science.gov (United States)

    Ramaiah, B J; Ramana, G V; Datta, Manoj

    2017-10-01

    The article presents the physical and mechanical properties of the emplaced municipal solid waste (MSW) recovered from different locations of the Ghazipur and Okhla dumps both located at Delhi, India. Mechanical compressibility and shear strength of the collected MSW were evaluated using a 300×300mm direct shear (DS) shear box. Compression ratio (C c ') of MSW at these two dumps varied between 0.11 and 0.17 and is falling on the lower bound of the range (0.1-0.5) of the data reported in the literature for MSW. Low C c ' of MSW is attributed to the relatively low percentages of compressible elements such as textiles, plastics and paper, coupled with relatively high percentages of inert materials such as soil-like and gravel sized fractions. Shear strength of MSW tested is observed to be displacement dependent. The mobilized shear strength parameters i.e., the apparent cohesion intercept (c') and friction angle (ϕ') of MSW at these two dumps are best characterized by c'=13kPa and ϕ'=23° at 25mm displacement and c'=17kPa and ϕ'=34° at 55mm displacement and are in the range reported for MSW in the literature. A large database on the shear strength of MSW from 18 countries that includes: the experimental data from 277 large-scale DS tests (in-situ and laboratory) and the data from back analysis of 11 failed landfill slopes is statistically analyzed. Based on the analysis, a simple linear shear strength envelope, characterized by c'=17kPa and ϕ'=32°, is proposed for MSW for preliminary use in the absence of site-specific data for stability evaluation of the solid waste landfill under drained conditions. Copyright © 2017 Elsevier Ltd. All rights reserved.

  2. studies on municipal solid wastes dumping on soil anions, cations

    African Journals Online (AJOL)

    Osondu

    and selected soil enzymes activities of Njoku solid waste dumpsite Owerri municipal, Nigeria were investigated. ... wastes) and sometimes commercial wastes collected by a ... Ethiopian Journal of Environmental Studies and Management Vol.

  3. Identifying areas under potential risk of illegal construction and demolition waste dumping using GIS tools.

    Science.gov (United States)

    Seror, Nissim; Portnov, Boris A

    2018-05-01

    Construction and demolition (C&D) waste, dumped illegally in ravines and open areas, contaminates soil and can cause underground water pollution and forests fires. Yet, effective monitoring of illegal C&D waste dumping and enforcing legislation against the offenders are often a difficult task due to the large size of geographic areas that need to be monitored, and limited human and financial resources available to environmental law enforcement agencies. In this study, we use Geographic Information System (GIS) tools and geo-statistical modelling to identify the areas under potentially elevated risk of illegal C&D waste dumping in the Haifa district of Israel. As our analysis shows, locational factors, significantly associated with the accumulated amount of waste in the existing illegal C&D waste sites, include: distance to the nearest main road, depth of the ravine present at the site (pwaste dumping for future monitoring. As we suggest, the proposed approach may be useful for environmental law enforcement authorities, by helping them to focus on specific sites for inspection, save resources, and act against the offenders more efficiently. Copyright © 2018 Elsevier Ltd. All rights reserved.

  4. Feathered Detectives: Real-Time GPS Tracking of Scavenging Gulls Pinpoints Illegal Waste Dumping.

    Directory of Open Access Journals (Sweden)

    Joan Navarro

    Full Text Available Urban waste impacts human and environmental health, and waste management has become one of the major challenges of humanity. Concurrently with new directives due to manage this human by-product, illegal dumping has become one of the most lucrative activities of organized crime. Beyond economic fraud, illegal waste disposal strongly enhances uncontrolled dissemination of human pathogens, pollutants and invasive species. Here, we demonstrate the potential of novel real-time GPS tracking of scavenging species to detect environmental crime. Specifically, we were able to detect illegal activities at an officially closed dump, which was visited recurrently by 5 of 19 GPS-tracked yellow-legged gulls (Larus michahellis. In comparison with conventional land-based surveys, GPS tracking allows a much wider and cost-efficient spatiotemporal coverage, even of the most hazardous sites, while GPS data accessibility through the internet enables rapid intervention. Our results suggest that multi-species guilds of feathered detectives equipped with GPS and cameras could help fight illegal dumping at continental scales. We encourage further experimental studies, to infer waste detection thresholds in gulls and other scavenging species exploiting human waste dumps.

  5. VULNERABILITY OF MOUNTAIN RIVERS TO WASTE DUMPING FROM NEAMT COUNTY, ROMANIA

    Directory of Open Access Journals (Sweden)

    FLORIN-CONSTANTIN MIHAI

    2012-11-01

    Full Text Available Lack of waste management facilities from mountain region often lead to uncontrolled disposal of waste on river banks polluting the local environment and damaging the tourism potential. Geographical conditions influences the distribution of human settlements which are located along the rivers and its tributaries. This paper aims to estimate the amounts of household waste generated and uncollected disposed into mountain rivers, taking into account several factors such as:proximity of rivers to the human settlements, the morphology of villages, length of river that crosses the locality(built up areas, local population, the access to waste collection services and waste management infrastructure. Vulnerability of rivers to illegal dumping is performed using GIS techniques, highlighting the localities pressure on rivers in close proximity. For this purpose, it developed a calculation model for estimation the amounts of waste (kg that are dumped on a river section (m that crosses a locality (village or it is in close proximity. This estimation is based on the “principle of proximity and minimum effort” it can be applied in any mountainous region that are lacking or partially access to waste collection services. It is an assessment tool of mountain rivers vulnerability to waste dumping,taking into account the geographical and demographic conditions of the study area. Also the current dysfunctions are analyzed based on field observations.

  6. IAEA programmes on controlled and accidental radioactive waste dumping at sea

    International Nuclear Information System (INIS)

    Sjoeblom, K.L.

    1993-01-01

    The IAEA data base on sources of radioactive material entering the marine environment consists of two modules at present. The module Sea Disposal of Radioactive Wastes includes information on wastes containing a total activity of 140 PBq dumped between 1946 and 1992. The second module Accidents and Losses at Sea contains confirmed information on 18 accidents involving nuclear submarines, aircraft etc., as well as losses in the sea of more than 100 sealed sources. (orig.)

  7. Waste dumps in local communities in developing countries and hidden danger to health.

    Science.gov (United States)

    Anetor, Gloria O

    2016-07-01

    The rapid industrialisation and urbanisation fuelled by a fast-growing population has led to the generation of a huge amount of waste in most communities in developing countries. The hidden disorders and health dangers in waste dumps are often ignored. The waste generated in local communities is usually of a mixed type consisting of domestic waste and waste from small-scale industrial activities. Among these wastes are toxic metals, lead (Pb), cadmium (Cd), arsenic (As), mercury (Hg), halogenated organic compounds, plastics, remnants of paints that are themselves mixtures of hazardous substances, hydrocarbons and petroleum product-contaminated devices. Therefore, there is the urgent need to create an awareness of the harmful health effect of toxic wastes in developing countries, especially Nigeria. This is a review aimed at creating awareness on the hidden dangers of waste dumps to health in local communities in developing countries. Many publications in standard outlets use the following keywords: cancer, chemical toxicity, modern environmental health hazards, waste management and waste speciation in PubMed, ISI, Toxbase environmental digest, related base journals, and some standard textbooks, as well as the observation of the researcher between 1959 and 2014. Studies revealed the preponderance of toxic chemicals such as Pb, Cd, As and Hg in dump sites that have the risk of entering food chain and groundwater supplies, and these can give rise to endemic malnutrition and may also increase susceptibility to mutagenic substances, thereby increasing the incidence of cancer in developing countries. Industrialisation and urbanisation have brought about a change in the waste that is generated in contemporary communities in developing countries. Therefore, there is the need to embrace speciation and sound management of waste, probably including bioremediation. The populations in the local communities need regulatory agencies who are health educators as positive change

  8. Monitoring the rehabilitated waste rock dumps at the Rum Jungle mine site

    International Nuclear Information System (INIS)

    Bennett, J.W.; Harries, J.R.; Ritchie, A.I.M.

    1988-01-01

    Acid drainage and the release of heavy metals create a major environmental problem at many mine sites and the problem can continue long after mine operations cease. The long term control of these pollutants is essential for the acceptance of mining as a temporary land use. There is a need to compare the advantages, disadvantages and costs of various rehabilitation techniques. This paper describes measurements on two dumps of pyritic mine wastes from open cut mining before and after rehabilitation of the dumps. The effectiveness of the rehabilitation is discussed

  9. Arsenic mineralogy and mobility in the arsenic-rich historical mine waste dump

    International Nuclear Information System (INIS)

    Filippi, Michal; Drahota, Petr; Machovič, Vladimír; Böhmová, Vlasta; Mihaljevič, Martin

    2015-01-01

    A more than 250 year-old mine dump was studied to document the products of long-term arsenopyrite oxidation under natural conditions in a coarse-grained mine waste dump and to evaluate the environmental hazards associated with this material. Using complementary mineralogical and chemical approaches (SEM/EDS/WDS, XRD, micro-Raman spectroscopy, pore water analysis, chemical extraction techniques and thermodynamic PHREEQC-2 modeling), we documented the mineralogical/geochemical characteristics of the dumped arsenopyrite-rich material and environmental stability of the newly formed secondary minerals. A distinct mineralogical zonation was found (listed based on the distance from the decomposed arsenopyrite): scorodite (locally associated with native sulfur pseudomorphs) plus amorphous ferric arsenate (AFA/pitticite), kaňkite, As-bearing ferric (hydr)oxides and jarosite. Ferric arsenates and ferric (hydr)oxides were found to dissolve and again precipitate from downward migrating As-rich solutions cementing rock fragments. Acidic pore water (pH 3.8) has elevated concentrations of As with an average value of about 2.9 mg L −1 . Aqueous As is highly correlated with pH (R 2 = 0.97, p < 0.001) indicating that incongruent dissolution of ferric arsenates controls dissolved As well as the pH of the percolating waste solution. Arsenic released from the dissolution of ferric arsenates into the pore water is, however, trapped by latter and lower-down precipitating jarosite and especially ferric (hydr)oxides. The efficiency of As sequestration by ferric (hydr)oxides in the waste dump and underlying soil has been found to be very effective, suggesting limited environmental impact of the mine waste dump on the surrounding soil ecosystems. - Highlights: • More than 250 year-old arsenopyrite-rich mine waste dump was studied. • Mineral transformation and the environmental stability of different secondary arsenic mineral phases were assessed. • High efficiency of As

  10. Potential conflicts connected with the recovery of secondary materials from post mining waste dump

    Directory of Open Access Journals (Sweden)

    Gawor Łukasz

    2017-12-01

    Full Text Available Coal mine spoil dumping grounds are present in the landscape of every mining region. Although the composition of waste material is in general safe for the environment (sedimentary rocks – sandstones, mudstones and siltstones, there may be up to 10% of coal particles in disposed wastes. The presence of organic material causes self-ignition processes and fire hazards. There is a need and the possibility of the recovery of coal, and which should be conducted according to legal regulations and environmental protection rules. The recovery should also be preceded by a feasibility study, a drilling campaign, laboratory tests and requires different environmental permissions. Recovery processes are connected with the work of a preparation plant, which is usually linked with protests from the local community and potential conflicts. This article presents the most significant hazards to the environment, health and human life connected with the functions associated with the installation of the recovery processes of coal from waste material deposited on the dumps. The methods of reducing these threats are described with regards to legal regulations, particularly law deeds concerning the safe recovery processes and further reclamation and restoration of degraded post-mining dumping grounds. The role and participation of interested community members at the preparation for investment stage as well as the period of realization of the preparation processes is described. The question of re-using and managing the post-mining dumping grounds after completion of the recovery processes is discussed.

  11. A heat source probe for measuring thermal conductivity in waste rock dumps

    International Nuclear Information System (INIS)

    Blackford, M.G.; Harries, J.R.

    1985-10-01

    The development and use of a heat source probe to measure the thermal conductivity of the material in a waste rock dump is described. The probe releases heat at a constant rate into the surrounding material and the resulting temperature rise is inversely related to the thermal conductivity. The probe was designed for use in holes in the dump which are lined with 50 mm i.d. polyethylene liners. The poor thermal contact between the probe and the liner and the unknown conductivity of the backfill material around the liner necessitated long heating and cooling times (>10 hours) to ensure that the thermal conductivity of the dump material was being measured. Temperature data acquired in the field were analysed by comparing them with temperatures calculated using a two-dimensional cylindrical model of the probe and surrounding material, and the heat transfer code HEATRAN

  12. A review of acid drainage from waste rock dumps and mine sites (Australian and Scandinavia)

    International Nuclear Information System (INIS)

    Harries, J.R.

    1990-05-01

    This report reviews the literature from Australia and Scandinavia on acid drainage from pyritic waste rock dumps with an emphasis on measurements and theory of processes that control the rage of oxidation and the release of pollutants. Conditions within waste rock dumps have been measured at several mine sites and a range of rehabilitation treatments have been tried to reduce the release of pollutants. A number of models have been proposed to calculate air flow, water transport and geochemistry. The data and experience at the mine sites are compared with predictions of the models. Details of Australian and Swedish mine sites where waste rock is a source of acid drainage are described in the Appendices. 92 refs., 2 tabs., 10 figs

  13. Radionuclide distributions in sediments of marine areas used for dumping solidified radioactive wastes

    International Nuclear Information System (INIS)

    Bowen, V.T.; Livingston, H.D.

    A number of sediment samples, collected both by coring and by grabbing, from the shallow Pacific solid waste radioactive dump site and from the Atlantic dump site, have been analyzed carefully for a number of long-lived radionuclides. Both dump sites yielded samples that were expected to serve as controls, collected at considerable distance from any visually-located waste containers, as well as other samples that were collected close to identified waste drums, some of which showed evidence of physical disintegration. The Atlantic site shows evidence of wide-spread, general contamination, with 137 Cs and possibly with 241 Am. The Pacific site is perhaps less generally contaminated with 137 Cs, but shows evidence of widespread general contamination with several transuranic nuclides. Samples collected near to identified waste containers, at both sites, show that significant portions of leached radioactivity ( 137 Cs, 239 240 Pu, 238 Pu, 241 Am, 242 Cm, and 244 Cm) are immobilized by the sediments within very short distances, possibly measured in meters or tens of meters. The data also suggest considerable differences among the horizontal trajectories of the various leached transuranic elements. It is argued that careful study of nuclide distributions around such old waste containers would provide data of great value in helping to predict long-term behavior of radionuclides released to marine environments

  14. The role of the IAEA in the London Convention 1972 on Dumping of Wastes at Sea

    International Nuclear Information System (INIS)

    Telleria, Diego; Berkovsky, Volodymyr; Jova Sed, Luis; Louvat, Didier

    2008-01-01

    Full text: The Convention on the Prevention of Marine Pollution by Dumping of Wastes and Other Matter was adopted after an Inter-Governmental Conference, held in London in 1972, following the principles for environmental protection enunciated in the Report of the United Nations Conference on Human Environment, held the same year in Stockholm. The IAEA has been involved since the early days of the London Convention when the Contracting Parties designated the IAEA as the competent international authority in matters related to sea disposal of radioactive waste, providing technical advice and services. The IAEA developed, for the Convention, the definition of 'radioactive wastes or radioactive matters unsuitable for dumping at sea' (e.g., high level radioactive waste) and recommended the technical basis applicable by the national authorities to issue special permits for those radioactive materials which could be dumped (mainly low and intermediate level radioactive waste, properly conditioned and 'de minimis' quantities). However, in 1985, based more on political reasons than on the existing radiation protection principles and policies, the Contracting Parties to the London Convention introduced a 'voluntary moratorium' on the disposal of low level radioactive wastes at sea, and later in 1993, a total ban of radioactive waste disposal at sea. The IAEA continues to support the objectives of the London Convention by providing scientific advice. Since 1989, at the request of the Contracting Parties, the IAEA has developed and maintained global databases on radioactive waste disposed of at sea in the past and on accidents and losses at sea involving radioactive material. The purpose of these databases is to serve as the basis for radiological impact assessment on the marine environment. The last revised reports on the above mentioned inventories were published in 1999 and in 2001 respectively. The databases are currently in the process of being updated. The paper presents

  15. Risk assessment and monitoring at the Farallon Islands (CA) radioactive waste dump sites

    International Nuclear Information System (INIS)

    Curl, H. Jr.; Ueber, E.; Roletto, J.

    1993-01-01

    Between 1946 and 1965 over 47,000 drums, concrete blocks and other containers of radioactive waste were dumped at three sites southwest of the Farallon Islands off the coast of San Francisco, CA. A total of approximately 4,500 Ci of thorium, uranium and other radionuclides was dumped. After 1965, and until 1972, dumping of dredged spoils, laboratory waste, etc. containing unknown amounts of toxic materials, continued. Concerns have arisen from time to time about the integrity of the containers and possible release of radionuclides and toxic materials into the ecosystem and the human food chain. Based on evaluation of all dumping records, sampling of fish and sediments, and modeling the authors conclude: the risk to resources at present is well below the level of concern. Hazard quotients of 4.7 x 10 exp -2 or less were calculated for all target species. The dominant radiation source is from external gamma radiation from the short-lived daughter of 137 Cs, 137 Ba, in sediments. Much of the 137 Cs has already decayed. The long-lived isotopes of Pu and Am will reach maximum advective release rates 80--200 after disposal. The maximum dose from these isotopes is an order of magnitude less than from 137 Cs. Radioanalysis of fish and sediments from one dumpsite in 1992 show values equal to those from two nearby reference sites

  16. Radiological characterisation of an industrial waste dump at a fertilizer plant in Tarragona (Spain)

    International Nuclear Information System (INIS)

    Ortega, X.; Amor Duch, M.; Valles, I.; Vargas, A.; Lopez, N.

    2006-01-01

    The solid waste coming from the fertilizer factory belonging to the Ercros Company in the town of Flix (Tarragona-Spain) is stocked in an industrial dump located close to the town. Measurements of natural radionuclide activity, principally from the U-238 chain, were done from mud samples taken from various depth points and areas within the dump. Specific activity of the various components of the chain reaches values in the range of 2000 to 4500 Bq/kg. There were some values outside this range, chiefly in the case of Th-230, which reached values of 13000 Bq/kg. The total radioactive inventory in the dump if long-period radioisotopes are considered, can be estimated to be approximately 9000 GBq. Determination of equivalent environmental dose using thermoluminescent dosemeters reached values less than 1.8 mSv/year, if permanence was supposed. Radiological testing of atmospheric dust collected at the site did not show significant values. Average radon concentrations of 30 Bq/m 3 , were measured, slightly higher than 10 Bq/m 3 , a value that was considered as a reference value for the area. Values for the increase of the effective dose due to external or internal exposure caused by the waste at the dump are lower than 1 mSv/year. (authors)

  17. Pollution of the Marine Environment by Dumping: Legal Framework Applicable to Dumped Chemical Weapons and Nuclear Waste in the Arctic Ocean

    OpenAIRE

    Lott, Alexander

    2016-01-01

    The Arctic seas are the world’s biggest dumping ground for sea-disposed nuclear waste and have served among the primary disposal sites for chemical warfare agents. Despite of scientific uncertainty, the Arctic Council has noted that this hazardous waste still affects adversely the Arctic marine environment and may have implications to the health of the Arctic people. The purpose of this manuscript is to establish the rights and obligations of the Arctic States in c...

  18. Waste picker livelihoods and inclusive neoliberal municipal solid waste management policies: The case of the La Chureca garbage dump site in Managua, Nicaragua.

    Science.gov (United States)

    Hartmann, Chris

    2018-01-01

    The modernization (i.e. mechanization, formalization, and capital intensification) and enclosure of municipal solid waste management (MSWM) systems threaten waste picker livelihoods. From 2009 to 2013, a major development project, embodying traditional neoliberal policies with inclusive social policies, transformed the Managua, Nicaragua, municipal solid waste site from an open-air dump where as many as 2,000 informal waste pickers toiled to a sanitary landfill. To investigate waste pickers' social and economic condition, including labor characteristics, household income, and poverty incidence, after the project's completion, 146 semi-structured survey questionnaires were administered to four communities adjacent to the landfill and 45 semi-structured interviews were completed with key stakeholders. Findings indicate that hundreds of waste pickers were displaced by the project, employment benefits from the project were unevenly distributed by neighborhood, and informal waste picking endures due to persistent impoverishment, thereby contributing to continued social and economic marginalization and environmental degradation. The findings highlight the limitations of inclusive neoliberal development efforts to transform MSWM in a low-income country. Copyright © 2017 Elsevier Ltd. All rights reserved.

  19. Emission of Polycyclic Aromatic Hydrocarbons from the Exhalation Zones of Thermally Active Mine Waste Dumps

    Directory of Open Access Journals (Sweden)

    Patrycja Kuna-Gwoździewicz

    2013-01-01

    Full Text Available The article presents results of research carried out on the occurrence of polycyclic aromatic hydrocarbons (PAH in gases of exhalation zones, created on the surface of a thermally active coal mine waste dump. The oxidation and self-heating of mine waste are accompanied with the intensive emission of flue gases, including PAH group compounds. Taking into consideration the fact the hydrocarbons show strong genotoxic, mutagenic and carcinogenic properties, research was conducted to establish their content in the examined gases. The research object was a gangue dump located in Rybnik. The research was performed in 2012. In total, 24 samples of gas were collected with PUF (polyurethane foam sampling cartridges with a quartz fibre filter and an aspirator. The collected samples were analysed with the use of high performance liquid chromatography (HPLC and a fluorescence detector (FLD to evaluate the amount of PAH present.

  20. Identification and analysis the illegal dumping spot of solid waste at Ciliwung segment 5 riverbanks

    Science.gov (United States)

    Indrawati, D.; Purwaningrum, P.

    2018-01-01

    Ciliwung River is the main river in the area of Jakarta that is divided into six segments across West Java and Jakarta. The study focuses on the fifth segment which is 30 km long, covering from Kelapa Dua Depok to Manggarai, South Jakarta. The survey of the river consists of 3 sub-segments: Lenteng Agung, Pejaten Timur and Manggarai. Objectives of the study are to describe the characteristics and typology of the residential surrounding the Ciliwung Segment 5 Riverbank, to identification the illegal dumping spot of solid waste, to measure the volume and composition of solid waste in the riverbank, to decide solid waste management for residential area surrounding river banks to control the river pollution. The study shows that there are 11 illegal dumping spot of solid waste consisting of 4.37 m3 solid waste volume. The average composition of solid waste consists of 44% organic, 14% woods, 12% papers, 11% plastics, 3% rubbers, 1% metals and 2% others. To control the river pollution efforts are restoring the function of riverbanks to become green open space area, installing the trash rack into the river, to manage domestic solid waste based on 3R (Reduce, Reuse, Recycle) concept.

  1. Characteristics and suitability of waste dump sites in Owerri, Nigeria ...

    African Journals Online (AJOL)

    A five point criteria screening of the three major waste dumpsites in Owerri Municipality was identified, and a ranking procedure adopted to determine the suitability or otherwise of the dumpsites. The sites were screened and ranked hydro-geologically and geo-technically in order of suitable, moderately suitable, and not ...

  2. Nitrate release from waste rock dumps in the Elk Valley, British Columbia, Canada.

    Science.gov (United States)

    Mahmood, Fazilatun N; Barbour, S Lee; Kennedy, C; Hendry, M Jim

    2017-12-15

    The origin, distribution and leaching of nitrate (NO 3 - ) from coal waste rock dumps in the Elk Valley, British Columbia, Canada were defined using chemical and NO 3 - isotope analyses (δ 15 N- and δ 18 O-NO 3 - ) of solids samples of pre- and post-blast waste rock and from thick (up to 180m) unsaturated waste rock dump profiles constructed between 1982 and 2012 as well as water samples collected from a rock drain located at the base of one dump and effluent from humidity cell (HC) and leach pad (LP) tests on waste rock. δ 15 N- and δ 18 O-NO 3 - values and NO 3 - concentrations of waste rock and rock drain waters confirmed the source of NO 3 - in the waste rock to be explosives and that limited to no denitrification occurs in the dump. The average mass of N released during blasting was estimated to be about 3-6% of the N in the explosives. NO 3 - concentrations in the fresh-blast waste rock and recently placed waste rock used for the HC and LP experiments were highly variable, ranging from below detection to 241mg/kg. The mean and median concentrations of these samples ranged from 10-30mg/kg. In this range of concentrations, the initial aqueous concentration of fresh-blasted waste rock could range from approximately 200-600mg NO 3 - -N/L. Flushing of NO 3 - from the HCs, LPs and a deep field profile was simulated using a scale dependent leaching efficiency (f) where f ranged from 5-15% for HCs, to 35-80% for the LPs, to 80-90% for the field profile. Our findings show aqueous phase NO 3 - from blasting residuals is present at highly variable initial concentrations in waste rock and the majority of this NO 3 - (>75%) should be flushed by recharging water during displacement of the first stored water volume. Copyright © 2017 Elsevier B.V. All rights reserved.

  3. Metal uptake by native plants and revegetation potential of mining sulfide-rich waste-dumps.

    Science.gov (United States)

    Gomes, Patrícia; Valente, Teresa; Pamplona, Jorge; Braga, Maria Amália Sequeira; Pissarra, José; Gil, José António Grande; de la Torre, Maria Luisa

    2014-01-01

    Waste dumps resulting from metal exploitation create serious environmental damage, providing soil and water degradation over long distances. Phytostabilization can be used to remediate these mining sites. The present study aims to evaluate the behavior of selected plant species (Erica arborea, Ulex europaeus, Agrostis delicatula, and Cytisus multiflorus) that grow spontaneously in three sulfide-rich waste-dumps (Lapa Grande, Cerdeirinha, and Penedono, Portugal). These sites represent different geological, climatic and floristic settings. The results indicate distinctive levels and types of metal contamination: Penedono presents highest sulfate and metal contents, especially As, with low levels of Fe. In contrast, at Lapa Grande and Cerdeirinha Fe, Mn, and Zn are the dominant metals. In accordance, each waste dump develops a typical plant community, providing a specific vegetation inventory. At Penedono, Agrostis delicatula accumulates As, Pb, Cu, Mn, and Zn, showing higher bioaccumulation factors (BF) for Mn (32.1) and As (24.4). At Cerdeirinha, Ulex europaeus has the highest BF for Pb (984), while at Lapa Grande, Erica arborea presents high BF for Mn (9.8) and Pb (8.1). Regarding TF, low values were obtained for most of the metals, especially As (TF < 1). Therefore, the results obtained from representative plant species suggest appropriate behavior for phytostabilization measures.

  4. International aspects of the management of low-level dumping of radioactive wastes in the oceans

    International Nuclear Information System (INIS)

    Templeton, W.L.

    1982-01-01

    The following topics are discussed: international regulations governing radioactive waste disposal; radiological principles as applied to disposal to the environment; historical dumping practices; assessment of the North East Atlantic dump site; IAEA generic studies; and national and international implications. A recent analysis of international issues associated with ocean disposal of low-level radioactive wastes indicated a number of points which impact on US needs and policies and need resolution. The first is that the development of adequate international criteria and standards will assist the US in evaluating the option of using the oceans for the disposal of low-level radioactive wastes. Secondly, it is essential that international cooperation in research and radiological surveillance be expanded. Thirdly, the delays in the agreements on international mechanisms, criteria and standards, sometimes as a direct result of a lack of coordinated US policies makes the implementation of the intent of the London Dumping Convention and the NEA mechanism more difficult. Last of all in the unresolved question of how the US should apply the London Convention to the 200 mile exclusive economic zone

  5. Decision of the Council establishing a multilateral consultation and surveillance mechanism for sea dumping of radioactive waste

    International Nuclear Information System (INIS)

    1977-01-01

    This Mechanism set up by the OECD Council on 22nd July, 1977 supplements the system established by the 1975 London Convention on prevention of marine pollution by dumping of wastes and the IAEA provisional definition and recommendations. It lays down further compulsory rules on sea dumping of radioactive waste and provides for a prior notification and consultation procedure (choice of dumping site, containers, ships etc), international surveillance and an information system consisting of regular updating of standards guidelines and recommendations to be applied in the field. (NEA) [fr

  6. Operational Waste Volume Projection

    Energy Technology Data Exchange (ETDEWEB)

    STRODE, J.N.

    2000-08-28

    Waste receipts to the double-shell tank system are analyzed and wastes through the year 2015 are projected based on generation trends of the past 12 months. A computer simulation of site operations is performed, which results in projections of tank fill schedules, tank transfers, evaporator operations, tank retrieval, and aging waste tank usage. This projection incorporates current budget planning and the clean-up schedule of the Tri-Party Agreement. Assumptions were current as of June. 2000.

  7. Operational waste volume projection

    International Nuclear Information System (INIS)

    Koreski, G.M.; Strode, J.N.

    1995-06-01

    Waste receipts to the double-shell tank system are analyzed and wastes through the year 2015 are projected based on generation trends of the past 12 months. A computer simulation of site operations is performed, which results in projections of tank fill schedules, tank transfers, evaporator operations, tank retrieval, and aging waste tank usage. This projection incorporates current budget planning and the clean-up schedule of the tri-party agreement. Assumptions are current as of June 1995

  8. Operational Waste Volume Projection

    International Nuclear Information System (INIS)

    STRODE, J.N.

    2000-01-01

    Waste receipts to the double-shell tank system are analyzed and wastes through the year 2015 are projected based on generation trends of the past 12 months. A computer simulation of site operations is performed, which results in projections of tank fill schedules, tank transfers, evaporator operations, tank retrieval, and aging waste tank usage. This projection incorporates current budget planning and the clean-up schedule of the Tri-Party Agreement. Assumptions were current as of June. 2000

  9. Moessbauer, TEM/SAED and XRD investigation on waste dumps of the Valea lui Stan gold mines

    Energy Technology Data Exchange (ETDEWEB)

    Constantinescu, Serban Grigore, E-mail: sconst@infim.ro [National Institute of Materials Physics, Bucharest-Magurele (Romania); Udubasa, Sorin S.; Udubasa, Gheorghe [University of Bucharest, Fac. of Geology and Geophysics (Romania); Kuncser, Victor; Popescu-Pogrion, Nicoleta; Mercioniu, Ionel; Feder, Marcel [National Institute of Materials Physics, Bucharest-Magurele (Romania)

    2012-03-15

    The complementary investigation techniques, Moessbauer spectroscopy, transmission electron microscopy with selected area electron diffraction (TEM/SAED), X-ray diffraction (XRD) have been used to investigate the fate of the Valea lui Stan, Romania, gold-ore nanoscale-minerals during the long time of residence in the waste dumps. The preliminary investigations showed such waste dumps to contain significant amount of metals which cannot be identified by conventional methods. An intense research activity started up in order to evaluate the possibilities to recycle Valea lui Stan waste dumps and to recover metals by chemical or phytoextraction procedures. The waste dumps naturally show different mineral constituents with clay minerals as major phases, observed by XRD-technique. Although the waste dumps materials have whitish-yellowish colours, MOeSSBAUER technique evidences the presence of the finely dispersed iron bearing minerals. The authors are focusing to inspect and analyze Fe-compounds in the samples collected from Valea lui Stan's waste dumps in order to identify the magnetic phases by Moessbauer technique.

  10. Joint Russian-Norwegian collaboration on radioactive contamination from dumped nuclear waste in the Kara Sea

    International Nuclear Information System (INIS)

    Nikitin, A.I.; Salbu, B.; Strand, P.

    1995-01-01

    Joint Russian-Norwegian expeditions to the Kara Sea have taken place annually since 1992. The 1992 expedition to the open Kara Sea included for the first time scientists from Western countries. During the 1993 expedition underwater investigations of dumped objects in the Tsivolky Fjord and the Stepovogo Fjord was performed in addition to sample collection. This program was also carried out in the Abrosimov Fjord and the Stepovogo Fjord in 1994. The enhanced levels of 137 Cs and 90 Sr, and the presence of 60 Co in sediments from Stepovogo Fjord as well as traces of 60 Co in samples from Tsivolky Fjord, show that leakage from dumped radioactive water has taken place. The contamination was localized to nearby dumped objects. The concentrations of radionuclides in waters and sediments in the open Kara Sea are presently very low and significantly lower than in other marine areas, e.g. the Irish Sea, the Baltic Sea, and the North Sea. The results imply that the impact of radioactive contamination from dumped radioactive waste on the Kara Sea environment is at present very low. 4 refs., 1 fig., 2 tabs

  11. Evaluation of the superficial water quality in the affected area of a waste dump

    Directory of Open Access Journals (Sweden)

    Anne Relvas Pereira

    2013-12-01

    Full Text Available Improper disposal of solid waste in dumps can create various environmental problems, including risk of contamination of surface and groundwater by leachate, a fact which may have serious consequences for public health. In this context, the objective of this work was to evaluate the superficial water quality of the Juma River near the Apui/AM dump. Analyses were performed in dry and rainy seasons and at two points, one upstream and one downstream from the dump. The following physical, chemical and biological parameters that comprise the Water Quality Index (Portuguese acronym, IQA were evaluated: thermotolerant coliforms, Biochemical Oxygen Demand (BOD5,20, total phosphorus, total nitrogen, dissolved oxygen, pH, total residue, water temperature and turbidity. All of the parameters were within the range permitted by regulation, with the exception of pH, which was out of the minimum permitted value, due to the natural characteristics of the watershed. The IQA showed good quality, varying from 62% to 66% between the collection points, indicating that the dump has no influence on water quality.

  12. Proceedings of the symposium on the management and rehabilitation of waste rock dumps

    International Nuclear Information System (INIS)

    Riley, S.R.; Waggitt, P.W.; McQuade, C.

    1993-01-01

    Waste rock management and rehabilitation are issues with economic, legal and scientific ramifications which may have significant effects on the viability and profitability of mining operations. Through this symposium the Office of the Supervising Scientist and the Australasian Institute of Mining and Metallurgy (Darwin branch) brought together five key disciplines essential for the efficient design and long term management of waste rock dump, planning and economics, hydrology, geochemistry, biology and geotechnics. The symposium was targeted at industry personnel who make the decisions in design planning and day-to-day management. Two out of the 13 papers have been separately indexed

  13. Selected Black-Coal Mine Waste Dumps in the Ostrava-Karviná Region: An Analysis of Their Potential Use

    Science.gov (United States)

    Niemiec, Dominik; Duraj, Miloš; Cheng, Xianfeng; Marschalko, Marian; Kubáč, Jan

    2017-12-01

    The paper aims to analyse the options for the use of selected black-coal mine waste dump bodies in the Ostrava-Karviná Region. In the Czech Republic there are approximately 70 mine waste dumps, out of which 50 are located in the Ostrava-Karviná Coal District. The issue is highly topical, particularly in the region, because the dump bodies significantly affect the landscape character of the Ostrava-Karviná Region and pose ecological risks. In such cases, their redevelopment and land reclamation are not easy either from the environmental or economic points of view. It is clear that the redevelopment of such geological environment is difficult, and it is vital to make the right decisions as for what purposes the mine waste dumps should be used. Next, it is important to take into account all the economic and environmental aspects of the locality in question.

  14. Investigation on the oxygen transport mechanisms in the Sarcheshmeh waste rock dumps

    Directory of Open Access Journals (Sweden)

    Saeed Yousefi

    2015-04-01

    Full Text Available Introduction Pyrite oxidation and acid mine drainage (AMD are the serious environmental problems associated with the mining activities in sulphide ores. The rate of pyrite oxidation is governed by the availability of oxygen (Borden, 2003. Therefore, the identifying oxygen supplying mechanism is one of the most important issues related to the environmental assessment of waste rock dumps (Cathles and Apps, 1975; Jaynes et al., 1984; Davis and Ritchie, 1986. Although comprehensive researches were performed on the mathematical description of oxygen transport processes using the numerical modeling (Morin et al., 1988; Blowes et al., 1991; Wunderly et al., 1986; Elberling et al., 1994; Jannesar Malakooti et al., 2014, so far, the interactions between these processes and geochemical and mineralogical characteristics has not been studied especially in waste rock dumps. Therefore the main objective of this study is to identify the evidences for knowing the oxygen transport mechanisms in the waste dumps and also, its role in intensity of pyrite oxidation. It is expected that such these structural studies could be useful for better understanding of dominant processes in numerical modeling and also providing environmental management strategies in the study area and other sites by similar characteristics. Materials and Methods In this study, thirty solid samples were collected from six excavated trenches in the waste rock dumps No. 19 and 31 of the Sarcheshmeh porphyry copper mine. Collected samples were studied using several methods such as XRD, ASTM-D2492, paste pH and grain size distribution. The results obtained from these methods were used with the field observations in order to characterize some detail information about oxygen supplying mechanisms for oxidation reactions in the waste rock dumps. Result The main minerals found by the XRD analysis were quartz and muscovite which were present in all samples. Pyrite, orthose, albite, and chlorite were also

  15. Requirements of the London Convention for dumping radioactive waste at sea

    International Nuclear Information System (INIS)

    Sutton, H.C.

    1982-10-01

    This report outlines the requirements of the London Convention for dumping radioactive waste at sea and considers their scientific basis more fully. It is intended primarily as an appraisal and aid to understanding of the two documents IAEA 210 and IAEA 211, published by the International Atomic Energy Agency, and relating to the oceanographic and radiobiological basis of their definitions of high level waste and recommendations relating to its dumping at sea, which were required for London Convention purposes. The adequacy and conservation in these recommendations are considered, and the report also compares the predictions of the model on which the recommendations are based with some limited but relevant observations on radiation doses resulting from natural causes (radium in the sea), and from fallout from nuclear bomb tests. It is concluded that if dumping is carried out within the limits and according to the recommendations required by the IAEA, then it is extremely unlikely that this could lead to significant human hazard, either now or in the future. Some of the reasons for this conclusion are summarised in the final chapter

  16. A preliminary assessment of potential doses to man from radioactive waste dumped in the Arctic Sea

    Energy Technology Data Exchange (ETDEWEB)

    Nielsen, S P [Forskningscente Risoe, Roskilde (Denmark); Iosjpe, M; Strand, P [Norwegian Radiation Protection Authority, Oesteraas (Norway)

    1995-09-01

    This report describes a preliminary radiological assessment of collective doses to the world population from radioactive material dumped in the Barents and Kara Seas in the period 1961-1991. Information on the dumped waste and the rates of release of radionuclides have been available from Russian sources and from the International Atomic Energy Agency. A box model has been used to simulate the dispersion of radionuclides in the marine environment and to calculate the contamination of seafood and the subsequent radiation doses to man. Two release scenarios have been adopted. The worst-case release scenario which ignores the presence of barriers between spent nuclear fuel and seawater is estimated to give rise to about 10 mansieverts calculated to 1000 years from the time of release. A more realistic release scenario is estimated to cause about 3 mansieverts. In both cases exposure from the radionuclide {sup 137}Cs is found to dominate the doses. (au) 8 tabs., 56 ills., 19 refs.

  17. A preliminary assessment of potential doses to man from radioactive waste dumped in the Arctic sea

    International Nuclear Information System (INIS)

    Nielsen, S.P.; Iosjpe, M.; Strand, P.

    1995-11-01

    This report describes a preliminary radiological assessment of collective doses to the world population from radioactive material dumped in the Kara and Barents Seas in the period 1961-1991. Information on the dumped waste and the rates of release of radionuclides have been available from Russian sources and from the International Atomic Energy Agency. A box model has been used to simulate the dispersion of radionuclides in the marine environment and to calculate the contamination of seafood and the subsequent radiation doses to man. Two release scenarios have been adopted. The worst-case release scenario, which ignores the presence of barriers between spent nuclear fuel and seawater, is estimated to give rise to about 10 mansievert calculated to 1000 years from the time of release. A more realistic release scenario is estimated to cause about 3 mansieverts. In both cases exposure from the radionuclide 137 Cs is found to dominate the doses. 19 refs., 56 figs., 8 tabs

  18. A preliminary assessment of potential doses to man from radioactive waste dumped in the Arctic Sea

    International Nuclear Information System (INIS)

    Nielsen, S.P.; Iosjpe, M.; Strand, P.

    1995-09-01

    This report describes a preliminary radiological assessment of collective doses to the world population from radioactive material dumped in the Barents and Kara Seas in the period 1961-1991. Information on the dumped waste and the rates of release of radionuclides have been available from Russian sources and from the International Atomic Energy Agency. A box model has been used to simulate the dispersion of radionuclides in the marine environment and to calculate the contamination of seafood and the subsequent radiation doses to man. Two release scenarios have been adopted. The worst-case release scenario which ignores the presence of barriers between spent nuclear fuel and seawater is estimated to give rise to about 10 mansieverts calculated to 1000 years from the time of release. A more realistic release scenario is estimated to cause about 3 mansieverts. In both cases exposure from the radionuclide 137 Cs is found to dominate the doses. (au) 8 tabs., 56 ills., 19 refs

  19. Closure Report for Corrective Action Unit 143: Area 25 Contaminated Waste Dumps, Nevada Test Site, Nevada

    International Nuclear Information System (INIS)

    Tobiason, D. S.

    2002-01-01

    This Closure Report (CR) has been prepared for the Area 25 Contaminated Waste Dumps (CWD), Corrective Action Unit (CAU) 143 in accordance with the Federal Facility Agreement and Consent Order [FFACO] (FFACO, 1996) and the Nevada Division of Environmental Protection (NDEP)-approved Corrective Action Plan (CAP) for CAU 143: Area 25, Contaminated Waste Dumps, Nevada Test Site, Nevada. CAU 143 consists of two Corrective Action Sites (CASs): 25-23-09 CWD No.1, and 25-23-03 CWD No.2. The Area 25 CWDs are historic disposal units within the Area 25 Reactor Maintenance, Assembly, and Disassembly (R-MAD), and Engine Maintenance, Assembly, and Disassembly (E-MAD) compounds located on the Nevada Test Site (NTS). The R-MAD and E-MAD facilities originally supported a portion of the Nuclear Rocket Development Station in Area 25 of the NTS. CWD No.1 CAS 25-23-09 received solid radioactive waste from the R-MAD Compound (East Trestle and West Trench Berms) and 25-23-03 CWD No.2 received solid radioactive waste from the E-MAD Compound (E-MAD Trench)

  20. Deep circulation in the Indian and Pacific Oceans and its implication for the dumping of low-level radioactive waste

    International Nuclear Information System (INIS)

    Harries, J.R.

    1980-06-01

    The complexity of ocean transport processes has meant that the limits for the dumping of low-activity radioactive wastes have had to be based on very simplified models of the oceans. This report discusses the models used to determine dumping limits and contrasts them with the known ocean circulation patterns. The deep circulations of the Indian and Pacific Oceans are reviewed to provide a basis for estimating the possible destinations and likely transit times for dissolved material released at the ocean floor

  1. Illegal Dumping of Toxic Waste and Its Effect on Human Health in Campania, Italy.

    Science.gov (United States)

    Mazza, Alfredo; Piscitelli, Prisco; Neglia, Cosimo; Della Rosa, Giulia; Iannuzzi, Leopoldo

    2015-06-16

    The region of Campania (particularly Naples and Caserta) has experienced an emergency in the waste management cycle during past years. Although the most critical phase has been overcome after the construction of the incineration plant in Acerra (an old-fashioned technology built up over a few months, whose impact on environment and health has not yet been assessed), most of the underlying problems have not been resolved. The illegal burning of wheels, plastics, textiles, and other industrial residuals, along with the detection of two thousand toxic substance dumping sites, still represents major concerns of environmental pollution and population health. This review summarizes the most relevant studies, which analyzed chemical contamination (primarily dioxins and polychlorinated biphenyls (PCBs)) of the air, soil, water, animals, and humans in Campania. In addition, we reviewed information on population health (i.e., mortality data, congenital malformations, and cancer incidence). Moving from a detailed mapping of (mostly illegal) waste dumping sites in Campania, we have focused on recent studies which have found: (a) high concentrations of dioxins (≥5.0 pg TEQ/g fat) in milk samples from sheep, cows, and river buffaloes; (b) remarkable contamination of dioxin and PCBs in human milk samples from those living in the Naples and Caserta areas (PCDDs+PCDFs and dioxin-like-PCBs (dl-PCBs) assessed at 16.6 pg TEQ/g of fat; range: 7.5-43 pg/g of fat); (c) potential age-adjusted standardized mortality rates associated with some specific cancer types; (d) a statistically significant association between exposure to illegal toxic waste dumping sites and cancer mortality, even after adjustment by socio-economic factors and other environmental indicators.

  2. Illegal Dumping of Toxic Waste and Its Effect on Human Health in Campania, Italy

    Directory of Open Access Journals (Sweden)

    Alfredo Mazza

    2015-06-01

    Full Text Available The region of Campania (particularly Naples and Caserta has experienced an emergency in the waste management cycle during past years. Although the most critical phase has been overcome after the construction of the incineration plant in Acerra (an old-fashioned technology built up over a few months, whose impact on environment and health has not yet been assessed, most of the underlying problems have not been resolved. The illegal burning of wheels, plastics, textiles, and other industrial residuals, along with the detection of two thousand toxic substance dumping sites, still represents major concerns of environmental pollution and population health. This review summarizes the most relevant studies, which analyzed chemical contamination (primarily dioxins and polychlorinated biphenyls (PCBs of the air, soil, water, animals, and humans in Campania. In addition, we reviewed information on population health (i.e., mortality data, congenital malformations, and cancer incidence. Moving from a detailed mapping of (mostly illegal waste dumping sites in Campania, we have focused on recent studies which have found: (a high concentrations of dioxins (≥5.0 pg TEQ/g fat in milk samples from sheep, cows, and river buffaloes; (b remarkable contamination of dioxin and PCBs in human milk samples from those living in the Naples and Caserta areas (PCDDs+PCDFs and dioxin-like-PCBs (dl-PCBs assessed at 16.6 pg TEQ/g of fat; range: 7.5–43 pg/g of fat; (c potential age-adjusted standardized mortality rates associated with some specific cancer types; (d a statistically significant association between exposure to illegal toxic waste dumping sites and cancer mortality, even after adjustment by socio-economic factors and other environmental indicators.

  3. Review of the continued suitability of the dumping site for radioactive waste in the North-East Atlantic

    International Nuclear Information System (INIS)

    1980-04-01

    Under the terms of the Decision of the OECD Council establishing a Multilateral Consultation and Surveillance Mechanism for Sea Dumping of Radioactive Waste, NEA is requested to assess, in consultation with the Environment Committee, the suitability of dumping sites proposed by the national authorities of Participating countries and to keep under review those previously considered suitable. Since 1974 radioactive waste sea dumping operations have been carried out in a single site located in the North-East Atlantic region. To fulfil the objectives of the Council Decision, an international group of oceanographic and radiation protection experts was convened by NEA in November 1979 to undertake a review of the continued suitability of the dumping site, taking into account the relevant provisions of the London Dumping Convention and the IAEA Definition and Recommendations for the purposes of the Convention. The results of the review are contained in this Report. The Steering Committee for Nuclear Energy confirmed in April 1980 that, on the basis of the review, the existing site was suitable for continued dumping of radioactive waste for the next five years, under the conditions specified by the Group of Experts in their conclusions and recommendations. At the same time, the Steering Committee for Nuclear Energy agreed on the need for developing a co-ordinated site-specific scientific programme to increase current knowledge of the processes controlling the transfert of radionuclides in the marine environment, so that future assessments can be based on more accurate and comprehensive scientific data

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

    International Nuclear Information System (INIS)

    Carlson, R.A.

    2006-01-01

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

  5. A revised definition of high-level radioactive wastes unsuitable for dumping at sea

    International Nuclear Information System (INIS)

    Morley, F.

    1979-01-01

    The IAEA is responsible for defining these wastes, and makes recommendations to be used as a basis for the issue of special permits for the dumping at sea of those radioactive materials not defined as 'unsuitable'. Two IAEA information Circulars list in detail the Provisional (INF CIRC/205/Add. 1. Vienna, IAEA (January 1975)) and Revised (INF/ CIRC/205/Add. 1/Rev. 1. Vienna, IAEA (August 1978)) Definitions with annex material. These two definitions are set out for comparison purposes. The definitions were based on oceanographic and radiological evidence, and a summary is given of the procedures followed during their preparation. (U.K.)

  6. Hydrology of an abandoned uranium mine waste rock dump, Northern Territory

    International Nuclear Information System (INIS)

    Evans, K.G.; Moliere, D.R.; Saynor, M.J.

    1999-01-01

    Field studies were conducted on an abandoned, degraded uranium mine in Kakadu National Park to obtain waste rock dump runoff data to test the ability of a landform evolution model to predict gullying caused by concentrated flow. Runoff data were collected from natural rainfall events on a concentrated flow site and an overland flow erosion site on the waste rock dump at Scinto 6 mine. The data were used to fit parameters to a rainfall/runoff model using a non-linear regression package (NLFIT-DISTFW) which allows a single set of parameters to be fitted to four discharge hydrographs simultaneously. The model generally predicted peak discharge and the rising stage of the observed hydrographs well but there was some lag in the falling stage of the predicted hydrographs. Kinematic wave parameters are dependent on each other and the concentrated flow parameter set was not significantly different from the overland flow set. The infiltration parameter sets were statistically different and difference in cumulative infiltration between sites is controlled by sorptivity

  7. MUNICIPAL SOLID WASTE ILLEGAL DUMPING AND IT’S SPATIAL AUTOREGRESSION: THE CASE OF THE REPUBLIC OF KOREA

    Directory of Open Access Journals (Sweden)

    Youngjae Chang

    2016-11-01

    Full Text Available We reviewed the data pertaining to the illegal dumping of municipal solid waste in the Republic of Korea for the year 2011 to check for the presence of spatial autoregression of illegal dumping among 224 basic autonomous units with reference to the “Broken Windows Theory.” We found that a pure neighborhood effect exists even after controlling for conventional variables that explain illegal dumping behavior. Interestingly, however, the neighborhood effect is largely offset by so-called relative price effect such that the number of illegal dumping reported in one region is in fact decreased as the price of vinyl bag for MSW in neighboring regions increases, which is seemingly against the implication of the “Broken Windows Theory.”

  8. Assessing soil pollution from a municipal waste dump in Islamabad, Pakistan. A study by INAA and AAS

    International Nuclear Information System (INIS)

    Waheed, S.; Siddique, N.

    2010-01-01

    INAA and AAS techniques have been employed to determine 40 elements in soil of a municipal waste dump in sector H-11, Islamabad. Background soil was also analyzed to study the extent of contamination of the dump site soil. Most of the major elements in these soils represented the geochemical composition of the soil in this area. The enrichment factors for quantified elements identified high Sb and Mg contents that could be attributed to the presence of PET and food materials in the waste. Geo-accumulation Index (I geo ), Pollution Index (PI) and the Integrated Pollution Index (IPI) have also been calculated for all elements. The values for these indices show that municipal waste has distorted the soil ambiance and the soil of waste dump site is slightly to moderately polluted as compared to the background soil. The dump soil was found to be moderately polluted by the elements Ba, Br, Ga, Rb, Zn, Ni and Pb. Significantly high Cu, Mg and Sb contamination was observed for the waste soil that is likely to pose an environmental issue if current waste disposal procedures are continuously employed. (author)

  9. Ocean Dumping Control Act

    International Nuclear Information System (INIS)

    1975-01-01

    This Act provides for the control of dumping of wastes and other substances in the ocean in accordance with the London Convention of 1972 on Prevention of Marine Pollution by the Dumping of Wastes and other Matter to which Canada is a Party. Radioactive wastes are included in the prohibited and restricted substances. (NEA)

  10. Heavy Metal Contamination of Soils around a Hospital Waste Incinerator Bottom Ash Dumps Site

    Directory of Open Access Journals (Sweden)

    M. Adama

    2016-01-01

    Full Text Available Waste incineration is the main waste management strategy used in treating hospital waste in many developing countries. However, the release of dioxins, POPs, and heavy metals in fly and bottom ash poses environmental and public health concerns. To determine heavy metal (Hg, Pb, Cd, Cr, and Ag in levels in incinerator bottom ash and soils 100 m around the incinerator bottom ash dump site, ash samples and surrounding soil samples were collected at 20 m, 40 m, 60 m, 80 m, 100 m, and 1,200 m from incinerator. These were analyzed using the absorption spectrophotometer method. The geoaccumulation (Igeo and pollution load indices (PLI were used to assess the level of heavy metal contamination of surrounding soils. The study revealed high concentrations in mg/kg for, Zn (16417.69, Pb (143.80, Cr (99.30, and Cd (7.54 in bottom ash and these were above allowable limits for disposal in landfill. The study also found soils within 60 m radius of the incinerator to be polluted with the metals. It is recommended that health care waste managers be educated on the implication of improper management of incinerator bottom ash and regulators monitor hospital waste incinerator sites.

  11. A simplified approach for slope stability analysis of uncontrolled waste dumps.

    Science.gov (United States)

    Turer, Dilek; Turer, Ahmet

    2011-02-01

    Slope stability analysis of municipal solid waste has always been problematic because of the heterogeneous nature of the waste materials. The requirement for large testing equipment in order to obtain representative samples has identified the need for simplified approaches to obtain the unit weight and shear strength parameters of the waste. In the present study, two of the most recently published approaches for determining the unit weight and shear strength parameters of the waste have been incorporated into a slope stability analysis using the Bishop method to prepare slope stability charts. The slope stability charts were prepared for uncontrolled waste dumps having no liner and leachate collection systems with pore pressure ratios of 0, 0.1, 0.2, 0.3, 0.4 and 0.5, considering the most critical slip surface passing through the toe of the slope. As the proposed slope stability charts were prepared by considering the change in unit weight as a function of height, they reflect field conditions better than accepting a constant unit weight approach in the stability analysis. They also streamline the selection of slope or height as a function of the desired factor of safety.

  12. Heavy Metal Contamination of Soils around a Hospital Waste Incinerator Bottom Ash Dumps Site.

    Science.gov (United States)

    Adama, M; Esena, R; Fosu-Mensah, B; Yirenya-Tawiah, D

    2016-01-01

    Waste incineration is the main waste management strategy used in treating hospital waste in many developing countries. However, the release of dioxins, POPs, and heavy metals in fly and bottom ash poses environmental and public health concerns. To determine heavy metal (Hg, Pb, Cd, Cr, and Ag) in levels in incinerator bottom ash and soils 100 m around the incinerator bottom ash dump site, ash samples and surrounding soil samples were collected at 20 m, 40 m, 60 m, 80 m, 100 m, and 1,200 m from incinerator. These were analyzed using the absorption spectrophotometer method. The geoaccumulation (I geo) and pollution load indices (PLI) were used to assess the level of heavy metal contamination of surrounding soils. The study revealed high concentrations in mg/kg for, Zn (16417.69), Pb (143.80), Cr (99.30), and Cd (7.54) in bottom ash and these were above allowable limits for disposal in landfill. The study also found soils within 60 m radius of the incinerator to be polluted with the metals. It is recommended that health care waste managers be educated on the implication of improper management of incinerator bottom ash and regulators monitor hospital waste incinerator sites.

  13. Heavy Metal Contamination of Soils around a Hospital Waste Incinerator Bottom Ash Dumps Site

    Science.gov (United States)

    Adama, M.; Esena, R.; Fosu-Mensah, B.; Yirenya-Tawiah, D.

    2016-01-01

    Waste incineration is the main waste management strategy used in treating hospital waste in many developing countries. However, the release of dioxins, POPs, and heavy metals in fly and bottom ash poses environmental and public health concerns. To determine heavy metal (Hg, Pb, Cd, Cr, and Ag) in levels in incinerator bottom ash and soils 100 m around the incinerator bottom ash dump site, ash samples and surrounding soil samples were collected at 20 m, 40 m, 60 m, 80 m, 100 m, and 1,200 m from incinerator. These were analyzed using the absorption spectrophotometer method. The geoaccumulation (I geo) and pollution load indices (PLI) were used to assess the level of heavy metal contamination of surrounding soils. The study revealed high concentrations in mg/kg for, Zn (16417.69), Pb (143.80), Cr (99.30), and Cd (7.54) in bottom ash and these were above allowable limits for disposal in landfill. The study also found soils within 60 m radius of the incinerator to be polluted with the metals. It is recommended that health care waste managers be educated on the implication of improper management of incinerator bottom ash and regulators monitor hospital waste incinerator sites. PMID:27034685

  14. INFLUENCE OF ILLEGAL WASTE DUMPING SITES OF NORTH-WEST PART OF BARLINEK COMMUNITY ON HEAVY METALS CONTENT IN SOILS

    Directory of Open Access Journals (Sweden)

    Kamil Szydłowski

    2017-02-01

    Full Text Available The in-depth analysis of the soil samples study included 6 from 17 catalogued illegal waste dumps localized in the Barlinek Commune (Gmina Barlinek area. The samples were taken from the middle part of each waste dump and at 5 meter distance toward north and south directions. In the collected material the pH values and concentration of lead, zinc, cadmium, cobalt, manganese, nickel, chromium, iron, copper and mercury were determined. The results of laboratory analysis were compared with current standards (Regulation of the Minister of Environment from 9th September 2002 on soil quality standards and quality standards of soil - Journal of Laws 2002 No 165, item 1359 and with the soils classification by the content of trace elements, according to Kabata-Pendias et al. The reason of diversified content of heavy metals in the collected soils samples from different waste dumps is various morphological composition of deposited waste. Nonetheless, waste landfilled on illegal dumps were not significantly influencing the levels of soil contamination with heavy metals. The concentration of Hg, Cd, Co, Cr, Cu, Mn, Ni, Pb, Zn, Fe qualifies those soils to geochemical natural levels of heavy metals content. Nevertheless, cadmium was the element, which concentration were most often (21 times exceeded.

  15. A survey of the existing international legal rules on the dumping of radioactive waste into the sea

    International Nuclear Information System (INIS)

    Cornelis, J.C.

    All nuclear activities generate radioactive wastes and, in the context of the problems raised by such wastes, the author analyses the international rules regulating their safe disposal into the sea and the motives underlying their elaboration. The review therefore covers the London Convention on the Prevention of Marine Pollution by Dumping of Waste and Other Matter, together with the IAEA provisional definition and recommendations in this respect, and the recently adopted OECD Multilateral Consultation and Surveillance Mechanism for Sea Dumping of Radioactive Waste. It is emphasized that while the London Convention deals with a wide range of products, the OECD Mechanism deals solely with radioactive waste. Finally, consideration is given to whether the Paris Convention and the Euratom Treaty may be of relevance in this field. (NEA) [fr

  16. Collective doses to man from dumping of radioactive waste in the Arctic Seas.

    Science.gov (United States)

    Nielsen, S P; Iosjpe, M; Strand, P

    1997-08-25

    A box model for the dispersion of radionuclides in the marine environment covering the Arctic Ocean and the North Atlantic Ocean has been constructed. Collective doses from ingestion pathways have been calculated from unit releases of the radionuclides 3H, 60Co, 63Ni, 90Sr, 129I, 137Cs, 239Pu and 241Am into a fjord on the east coast of NovayaZemlya. The results show that doses for the shorter-lived radionuclides (e.g. 137Cs) are derived mainly from seafood production in the Barents Sea. Doses from the longer-lived radionuclides (e.g. 239Pu) are delivered through marine produce further away from the Arctic Ocean. Collective doses were calculated for two release scenarios, both of which are based on information of the dumping of radioactive waste in the Barents and Kara Seas by the former Soviet Union and on preliminary information from the International Arctic Sea Assessment Programme. A worst-case scenario was assumed according to which all radionuclides in liquid and solid radioactive waste were available for dispersion in the marine environment at the time of dumping. Release of radionuclides from spent nuclear fuel was assumed to take place by direct corrosion of the fuel ignoring the barriers that prevent direct contact between the fuel and the seawater. The second scenario selected assumed that releases of radionuclides from spent nuclear fuel do not occur until after failure of the protective barriers. All other liquid and solid radioactive waste was assumed to be available for dispersion at the time of discharge in both scenarios. The estimated collective dose for the worst-case scenario was about 9 manSv and that for the second scenario was about 3 manSv. In both cases, 137Cs is the radionuclide predicted to dominate the collective doses as well as the peak collective dose rates.

  17. Sea dumping of radioactive wastes. Part 1: Basic considerations of marine environment

    International Nuclear Information System (INIS)

    Krejsa, P.

    1983-04-01

    Sea dumping of low level radioactive waste is a disposal method practised by a number of states, controlled by OECD/NEA. It makes use of the capacity of the oceans to dilute the radionuclides to levels acceptable concerning resulting dose burdens. For the determination of release rates some oceanographic model have been developed, describing the physical behaviour of the released radionuclides. It is not to be assumed that a complete mathematical description of the involved processes can be made. Too many parameters are dependent and varying as there is the chemical behaviour of different valence states, complexing agents, distribution patterns etc. But it can be seen that the existing description methods allow the adequate modelling of the short and the long term behaviour of the radionuclides. The use of pessimistic assumptions for distribution and reconcentration is sufficient to consider uncertainties of the model. Therefore the arguments of Greenpeace, kindly submitted by this organisation for this study, show no open question, which has not been considered on the sea dumping procedures under surveillance of the OECD/NEA. (Author)

  18. Risk assessment of particle dispersion and trace element contamination from mine-waste dumps.

    Science.gov (United States)

    Romero, Antonio; González, Isabel; Martín, José María; Vázquez, María Auxiliadora; Ortiz, Pilar

    2015-04-01

    In this study, a model to delimit risk zones influenced by atmospheric particle dispersion from mine-waste dumps is developed to assess their influence on the soil and the population according to the concentration of trace elements in the waste. The model is applied to the Riotinto Mine (in SW Spain), which has a long history of mining and heavy land contamination. The waste materials are separated into three clusters according to the mapping, mineralogy, and geochemical classification using cluster analysis. Two of the clusters are composed of slag, fresh pyrite, and roasted pyrite ashes, which may contain high concentrations of trace elements (e.g., >1 % As or >4 % Pb). The average pollution load index (PLI) calculated for As, Cd, Co, Cu, Pb, Tl, and Zn versus the baseline of the regional soil is 19. The other cluster is primarily composed of sterile rocks and ochreous tailings, and the average PLI is 3. The combination of particle dispersion calculated by a Gaussian model, the PLI, the surface area of each waste and the wind direction is used to develop a risk-assessment model with Geographic Information System GIS software. The zone of high risk can affect the agricultural soil and the population in the study area, particularly if mining activity is restarted in the near future. This model can be applied to spatial planning and environmental protection if the information is complemented with atmospheric particulate matter studies.

  19. Collective doses to man from dumping of radioactive waste in the Arctic Seas

    DEFF Research Database (Denmark)

    Nielsen, S.P.; Iosjpe, M.; Strand, P.

    1997-01-01

    A box model for the dispersion of radionuclides in the marine environment covering the Arctic Ocean and the North Atlantic Ocean has been constructed. Collective doses from ingestion pathways have been calculated from unit releases of the radionuclides H-3, (CO)-C-60, Ni-63, Sr-90, I-129, (CS...... Assessment Programme. A worst-case scenario was assumed according to which all radionuclides in liquid and solid radioactive waste were available for dispersion in the marine environment at the time of dumping. Release of radionuclides from spent nuclear fuel was assumed to take place by direct corrosion...... to be available for dispersion at the time of discharge in both scenarios. The estimated collective dose for the worst-case scenario was about 9 manSv and that for the second scenario was about 3 manSv. In both cases, Cs-137 is the radionuclide predicted to dominate the collective doses as well as the peak...

  20. Impact of mine waste dumps on growth and biomass of economically important crops.

    Science.gov (United States)

    Mathiyazhagan, Narayanan; Natarajan, Devarajan

    2012-11-01

    The present study aimed to investigate the effect of magnesite and bauxite waste dumps on growth and biochemical parameters of some edible and economically important plants such as Vigna radiata, V. mungo, V. unguiculata, Eleusine coracana, Cajanus cajan, Pennisetum glaucum, Macrotyloma uniflorum, Oryza sativa, Sorghum bicolour, Sesamum indicum, Ricinus communis, Brassica juncea, Gossypium hirsutum and Jatropha curcas. The growth rate of all the crops was observed in the range of 75 to 100% in magnesite and 15 to 100% in bauxite mine soil. The moisture content of roots and shoots of all the crops were in the range of 24 to 77, 20 to 88% and 42 to 87, 59 to 88% respectively. The height of the crops was in the range of 2.6 to 48 cm in magnesite soil and 3 to 33 cm in bauxite soil. Thus the study shows that both mine soils reflects some physical and biomolecule impact on selected crops.

  1. Estimates of water and solute release from a coal waste rock dump in the Elk Valley, British Columbia, Canada.

    Science.gov (United States)

    Villeneuve, S A; Barbour, S L; Hendry, M J; Carey, S K

    2017-12-01

    Long term (1999 to 2014) flow and water quality data from a rock drain located at the base of a coal waste rock dump constructed in the Elk Valley, British Columbia was used to characterize the release of three solutes (NO 3 - , Cl - and SO 4 2- ) from the dump and obtain whole dump estimates of net percolation (NP). The concentrations of dump derived solutes in the rock drain water were diluted by snowmelt waters from the adjacent natural watershed during the spring freshet and reached a maximum concentration during the winter baseflow period. Historical peak baseflow concentrations of conservative ions (NO 3 - and Cl - ) increased until 2006/07 after which they decreased. This decrease was attributed to completion of the flushing of the first pore volume of water stored within the dump. The baseflow SO 4 2- concentrations increased proportionally with NO 3 - and Cl - to 2007, but then continued to slowly increase as NO 3 - and Cl - concentrations decreased. This was attributed to ongoing production of SO 4 2- due to oxidation of sulfide minerals within the dump. Based on partitioning of the annual volume of water discharged from the rock drain to waste rock effluent (NP) and water entering the rock drain laterally from the natural watershed, the mean NP values were estimated to be 446±50mm/a (area normalized net percolation/year) for the dump and 172±71mm/a for the natural watershed. The difference was attributed to greater rates of recharge in the dump from summer precipitation compared to the natural watershed where rainfall interception and enhanced evapotranspiration will increase water losses. These estimates included water moving through subsurface pathways. However, given the limitations in quantifying these flows the estimated NP rates for both the natural watershed and the waste rock dump are considered to be low, and could be much higher (e.g. ~450mm/a and ~800mm/a). Copyright © 2017 Elsevier B.V. All rights reserved.

  2. Dumping of radioactive waste and investigation of contamination in the Kara Sea. Results from 3 years of investigations (1992-1994) in the Kara Sea

    Energy Technology Data Exchange (ETDEWEB)

    Strand, P [Statens Straalevern, Oesteraas (Norway); Foeyn, L [Norsk Inst. for Vannforskning, Oslo (Norway); Nikitin, A I [SPA ` ` Typhoon` ` , Roshydromet (Russian Federation); and others

    1996-03-01

    The report summarises the results obtained from the joint Russian-Norwegian investigation concerning the consequences of dumping of radioactive waste in the Kara Sea. Three expeditions were undertaken to the Kara Sea and the present dumping sites for radioactive waste. Samples of water, sediments and biota were collected and analysed. An impact and risk assessment was performed, based on the information provided through the joint cooperation. Enhanced levels and artificially produced radionuclides in the sediments collected in the very close vicinity of almost all localised dumped objects, demonstrate that leakage occur. No contribution from dumped radioactive waste was observed in the open Kara Sea. Due to the potential for leakage from the dumped waste in the future and the presence of other potential sources in the area, a regular monitoring programme is highly recommended. 65 refs., 42 figs., 16 tabs.

  3. Dumping of radioactive waste and investigation of contamination in the Kara Sea. Results from 3 years of investigations (1992-1994) in the Kara Sea

    International Nuclear Information System (INIS)

    Strand, P.; Foeyn, L.; Nikitin, A.I.

    1996-03-01

    The report summarises the results obtained from the joint Russian-Norwegian investigation concerning the consequences of dumping of radioactive waste in the Kara Sea. Three expeditions were undertaken to the Kara Sea and the present dumping sites for radioactive waste. Samples of water, sediments and biota were collected and analysed. An impact and risk assessment was performed, based on the information provided through the joint cooperation. Enhanced levels and artificially produced radionuclides in the sediments collected in the very close vicinity of almost all localised dumped objects, demonstrate that leakage occur. No contribution from dumped radioactive waste was observed in the open Kara Sea. Due to the potential for leakage from the dumped waste in the future and the presence of other potential sources in the area, a regular monitoring programme is highly recommended. 65 refs., 42 figs., 16 tabs

  4. Plant occurrence on burning coal waste – a case study from the Katowice-Wełnowiec dump, Poland

    Directory of Open Access Journals (Sweden)

    Ciesielczuk Justyna

    2015-06-01

    Full Text Available Coal-waste dumps superimposed on former rubbish dump frequently undergo selfheating and selfignition of organic matter dispersed in the waste. The special conditions for plant growth generated as a result have been investigated since 2008 on the municipal dump reclaimed with coal wastes in Katowice-Wełnowiec, Poland. The plants observed most frequently where heating has occurred are Sisymbrium loeselii, Artemisia vulgaris, Sonchus arvensis, Chenopodium album, Achillea millefolium, Cirsium arvense, Amaranthus retroflexus, Atriplex nitens and Solanum nigrum. Some new, rare species such as Portulaca oleracea, first noticed in 2011, may be added. Most of encroaching species are annual, alien archeophytes and neophytes. Native species are mainly perennials. The majority of these species show a tendency to form specimens of huge size (gigantism. The abundance of emitted CO2 and nitrogen compounds is the likely cause of this. Additionally, the plants growing there are not attacked by insects. The heating of the ground liquidates the natural seed bank. After cooling, these places are seeded by species providing seeds at that very moment (pioneer species. Heated places on the dumps allow plant growth even in the middle of winter. As the seasonal vegetation cycle is disturbed, plants may be found seeding, blooming and fruiting at the same time.

  5. Radionuclides in fishes and mussels from the Farallon Islands Nuclear Waste Dump Site, California.

    Science.gov (United States)

    Suchanek, T H; Lagunas-Solar, M C; Raabe, O G; Helm, R C; Gielow, F; Peek, N; Carvacho, O

    1996-08-01

    The Farallon Islands Nuclear Waste Dump Site (FINWDS), approximately 30 miles west of San Francisco, California, received at least 500 TBq encapsulated in more than 47,500 containers from approximately 1945 to 1970. During several seasons in 1986/87 deep-sea bottom feeding fishes (Dover sole = Microstomus pacificus; sablefish = Anoplopoma fimbria; thornyheads = Sebastolobus spp.) and intertidal mussels (Mytilus californianus) were collected from the vicinity of the FINWDS and from comparable depths at a reference site near Point Arena, CA. Tissues were analyzed for several radionuclides (137Cs, 238Pu, 239+240Pu, and 241Am). Radionuclide concentrations for fish mussel tissue ranged from non-detectable to 4,340 mBq kg(-1) wet weight, with the following means for Farallon fishes: 137Cs = 1,110 mBq kg(-1); 238Pu = 390 mBq kg(-1); 239+240Pu = 130 mBq kg(-1); and 241Am = 1,350 mBq kg(-1). There were no statistically significant differences in the radionuclide concentrations observed in samples from the Farallon Islands compared to reference samples from Point Arena, CA. Concentrations of both 238Pu and 241Am in fish tissues (from both sites) were notably higher than those reported in literature from any other sites world-wide, including potentially contaminated sites. Concentrations of 239+24OPu from both sites were typical of low values found at some contaminated sites worldwide. These results show approximately 10 times higher concentrations of 239+240Pu and approximately 40-50 times higher concentrations of 238Pu than those values reported for identical fish species from 1977 collections at the FINWDS. Radionuclide concentrations were converted to a hypothetical per capita annual radionuclide intake for adults, yielding the following values of annual Committed Effective Dose Equivalent (CEDE) from ionizing radiation emitted from these radionuclides: 0.000 mSv y(-1) for 137Cs, 0.009 mSv Y(-1) for 228Pu, and 0.003 mSv y(-1) for 239+240Pu. For 241Am, projected CEDE for

  6. The IAEA's work for the convention on the prevention of marine pollution by dumping of wastes and other matter

    International Nuclear Information System (INIS)

    Phuong, H.V.

    1976-01-01

    One of the several techniques for the disposal of radioactive waste which has been used by some countries, often as a combined international operation, is sea-disposal under carefully controlled conditions. The waste is placed in drums encased in concrete and dumped in selected known ocean areas, currently at least 4000 metres in depth and well away from fishing grounds. The International Atomic Energy Agency is, therefore, directly addressed to by the Convention on the Prevention of Marine Pollution by Dumping of Wastes and Other Matter as the competent international body to work out safety criteria, conditions and procedures and to draw up recommendations for the implementation of the Convention with regard to radioactive materials. (author)

  7. A meta-analysis of mortality data in Italian contaminated sites with industrial waste landfills or illegal dumps

    Directory of Open Access Journals (Sweden)

    Lucia Fazzo

    2014-09-01

    Full Text Available Objectives. Adverse effects of waste management represent a public health issue. Mortality meta-analysis in Italian National Priority Contaminated Sites (NPCSs with industrial waste landfills or illegal dumps is presented. Methods. 24 NPCSs include industrial waste landfills or illegal dumps. Class 1 (10 NPCSs with industrial waste landfills and Class 2 (14 NPCSs with illegal dumps were categorized. Random-effects model meta-analyses of Standardized Mortality Ratios non-adjusted (SMRs and adjusted for Deprivation (DI-SMRs computed for each CS (1995-2002 were performed for overall 24 NPCSs and the two classes. The North-Southern gradient was considered. Results. 24 CSs pooled-SMRs are significantly increased in both genders for cancer of liver (men: SMR = 1.13; women: SMR = 1.18, bladder (men: SMR = 1.06; women: SMR = 1.11, and for cirrhosis (men: SMR = 1.09; women: SMR = 1.13. In Class 2 the increase is confirmed in both genders for liver and bladder cancers and for cirrhosis and in men only for lung cancer. Congenital anomalies and adverse perinatal conditions are not increased. Conclusion. The results are consistent with the hypothesis of adverse health effects of non-adequately managed hazardous waste. Causal interpretation is not allowed, but the meta-analytic approach provides more confidence in the findings.

  8. Radiological assessment for the dumping of radioactive wastes in the oceans

    International Nuclear Information System (INIS)

    Templeton, W.L.

    1993-06-01

    Over the last three decades or so, a number of international meetings have been convened to treat the specific problem of radioactive waste disposal into the oceans. The first of these meetings was held in 1958 at the United Nations Conference on the Law of the Sea. Immediately following, the International Atomic Energy Agency (IAEA), in the Brynielsson Report, recommended measures for ensuring that disposal of radioactive waste into the sea would not result in unacceptable hazards to man (IAEA 1961). Since that time, major changes have occurred in the philosophy and recommendations of the International Commission on Radiological Protection that are crucial to the assessments of impacts arising from this practice. Knowledge of oceanographic processes has improved markedly, providing better understanding of the physical transport process and of the pathways by which radionuclides are transported from marine dumping and disposal sites back to man. Finally, radioecology has developed to the stage where predictions of radionuclide cycling pathways and rates are possible. The IAEA report of 1961 was revised in 1983 (IAEA 1983). The IAEA has published many documents (Safety Series and Technical Documents) covering relevant areas such as oceanographic models, bioaccumulation factors, sediment distribution coefficients, and effects of ionizing radiation on organisms

  9. Management of dumping of packaged low-level wastes in the deep ocean with emphasis on the North East Atlantic dump site

    International Nuclear Information System (INIS)

    Templeton, W.L.

    1981-08-01

    The following aspects are discussed: radiological principles as applied to disposal to the environment; international regulations; historical dumping practices; assessment of the Northeast Atlantic dump site; IAEA generic studies; and implications of issues on US needs and policies

  10. Considerations concerning ''de minimis'' quantities of radioactive waste suitable for dumping at sea under a general permit

    International Nuclear Information System (INIS)

    1981-02-01

    Following the principles proposed by the ICRP of balancing the costs and detriments of any practice involving radioactivity, there must be some level of radioactivity below which considerations other than those of the radioactivity itself are of overriding importance. For very low-level radioactive wastes, it is necessary to define a quantitative criterion which allows practical implementation of these principles within the terms of the London Dumping Convention. It will be necessary therefore to consider how these requirements can be met by defining material that can be regarded as non-radioactive for the purposes of the London Dumping Convention, defining a category of radioactivity in wastes whose content is sufficiently low (de minimis) that it can be dumped under a general permit if its other characteristics so permit. It is stressed that even if a material has been deemed to contain less than de minimis quantities of radioactive materials its suitability for dumping due to it's other constituents must still be carried out. The question of defining such a de minimis level of radioactivity was considered by an Advisory Group meeting convened at the IAEA headquarters in Vienna from 2 to 6 July 1979

  11. Research over the extraction process in order to simulate 226Ra and Unat radionuclides migration in uranium waste dumps

    International Nuclear Information System (INIS)

    Bragea, Mihaela; Toro, Laszlo; Cristache, Carmen

    2008-01-01

    To simulate the phenomenon of migration availability of radioactive elements in uranium waste product from waste dump into the environment it was taken into account the Ciudanovita, Romania area with its uranium waste dumps. It were made studies through experiments of static extraction in agitation pot (static regime), which allow to pursue the evolution of contaminants along a specific period of time. It was accomplish a study about sorption and adsorption process on the geological environment (clay). It was observed that 226 Ra and U nat transition through the sorption and adsorption processes were induced by the type of clay (due to variable solubility of clay and the physics and chemical status of 226 Ra and U nat into the clay) and the time interval until the water contacts the clay. The concentration measurements of radionuclides into different dimension of clay particles were made to give pertinent information about the way of chosen the repair strategies for the studied site. The present work is based mainly on this research direction: optimization and improvement of the performances obtained from the geo-chemical processes investigation methods in the waste dumps and the surrounding geological structures to isolate them, in order to reduce the negative environmental impact. Measurements of the two radionuclides concentrations in particles with different dimensions were made to supply accurate information regarding the selection of remediation strategies for the dumpsite in study. (author)

  12. Nuclear Waste Education Project

    International Nuclear Information System (INIS)

    1989-01-01

    In summary, both the Atlanta and Albuquerque pilot seminars achieved the Nuclear Waste Education Project's goal of informing citizens on both the substance and the process of nuclear waste policy so that they can better participate in future nuclear waste decisions. Nuclear waste issues are controversial, and the seminars exposed the nature of the controversy, and utilized the policy debates to create lively and provocative sessions. The format and content of any citizen education curriculum must be made to fit the particular goal that has been chosen. If the Department of Energy and the LWVEF decide to continue to foster an informed dialogue among presenters and participants, the principles of controversial issues education would serve this goal well. If, however, the Department of Energy and/or the LWVEF decide to go beyond imparting information and promoting a lively discussion of the issues, towards some kind of consensus-building process, it would be appropriate to integrate more interactive sessions into the format. As one evaluator wrote, ''In-depth participation in finding solutions or establishing policy -- small group discussion'' would have been preferable to the plenary sessions that mostly were in the form of lectures and expert panel discussion. The evaluator continued by saying, ''Since these [small group discussions] would require more time commitment, they might be part of follow-up workshops focused on particular topics.''

  13. Meeting the specifications for mechanical-biological waste treament and dumping; Umsetzung der Ablagerungsanforderungen im MBA- und Deponiebetrieb

    Energy Technology Data Exchange (ETDEWEB)

    Ketelsen, K. [IBA Ingenieurbuero fuer Abfallwirtschaft und Entsorgung GmbH, Hannover (Germany)

    2001-07-01

    The new German ordinances will have a dramatic influence on the waste treatment processes and air/exhaust management in mechanical-biological waste treatment plants. The potentials of process control and optimization should be fully utilized. The extensive in-service inspections and specifications will change the requirements on the process and staff qualification. The additional cost must be balanced by technically and economically feasible projecting and solutions. The need to keep up with thermal processes will lead to the construction of plants with a size of 50,000 Mg/a and more as these have higher economic efficiency, i.e. small regional utilities will have to co-operate. In mechanical-biological waste treatment plants, about 40-50% of the total cost is accounted for by the waste treatment process, i.e. economic efficiency will depend on the cost of dumping of the stabilized fine-grained fraction(about 20%) and the cost of utilization of the high-calorific waste (about 30%). In view of the high fixed cost, mechanical-biological waste treatment concepts will be economically efficient only if the plant capacity is fully utilized. [German] Mit Verabschiedung der Verordnungen ist die MBA 'gesellschaftsfaehiger' geworden. Die Verordnungen werden einen nachhaltigen Einfluss auf die Verfahrenstechnik und das gesamte Luft-/Abgasmanagement haben. Die Entwicklungspotentiale in der Prozesssteuerung und -optimierung muessen verstaerkt ausgeschoepft werden. Durch die geforderten umfangreichen Untersuchungs- und Nachweispflichten werden sich die Anforderungen an die Betriebsfuehrung und Personalqualifikation veraendern. Die aus den hoeheren Anforderungen resultierenden Mehrkosten muessen durch technisch und wirtschftlich sinnvolle Planungen und Loesungen in vertretbaren Grenzen gehalten werden. Die Notwendigkeit zur Wirtschaftlichkeit im Wettbewerb mit rein thermischen Verfahren wird auch bei den MBA zur Realisierung wirtschaftlicher Anlagengroessen von groesser

  14. Record of Technical Change No.2 for ''Corrective Action Investigation Plan for Corrective Action Unit 143: Area 25 Contaminated Waste Dumps, Nevada Test Site, Nevada''

    International Nuclear Information System (INIS)

    1999-01-01

    This Record of Technical Change provides updates to the technical information included in ''Corrective Action Investigation Plan for Corrective Action Unit 143: Area 25 Contaminated Waste Dumps, Nevada Test Site, Nevada.''

  15. EFFICIENCY OF PRE-TREATMENT OF LEACHATE FROM MUNICIPAL WASTE DUMPS BY GASEOUS DESORPTION (STRIPPING OF AMMONIA

    Directory of Open Access Journals (Sweden)

    Justyna Koc-Jurczyk

    2017-05-01

    Full Text Available The paper studies the efficiency of pre-treatment of landfill leachate by gaseous desorption of ammonia. The research was done on a municipal non-hazardous waste dump in Krosno (Sub-Carpathian Province, Poland. The pretreatment provided a favorable BOD5/COD ratio in leachate. Also concentrations of 16 PAHs and heavy metals did not exceed the legal limits. However, gaseous desorption of ammonia was insufficiently efficient in recovering ammonia nitrogen from leachate.

  16. Radiation damage and waste management options for the sombrero final focus system and neutron dumps

    International Nuclear Information System (INIS)

    Reyes, S.; Latkowski, J.F.; Meier, W.R.; Reyes, S.

    2000-01-01

    Previous studies of the safety and environmental aspects of the SOMBRERO inertial fusion energy (IFE) power plant design did not completely address the issues associated with the final focus system. While past work calculated neutron fluences for a grazing incidence metal mirror (GIMM) and a final focus mirror, scattering off of the final optical component was not included, and thus, fluences in the final focus mirror were significantly underestimated. In addition, past work did not consider neutron-induced gamma-rays. Finally, power plant lifetime waste volumes may have been underestimated as neutron activation of the neutron dumps and building structure were not addressed. In the present work, a modified version of the SOMBRERO target building is presented where a significantly larger open solid-angle fraction (5%) is used to enhance beam smoothing of a diode-pumped solid-state laser (DPSSL). The GIMMs are replaced with transmissive fused silica wedges and have been included in three-dimensional neutron and photon transport calculations. This work shows that a power plant with a large open solid-angle fraction, needed for beam smoothing with a DPSSL, is acceptable from tritium breeding, and neutron activation points-of-view. (authors)

  17. Areal variability of the mineral soil cover in a reclaimed soda waste dumping site

    Directory of Open Access Journals (Sweden)

    Klatka Sławomir

    2017-03-01

    Full Text Available Areal variability of the mineral soil cover in a reclaimed soda waste dumping site. This paper provides an analysis of the areal variability of the thickness and selected physical and chemical properties of the mineral cover formed in the process of settling ponds reclamation at the former Krakow Soda Plant “Solvay”. The topsoil is intended to provide a substrate for plants, therefore, its quality is the main determinant of the development for herbaceous and woody vegetation. Areal variability of the topsoil parameters was determined by kriging. In the context of the envisaged direction of management of the settling ponds, the analysis showed that electrical conductivity, thickness of the soil cover and the sand fraction content have potentially the highest impact on the diversification of vegetation. Understanding the spatial variability of the soil cover parameters, that are essential for vegetation, may contribute to increasing the efficiency of biological reclamation and also to cost reduction. Precise selection of the areas unsuitable for plant growth makes it possible to improve soil parameters on limited areas similarly as in the precision agriculture.

  18. A model for the description of oxidation in sulfidic waste rock dumps

    International Nuclear Information System (INIS)

    Bennett, J. W.; Pantelis, G.; Ritchie, A.I.M.; Stepanyants, Y.A.

    2000-03-01

    Basic mathematical equations which describe the processes of sulfide oxidation and gas and water transport in waste rock dumps are presented and discussed. The governing equations account for gas and water flow, vaporisation and condensation with latent heat effects, heat transport and mass balance. Gas, water and solid phases are assumed to be in local thermal equilibrium at all times. Air is approximated as an ideal three-component gas. Different semi-empirical relationships between physical values are used: Darcy's law for fluid flow, ideal gas law, the Van Genuchten formula for the relationship between degree of water saturation and pressure head, Mualem's formula for the relative hydraulic conductivity as a function of pressure head, etc. Some important global quantities, such as the fraction of sulfide sulfur oxidised and the global oxidation rate, are defined and considered as functions of time. The full set of equations is collected and presented in explicit form, convenient for further numerical modelling. The glossary of some technical terms and the table of definitions of the main parameters as well as their units and characteristic values are given

  19. Sustainable waste management in Africa through CDM projects.

    Science.gov (United States)

    Couth, R; Trois, C

    2012-11-01

    Only few Clean Development Mechanism (CDM) projects (traditionally focussed on landfill gas combustion) have been registered in Africa if compared to similar developing countries. The waste hierarchy adopted by many African countries clearly shows that waste recycling and composting projects are generally the most sustainable. This paper undertakes a sustainability assessment for practical waste treatment and disposal scenarios for Africa and makes recommendations for consideration. The appraisal in this paper demonstrates that mechanical biological treatment of waste becomes more financially attractive if established through the CDM process. Waste will continue to be dumped in Africa with increasing greenhouse gas emissions produced, unless industrialised countries (Annex 1) fund carbon emission reduction schemes through a replacement to the Kyoto Protocol. Such a replacement should calculate all of the direct and indirect carbon emission savings and seek to promote public-private partnerships through a concerted support of the informal sector. Copyright © 2012 Elsevier Ltd. All rights reserved.

  20. Corrective Action Plan for Corrective Action Unit 143: Area 25 Contaminated Waste Dumps, Nevada Test Site, Nevada

    International Nuclear Information System (INIS)

    Gustafason, D.L.

    2001-01-01

    This Corrective Action Plan (CAP) has been prepared for Corrective Action Unit (CAU) 143: Area 25 Contaminated Waste Dumps, Nevada Test Site, Nevada, in accordance with the Federal Facility Agreement and Consent Order of 1996. This CAP provides the methodology for implementing the approved corrective action alternative as listed in the Corrective Action Decision Document (U.S. Department of Energy, Nevada Operations Office, 2000). The CAU includes two Corrective Action Sites (CASs): 25-23-09, Contaminated Waste Dump Number 1; and 25-23-03, Contaminated Waste Dump Number 2. Investigation of CAU 143 was conducted in 1999. Analytes detected during the corrective action investigation were evaluated against preliminary action levels to determine constituents of concern for CAU 143. Radionuclide concentrations in disposal pit soil samples associated with the Reactor Maintenance, Assembly, and Disassembly Facility West Trenches, the Reactor Maintenance, Assembly, and Disassembly Facility East Trestle Pit, and the Engine Maintenance, Assembly, and Disassembly Facility Trench are greater than normal background concentrations. These constituents are identified as constituents of concern for their respective CASs. Closure-in-place with administrative controls involves use restrictions to minimize access and prevent unauthorized intrusive activities, earthwork to fill depressions to original grade, placing additional clean cover material over the previously filled portion of some of the trenches, and placing secondary or diversion berm around pertinent areas to divert storm water run-on potential

  1. Mobilisation and immobilisation of uranium-DOC-species in three waste dumps in the district of Schlema/Alberoda

    International Nuclear Information System (INIS)

    Kupsch, H.

    1998-01-01

    The modelling of geochemical processes needs the detailed and comprehensive knowledge of all chemical interactions which are able to exist in the flow path of waste dumps, soils and aquifer. This includes the adsorption, displacement and transport of heavy metal species of fulvic and humic acids which represent the main amount of DOC in the liquid / solid system of flow path. Comparative measurements of DOC concentrations in the input and output flow at the three waste dumps in the district Schlema / Alberoda have indicated that DOC is produced and / or supplied within of waste dumps. The speciation of heavy metal compounds of fulvic and humic acids was realized by means of two methods (sequential chromatographic analysis SCA; ions focussed electrophoresis IFE). Between 5 and 20% of uranium in the flow path exist in the form of fulvic and humic acids species in which the bond of uranium is permanently. Their distribution coefficients are strongly correlated with the pH values of the several geochemical systems. (orig.) [de

  2. A survey of the environmental radioactivity in the east sea related to the Russian ocean dumping of the radioactive waste

    International Nuclear Information System (INIS)

    Kim, Kyehoon; Kim, Changkyu; Lee, Mosung

    1994-01-01

    From October 24 - December 30, 1993 a joint survey by the Office of Fisheries, Korea Institute of Nuclear Safety, Korea Ocean Research and Development Institute, and several other governmental institutes which was supervised by Ministry of Science and Technology was carried out to investigate present marine environmental radioactivity of the East Sea where former USSR and Russia had dumped radioactive waste since 1957. Exposure rate was measured and the radioactivity of seawater, both surface and deep water, bottom sediment, fish, and planktonic organisms from the areas around the dumping sites and the East Sae were analyzed. Results showed that the radioactivities of Cs-137 in the sea water from dumping sites were less than 0.0038 Bq/L, which was similar to the background level of the East Sea. The radioactivity level of fish and bottom sediment from dumping sites also did not increased. A detailed Ocean Environmental Monitoring Plan, however, should be established and the monitoring must be carried out continuously to protect people from potential radioactive hazards

  3. Waste Management Process Improvement Project

    International Nuclear Information System (INIS)

    Atwood, J.; Borden, G.; Rangel, G. R.

    2002-01-01

    The Bechtel Hanford-led Environmental Restoration Contractor team's Waste Management Process Improvement Project is working diligently with the U.S. Department of Energy's (DOE) Richland Operations Office to improve the waste management process to meet DOE's need for an efficient, cost-effective program for the management of dangerous, low-level and mixed-low-level waste. Additionally the program must meet all applicable regulatory requirements. The need for improvement was highlighted when a change in the Groundwater/Vadose Zone Integration Project's waste management practices resulted in a larger amount of waste being generated than the waste management organization had been set up to handle

  4. Waste dumping sites as a potential source of POPs and associated health risks in perspective of current waste management practices in Lahore city, Pakistan

    Energy Technology Data Exchange (ETDEWEB)

    Hafeez, Saba [Environmental Biology and Ecotoxicology Laboratory, Department of Environmental Sciences, Faculty of Biological Sciences, Quaid-i-Azam University, Islamabad 45320 (Pakistan); Mahmood, Adeel [Department of Biosciences, COMSATS Institute of Information Technology, Islamabad PO: 45550 (Pakistan); State Key Laboratory of Organic Geochemistry, Guangzhou Institute of Geochemistry, Chinese Academy of Sciences, Guangzhou 510640 (China); Syed, Jabir Hussain; Li, Jun [State Key Laboratory of Organic Geochemistry, Guangzhou Institute of Geochemistry, Chinese Academy of Sciences, Guangzhou 510640 (China); Ali, Usman [Environmental Biology and Ecotoxicology Laboratory, Department of Environmental Sciences, Faculty of Biological Sciences, Quaid-i-Azam University, Islamabad 45320 (Pakistan); Malik, Riffat Naseem, E-mail: r_n_malik2000@yahoo.co.uk [Environmental Biology and Ecotoxicology Laboratory, Department of Environmental Sciences, Faculty of Biological Sciences, Quaid-i-Azam University, Islamabad 45320 (Pakistan); Zhang, Gan [State Key Laboratory of Organic Geochemistry, Guangzhou Institute of Geochemistry, Chinese Academy of Sciences, Guangzhou 510640 (China)

    2016-08-15

    Persistent organic pollutants (POPs) including polychlorinated biphenyls (PCBs), polybrominated diphenyl ethers (PBDEs) and dechloran plus (DP) were analyzed in air, dust, soil and water samples from waste dump site, Lahore, Pakistan. It was revealed that PCB levels were detected higher in all matrices than PBDEs and DPs. Principal Component Analysis (PCA) showed higher usage of BDE-47, -99 and di-CBs, tri-CBs, tetra-CBs and penta-CBs. Health risk assessment of PCBs and PBDEs from soil and dust indicated low to moderate risk to the local population via different exposure pathways. It is recommended to improve current waste management practices in order to avoid emissions of contaminants and open dumping grounds should be modified into sanitary landfill. - Highlights: • The pioneer study provides the baseline data from waste dumping site from Lahore. • Dump site of Lahore is the potential source of PCBs, PBDEs and DPs in nearby environment. • Fugacity fractions indicated air to soil deposition of PCBs and PBDEs.

  5. Waste dumping sites as a potential source of POPs and associated health risks in perspective of current waste management practices in Lahore city, Pakistan

    International Nuclear Information System (INIS)

    Hafeez, Saba; Mahmood, Adeel; Syed, Jabir Hussain; Li, Jun; Ali, Usman; Malik, Riffat Naseem; Zhang, Gan

    2016-01-01

    Persistent organic pollutants (POPs) including polychlorinated biphenyls (PCBs), polybrominated diphenyl ethers (PBDEs) and dechloran plus (DP) were analyzed in air, dust, soil and water samples from waste dump site, Lahore, Pakistan. It was revealed that PCB levels were detected higher in all matrices than PBDEs and DPs. Principal Component Analysis (PCA) showed higher usage of BDE-47, -99 and di-CBs, tri-CBs, tetra-CBs and penta-CBs. Health risk assessment of PCBs and PBDEs from soil and dust indicated low to moderate risk to the local population via different exposure pathways. It is recommended to improve current waste management practices in order to avoid emissions of contaminants and open dumping grounds should be modified into sanitary landfill. - Highlights: • The pioneer study provides the baseline data from waste dumping site from Lahore. • Dump site of Lahore is the potential source of PCBs, PBDEs and DPs in nearby environment. • Fugacity fractions indicated air to soil deposition of PCBs and PBDEs.

  6. High power beam dump project for the accelerator prototype LIPAc: cooling design and analysis

    International Nuclear Information System (INIS)

    Parro Albeniz, M.

    2015-01-01

    In the nuclear fusion field running in parallel to ITER (International Thermonuclear Experimental Reactor) as one of the complementary activities headed towards solving the technological barriers, IFMIF (International Fusion Material Irradiation Facility) project aims to provide an irradiation facility to qualify advanced materials resistant to extreme conditions like the ones expected in future fusion reactors like DEMO (DEMOnstration Power Plant). IFMIF consists of two constant wave deuteron accelerators delivering a 125 mA and 40 MeV beam each that will collide on a lithium target producing an intense neutron fluence (1017 neutrons/s) with a similar spectra to that of fusion neutrons [1], [2]. This neutron flux is employed to irradiate the different material candidates to be employed in the future fusion reactors, and the samples examined after irradiation at the so called post-irradiative facilities. As a first step in such an ambitious project, an engineering validation and engineering design activity phase called IFMIF-EVEDA (Engineering Validation and Engineering Design Activities) is presently going on. One of the activities consists on the construction and operation of an accelerator prototype named LIPAc (Linear IFMIF Prototype Accelerator). It is a high intensity deuteron accelerator identical to the low energy part of the IFMIF accelerators. The LIPAc components, which will be installed in Japan, are delivered by different european countries. The accelerator supplies a 9 MeV constant wave beam of deuterons with a power of 1.125 MW, which after being characterized by different instruments has to be stopped safely. For such task a beam dump to absorb the beam energy and take it to a heat sink is needed. Spain has the compromise of delivering such device and CIEMAT (Centro de Investigaciones Energéticas Medioambientales y Tecnológicas) is responsible for such task. The central piece of the beam dump, where the ion beam is stopped, is a copper cone with

  7. Estimating the possible range of recycling rates achieved by dump waste pickers: The case of Bantar Gebang in Indonesia.

    Science.gov (United States)

    Sasaki, Shunsuke; Araki, Tetsuya

    2014-06-01

    This article presents informal recycling contributions made by scavengers in the surrounding area of Bantar Gebang final disposal site for municipal solid waste generated in Jakarta. Preliminary fieldwork was conducted through daily conversations with scavengers to identify recycling actors at the site, and then quantitative field surveys were conducted twice. The first survey (n = 504 households) covered 33% of all households in the area, and the second survey (n = 69 households) was conducted to quantify transactions of recyclables among scavengers. Mathematical equations were formulated with assumptions made to estimate the possible range of recycling rates achieved by dump waste pickers. Slightly over 60% of all respondents were involved in informal recycling and over 80% of heads of households were waste pickers, normally referred to as live-in waste pickers and live-out waste pickers at the site. The largest percentage of their spouses were family workers, followed by waste pickers and housewives. Over 95% of all households of respondents had at least one waste picker or one small boss who has a coequal status of a waste picker. Average weight of recyclables collected by waste pickers at the site was estimated to be approximately 100 kg day(-1) per household on the net weight basis. The recycling rate of solid wastes collected by all scavengers at the site was estimated to be in the range of 2.8-7.5% of all solid wastes transported to the site. © The Author(s) 2014.

  8. Assessment of nonpoint source chemical loading potential to watersheds containing uranium waste dumps associated with uranium exploration and mining, Browns Hole, Utah

    Science.gov (United States)

    Marston, Thomas M.; Beisner, Kimberly R.; Naftz, David L.; Snyder, Terry

    2012-01-01

    During August of 2008, 35 solid-phase samples were collected from abandoned uranium waste dumps, undisturbed geologic background sites, and adjacent streambeds in Browns Hole in southeastern Utah. The objectives of this sampling program were (1) to assess impacts on human health due to exposure to radium, uranium, and thorium during recreational activities on and around uranium waste dumps on Bureau of Land Management lands; (2) to compare concentrations of trace elements associated with mine waste dumps to natural background concentrations; (3) to assess the nonpoint source chemical loading potential to ephemeral and perennial watersheds from uranium waste dumps; and (4) to assess contamination from waste dumps to the local perennial stream water in Muleshoe Creek. Uranium waste dump samples were collected using solid-phase sampling protocols. Solid samples were digested and analyzed for major and trace elements. Analytical values for radium and uranium in digested samples were compared to multiple soil screening levels developed from annual dosage calculations in accordance with the Comprehensive Environmental Response, Compensation, and Liability Act's minimum cleanup guidelines for uranium waste sites. Three occupancy durations for sites were considered: 4.6 days per year, 7.0 days per year, and 14.0 days per year. None of the sites exceeded the radium soil screening level of 96 picocuries per gram, corresponding to a 4.6 days per year exposure. Two sites exceeded the radium soil screening level of 66 picocuries per gram, corresponding to a 7.0 days per year exposure. Seven sites exceeded the radium soil screening level of 33 picocuries per gram, corresponding to a 14.0 days per year exposure. A perennial stream that flows next to the toe of a uranium waste dump was sampled, analyzed for major and trace elements, and compared with existing aquatic-life and drinking-water-quality standards. None of the water-quality standards were exceeded in the stream samples.

  9. The effect of the cover and landscape design of waste rock dumps and tailings ponds on the water balance

    International Nuclear Information System (INIS)

    Haehne, R.; Eckart, M.; Marski, R.; Wolf, J.

    1998-01-01

    The dimensioning of cover systems for waste rock dumps and tailings ponds requires the prognosis of the water balances. Site specific field experiments as well as additional modelling efforts are necessary. The cover system could be a simple recultivation layering or a storage systems or a complex multi-layer-system. Uncovered dumps show typical percolation rates between 30 and 60%. Storage cover systems reduce the percolation rate down to 15 to 35%. The evapotranspiration rate is influenced especially by exposition and vegetation. Specific features for the cover of tailings ponds include a very low surface slope and the of percolation rate below 10%. Therefore, multi-layer-systems are most suitable, also because it is characterized by very low drainage velocities of hypodermic runoffs. The resulting, but temporarily high moisture and almost standing water at the surface leads to extreme evapotranspiration rates and consequently to an increase of percolation. (orig.) [de

  10. Layout considerations on the 25GeV/300kW beam dump of the XFEL project

    International Nuclear Information System (INIS)

    Maslov, M.; Sychev, V.; Schmitz, M.

    2006-08-01

    The European X-Ray Free Electron Laser (XFEL) project, which is currently under design at DESY, requires 3 beam dumps downstream of the accelerator. By means of energy deposition, temperature and mechanical stress calculations the layout of a solid edge cooled beam dump is presented. This dump is able to withstand a high cyclic impact, as induced by each subsequent bunch train of up to 2.5.10 13 electrons in combination with a large amount of dissipated power density (∼1.8 kW/cm) coming from a beam with an average power of up to 300 kW at a variable energy up to 25 GeV. The cyclic impact is faced by using graphite as a core material in the dump and setting a lower limit for the incoming beam size at σ beam ≥2 mm. Introducing a slow (not within the bunch train) circular beam sweep answers the question of heat extraction. Alternative layouts are investigated in order to avoid active beam sweeping. Unfortunately more severe risks and disadvantages are coming along with them. That is why theses solutions are not regarded as reliable alternatives and the dump design with beam sweeping is considered to be the baseline solution, for which a technical layout is under way. (orig.)

  11. Layout considerations on the 25GeV/300kW beam dump of the XFEL project

    Energy Technology Data Exchange (ETDEWEB)

    Maslov, M.; Sychev, V. [Institute for High Energy Physics (IHEP), Protvino (Russian Federation); Schmitz, M. [Deutsches Elektronen-Synchrotron (DESY), Hamburg (Germany)

    2006-08-15

    The European X-Ray Free Electron Laser (XFEL) project, which is currently under design at DESY, requires 3 beam dumps downstream of the accelerator. By means of energy deposition, temperature and mechanical stress calculations the layout of a solid edge cooled beam dump is presented. This dump is able to withstand a high cyclic impact, as induced by each subsequent bunch train of up to 2.5.10{sup 13} electrons in combination with a large amount of dissipated power density ({approx}1.8 kW/cm) coming from a beam with an average power of up to 300 kW at a variable energy up to 25 GeV. The cyclic impact is faced by using graphite as a core material in the dump and setting a lower limit for the incoming beam size at {sigma}{sub beam}{>=}2 mm. Introducing a slow (not within the bunch train) circular beam sweep answers the question of heat extraction. Alternative layouts are investigated in order to avoid active beam sweeping. Unfortunately more severe risks and disadvantages are coming along with them. That is why theses solutions are not regarded as reliable alternatives and the dump design with beam sweeping is considered to be the baseline solution, for which a technical layout is under way. (orig.)

  12. One project's waste is another project's resource

    International Nuclear Information System (INIS)

    Short, J.

    1997-01-01

    The author describes the efforts being made toward pollution prevention within the DOE complex, as a way to reduce overall project costs, in addition to decreasing the amount of waste to be handled. Pollution prevention is a concept which is trying to be ingrained into project planning. Part of the program involves the concept that ultimately the responsibility for waste comes back to the generator. Parts of the program involve efforts to reuse materials and equipment on new projects, to recycle wastes to generate offsetting revenue, and to increase awareness, accountability and incentives so as to stimulate action on this plan. Summaries of examples are presented in tables

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

    Science.gov (United States)

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

    2014-08-01

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

  14. Ocean Dumping: International Treaties

    Science.gov (United States)

    The London Convention and London Protocol are global treaties to protect the marine environment from pollution caused by the ocean dumping of wastes. The Marine, Protection, Research and Sanctuaries Act implements the requirements of the LC.

  15. Radon emission from uranium mining waste rock dumps and resulting radon immission; Radonemissionsverhalten von Halden des Uranbergbaus und daraus resultierende Radonemissionen

    Energy Technology Data Exchange (ETDEWEB)

    Regner, J.; Hinz, W.; Schmidt, P. [Wismut GmbH, Chemnitz (Germany)

    2016-07-01

    Since more than 20 years, Wismut GmbH has been investigating the radon situation at uranium mining waste rock dumps. In the present paper the results of 19 complex studies at uranium mining dumps in the Erzgebirge (Ore Mountains) are reported. Although the mean specific activity of Ra-226 of the waste rock material was on a rather low level of about 0.5 Bq/g, the mean radon concentration in free atmosphere at the public exposure sites in the immediate vicinity of the dumps reached a value of about 1000 Bq/m{sup 3} for a half-year exposition and of about 600 Bq/m{sup 3} for a one-year exposition. Certain geometries and structures of waste rock dumps and the occurrence of convective airflows in the dumps are main reasons for the high radon emission despite of the relatively low specific Ra-226 activity. A case study for two buildings directly on the top of a waste rock dump in the town Johanngeorgenstadt is presented. The hypothetical interpolation of the results for Ra-226-activity to a value below the threshold value of 0.2 Bq/g leads to the assumption that problematic radon situations may also occur outside the areas of legacies of uranium mining. Considering the aspects mentioned, a clearance level for NORM of 1 Bq/g is questionable.

  16. Radioactive contamination at dumping sites for nuclear waste in the Kara Sea. Results from the Russian-Norwegian 1993 expedition to the Kara Sea

    Energy Technology Data Exchange (ETDEWEB)

    Strand, P; Rudjord, A L [Statens Straalevern, Oesteraas (Norway); Salbu, B [Norges Landbrukshoegskole, Vollebekk (Norway); and others

    1994-11-01

    During the 1993 Joint Russian-Norwegian Expedition to the Kara Sea, three dumping sites for nuclear waste were investigated: The Tsivolky Bay, the Stepovogo bay and an area in the open Kara Sea (The Novaya Zemlya Trough). Dumped waste was localized and inspected in the Tsivolky Bay and in the Stepovogo Bay using side scanning sonar and underwater camera. In the Stepovogo Bay, the dumped nuclear submarine no. 601, containing spent nuclear fuel was localized. Samples of waters, sediments and biota were collected at nine stations and later analyzed for several radionuclides (gammaemitters, {sup 90}Sr, {sup 238}Pu, {sup 239,240}Pu and {sup 241}Am). The analyses of the samples al the following conclusions to be drawn: (1) Elevated levels of {sup 137}Cs and {sup 90}Sr and presence of {sup 60}Co were observed in the inner part of the Stepovogo Bay, and in one sample collected close to the hull of the dumped nuclear submarine in the Stepovogo Bay. {sup 60}Co was also observed in the Tsivolky Bay. This radioactive contamination most likely originates from the dumped radioactive material. It may be due to leaching from the waste. (2) The enhanced levels of contamination caused by dumped nuclear waste are still low and restricted to small areas. Thus, radiation doses from the existing contamination would be negligible. Radioactive contamination outside these areas is similar to the activity levels in the open Kara Sea. 46 refs.

  17. Radioactive contamination at dumping sites for nuclear waste in the Kara Sea. Results from the Russian-Norwegian 1993 expedition to the Kara Sea

    International Nuclear Information System (INIS)

    Strand, P.; Rudjord, A.L.; Salbu, B.

    1994-11-01

    During the 1993 Joint Russian-Norwegian Expedition to the Kara Sea, three dumping sites for nuclear waste were investigated: The Tsivolky Bay, the Stepovogo bay and an area in the open Kara Sea (The Novaya Zemlya Trough). Dumped waste was localized and inspected in the Tsivolky Bay and in the Stepovogo Bay using side scanning sonar and underwater camera. In the Stepovogo Bay, the dumped nuclear submarine no. 601, containing spent nuclear fuel was localized. Samples of waters, sediments and biota were collected at nine stations and later analyzed for several radionuclides (gammaemitters, 90 Sr, 238 Pu, 239,240 Pu and 241 Am). The analyses of the samples al the following conclusions to be drawn: 1) Elevated levels of 137 Cs and 90 Sr and presence of 60 Co were observed in the inner part of the Stepovogo Bay, and in one sample collected close to the hull of the dumped nuclear submarine in the Stepovogo Bay. 60 Co was also observed in the Tsivolky Bay. This radioactive contamination most likely originates from the dumped radioactive material. It may be due to leaching from the waste. 2) The enhanced levels of contamination caused by dumped nuclear waste are still low and restricted to small areas. Thus, radiation doses from the existing contamination would be negligible. Radioactive contamination outside these areas is similar to the activity levels in the open Kara Sea. 46 refs

  18. Health risk reduction behaviors model for scavengers exposed to solid waste in municipal dump sites in Nakhon Ratchasima Province, Thailand

    Directory of Open Access Journals (Sweden)

    Thirarattanasunthon P

    2012-08-01

    Full Text Available Phiman Thirarattanasunthon,1 Wattasit Siriwong,1,2 Mark Robson,2–4 Marija Borjan3 1College of Public Health Sciences, Chulalongkorn University, 2Thai Fogarty ITREOH Center, Chulalongkorn University, Bangkok, Thailand; 3School of Environmental and Biological Sciences, Rutgers University, New Brunswick, 4UMDNJ-School of Public Health, Piscataway, NJ, USAAbstract: The aim of this study was to evaluate the effect of comprehensive health risk protection behaviors, knowledge, attitudes, and practices among scavengers in open dump sites. A control group of 44 scavengers and an intervention group of 44 scavengers participated in this study. Interventions included the use of personal protective equipment, health protection training, and other measures. The analysis showed significant differences before and after the intervention program and also between the control and intervention groups. These observations suggest that further action should be taken to reduce adverse exposure during waste collection. To reduce health hazards to workers, dump site scavenging should be incorporated into the formal sector program. Solid waste and the management of municipal solid waste has become a human and environmental health issue and future research should look at constructing a sustainable model to help protect the health of scavengers and drive authorities to adopt safer management techniques.Keywords: scavenger, health risk reduction behaviors model (HRRBM, personal protective equipment (PPE, knowledge, attitude, and practice (KAP, waste health coordinator (WHC

  19. Collective dose estimates by the marine food pathway from liquid radioactive wastes dumped in the Sea of Japan

    International Nuclear Information System (INIS)

    Togawa, O.; Povinec, P.P.; Pettersson, H.B.L.

    1999-01-01

    IAEA-MEL has been engaged in an assessment programme related to radioactive waste dumping by the former USSR and other countries in the western North Pacific Ocean and its marginal seas. This paper focuses on the Sea of Japan and on estimation of collective doses from liquid radioactive wastes. The results from the Japanese-Korean-Russian joint expeditions are summarized, and collective doses for the Japanese population by the marine food pathway are estimated from liquid radioactive wastes dumped in the Sea of Japan and compared with those from global fallout and natural radionuclides. The collective effective dose equivalents by the annual intake of marine products caught in each year show a maximum a few years after the disposals. The total dose from all radionuclides reaches a maximum of 0.8 man Sv in 1990. Approximately 90% of the dose derives from 137Cs, most of which is due to consumption of fish. The total dose from liquid radioactive wastes is approximately 5% of that from global fallout, the contribution of which is below 0.1% of that of natural 210Po

  20. Application of two-barrier model of radioactive agent transport in sea water for analyzing artificial radionuclide release from containers with radioactive waste dumped in Kara Sea

    Energy Technology Data Exchange (ETDEWEB)

    Grishin, Denis S.; Laykin, Andrey I.; Kuchin, Nickolay L.; Platovskikh, Yuri A. [Krylov State Research Center, Saint Petersburg, 44 Moskovskoe shosse, 196158 (Russian Federation)

    2014-07-01

    Modeling of artificial radionuclide transport in sea water is crucial for prognosis of radioecological situation in regions where dumping of radioactive waste had been made and/or accidents with nuclear submarines had taken place. Distribution of artificial radionuclides in bottom sediments can be a detector of radionuclide release from dumped or sunk objects to marine environment. Proper model can determine the dependence between radionuclide distribution in sediments and radionuclide release. Following report describes two-barrier model of radioactive agent transport in sea water. It was tested on data from 1994 - 2013 expeditions to Novaya Zemlya bays, where regular dumping of solid radioactive waste was practiced by the former USSR from the early 1960's until 1990. Two-barrier model agrees with experimental data and allows more accurate determination of time and intensity of artificial radionuclide release from dumped containers. (authors)

  1. EPRI waste processing projects

    International Nuclear Information System (INIS)

    Shaw, R.A.

    1987-01-01

    The Electric Power Research Institute (EPRI) manages research for its sponsoring electric utilities in the United States. Research in the area of low level radioactive waste (LLRW) from light water reactors focuses primarily on waste processing within the nuclear power plants, monitoring of the waste packages, and assessments of disposal technologies. Accompanying these areas and complimentary to them is the determination and evaluation of the sources of nuclear power plants radioactive waste. This paper focuses on source characterization of nuclear power plant waste, LLRW processing within nuclear power plants, and the monitoring of these wastes. EPRI's work in waste disposal technology is described in another paper in this proceeding by the same author. 1 reference, 5 figures

  2. Radioactive-waste ocean dumping will have negligible enviromental impact. Conclusion of draft assessment of NSB

    Energy Technology Data Exchange (ETDEWEB)

    1976-11-01

    This draft report is the result of extensive studies based on the best available information in the field of oceanography, marine radiobiology and health physics. On various basic considerations, assessment was undertaken, and the following conclusion was reached. The quantity of radioactivity to be dumped at one time is assumed to be 500 Ci in the case of test dumping, and 10/sup 5/ Ci/year in the case of full-scale dumping. The conditions required for the dumping sea area are that the bottom water flow and upwelling amount are limited, and that the sea bottom is flat. The horizontal dispersion coefficient of 10/sup 7/ cm/sup 2//sec and the vertical dispersion coefficient of 2 x 10/sup 2/ cm/sup 2//sec are assumed. It is assumed that the radionuclides in the disposed package would leached out as soon as it reaches the sea bottom, and would not show any physicochemical behavior. Typycal radionuclides are classified into 5 groups in terms of their half lives, and their estimated concentrations at 1 km depth are tabulated. The maximum level of individual dose and the magnitude of population dose were assessed on the fishermen working in the dumping sea area, and the adults, children and infants who were expected to receive higher dose on account of the larger intake of fish products than average. The dose level given with the dose assessment model and various panamentors under the dumping conditions is much lower than natural radiation and the permissible level recommended by ICRP.

  3. Effects of Occupational Exposure on the Health of Rag Pickers Due to Fungal Contamination at Waste Dumping Sites in Gwalipor (India

    Directory of Open Access Journals (Sweden)

    Harandra K. Sharma

    2017-02-01

    Full Text Available We investigated fungal contamination near different waste dumping sites and assessed the health risk factors of rag pickers associated with collection of waste in Gwalior during the year 2014-15. Petri plates were exposed at waste dumping sites and were transferred to the laboratory, analysis and identification was mainly carried out by culturing the fungal colonies by following standard procedures. A pretested questionnaire was used to evaluate the health problems among the rag pickers. Results indicated that all the dumping sites are contaminated with different types of fungal pathogens like Alternaria alternate, Aspergillus flavus, A. fumigates, A. niger, Cladosporium, Fusarium, Mucor, Penicillium and Rhizopus. Our study reported higher incidence of musculoskeletal and respiratory diseases among rag pickers. There is also strong need for carrying out similar assessment studies for other cities too. This will entail generation of more precise site specific information regarding fungal species and associated health risk factor.

  4. Effects of Occupational Exposure on the Health of Rag Pickers Due to Fungal Contamination at Waste Dumping Sites in Gwalior (India

    Directory of Open Access Journals (Sweden)

    Harandra K. Sharma

    2017-02-01

    Full Text Available We investigated fungal contamination near different waste dumping sites and assessed the health risk factors of rag pickers associated with collection of waste in Gwalior during the year 2014-15. Petri plates were exposed at waste dumping sites and were transferred to the laboratory, analysis and identification was mainly carried out by culturing the fungal colonies by following standard procedures. A pretested questionnaire was used to evaluate the health problems among the rag pickers. Results indicated that all the dumping sites are contaminated with different types of fungal pathogens like Alternaria alternate, Aspergillus flavus, A. fumigates, A. niger, Cladosporium, Fusarium, Mucor, Penicillium and Rhizopus. Our study reported higher incidence of musculoskeletal and respiratory diseases among rag pickers. There is also strong need for carrying out similar assessment studies for other cities too. This will entail generation of more precise site specific information regarding fungal species and associated health risk factor.

  5. Definition and recommendations for the convention on the prevention of marine pollution by dumping of wastes and other matter, 1972. 1986 ed.

    International Nuclear Information System (INIS)

    1986-01-01

    Under the terms of the Convention on the Prevention of Marine Pollution by Dumping of Wastes and Other Matter, the IAEA is the organization with the responsibility for defining high level radioactive wastes or other high level radioactive matter which is unsuitable for dumping at sea, and for making recommendations to Contracting Parties about the issue of permits for dumping radioactive waste or other radioactive matter. The IAEA established a provisional Definition and Recommendations in 1974 and a revised version in 1978. This Safety Series document contains the second revised Definition and Recommendations, which were established in 1985. The Annexes to the document contain a description of the calculations which form the basis of the quantitative Definition, a comparison between the new and the previous version and a list of all the meetings held during the process of establishing the new document

  6. Rock waste dumps on the Davydov Glacier (Akshyirak Range, Tien Shan

    Directory of Open Access Journals (Sweden)

    V. A. Kuzmichenok

    2012-01-01

    Full Text Available Since 1995, a barren rock has been formed at the Davydov Glacier, due to the works at the Kumtor Gold Mine. By the end of 2010, total amount of the rock, stockpiled on the glacier, apparently exceeded 200 million tons, the height of dumps of rock sometimes exceeded 50 meters. The most noticeable effects of this are provoking local surges of the Davydov Glacier and squeezing glacier ice out of the dumps of rock. For a detailed analysis of both processes, we also used the results of periodic geodetic measurements (over 8000 of monitoring rods (about 800 rods of the gold mining company. A number of local surges of the glacier has been found, the first of which began in March–April 2002. To analyze glacier squeezing out of the dumps of rock, mathematical modeling of that process has been done. It was established that in most cases, the glacier is almost completely squeezed out of for 1–2 years.

  7. Sustainable waste management in Africa through CDM projects

    Energy Technology Data Exchange (ETDEWEB)

    Couth, R. [CRECHE, Centre for Research in Environmental, Coastal and Hydrological Engineering, School of Engineering, University of KwaZulu-Natal, Durban 4041 (South Africa); Trois, C., E-mail: troisc@ukzn.ac.za [CRECHE, Centre for Research in Environmental, Coastal and Hydrological Engineering, School of Engineering, University of KwaZulu-Natal, Durban 4041 (South Africa)

    2012-11-15

    Highlights: Black-Right-Pointing-Pointer This is a compendium on GHG reductions via improved waste strategies in Africa. Black-Right-Pointing-Pointer This note provides a strategic framework for Local Authorities in Africa. Black-Right-Pointing-Pointer Assists LAs to select Zero Waste scenarios and achieve sustained GHG reduction. - Abstract: Only few Clean Development Mechanism (CDM) projects (traditionally focussed on landfill gas combustion) have been registered in Africa if compared to similar developing countries. The waste hierarchy adopted by many African countries clearly shows that waste recycling and composting projects are generally the most sustainable. This paper undertakes a sustainability assessment for practical waste treatment and disposal scenarios for Africa and makes recommendations for consideration. The appraisal in this paper demonstrates that mechanical biological treatment of waste becomes more financially attractive if established through the CDM process. Waste will continue to be dumped in Africa with increasing greenhouse gas emissions produced, unless industrialised countries (Annex 1) fund carbon emission reduction schemes through a replacement to the Kyoto Protocol. Such a replacement should calculate all of the direct and indirect carbon emission savings and seek to promote public-private partnerships through a concerted support of the informal sector.

  8. Closure Report for Corrective Action Unit 357: Mud Pits and Waste Dump, Nevada Test Site, Nevada, Rev. No.: 0

    Energy Technology Data Exchange (ETDEWEB)

    Laura A. Pastor

    2005-04-01

    This Closure Report (CR) presents information supporting closure of Corrective Action Unit (CAU) 357: Mud Pits and Waste Dump, Nevada Test Site (NTS), Nevada. The CR complies with the requirements of the Federal Facility Agreement and Consent Order (FFACO) that was agreed to by the State of Nevada, U.S. Department of Energy (DOE), and the U.S. Department of Defense (FFACO, 1996). Corrective Action Unit 357 is comprised of 14 Corrective Action Sites (CASs) located in Areas 1, 4, 7, 8, 10, and 25 of the NTS (Figure 1-1). The NTS is located approximately 65 miles (mi) northwest of Las Vegas, Nevada. Corrective Action Unit 357 consists of 11 CASs that are mud pits located in Areas 7, 8, and 10. The mud pits were associated with drilling activities conducted on the NTS in support of the underground nuclear weapons testing. The remaining three CASs are boxes and pipes associated with Building 1-31.2el, lead bricks, and a waste dump. These CAS are located in Areas 1, 4, and 25, respectively. The following CASs are shown on Figure 1-1: CAS 07-09-02, Mud Pit; CAS 07-09-03, Mud Pit; CAS 07-09-04, Mud Pit; CAS 07-09-05, Mud Pit; CAS 08-09-01, Mud Pit; CAS 08-09-02, Mud Pit; CAS 08-09-03, Mud Pit; CAS 10-09-02, Mud Pit; CAS 10-09-04, Mud Pit; CAS 10-09-05, Mud Pit; CAS 10-09-06, Mud Pit, Stains, Material; CAS 01-99-01, Boxes, Pipes; CAS 04-26-03, Lead Bricks; and CAS 25-15-01, Waste Dump. The purpose of the corrective action activities was to obtain analytical data that supports the closure of CAU 357. Environmental samples were collected during the investigation to determine whether contaminants exist and if detected, their extent. The investigation and sampling strategy was designed to target locations and media most likely to be contaminated (biased sampling). A general site conceptual model was developed for each CAS to support and guide the investigation as outlined in the Streamlined Approach for Environmental Restoration (SAFER) Plan (NNSA/NSO, 2003b). This CR

  9. The Influence of Engineering-Geological Conditions on the Construction of the Radioactive Waste Dump

    Directory of Open Access Journals (Sweden)

    Jozef Kuzma

    2007-01-01

    Full Text Available A secure stability and reliable serviceability of the radioactive dump is a difficult engineering problem. Due to the difficult geological formations determined mainly by a high compressibility, the low shear strength of soils, and the high ground water level, or a high upward hydrostatic pressure these demands will increase. An influence of the required reliability and the lifespan on the structure of these specific objects is considerable. In this contribution, we are trying to contribute to the problem of solving these difficulties and complicated problems.

  10. Act No. 305 of 2 May 1983. Ratification and execution of the Convention on the Prevention of Marine Pollution by Dumping of Wastes and other Matter, opened for signature in Mexico, London, Moscow and Washington on 29th December 1972, as modified by the amendments annexed to the resolution adopted in London on 12 October 1978

    International Nuclear Information System (INIS)

    1983-01-01

    The London Convention provides for a system classifying radioactive waste for sea dumping. It prohibits the dumping of high level radioactive waste and makes the dumping of other categories of such waste subject to and in compliance with a special permit. (NEA) [fr

  11. A simple model for the dispersion of radioactive wastes dumped on the deep-sea bed

    International Nuclear Information System (INIS)

    Shepherd, J.G.

    1976-01-01

    A simple model has been developed for the dispersion of radioactive materials in a closed and finite ocean. It allows for the simultaneous action of both diffusion and horizontal (but not vertical) advection, and thus avoids the major limitations of previous models. It is sufficiently versatile to handle non-Fickian diffusion and radioactive decay, but requires numerical integration using some semi-empirical form for the Green function of diffusion from a point source. The model has been used to estimate equilibrium concentrations of radioactive materials in sea water arising from the continuous release of material from a dump on the bottom of the deep ocean, using parameters appropriate for the North Atlantic. It is found that except under rather extreme conditions the surface concentrations do not exceed the long-term average value which would be established in a perfectly mixed ocean. The concentrations are also rather insensitive to the values of the diffusion and advection parameters used, except for that for vertical diffusion, but depend strongly on the overall removal rate of material from the ocean, including processes other than radioactive decay. It is suggested that safety assessments of deep-sea dumping should utilize estimates of the environmental capacities of the oceans based on the long-term 'well-mixed' average concentrations (which are very easily calculated) using a safety factor of no more than ten to allow for the possible effects of pluming and upwelling. (author)

  12. Waste Management Project Contingency Analysis

    International Nuclear Information System (INIS)

    Edward L. Parsons, Jr.

    1999-01-01

    The purpose of this report is to provide the office of Waste Management (WM) with recommended contingency calculation procedures for typical WM projects. Typical projects were defined as conventional construction-type activities that use innovative elements when necessary to meet the project objectives. Projects involve treatment, storage, and disposal of low level, mixed low level, hazardous, transuranic, and high level waste. Cost contingencies are an essential part of Total Cost Management. A contingency is an amount added to a cost estimate to compensate for unexpected expenses resulting from incomplete design, unforeseen and unpredictable conditions, or uncertainties in the project scope (DOE 1994, AACE 1998). Contingency allowances are expressed as percentages of estimated cost and improve cost estimates by accounting for uncertainties. The contingency allowance is large at the beginning of a project because there are more uncertainties, but as a project develops, the allowance shrinks to adjust for costs already incurred. Ideally, the total estimated cost remains the same throughout a project. Project contingency reflects the degree of uncertainty caused by lack of project definition, and process contingency reflects the degree of uncertainty caused by use of new technology. Different cost estimation methods were reviewed and compared with respect to terminology, accuracy, and Cost Guide standards. The Association for the Advancement of Cost Engineering (AACE) methods for cost estimation were selected to represent best industry practice. AACE methodology for contingency analysis can be readily applied to WM Projects, accounts for uncertainties associated with different stages of a project, and considers both project and process contingencies and the stage of technical readiness. As recommended, AACE contingency allowances taper off linearly as a project nears completion

  13. A simple model for the dispersion of radioactive wastes dumped on the deep-sea bed

    International Nuclear Information System (INIS)

    Shepherd, J.G.

    1976-01-01

    A simple model has been developed for the dispersion of radioactive materials in a closed and finite ocean. It allows for the simultaneous action of both diffusion and horizontal (but not vertical) advection, and thus avoids the major limitations of previous models such as that of Webb and Morley. It is sufficiently versatile to handle non-Fickian diffusion and radioactive decay, but requires numerical integration using some semi-empirical form for the Green's function of diffusion from a point source. The model has been used to estimate equilibrium concentrations of radioactive materials in sea water arising from the continuous release of material from a dump on the bottom of the deep ocean, using parameters appropriate for the North Atlantic. It is found that except under rather extreme conditions the surface concentrations do not exceed the long-term average value which would be established in a perfectly mixed ocean. The concentrations are also rather insensitive to the values of the diffusion and advection parameters used, except for that for vertical diffusion, but depend strongly on the overall removal rate of material from the ocean, including processes other than radioactive decay. It is suggested that safety assessments of deep-sea dumping should utilize estimates of the environmental capacities of the oceans based on the long-term 'well-mixed' average concentrations (which are very easily calculated) using a safety factor of no more than ten to allow for the possible effects of pluming and upwelling. In so far as their results are comparable, the present model yields estimates which are close to those of the Webb-Morley model for overall half-lives between 30 and 3000 years, but which become increasingly more restrictive for longer-lived materials. (author)

  14. Social dumping

    DEFF Research Database (Denmark)

    Pedersen, Klaus

    2010-01-01

    bidrag til, at OK-2010 "landes" fredeligt, fordi aftalen giver fagforeningerne en væsentlig indrømmelse i indsatsen mod social dumping. Aftalen har rigtignok til formål at imødekomme et af fagbevægelsens centrale overenskomstkrav om nye redskaber i indsatsen mod "social dumping". Men hvad er det aftalen...

  15. Dumping at Sea Act 1974

    International Nuclear Information System (INIS)

    1974-01-01

    This Act enables the United Kingdom Government to ratify both the Oslo Convention of 1972 for the Prevention of Marine Pollution by Dumping from Ships and Aircraft and the London Convention of 1972 on the Prevention of Marine Pollution by Dumping of Wastes and Other Matter. (NEA) [fr

  16. Corrective action investigation plan for Corrective Action Unit 143: Area 25 contaminated waste dumps, Nevada Test Site, Nevada, Revision 1 (with Record of Technical Change No. 1 and 2)

    Energy Technology Data Exchange (ETDEWEB)

    USDOE Nevada Operations Office (DOE/NV)

    1999-06-28

    This plan contains the US Department of Energy, Nevada Operations Office's approach to collect the data necessary to evaluate correction action alternatives appropriate for the closure of Corrective Action Unit (CAU) 143 under the Federal Facility Agreement and Consent Order. Corrective Action Unit 143 consists of two waste dumps used for the disposal of solid radioactive wastes. Contaminated Waste Dump No.1 (CAS 25-23-09) was used for wastes generated at the Reactor Maintenance Assembly and Disassembly (R-MAD) Facility and Contaminated Waste Dump No.2 (CAS 25-23-03) was used for wastes generated at the Engine Maintenance Assembly and Disassembly (E-MAD) Facility. Both the R-MAD and E-MAD facilities are located in Area 25 of the Nevada Test Site. Based on site history, radionuclides are the primary constituent of concern and are located in these disposal areas; vertical and lateral migration of the radionuclides is unlikely; and if migration has occurred it will be limited to the soil beneath the Contaminated Waste Disposal Dumps. The proposed investigation will involve a combination of Cone Penetrometer Testing within and near the solid waste disposal dumps, field analysis for radionuclides and volatile organic compounds, as well as sample collection from the waste dumps and surrounding areas for off-site chemical, radiological, and geotechnical analyses. The results of this field investigation will support a defensible evaluation of corrective action alternatives in the corrective action decision document.

  17. Convention on the Prevention of Marine Pollution by Dumping of Wastes and other Matter. The Definition Required by Annex I, paragraph 6 to the Convention and the Recommendations Required by Annex II, Section D

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1975-01-10

    Paragraph 6 of Annex I to the Convention on the Prevention of Marine Pollution by Dumping of Wastes and Other Matter provides for the Agency to define high-level radioactive wastes or other high-level radioactive matter as unsuitable for dumping at sea, and section D of Annex II provides for the Agency to make recommendations which the Contracting Parties to the Convention should take fully into account in issuing permits for the dumping at sea of radioactive wastes or other radioactive matter ''not included in Annex I''.

  18. Convention on the Prevention of Marine Pollution by Dumping of Wastes and other Matter. The Definition Required by Annex I, paragraph 6 to the Convention and the Recommendations Required by Annex II, Section D

    International Nuclear Information System (INIS)

    1975-01-01

    Paragraph 6 of Annex I to the Convention on the Prevention of Marine Pollution by Dumping of Wastes and Other Matter provides for the Agency to define high-level radioactive wastes or other high-level radioactive matter as unsuitable for dumping at sea, and section D of Annex II provides for the Agency to make recommendations which the Contracting Parties to the Convention should take fully into account in issuing permits for the dumping at sea of radioactive wastes or other radioactive matter ''not included in Annex I''.

  19. Corrective Action Investigation Plan for Corrective Action Unit 140: Waste Dumps, Burn Pits, and Storage Area, Nevada Test Site, Nevada, July 2002, Rev. No. 0

    International Nuclear Information System (INIS)

    2002-01-01

    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) 140 under the Federal Facility Agreement and Consent Order. Corrective Action Unit 140 consists of nine Corrective Action Sites (CASs): 05-08-01, Detonation Pits; 05-08-02, Debris Pits; 05-17-01, Hazardous Waste Accumulation Site (Buried); 05-19-01, Waste Disposal Site; 05-23-01, Gravel Gertie; 05-35-01, Burn Pit; 05-99-04, Burn Pit; 22-99-04, Radioactive Waste Dump; 23-17-01, Hazardous Waste Storage Area. All nine of these CASs are located within Areas 5, 22, and 23 of the Nevada Test Site (NTS) in Nevada, approximately 65 miles northwest of Las Vegas. This CAU is being investigated because disposed waste may be present without appropriate controls (i.e., use restrictions, adequate cover) and hazardous and/or radioactive constituents may be present or migrating at concentrations and locations that could potentially pose a threat to human health and the environment. The NTS has been used for various research and development projects including nuclear weapons testing. The CASs in CAU 140 were used for testing, material storage, waste storage, and waste disposal. A two-phase approach has been selected to collect information and generate data to satisfy needed resolution criteria and resolve the decision statements. Phase I will determine if contaminants of potential concern (COPCs) are present in concentrations exceeding preliminary action levels. This data will be evaluated at all CASs. Phase II will determine the extent of the contaminant(s) of concern (COCs). This data will only be evaluated for CASs with a COC identified during Phase I. Based on process knowledge, the COPCs for CAU 140 include volatile organics, semivolatile organics, petroleum hydrocarbons, explosive residues

  20. A critical study on the IAEA definition of high level radioactive waste unsuitable for dumping at sea

    International Nuclear Information System (INIS)

    Miyake, Yasuo; Saruhashi, Katsuko.

    1976-01-01

    The definition of high level radioactive waste and other high level radioactive matter not suitable for dumping at sea has been given by IAEA (1975). Since this definition is based on the report by Webb and Morley (1973), a critical study is made on their report. The result of study shows that owing to the assumption of a very small value of the horizontal eddy diffusion coefficient (10 4 cm 2 /s) for the sake of safety for these nuclides, the limiting environmental capacity for such nuclides as 226 Ra and 239 Pu with longer half-lives is extremely overestimated. And due to a very small value of a daily intake of marine foods (6 g/d) and a larger value of the ratio of nuclidic concentrations between the top of the deep layer and the surface layer (100), the environmental capacity is also overestimated for every nuclide. It is proposed that the definition of high level radioactive waste should be reassessed carefully by experts in various countries. (auth.)

  1. Dumping and Illegal Transport of Hazardous Waste, Danger of Modern Society

    OpenAIRE

    Obradović, Mario; Kalambura, Sanja; Smolec, Danijel; Jovičić, Nives

    2014-01-01

    Increasing the production of hazardous waste during the past few years and stricter legislation in the area of​ permanent disposal and transportation costs were significantly elevated above activities. This creates a new, highly lucrative gray market which opens the way for the criminalization. Of great importance is the identification of illegal trafficking of hazardous waste since it can have a significant impact on human health and environmental pollution. Barriers to effective engagement ...

  2. Radioactive waste inventories and projections

    International Nuclear Information System (INIS)

    McLaren, L.H.

    1982-11-01

    This bibliography contains information on radioactive waste inventories and projections included in the Department of Energy's Energy Data Base from January 1981 through September 1982. The arrangement is by report number for reports, followed by nonreports in reverse chronological order. These citations are to research reports, journal articles, books, patents, theses, and conference papers from worldwide sources. Five indexes, each preceded by a brief description, are provided: Corporate Author, Personal Author, Subject, Contract Number, and Report Number. (25 abstracts)

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1994-01-01

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

  4. Investigation of environmental radioactivity in waste dumping areas of the far eastern seas. JAERI`s activities in the 1st Japanese-Korean-Russian joint expedition 1994

    Energy Technology Data Exchange (ETDEWEB)

    Amano, Hikaru; Matsunaga, Takeshi [Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment; Yabuuchi, Noriaki

    1996-10-01

    Large quantities of radioactive waste have been dumped in the Far Eastern Sea by the former USSR and Russia. In order to survey marine radioactive contamination in the Far Eastern Sea, the first Japanese-Korean-Russian joint expedition was conducted according to the governmental agreement. The joint expedition was conducted at the areas of the Russian radioactive waste dumping site from March 18 1994 to April 6, 1994. JAERI participated in this expedition according to the request from STA Japan, and conducted mainly on-board measurement of marine radioactivities. The results showed that the radionuclides concentrations in seawater and seabed sediment samples from the study site were not different from those in the western North Pacific. This report summarises JAERI`s activities in the expedition. Final report by Japanese-Korean-Russian government and IAEA is annexed. (author)

  5. Investigation of environmental radioactivity in waste dumping areas of the far eastern seas. JAERI's activities in the 1st Japanese-Korean-Russian joint expedition 1994

    International Nuclear Information System (INIS)

    Amano, Hikaru; Matsunaga, Takeshi; Yabuuchi, Noriaki.

    1996-10-01

    Large quantities of radioactive waste have been dumped in the Far Eastern Sea by the former USSR and Russia. In order to survey marine radioactive contamination in the Far Eastern Sea, the first Japanese-Korean-Russian joint expedition was conducted according to the governmental agreement. The joint expedition was conducted at the areas of the Russian radioactive waste dumping site from March 18 1994 to April 6, 1994. JAERI participated in this expedition according to the request from STA Japan, and conducted mainly on-board measurement of marine radioactivities. The results showed that the radionuclides concentrations in seawater and seabed sediment samples from the study site were not different from those in the western North Pacific. This report summarises JAERI's activities in the expedition. Final report by Japanese-Korean-Russian government and IAEA is annexed. (author)

  6. Remaining Sites Verification Package for the 120-F-1 Glass Dump Waste Site. Attachment to Waste Site Reclassification Form 2008-028

    International Nuclear Information System (INIS)

    Capron, J.M.

    2008-01-01

    The 120-F-1 waste site consisted of two dumping areas located 660 m southeast of the 105-F Reactor containing laboratory equipment and bottles, demolition debris, light bulbs and tubes, small batteries, small drums, and pesticide contaminated soil. It is probable that 108-F was the source of the debris but the material may have come from other locations within the 100-F Area. In accordance with this evaluation, the verification sampling results support a reclassification of this site to Interim Closed Out. The results of verification sampling show that residual contaminant concentrations do not preclude any future uses and allow for unrestricted use of shallow zone soils. The results also demonstrate that residual contaminant concentrations are protective of groundwater and the Columbia River

  7. Dumping and illegal transport of hazardous waste, danger of modern society.

    Science.gov (United States)

    Obradović, Mario; Kalambura, Sanja; Smolec, Danijel; Jovicić, Nives

    2014-06-01

    Increasing the production of hazardous waste during the past few years and stricter legislation in the area of permanent disposal and transportation costs were significantly elevated above activities. This creates a new, highly lucrative gray market which opens the way for the criminalization. Of great importance is the identification of illegal trafficking of hazardous waste since it can have a significant impact on human health and environmental pollution. Barriers to effective engagement to prevent these activities may vary from region to region, country to country, but together affect the ability of law enforcement authorities to ensure that international shipments of hazardous waste comply with national laws and maritime regulations. This paper will overview the legislation governing these issues, and to analyze the barriers to their implementation, but also try to answer the question of why and how this type of waste traded. Paper is an overview of how Croatia is prepared to join the European Union in this area and indicates the importance and necessity of the cooperation of all of society, and international organizations in the fight with the new trend of environmental crime.

  8. Radioactive contamination from dumped nuclear waste in the Kara Sea--results from the joint Russian-Norwegian expeditions in 1992-1994.

    Science.gov (United States)

    Salbu, B; Nikitin, A I; Strand, P; Christensen, G C; Chumichev, V B; Lind, B; Fjelldal, H; Bergan, T D; Rudjord, A L; Sickel, M; Valetova, N K; Føyn, L

    1997-08-25

    Russian-Norwegian expeditions to the Kara Sea and to dumping sites in the fjords of Novaya Zemlya have taken place annually since 1992. In the fjords, dumped objects were localised with sonar and ROV equipped with underwater camera. Enhanced levels of 137Cs, 60Co, 90Sr and 239,240Pu in sediments close to dumped containers in the Abrosimov and Stepovogo fjords demonstrated that leaching from dumped material has taken place. The contamination was inhomogeneously distributed and radioactive particles were identified in the upper 10 cm of the sediments. 137Cs was strongly associated with sediments, while 90Sr was more mobile. The contamination was less pronounced in the areas where objects presumed to be reactor compartments were located. The enhanced level of radionuclides observed in sediments close to the submarine in Stepovogo fjord in 1993 could, however, not be confirmed in 1994. Otherwise, traces of 60Co in sediments were observed in the close vicinity of all localised objects. Thus, the general level of radionuclides in waters, sediments and biota in the fjords is, somewhat higher or similar to that of the open Kara Sea, i.e. significantly lower than in other adjacent marine systems (e.g. Irish Sea, Baltic Sea, North Sea). The main sources contributing to radioactive contamination were global fallout from atmospheric nuclear weapon tests, river transport from Ob and Yenisey, marine transport of discharges from Sellafield, UK and fallout from Chernobyl. Thus, the radiological impact to man and the arctic environment of the observed leakages from dumped radioactive waste today, is considered to be low. Assuming all radionuclides are released from the waste, preliminary assessments indicate a collective dose to the world population of less than 50 man Sv.

  9. Some historical background to the IAEA Definition and Recommendations concerning high-level radioactive wastes or other high-level radioactive matter unsuitable for dumping at sea

    International Nuclear Information System (INIS)

    Nishiwaki, Y.

    1981-01-01

    The need for internationally acceptable standards and regulations for preventing pollution of the sea by radioactive materials was recognized by the United Nations Conference on the Law of the Sea, which adopted the Convention on the High Seas in April 1958. Article 25 of the Convention provides that ''every State shall take measures to prevent pollution of the seas from the dumping of radioactive wastes, taking into account any standards and regulations which may be formulated by the competent international organizations.'' The Conference also adopted a resolution recommending that the IAEA pursue studies and take action to assist States in controlling the discharge of radioactive materials into the sea. When the Convention on the Prevention of Marine Pollution by Dumping of Wastes and Other Matter was adopted at the Intergovernmental Conference in London, 1972, the IAEA was given specific responsibilities to define criteria and standards for dealing with the questions of sea disposal of radioactive wastes. The IAEA Definition and Recommendations concerning ''high-level radioactive wastes or other high-level radioactive matter unsuitable for dumping at sea'' identify material, the radioactive content of which is at such a level that the Parties to the Convention would wish to prevent any participating State from issuing a special permit even after a detailed appraisal of the safety of the proposed operation, and even for the sector of the marine environment furthest removed from man, i.e. the deep sea with depth greater than 4000 m. Some historical background to these problems is discussed and some of the Japanese findings of the deep sea survey in the Pacific are introduced for comparison with the North Atlantic data which formed a basis of the IAEA Definition and Recommendations for the London Dumping Convention

  10. Corrective Action Decision Document/Closure Report for Corrective Action Unit 511: Waste Dumps (Piles and Debris) Nevada Test Site, Nevada, Rev. No.: 0

    Energy Technology Data Exchange (ETDEWEB)

    Pastor, Laura

    2005-12-01

    This Corrective Action Decision Document/Closure Report has been prepared for Corrective Action Unit (CAU) 511, Waste Dumps (Piles & Debris). The CAU is comprised of nine corrective action sites (CASs) located in Areas 3, 4, 6, 7, 18, and 19 of the Nevada Test Site, Nevada, in accordance with the ''Federal Facility Agreement and Consent Order'' (1996). Corrective Action Unit 511 is comprised of nine CASs: (1) 03-08-02, Waste Dump (Piles & Debris); (2) 03-99-11, Waste Dump (Piles); (3) 03-99-12, Waste Dump (Piles & Debris); (4) 04-99-04, Contaminated Trench/Berm; (5) 06-16-01, Waste Dump (Piles & Debris); (6) 06-17-02, Scattered Ordnance/Automatic Weapons Range; (7) 07-08-01, Contaminated Mound; (8) 18-99-10, Ammunition Dump; and (9) 19-19-03, Waste Dump (Piles & Debris). The purpose of this Corrective Action Decision Document/Closure Report is to provide justification and documentation supporting the recommendation for closure of CAU 511 with no further corrective action. To achieve this, corrective action investigation (CAI) and closure activities were performed from January 2005 through August 2005, as set forth in the ''Corrective Action Investigation Plan for Corrective Action Unit 511: Waste Dumps (Piles & Debris)'' (NNSA/NSO, 2004) and Record of Technical Change No. 1. The purpose of the CAI was to fulfill the following data needs as defined during the data quality objective process: (1) Determine whether contaminants of concern (COCs) are present. (2) If COCs are present, determine their nature and extent. (3) Provide sufficient information and data to complete appropriate corrective actions. The CAU 511 dataset from the investigation results was evaluated based on the data quality indicator parameters. This evaluation demonstrated the quality and acceptability of the dataset for use in fulfilling the data quality objective data needs. Analytes detected during the CAI were evaluated against appropriate preliminary

  11. A non-fickian approach to the consequences of dumping solid radioactive wastes in a finite ocean

    International Nuclear Information System (INIS)

    Sarma, T.P.; D'Souza, R.S.; Sastry, V.N.; Soman, S.D.

    1981-01-01

    A mathematical model is developed to describe the spatial and temporal distributions of radionuclides released from solid wastes dumped on a sea bed. It takes into account the field tested dependence of horizontal eddy diffusion coefficients by the '4/3 power law' and the geochemical mean residence times of these elements in oceans. Since ocean dimensions cannot be considered infinite except for very short lived nuclides (a few months), the reflections of nuclides at the boundaries and the consequent effects on the overall concentrations have been assessed. The computations indicate that the entire activity is confined to the ocean dimensions, and the integral mean concentration value over the entire depth approaches the well-mixed value at large times. The effect of using the geochemical residence time concept leads to much lower concentration levels in waters for transuranic nuclides such as 239 Pu because of the much shorter geochemical residence times compared to the physical half-lives; in contrast for the majority of the other nuclides, the governing factor is essentially the radioactive decay only. (author)

  12. Electromagnetic methods to characterize the Savoia di Lucania waste dump (Southern Italy)

    Science.gov (United States)

    Bavusi, M.; Rizzo, E.; Lapenna, V.

    2006-11-01

    The aim of this work is the joint application and integration of non-invasive geoelectrical methods for studying the landfill of Savoia di Lucania (Southern Italy). This landfill for its engineering features and small dimensions (70 m × 30 m × 6 m) represents an optimal test site to assess a geophysical survey protocol for municipal solid waste landfills investigation and monitoring. The landfill of Savoia di Lucania has been built with a reinforced concrete material and coated with a high-density polyethylene (HDPE) liner. Three electrical resistivity tomographies (ERT), two self-potential (SP) map surveys and one induced polarization (IP) section have been performed, both in the surrounding area and inside the waste landfill. The geophysical investigations have well defined some buried boundaries of the landfill basin and localized the leachate accumulation zones inside the dumpsite. Comparison of our results with other engineering and geological investigations could be the key for evaluating the integrity of the HDPE liner. Finally, the joint use of the ERT, IP and SP methods seems to be a promising tool for studying and designing new monitoring systems able to perform a time-lapse analysis of waste landfill geometry and integrity.

  13. SISTEM PENGOLAHAN AIR ASAM TAMBANG PADA WATER POND DAN APLIKASI MODEL ENCAPSULATION IN-PIT DISPOSAL PADA WASTE DUMP TAMBANG BATUBARA (Acid Mine Drainage Treatment System in Water Pond and Application of Encapsulation In-Pit Disposal Model in Waste Dump

    Directory of Open Access Journals (Sweden)

    Andy R. Erwin Wijaya

    2010-03-01

    Full Text Available ABSTRAK Kegiatan pertambangan batubara umumnya dapat menimbulkan dampak negatif terhadap lingkungan di lokasi penambangan. Salah satu dampak negatif yang signifikan adalah terjadinya pencemaran air asam tambang yang dapat merusak fungsi lingkungan seperti komponen air dan tanah. Umumnya lokasi tambang batubara yang berpotensi besar sebagai sumber terbentuknya air asam tambang adalah kolam penampungan air tambang (water pond dan tempat penimbunan material buangan sulfida (waste dump. Penelitian ini bertujuan untuk mengendalikan rembesan air asam tambang yang berasal dari kolam penampungan air (water pond dan mengurangi terbentuknya air asam tambang pada tempat penimbunan material buangan sulfida (waste dunp. Sistem pengendalian pencemaran air asam tambang meliputi pengolahan air asam tambang (water pond dan pengelolaan material sulfida (waste dump. Metode pengolahan air asam tambang adalah menetralisasi air asam dengan reagen alkali. Reagen alkali yang paling efektif dan ekonomis adalah batugamping (kalsium karbonat. Jumlah batugamping yang dibutuhkan untuk menetralkan air asam lambang pada water pond (5040 m3 sebesar 104,56 kg. Pengelolaan material buangan sulfida (waste dump adalah menerapkan model encapsulation in-pit disposal. Hal ini sangat efektif untuk mencegah terbentuknya air asam tambang. Material perlapisan yang digunakan adalah lempung (clay, karena mempunyai nilai permeabilitas yang sangat kecil yaitu sebesar 2,3148 x 10-9 m/det dan ketersediaannya mencukupi.   ABSTRACT Coal mining activity generally can generate negative impact to environment on mining location. One of the negative impact is contamination of acid mine drainage which able to destroy environment and ecosystem as water and soil. High potency source of acid mine drainage formed on coal mining location are water pond and waste dump. This aim of the research are control of acid mine drainage from water pond and prevention of acid mine drainage formed on the waste dump

  14. Basalt waste isolation project overview

    International Nuclear Information System (INIS)

    Dahlem, D.H.

    1987-01-01

    The proposed candidate site for a high-level nuclear waste repository is located beneath the Hanford Nuclear Reservation in southeastern Washington State. At this point, the Hanford Reservation has been selected as one of three preferred candidates in the draft environmental assessment. Project activities have concentrated on understanding the site location with respect to the 10CFR60, 40CFR191, and 10CFR960, identifying critical parameters for design of water package and repository seals, and identifying parameters for repository design. This paper describes the program to evaluate the site and to identify the natural processes that would effect isolation

  15. Infrastructure Task Force Tribal Solid Waste Management

    Science.gov (United States)

    These documents describe 1) issues to consider when planning and designing community engagement approaches for tribal integrated waste management programs and 2) a proposed approach to improve tribal open dumps data and solid waste projects, and 3) an MOU.

  16. Arsenic mineralogy and mobility in the arsenic-rich historical mine waste dump

    Czech Academy of Sciences Publication Activity Database

    Filippi, Michal; Drahota, P.; Machovič, V.; Böhmová, Vlasta; Mihaljevič, M.

    2015-01-01

    Roč. 536, 1 December (2015), s. 713-728 ISSN 0048-9697 R&D Projects: GA AV ČR KJB300130702 Institutional support: RVO:67985831 Keywords : arsenopyrite * pitticite * scorodite * sulfur * kaňkite * amorphous ferric arsenate (AFA) Subject RIV: DD - Geochemistry Impact factor: 3.976, year: 2015

  17. Operational waste volume projection. Revision 20

    International Nuclear Information System (INIS)

    Koreski, G.M.; Strode, J.N.

    1994-01-01

    Waste receipts to the double-shell tank system are analyzed and wastes through the year 2015 are projected based on generation trends of the past 12 months. A computer simulation of site operations is performed, which results in projections of tank fill schedules, tank transfers, evaporator operations, tank retrieval, and aging waste tank usage. This projection incorporates current budget planning and the clean-up schedule of the Tri-Party Agreement. Assumptions were current as of July 1994

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

    International Nuclear Information System (INIS)

    Randklev, E.H.

    1993-06-01

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

  19. Analysis of the potential impact of capillarity on long-term geochemical processes in sulphidic waste-rock dumps

    International Nuclear Information System (INIS)

    Pedretti, Daniele; Lassin, Arnault; Beckie, Roger D.

    2015-01-01

    Highlights: • Capillarity may affect geochemical reactions generating acid-rock drainage. • We studied its impact in a simplified, synthetic WRD. • Capillarity mainly affects the formation of secondary minerals. • It can strongly control long-term formation of gypsum and in turn sulfate release. • Capillarity can be also important for the analysis of calcite passivation. - Abstract: Assessing long-term production of acid rock drainage (ARD) from waste-rock dumps (WRDs) requires a careful analysis of the processes controlling acid-generating geochemical reactions under unsaturated conditions. In this work, we focus on the potential control of capillarity on these reactions, as previous studies showed that capillarity affects the activity of water and solutes in the unsaturated zone through the pore water pressure. We used capillarity-corrected thermodynamic databases and compared calculated speciation and solubility results with those from databases that do not account for capillarity. We developed a simple dynamic model with reduced geochemical components to analyze in detail the effect of capillarity. Results indicate that under low pH conditions simulations with capillarity-controlled reactions generate relatively larger dissolved sulfate concentrations from the WRDs over longer time scales, when compared against simulations without capillarity control. This occurs because capillarity strongly controls the formation of secondary sulfate-bearing minerals such as gypsum. When sufficient oxygen and carbon dioxide partial pressures are maintained within WRDs (such as in well-ventilated systems) and calcite content is insufficient to buffer acidity, the amount of secondary gypsum was calculated to be much larger in capillarity-corrected models. No appreciable effects of capillarity were observed under conditions where gypsum was not generated. Model results are also insensitive to temperature changes in typical climatic ranges. These results indicate some of

  20. Experimental study on the properties of drum-packed, cement solidified waste package of pre and after sea dumping test of sea depth 30m and 100m

    International Nuclear Information System (INIS)

    Maki, Yasuro; Abe, Hirotoshi; Hattori, Seiichi

    1976-01-01

    Japan Marine Science and Technology Center has been tackling with the development of the monitoring system to confirm the soundness of drum-packed, cement-solidified low level radioactive waste (the package) during falling and after reaching at sea bed when it is dumped into sea. The test was carried out at Sagami Bay of 30 m and 100 m sea depth using non-radioactive packages. The observation of the falling behaviour of packages in sea was carried out by taking photographs of the motion of packages with an underwater 16 mm movie camera and an underwater industrial TV (ITV), and the observation of the soundness and the area of packages scattered on sea bed was carried out with an underwater ITV and an underwater 70 mm snap camera which were set up on the frame. The proportion of cement-solidified waste was decided so that the uni-axial compressive strength of the cement-solidified waste satisfies the condition of ''The tentative guideline''. Prior to tests at sea, hydrostatic pressure test of packages are carried out on land. After that, core specimens were sampled to obtain the uniaxial compressive strength from packages and were tested. After sea dumping tests, 6 packages were recovered from sea bed, and the soundness were tested. As the results, the deformation and damage of drums and cement solidified waste packages did not occur at all. (Kako, I.)

  1. Calculation of projected waste loads for transuranic waste management alternatives

    International Nuclear Information System (INIS)

    Hong, K.; Kotek, T.; Koebnick, B.; Wang, Y.; Kaicher, C.

    1995-01-01

    The level of treatment and the treatment and interim storage site configurations (decentralized, regional, or centralized) impact transuranic (TRU) waste loads at and en route to sites in the US Department of Energy (DOE) complex. Other elements that impact waste loads are the volume and characteristics of the waste and the unit operation parameters of the technologies used to treat it. Projected annual complexwide TRU waste loads under various TRU waste management alternatives were calculated using the WASTEunderscoreMGMT computational model. WASTEunderscoreMGMT accepts as input three types of data: (1) the waste stream inventory volume, mass, and contaminant characteristics by generating site and waste stream category; (2) unit operation parameters of treatment technologies; and (3) waste management alternative definitions. Results indicate that the designed capacity of the Waste Isolation Pilot Plant, identified under all waste management alternatives as the permanent disposal facility for DOE-generated TRU waste, is sufficient for the projected complexwide TRU waste load under any of the alternatives

  2. Integrated waste hydrogen utilization project

    International Nuclear Information System (INIS)

    Armstrong, C.

    2004-01-01

    'Full text:' The BC Hydrogen Highway's, Integrated Waste Hydrogen Utilization Project (IWHUP) is a multi-faceted, synergistic collaboration that will capture waste hydrogen and promote its use through the demonstration of 'Hydrogen Economy' enabling technologies developed by Canadian companies. IWHUP involves capturing and purifying a small portion of the 600 kg/hr of by-product hydrogen vented to the atmosphere at the ERCO's electrochemical sodium chlorate plant in North Vancouver, BC. The captured hydrogen will then be compressed so it is suitable for transportation on roadways and can be used as a fuel in transportation and stationary fuel cell demonstrations. In summary, IWHUP invests in the following; Facilities to produce up to 20kg/hr of 99.999% pure 6250psig hydrogen using QuestAir's leading edge Pressure Swing Absorption technology; Ultra high-pressure transportable hydrogen storage systems developed by Dynetek Industries, Powertech Labs and Sacre-Davey Engineering; A Mobile Hydrogen Fuelling Station to create Instant Hydrogen Infrastructure for light-duty vehicles; Natural gas and hydrogen (H-CNG) blending and compression facilities by Clean Energy for fueling heavy-duty vehicles; Ten hydrogen, internal combustion engine (H-ICE), powered light duty pick-up vehicles and a specialized vehicle training, maintenance, and emissions monitoring program with BC Hydro, GVRD and the District of North Vancouver; The demonstration of Westport's H-CNG technology for heavy-duty vehicles in conjunction with local transit properties and a specialized vehicle training, maintenance, and emissions monitoring program; The demonstration of stationary fuel cell systems that will provide clean power for reducing peak-load power demands (peak shaving), grid independence and water heating; A comprehensive communications and outreach program designed to educate stakeholders, the public, regulatory bodies and emergency response teams in the local community, Supported by industry

  3. Huelva (phosphogypsum and Cs 137 wastes). Radiological controls on phosphogypsum storage lagoons and of the CRI-9 dump. Measurement of the external exposure. Soil, wastes and water radiological characterization

    International Nuclear Information System (INIS)

    2007-11-01

    This document reports radiological measurements and sampling performed in lagoons where phosphogypsum wastes coming from the Huelva industrial complex are stored. All samples (soils, sediments, solid wastes, waters) were analysed by high resolution gamma spectrometry. First, the authors analyse and report the impact of phosphogypsum storages through on-site gamma radiation measurements and through laboratory analyses. Then they report the assessment of the impact of a specific dump where caesium 137 contaminated wastes are present since an accident which occurred in the Acerinox factory. Some recommendations are given to solve the radioprotection problems created by these storages

  4. Phytoremediation of spoil coal dumps in Western Donbass (Ukraine)

    Science.gov (United States)

    Klimkina, Iryna; Kharytonov, Mykola; Wiche, Oliver; Heilmeier, Hermann

    2017-04-01

    At the moment, in Ukraine about 150 thousand hectares of fertile land are occupied by spoil dumps. Moreover, this figure increases every year. According to the technology used about 1500 m3 of adjacent stratum is dumped at the surface per every 1000 tons of coal mined. Apart from land amortization, waste dumps drastically change the natural landscape and pollute air, soil and water sources as the result of water and wind erosion, as well as self-ignition processes. A serious concern exists with respect to the Western Donbass coal mining region in Ukraine, where the coal extraction is made by the subsurface way and solid wastes are represented by both spoil dumps and wastes after coal processing. Sulphides, mostly pyrite (up to 4% of waste material), are widely distributed in the waste heaps freshly removed due to coal mining in Western Donbass.The oxidation of pyrite with the presence of oxygen and water is accompanied by a sharp drop in the pH from the surface layer to the spoil dumps(from 5.2-6.2 to 3.9-4.2 in soil substrates with chernozen and from 8.3-8.4 to 6.7-7.2 in soil substrates with red-brown clay, stabilizing in dump material in both cases at 2.9-3.2). Low pH generates the transformation of a number of toxic metals and other elementspresent in waste rock (e.g. Fe, Al, Mn, Zn, Mo, Co, As, Cd, Bi, Pb, U) into mobile forms. To stabilize and reduce metal mobility the most resistant plants that occur naturally in specified ecosystems can be used. On coal spoil dumpsin Western Donbas the dominant species are Bromopsis inermis, subdominant Artemisia austriaca; widespread are also Festucas pp., Lathyrus tuberosus, Inula sp., Calamagrostis epigeios, Lotus ucrainicus, and Vicias pp. Identification of plants tolerant to target metals is a key issue in phytotechnology for soil restoration. It is hypothesized that naturally occurring plants growing on coal spoil dumps can be candidates for phytostabilization, phytoextraction (phytoaccumulation) and phytomining

  5. Spent fuel and waste inventories and projections

    International Nuclear Information System (INIS)

    Carter, W.L.; Finney, B.C.; Alexander, C.W.; Blomeke, J.O.; McNair, J.M.

    1980-08-01

    Current inventories of commercial spent fuels and both commercial and US Department of Energy radioactive wastes were compiled, based on judgments of the most reliable information available from Government sources and the open literature. Future waste generation rates and quantities to be accumulated over the remainder of this century are also presented, based on a present projection of US commercial nuclear power growth and expected defense-related activities. Spent fuel projections are based on the current DOE/EIA estimate of nuclear growth, which projects 180 GW(e) in the year 2000. It is recognized that the calculated spent fuel discharges are probably high in view of recent reactor cancellations; hence adjustments will be made in future updates of this report. Wastes considered, on a chapter-by-chapter basis, are: spent fuel, high-level wastes, transuranic wastes, low-level wastes, mill tailings (active sites), and remedial action wastes. The latter category includes mill tailings (inactive sites), surplus facilities, formerly utilized sites, and the Grand Junction Project. For each category, waste volume inventories and projections are given through the year 2000. The land usage requirements are given for storage/disposal of low-level and transuranic wastes, and for present inventories of mill tailings

  6. APPLICATION OF PSEUDOMONAS PUTIDA AND RHODOCOCCUS SP. BY BIODEGRADATION OF PAH(S, PCB(S AND NEL SOIL SAMPLES FROM THE HAZARDOUS WASTE DUMP IN POZĎÁTKY (CZECH REPUBLIC

    Directory of Open Access Journals (Sweden)

    Radmila Kucerova

    2006-12-01

    Full Text Available The objective of the project was a laboratory check of biodegradation of soil samples contaminated by PAH(s, PCB(s and NEL from the hazardous waste dump in the Pozďátky locality. For the laboratory check, pure bacterial cultures of Rhodococcus sp. and Pseudomonas putida have been used. It is apparent from the laboratory experiments results that after one-month bacterial leaching, applying the bacterium of Rhodococcus sp. there is a 83 % removal of NEL, a 79 % removal of PAH(s and a 14 % removal of PCB(s. Applying a pure culture of Pseudomonas putida there is a 87 % removal of NEL, a 81 % removal of PAH(s and a 14 % removal of PCB(s.

  7. The oceanographic and radiological basis for the definition of high-level wastes unsuitable for dumping at sea

    International Nuclear Information System (INIS)

    1984-01-01

    The document has taken two of the models recommended in the Group of Experts on the Scientific Aspects of Marine Pollution (GESAMP) Report in 1983 and applied them to the purpose of setting dumping rate limits into an ocean basin. This guide details the assumptions underlying oceanographic model selection, analytic solutions to the models and the radiological basis used

  8. Waste Treatment & Immobilization Plant Project

    Data.gov (United States)

    Federal Laboratory Consortium — In southeastern Washington State, Bechtel National, Inc. is designing, constructing and commissioning the world's largest radioactive waste treatment plant for the...

  9. Studying microfungi-mineral interactions in sulphide-bearing waste-rock dumps: a 7 years survey in the Libiola mine, North-Eastern Italy

    Science.gov (United States)

    Marescotti, P.; Cecchi, G.; Di Piazza, S.; Lucchetti, G.; Zotti, M.

    2015-12-01

    Sulphide-bearing waste-rock dumps represent complex geological systems characterised by high percentages of low-grade mineralisations and non-valuable sulphides (such as pyrite and pyrrhotite). The sulphide oxidation triggers acid mine drainage (AMD) processes and the release of several metals of environmental concern. The severe physicochemical properties of these metal-contaminated environments tend to inhibit soil forming processes and represent an important stress factor for the biotic communities by exerting a strong selective pressure. Some macro- and micro-fungi are pioneer and extremophile organisms, which may survive and tolerate high concentrations of toxic metals in contaminated environments. Many studies show the fungal capability to bioaccumulate, biosorb, and store in their cells a high concentration of ecotoxic metals. A 7 years multidisciplinary survey was carried out in the Libiola sulphide mine. The results evidenced that the waste rock dumps of the area are characterized by an extremely poor flora and a specific mycobiota, due to the soil acidity, high concentration of trace metals, and unavailability or paucity of nutrients and organic matter. Our studies allowed the complete mineralogical, geochemical, and mycological characterization of one of the biggest dumps of the mine. 30 microfungal vital strains were isolated in pure cultures and studied with molecular and morphological approach, for their identification. The results allowed the isolation of some rare and important extremophilic species. Penicillium was the most recurrent genus, together with Trichoderma and Cladosporium. In particular, Penicillium glandicola is a rare species previously isolated from cave or arid environments, whereas P. brevicompactum is one of the most important fungi for metal corrosion. Hence, some bioaccumulation tests allowed to select a Trichoderma harzianum strain efficient to uptake Cu and Ag from pyrite-bearing soils, highlighting its central role in fungal

  10. Monitoring of Thermal and Gas Activities in Mining Dump Hedvika, Czech Republic

    Science.gov (United States)

    Surovka, D.; Pertile, E.; Dombek, V.; Vastyl, M.; Leher, V.

    2017-10-01

    The negative consequences of mining of the black coal is occurrence of extractive waste storage locations - mining dumps. The mining activities carried out within the area of Ostrava are responsible for at least six mine dumps of loose materials arising as wastes from mining of mineral resources, many of which show presence of thermal processes. The thermal activity in dumps is responsible for many hazardous substances that pollute the environment and harm human health in the surroundings. This paper deals with the results of the first phase of project CZ.11.4.120/0.0/0.0/15_006/0000074 TERDUMP, on exploration of thermally active mining dumps are published in the article. As a first studied thermally active dump was a Hedvika dump. To localize of hot spots with hot gas emission was used a thermovision scanning by drone. The place with high temperature (49.8 °C) identified natural gas emission through natural cracks. Analysing the occurring pollutants in Hedvika Dump using the GC-MS or HPLC, respectively and the inert gases (CO2, CO and SO2) were determined by ion chromatography. The pollutants were determined in five sampling points during two measurements executed from July to August 2017.

  11. Solid Waste Projection Model: Model user's guide

    International Nuclear Information System (INIS)

    Stiles, D.L.; Crow, V.L.

    1990-08-01

    The Solid Waste Projection Model (SWPM) system is an analytical tool developed by Pacific Northwest Laboratory (PNL) for Westinghouse Hanford company (WHC) specifically to address solid waste management issues at the Hanford Central Waste Complex (HCWC). This document, one of six documents supporting the SWPM system, contains a description of the system and instructions for preparing to use SWPM and operating Version 1 of the model. 4 figs., 1 tab

  12. Assessment of nonpoint source chemical loading potential to watersheds containing uranium waste dumps and human health hazards associated with uranium exploration and mining, Red, White, and Fry Canyons, southeastern Utah, 2007

    Science.gov (United States)

    Beisner, Kimberly R.; Marston, Thomas M.; Naftz, David L.; Snyder, Terry; Freeman, Michael L.

    2010-01-01

    During May, June, and July 2007, 58 solid-phase samples were collected from abandoned uranium mine waste dumps, background sites, and adjacent streambeds in Red, White, and Fry Canyons in southeastern Utah. The objectives of this sampling program were to (1) assess the nonpoint-source chemical loading potential to ephemeral and perennial drainage basins from uranium waste dumps and (2) assess potential effects on human health due to recreational activities on and around uranium waste dumps on Bureau of Land Management property. Uranium waste-dump samples were collected using solid-phase sampling protocols. After collection, solid-phase samples were homogenized and extracted in the laboratory using a leaching procedure. Filtered (0.45 micron) water samples were obtained from the field leaching procedure and were analyzed for major and trace elements at the Inductively Coupled Plasma-Mass Spectrometry Metals Analysis Laboratory at the University of Utah. A subset of the solid-phase samples also were digested with strong acids and analyzed for major ions and trace elements at the U.S. Geological Survey Geologic Division Laboratory in Denver, Colorado. For the initial ranking of chemical loading potential for uranium waste dumps, results of leachate analyses were compared with existing aquatic-life and drinking-water-quality standards. To assess potential effects on human health, solid-phase digestion values for uranium were compared to soil screening levels (SSL) computed using the computer model RESRAD 6.5 for a probable concentration of radium. One or more chemical constituents exceeded aquatic life and drinking-water-quality standards in approximately 64 percent (29/45) of the leachate samples extracted from uranium waste dumps. Most of the uranium waste dump sites with elevated trace-element concentrations in leachates were located in Red Canyon. Approximately 69 percent (31/45) of the strong acid digestible soil concentration values were greater than a calculated

  13. Ocean Dumping Control Regulations

    International Nuclear Information System (INIS)

    1978-01-01

    These Regulations were made further to the Ocean Dumping Control Act which provides for restrictions in dumping operations. The Regulations contain model applications for permits to dump or load a series of materials. (NEA)

  14. Integrated Data Base: Status and waste projections

    International Nuclear Information System (INIS)

    Klein, J.A.

    1990-01-01

    The Integrated Data Base (IDB) is the official US Department of Energy (DOE) data base for spent fuel and radioactive waste inventories and projections. DOE low-level waste (LLW) is just one of the many waste types that are documented with the IDB. Summary-level tables and figures are presented illustrating historical and projected volume changes of DOE LLW. This information is readily available through the annual IDB publication. Other presentation formats are also available to the DOE community through a request to the IDB Program. 4 refs., 6 figs., 5 tabs

  15. Joint Russian-Norwegian expedition to the dumping sites for radioactive waste and spent nuclear fuel in the Stepovogo fjord of the Kara sea, August - September 2012: investigations performed and main results

    Energy Technology Data Exchange (ETDEWEB)

    Nikitin, Aleksandr; Shershakov, Viacheslav; Valetova, Nailja; Petrenko, Galina; Katrich, Ivan; Fedorova, Anastasia [Research and Production Association ' Typhoon' , 249038, Obninsk, Kaluga Region (Russian Federation); Kazennov, Alexey [National Research Centre ' Kurchatov Institute' , Moscow (Russian Federation); Lind, Bjorn; Gwynn, Justin; Rudjord, Anne Liv [Norwegian Radiation Protection Authority, Oesteraas (Norway); Heldal, Hilde Elise [Institute of Marine Research, Bergen (Norway); Blinova, Oxana; Osvath, Iolanda; Levy, Isabelle; Bartocci, Jean; Khanh Pham, Mai; Sam, Adam; Nies, Hartmut [IAEA-MEL (Monaco); Grishin, Denis [Krylov State Research Centre, St. Petersburg (Russian Federation); Salbu, Brit; Ole- Christian, Lind; Teien, Hans-Cristian [Norwegian University of Life Sciences, Aas (Norway); Sidhu, Rajdeep Singh; Straalberg, Elisabeth [Institute for Energy Technology, Kjeller (Norway); Logoyda, Igor [State Scientific Centre ' Yuzhmorgeologiya' , Gelendzhik (Russian Federation)

    2014-07-01

    Stepovogo fjord, located on the Eastern coast of Novaya Zemlya, is one of the most important former Soviet Union dumping sites for radioactive waste in the Kara Sea. In addition to some 2000 dumped containers with conventional radioactive wastes, the nuclear submarine K-27 was dumped in Stepovogo fjord with two reactors loaded with spent nuclear fuel (SNF).Joint Russian and Norwegian surveys of the marine environment in Stepovogo fjord were first conducted in 1993 and 1994. In accordance with the working plan of the Joint Russian-Norwegian Expert Group on the Investigation of Radioactive Contamination in the Northern Areas, a follow up expedition into the radioecological status of Stepovogo fjord was carried out in August and September of 2012 onboard the R.V. 'Ivan Petrov' of the Roshydromet Northern Department. Investigations carried out in Stepovogo fjord during the expedition included: Sonar surveys, ROV inspections and in situ gamma measurements of the dumped nuclear submarine K-27 and dumped containers with radioactive waste Sampling of seawater, bottom sediments and marine biota. Results of the analysis of marine environmental samples performed by Russia, Norway and the IAEA, are presented and discussed in the paper. Preliminary measurements on surface sediments and water samples showed that the level of {sup 137}Cs contamination was generally low. However, slightly enhanced levels of {sup 137}Cs were detected in bottom seawater and sediment collected in the area with dumped containers. Measurements taken around the dumped nuclear submarine K-27 did not indicate any leakage of radioactive substances from the submarine. A similar picture for the level of radioactive contamination in Stepovogo fjord was observed in the first joint Russian-Norwegian expedition in 1993-94. (authors)

  16. Project safety studies - nuclear waste management (PSE)

    International Nuclear Information System (INIS)

    1981-10-01

    The project 'Safety Studies-Nuclear Waste Management' (PSE) is a research project performed by order of the Federal Minister for Research and Technology, the general purpose of which is to deepen and ensure the understanding of the safety aspects of the nuclear waste management and to prepare a risk analysis which will have to be established in the future. Owing to this the project is part of a series of projects which serve the further development of the concept of nuclear waste management and its safety, and which are set up in such a way as to accompany the realization of that concept. This report contains the results of the first stage of the project from 1978 to mid-1981. (orig./RW) [de

  17. One project`s waste is another project`s resource

    Energy Technology Data Exchange (ETDEWEB)

    Short, J.

    1997-02-01

    The author describes the efforts being made toward pollution prevention within the DOE complex, as a way to reduce overall project costs, in addition to decreasing the amount of waste to be handled. Pollution prevention is a concept which is trying to be ingrained into project planning. Part of the program involves the concept that ultimately the responsibility for waste comes back to the generator. Parts of the program involve efforts to reuse materials and equipment on new projects, to recycle wastes to generate offsetting revenue, and to increase awareness, accountability and incentives so as to stimulate action on this plan. Summaries of examples are presented in tables.

  18. The International Arctic Seas Assessment Project

    International Nuclear Information System (INIS)

    Linsley, G.S.; Sjoeblom, K.L.

    1994-01-01

    The International Arctic Seas Assessment Project (IASAP) was initiated in 1993 to address widespread concern over the possible health and environmental impacts associated with the radioactive waste dumped into the shallow waters of the Arctic Seas. This article discusses the project with these general topics: A brief history of dumping activities; the international control system; perspectives on arctic Seas dumping; the IASAP aims and implementation; the IASAP work plan and progress. 2 figs

  19. Some of the bases of the IAEA definition and recommendations concerning high-level radioactive waste unsuitable for dumping at sea and some of the Japanese findings of deep sea survey in the Pacific

    International Nuclear Information System (INIS)

    Nishiwaki, Y.

    1980-01-01

    The Provisional Definition and Recommendations Concerning Radioactive Wastes and Other Radioactive Matter referred to in Annexes I and II to the London Convention of 1972 on the Prevention of Marine Pollution by Dumping of Wastes and Other Matter have been reviewed and revised by the IAEA during 1975-1978. The Revised Definition and Recommendations and of the Annex thereto for the purposes of the Convention emphasize that the definition and recommendations set forth by the IAEA should not be interpreted as precluding the adoption of more restrictive requirements by any Party to the Convention or appropriate national authorities, and that nothing in the document shall be construed as encouraging the dumping at sea of radioactive waste or other radioactive matter. With these reservations, the Definition of High-Level Radioacive Wastes or Other High-Level Radioactive Matter Unsuitable for Dumping at Sea is given, distinguishing between α-emitters, β/γ-emitters with half-lives of at least 0.5 years and of unknown half-lives; and tritium and β/γ-emitters with half-lives of less than 0.5 years. Bases of the IAEA definition and recommendations concerning high level radioactive waste unsuitable for dumping at sea and reservations attached to the given concentration limits are discussed. (orig.) [de

  20. Waste diminution in Construction projects: Environmental Predicaments

    Science.gov (United States)

    Gharehbaghi, Koorosh; Scott-Young, Christina

    2018-03-01

    Waste diminution in construction projects is not only a behavioural issue, but also an energy consumption and reduction concern. With construction waste equating to the significant amount of exhausted energy together with increased pollution, this contributes to a series of environmental predicaments. The overall goal of construction solid Waste Management is to collect, treat and dispose of solid wastes generated by project activities in an environmentally and socially satisfactory manner, using the most economical means available. As cities expand, their construction activities and consumption patterns further drive up the solid waste quantities. Governments are usually authorized to have responsibility for providing solid Waste Management services, and various administrative laws give them exclusive ownership over the waste produced. In addition, construction waste processing can be further controlled and minimized according to specialized authorities such as Environmental Protection Agencies (EPA) and their relevant acts and regulations. Moreover, a Construction Environmental Management Plan (CEMP) can further control the treatment of waste and therefore, reduce the amount produced. Key elements of a CEMP not only include complying with relevant legislation, standards and guidance from the EPA; however, also to ensuring that there are systems in place to resolve any potential problems associated with site activities. Accordingly, as a part of energy consumption and lessening strategies, this paper will discuss various effective waste reduction methods for construction projects. Finally, this paper will also examine tactics to further improve energy efficiency through innovative construction Waste Management strategies (including desirability rating of most favourable options) to promote the lessening of overall CO2production.

  1. Solid waste

    International Nuclear Information System (INIS)

    1995-01-01

    The article drawn up within the framework of 'the assessment of the state of the environment in Lebanon' provides an overview of solid waste management, and assesses future wastes volume and waste disposal issues.In particular it addresses the following concerns: - Long term projections of solid waste arisings (i.e. domestic, industrial, such commercial wastes, vehicle types, construction waste, waste oils, hazardous toxic wastes and finally hospital and clinical wastes) are described. - Appropriate disposal routes, and strategies for reducing volumes for final disposal - Balance between municipal and industrial solid waste generation and disposal/treatment and - environmental impacts (aesthetics, human health, natural environment )of existing dumps, and the potential impact of government plans for construction of solid waste facilities). Possible policies for institutional reform within the waste management sector are proposed. Tables provides estimations of generation rates and distribution of wastes in different regions of Lebanon. Laws related to solid waste management are summarized

  2. Technical reclamations are wasting the conservation potential of post-mining sites. A case study of black coal spoil dumps

    Czech Academy of Sciences Publication Activity Database

    Tropek, Robert; Kadlec, Tomáš; Hejda, Martin; Kočárek, P.; Skuhrovec, J.; Malenovský, I.; Vodka, Štěpán; Spitzer, Lukáš; Baňař, P.; Konvička, Martin

    2012-01-01

    Roč. 43, JUN (2012), s. 13-18 ISSN 0925-8574. [International Symposium on Environmental Issues and Waste Management in Energy and Mineral Production (SWEMP) /12./. Prague, 24.05.2010-26.05.2010] R&D Projects: GA ČR GD206/08/H044; GA ČR GD206/08/H049; GA MŠk LC06073; GA ČR GAP504/12/2525; GA ČR(CZ) GAP505/11/1112 Grant - others:Ministerstvo kultury(CZ) MK 00009486201; Ministerstvo zemědělství(CZ) CZ0002700604 Institutional research plan: CEZ:AV0Z50070508; CEZ:AV0Z60050516 Keywords : biodiversity conservation * conservation legislation * landscape restoration Subject RIV: EH - Ecology, Behaviour Impact factor: 2.958, year: 2012 http://www.sciencedirect.com/science/article/pii/S0925857411003296

  3. Waste management project technical baseline description

    International Nuclear Information System (INIS)

    Sederburg, J.P.

    1997-01-01

    A systems engineering approach has been taken to describe the technical baseline under which the Waste Management Project is currently operating. The document contains a mission analysis, function analysis, requirement analysis, interface definitions, alternative analysis, system definition, documentation requirements, implementation definitions, and discussion of uncertainties facing the Project

  4. Accuracy of hazardous waste project estimates

    International Nuclear Information System (INIS)

    Hackney, J.W.

    1989-01-01

    The HAZRATE system has been developed to appraise the current state of definition of hazardous waste remedial projects. This is shown to have a high degree of correlation to the financial risk of such projects. The method employs a weighted checklist indicating the current degree of definition of some 150 significant project elements. It is based on the author's experience with a similar system for establishing the risk characteristics of process plant projects (Hackney, 1965 and 1989; 1985). In this paper definition ratings for 15 hazardous waste remedial projects have been correlated with the excesses of their actual costs over their base estimates, excluding any allowances for contingencies. Equations are presented, based on this study, for computation of the contingency allowance needed and estimate accuracy possible at a given stage of project development

  5. Technical program plan, Basalt Waste Isolation Project

    International Nuclear Information System (INIS)

    1979-12-01

    The Basalt Waste Isolation Project (BWIP) program as administered by the DOE's Richland Operations Office and Rockwell Hanford Operations is described. The objectives, scope and scientific technologies are discussed. The work breakdown structure of the project includes: project management and support, systems integration, geosciences, hydrology, engineered barriers, test facility design and construction, engineering testing, repository studies, and schedules. The budget of the program including operating and capital cost control is also included

  6. Radioecological aspects of at-sea dumping of nuclear wastes resulting from the FSU nuclear fleet activities: Reliability of packings and necessity of rehabilitation measures

    International Nuclear Information System (INIS)

    Lavkovsky, S.; Kvasha, N.; Kobzev, V.; Sadovnikov, V.; Goltsev, V.

    2002-01-01

    The practice of radioactive waste treatment in the former USSR was that prior to at-sea dumping of objects with spent nuclear fuel (SNF) a set of design and technological measures was undertaken with a view to form packings with additional barriers to prevent radionuclide release in the environment. Based upon the results of most conservative evaluations of the protective barrier corrosion resistance it was concluded, that till Year 2300 there will be no grounds to worry about a possibility of the loss of tightness of the majority of packings. However, should unfavourable external natural factors combine, the loss of sealing of the packing with the screening assembly of the nuclear icebreaker 'Lenin' can occur at any moment. (author)

  7. Geophysical exploration of historical mine dumps for the estimation of valuable residuals

    Science.gov (United States)

    Martin, Tina; Knieß, Rudolf; Noell, Ursula; Hupfer, Sarah; Kuhn, Kerstin; Günther, Thomas

    2015-04-01

    Within the project ROBEHA, funded by the German Federal Ministry of Education and Research (033R105) the economic potential of different abandoned dump sites for mine waste in the Harz Mountains was investigated. Two different mining dumps were geophysically and mineralogically analysed in order to characterize the mine dump structure and to estimate the volume of the potential recycling material. The geophysical methods comprised geoelectrics, radar, and spectral induced polarization (SIP). One about 100-year old mining dump containing residues from density separated Ag- and Sb-rich Pb (Zn)-gangue ores was investigated in detail. Like most small-scale mining waste disposal sites this investigated dump is very heterogeneously structured. Therefore, 27 geoelectrical profiles, more than 50 radar profiles, and several SIP profiles were measured and analysed. The results from the radar measurements, registered with the GSSI system and a shielded 200 MHz antenna, show the near surface boundary layer (down to 3-4 m beneath surface) of the waste residuals. These results can be used as pre-information for the inversion process of the geoelectrical data. The geoelectrical results reveal the mineral residues as layers with higher resistivities (> 300 Ohm*m) than the surrounding material. The SIP method found low phase signals (mine dump and other parameters we get a first estimate for the volume of the residues but the economical viability and the environmental impact of the reworking of the dump still needs to be evaluated in detail. The results of the second mine dump, an abandoned Cu and Zn-rich slag heap, show that the slag residues are characterized by higher resistivities and higher phases. A localization of the slag residues which are covered by organic material could be realized applying these geophysical methods.

  8. Project No. 4 - Waste incineration facility

    International Nuclear Information System (INIS)

    2000-01-01

    There are currently 12000 m 3 of combustible waste stored at the Ignalina NPP site. It is estimated that by 2005 the volume will have increase to 15000 m 3 (filters, personnel protection, clothing and plastics). As a part of the preparation for the closure of the Ignalina NPP an incineration facility will be required to process combustible wastes to reduce the overall volume of short-lived radioactive wastes stored at the Ignalina NPP site, thus reducing the overall risk to the environment. Project activities includes the design, construction and commissioning of the proposed facility, including all licensing documentation

  9. Projection of Big Cities Waste Management and Cost Based on Economic and Demographic Factors in Indonesia

    Science.gov (United States)

    Prajati, Gita; Padmi, Tri; Benno Rahardyan, dan

    2017-12-01

    Nowadays, solid waste management continues to be a major challenge in urban areas, especially in developing country. It is triggered by population growth, economic growth, industrialization and urbanization. Indonesia itselfs categorized into developing country. Indonesia's government has many program in order to increase the economic growth. One of them is MP3EI (Masterplan Percepatan dan Perluasan Pembangunan Ekonomi Indonesia. This program should be suppported by right waste management system. If Indonesia's waste management system can't afford the economic growth, it will trigger health and environmental problems. This study's purpose is to develop the socio-economic-environment model that can be used as a basis planning for the facility and cost of waste management systems. In this paper we used the development of Khajuria model test method. This method used six variables, which are GDP, population, population density, illiteracy, school's period and economic growth. The result showed that development of Khajuria test could explained the influence of economic and demographic factors to waste generation, 65.6%. The projection of waste generation shows that Pangkalpinang, Pekanbaru and Serang are the cities with the highest waste generation for the next five years. The number of dump truck and TPS in DKI Jakarata is the highest within another city, which is 39.37%. For the next five years, the waste management system in our study areas cost maximum 0.8% from GDP (Gross Domestic Products).

  10. Tank Waste Remediation System Projects Document Control Plan

    International Nuclear Information System (INIS)

    Slater, G.D.; Halverson, T.G.

    1994-01-01

    The purpose of this Tank Waste Remediation System Projects Document Control Plan is to provide requirements and responsibilities for document control for the Hanford Waste Vitrification Plant (HWVP) Project and the Initial Pretreatment Module (IPM) Project

  11. 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.

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

    International Nuclear Information System (INIS)

    Alfred Wickline

    2007-01-01

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

  13. Radiological assessment of the impact on human populations and the environment of the 1949 to 1982 dumping of low and intermediate level radioactive waste in the deep North-East Atlantic

    International Nuclear Information System (INIS)

    Chartier, M.; Menard, F.

    1990-12-01

    A thorough radiological assessment of the impact of the 1949 to 1982 dumping of low- and intermediate- level radioactive waste in the deep North-East Atlantic is performed with the numerical compartmental REJMAR model. The calculations include the assessment of the dose equivalent to the individuals of a theoretical critical group through a large set of pathways, and the collective dose to mankind through the ingestion pathways. The complete dumping performed in the deep North-East Atlantic is taken into account. The assumptions of biological short-circuit through marin food chains are tested. The order of magnitude of the dose delivered to marine organisms living near the dumping site is assessed [fr

  14. Site identification presentation: Basalt Waste Isolation Project

    International Nuclear Information System (INIS)

    1979-11-01

    The final step in the site identification process for the Basalt Waste Isolation Project is described. The candidate sites are identified. The site identification methodology is presented. The general objectives which must be met in selecting the final site are listed. Considerations used in the screening process are also listed. Summary tables of the guidelines used are included

  15. Corrective Action Decision Document for Corrective Action Unit 168: Area 25 and 26 Contaminated Materials and Waste Dumps, Nevada Test Site, Nevada, Rev. No.: 2 with Errata Sheet

    Energy Technology Data Exchange (ETDEWEB)

    Wickline, Alfred

    2006-12-01

    This Corrective Action Decision Document has been prepared for Corrective Action Unit (CAU) 168: Area 25 and 26, Contaminated Materials and Waste Dumps, Nevada Test Site, Nevada. The purpose of this Corrective Action Decision Document is to identify and provide a rationale for the selection of a recommended corrective action alternative for each corrective action site (CAS) within CAU 168. The corrective action investigation (CAI) was conducted in accordance with the ''Corrective Action Investigation Plan for Corrective Action Unit 168: Area 25 and 26, Contaminated Materials and Waste Dumps, Nevada Test Site, Nevada'', as developed under the ''Federal Facility Agreement and Consent Order'' (1996). Corrective Action Unit 168 is located in Areas 25 and 26 of the Nevada Test Site, Nevada and is comprised of the following 12 CASs: CAS 25-16-01, Construction Waste Pile; CAS 25-16-03, MX Construction Landfill; CAS 25-19-02, Waste Disposal Site; CAS 25-23-02, Radioactive Storage RR Cars; CAS 25-23-13, ETL - Lab Radioactive Contamination; CAS 25-23-18, Radioactive Material Storage; CAS 25-34-01, NRDS Contaminated Bunker; CAS 25-34-02, NRDS Contaminated Bunker; CAS 25-99-16, USW G3; CAS 26-08-01, Waste Dump/Burn Pit; CAS 26-17-01, Pluto Waste Holding Area; and CAS 26-19-02, Contaminated Waste Dump No.2. Analytes detected during the CAI were evaluated against preliminary action levels (PALs) to determine contaminants of concern (COCs) for CASs within CAU 168. Radiological measurements of railroad cars and test equipment were compared to unrestricted (free) release criteria. Assessment of the data generated from the CAI activities revealed the following: (1) Corrective Action Site 25-16-01 contains hydrocarbon-contaminated soil at concentrations exceeding the PAL. The contamination is at discrete locations associated with asphalt debris. (2) No COCs were identified at CAS 25-16-03. Buried construction waste is present in at least two

  16. Nuclear fuel cycle and marine environment. Behavior of the Rhone river effluents in the mediterranean sea and of wastes dumped in the northeast atlantic

    International Nuclear Information System (INIS)

    Charmasson, S.

    1998-01-01

    Man-made radionuclides released into the marine environment by the installations from the nuclear fuel cycle are used as tracers of various bio-geochemical processes. Several installations belonging to the whole nuclear fuel cycle, except the uranium mining, are set up on the Rhone River Banks. The sea disposal of low and intermediate level radioactive waste has never been authorized in the Mediterranean sea but several sites have been used in the North-East especially in abyssal waters. Radionuclides released by the Rhone river installations are used in order to study the dynamics of the Rhone inputs into the Mediterranean Sea. In the river, freshwater samples reflect quite accurately the discharge composition with a predominance of 106 Ru, a radionuclide mostly released by the spent nuclear fuel reprocessing plant in Marcoule. Conversely, at the Rhone mouth, in the sediment compartment 106 Ru yields to caesium isotopes ( 134 Cs and 137 Cs) in importance. As these two isotopes demonstrate very different half-lives (30,2 and 2,1 years respectively), the temporal evolution of their ratio acts as a chronometer enabled to date sediment accumulation near the river mouth. Mean accumulation rates greater than 35 cm y -1 have been determined in the pro-deltaic zone near the Roustan buoys over the period 1983-1991. Accumulation rates decrease rapidly with distance from the mouth and therefore most of the 137 Cs inventory in this part of the Gulf of Lions is limited to the pro-deltaic area. A first study about the part the different 137 Cs sources in the Mediterranean Sea play in this inventory has been carried out. Direct (atmospheric) and indirect (fluviatile) inputs due to fallout from both past nuclear tests and the Chernobyl accident could contribute to this inventory at the highest to 40 % while the industrial releases could contribute at the lowest to 60 %. The last site used for the dumping of low and intermediate level radioactive waste in the North-East Atlantic

  17. Preliminary Study of the Pozzolanic Activity of Dumped Mine Wastes Obtained from the North Bohemian Basin in the Czech Republic

    Directory of Open Access Journals (Sweden)

    Konstantinos SOTIRIADIS

    2017-02-01

    Full Text Available Three dumped raw materials, a tuff and two bentonites, obtained from two mining sites at the North Bohemian basin in the Czech Republic, have been studied in order to evaluate them as pozzolanic admixtures in lime mortars for employment in restoration of cultural heritage objects. After thermal activation (800 °C; 5 h, their pozzolanic properties were compared with those of commercial metakaolin. Quantitative phase analysis with the Rietveld method from X-ray powder diffraction patterns, morphological observations, as well as the Frattini and the modified Chapelle tests were performed. In addition, lime mortars, incorporating the fired materials, were prepared and subjected to simultaneous thermal analysis after a 28-day initial curing (20 ± 1 °C; 60 ± 5 % RH. The results showed that all three materials possess pozzolanic activity. However, when employed in lime mortars they did not result in formation of pozzolanic reaction products. Two methods were proposed to improve their reactivity; grinding to obtain finer particle size and removal of quartz content where necessary.DOI: http://dx.doi.org/10.5755/j01.ms.23.1.14864

  18. FY-1981 project status for the Transuranic Waste Treatment Facility

    International Nuclear Information System (INIS)

    Benedetti, R.L.; Tait, T.D.

    1981-11-01

    The primary objective of the Transuranic Waste Treatment Facility (TWTF) Project is to provide a facility to process low-level transuranic waste stored at the Idaho National Engineering Laboratory (INEL) into a form acceptable for disposal at the Waste Isolation Pilot Plant. This report provides brief summary descriptions of the project objectives and background, project status through FY-1981, planned activities for FY-1982, and the EG and G TWTF Project office position on processing INEL transuranic waste

  19. Hanford Waste Vitrification Project overview and status

    International Nuclear Information System (INIS)

    Swenson, L.D.; Smets, J.L.

    1993-01-01

    The Hanford Waste Vitrification Project (HWVP) is being constructed at the US DOE's Hanford Site in Richland, WA. Engineering and design are being accomplished by Fluor Daniel Inc. in Irvine, CA. Technical input is furnished by Westinghouse Hanford Co. and construction management services by UE ampersand C-Catalytic Inc. The HWVP will immobilize high level nuclear waste in a glass matrix for eventual disposal in the federal repository. The HWVP consists of several structures, the major ones being the Vitrification Building, the Canister Storage Building, fan house, sand filter, waste hold tank, pump house, and administration and construction facilities. Construction started in April 1992 with the clearing and grubbing activities that prepared the site for fencing and construction preparation. Several design packages have been released for procurement activities. The most significant package release is for the Canister Storage Building, which will be the first major structure to be constructed

  20. Corrective Action Decision Document for Corrective Action Unit 140: Waste Dumps, Burn Pits, and Storage Area, Nevada Test Site, Nevada, Revision 1 with ROTC 1

    International Nuclear Information System (INIS)

    Boehlecke, Robert

    2004-01-01

    This Corrective Action Decision Document (CADD) has been prepared for Corrective Action Unit (CAU) 140: Waste Dumps, Burn Pits, and Storage Area, Nevada Test Site (NTS), Nevada, in accordance with the ''Federal Facility Agreement and Consent Order'' (1996). Corrective Action Unit 140 is located within Areas 5, 22, and 23 of the NTS and is comprised of the following corrective action sites (CASs): 05-08-01, Detonation Pits; 05-08-02, Debris Pits; 05-17-01, Hazardous Waste Accumulation Site (Buried); 05-19-01, Waste Disposal Site; 05-23-01, Gravel Gertie; 05-35-01, Burn Pit; 05-99-04, Burn Pit; 22-99-04, Radioactive Waste Dump; and 23-17-01, Hazardous Waste Storage Area. The purpose of this CADD is to identify and provide a rationale for the recommendation of a corrective action alternative for each CAS within CAU 140. Corrective action investigation activities were performed from November 13 through December 11, 2002. Additional sampling to delineate the extent of contaminants of concern (COCs) was conducted on February 4 and March 18 and 19, 2003. Corrective action investigation activities were performed as set forth in the Corrective Action Investigation Plan for CAU 140. Analytes detected during the corrective action investigation were evaluated against appropriate preliminary action levels to identify COCs for each CAS. Assessment of the data generated from investigation activities revealed the following: (1) CAS 05-08-01 contains the COCs lead and the radioisotope thorium-234 in the surface soil at sample location A05. (2) CAS 05-23-01 did not have any COCs identified during the field investigation; however, based on historical knowledge of activities at this site, the interior of the Gravel Gertie is considered contaminated with uranium. (3) CAS 23-17-01 contains the COC total petroleum hydrocarbons (diesel-range organics) at location J20 at a depth of 9 to 10 feet below ground surface. (4) No COCs were identified at CASs 05-08-02, 05-17-01, 05-19-01, 05

  1. Tank waste remediation system characterization project quality policies. Revision 1

    International Nuclear Information System (INIS)

    Trimble, D.J.

    1995-01-01

    These Quality Policies (QPs) describe the Quality Management System of the Tank Waste Characterization Project (hereafter referred to as the Characterization Project), Tank Waste Remediation System (TWRS), Westinghouse Hanford Company (WHC). The Quality Policies and quality requirements described herein are binding on all Characterization Project organizations. To achieve quality, the Characterization Project management team shall implement this Characterization Project Quality Management System

  2. Financing Waste to Wealth Project-Malaysian Experience

    International Nuclear Information System (INIS)

    Abdul Nasir Adnan

    2010-01-01

    In Malaysia, waste were coming from industrial waste, residential waste and others. So, all of these wastes were dumped into landfill and some was treated back for several purposes. All these efforts will need more money to make sure it proceeds. So, this presentation focused on how we can generate back our money from these waste. According to statistics, more than 95 % waste will go to landfills and only 5 % was recycled. 47 % were organic waste, 15 % paper, 14 % plastics, 4 % metal and only 3 % were glass or ceramics with 291 open dumpsites all over the country. So, with the establishment of RRC/ RDF-WTE, all of these wastes were managed systematically. The establishment of waste RDF plants to generate electricity also can give opportunities to government as alternative ways from depending on fossil fuel plants. Although there are several challenges such as market failure, absence of legal framework, lack of institutional measures and others, these will not break the spirit to make sure that someday all of these efforts will meet their targets.

  3. Corrective Action Plan for Corrective Action Unit 168: Area 25 and 26 Contaminated Materials and Waste Dumps, Nevada Test Site, Nevada, REV 1

    International Nuclear Information System (INIS)

    NSTec Environmental Restoration

    2007-01-01

    Corrective Action Unit (CAU) 168 is identified in the Federal Facility Agreement and Consent Order of 1996 as Area 25 and 26 Contaminated Materials and Waste Dumps. CAU 168 consists of twelve Corrective Action Sites (CASs) in Areas 25 and 26 of the Nevada Test Site, which is approximately 105 kilometers (65 miles) northwest of Las Vegas, Nevada. The CASs contain surface and subsurface debris, impacted soil, and contaminated materials. Site characterization activities were conducted in 2002, and the results are presented in the Corrective Action Decision Document (CADD) for CAU 168 (U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office [NNSA/NSO], 2006). Site characterization results indicated that soil at several sites exceeded the clean-up criteria for total petroleum hydrocarbons (TPH), polychlorinated biphenyls (PCBs), and radionuclides. The Nevada Division of Environmental Protection approved the proposed corrective actions specified in the CADD (NNSA/NSO, 2006). The approved corrective actions include no further action, clean closure, and closure in place with administrative controls

  4. Specifications for dumping of residues from mechanical-biological waste treament facilities; Anforderungen an die Ablagerung von MBA-Abfaellen

    Energy Technology Data Exchange (ETDEWEB)

    Bockreis, A.; Steinberg, I.; Jager, J. [Fachgebiet Afalltechnik, Institut WAR, TU Darmstadt (Germany)

    2001-07-01

    For purposes of assessing the dumpability of wastes, Article 1 - Ordinance on the Environmentally Responsible Landfilling of Household Wastes (AbfAblV) - of the Ordinance on the Environmentally Responsible Landfilling of Household Wastes and Biological Waste Treatment Plants defines classificaton criteria for biologically and mechanically treated wastes destined for landfilling. The practical experiences that have been gathered with these classification criteria and values were evaluated in a questionnaire-based survey. This was done in particular for the purpose of verifying and validating proposals on the methodology of respiration and fermentation tests. A general finding has been that the application and implementation of the regulations of the AbfAblV is fraught with difficulties. This is evident for one thing in the frequency of analyses and for another in the difficulty of complying with the limit values of the classification criteria. The authors are in support of demands that the methodological specifications for AT{sub 4} and GB21 and their classification values in connection with those for TOC both in the solid phase and in the eluate and with the calorific values H{sub o} must be thoroughly reassessed and revised after further practical experiences have been gathered. [German] Zur Beurteilung der Ablagerbarkeit wurden Zuordnungskriterien fuer mechanisch-biologisch behandelte Abfaelle zur Ablagerung im Artikel 1 - Verordnung ueber die umweltvertraegliche Ablagerung von Siedlungsabfaellen (Abfallablagerungsverordnung - AbfAblV) - der Verordnung ueber die umweltvertraegliche Ablagerung von Siedlungsabfaellen und ueber biologische Abfallbehandlungsanlagen definiert. Im Rahmen einer Fragebogenaktion wurde ausgewertet, welche Erfahrungen in der Praxis mit den Zuordnungskriterien und -werten gesammelt wurden, um insbesondere die Methodenvorschlaege zur Durchfuehrung des Atmungs- bzw. Gaertests fuer feste Abfallstoffe verifizieren und validieren zu koennen

  5. Solid Waste Projection Model: Database User's Guide

    International Nuclear Information System (INIS)

    Blackburn, C.L.

    1993-10-01

    The Solid Waste Projection Model (SWPM) system is an analytical tool developed by Pacific Northwest Laboratory (PNL) for Westinghouse Hanford Company (WHC) specifically to address Hanford solid waste management issues. This document is one of a set of documents supporting the SWPM system and providing instructions in the use and maintenance of SWPM components. This manual contains instructions for using Version 1.4 of the SWPM database: system requirements and preparation, entering and maintaining data, and performing routine database functions. This document supports only those operations which are specific to SWPM database menus and functions and does not Provide instruction in the use of Paradox, the database management system in which the SWPM database is established

  6. HISPANIC ENVIRONMENTAL AND WASTE MANAGEMENT OUTREACH PROJECT

    Energy Technology Data Exchange (ETDEWEB)

    Sebastian Puente

    1998-07-25

    The Department of Energy Office of Environmental Management (DOE-EM) in cooperation with the Self Reliance Foundation (SRF) is conducting the Hispanic Environmental and Waste Management Outreach Project (HEWMO) to increase science and environmental literacy, specifically that related to nuclear engineering and waste management in the nuclear industry, among the US Hispanic population. The project will encourage Hispanic youth and young adults to pursue careers through the regular presentation of Spanish-speaking scientists and engineers and other role models, as well as career information on nationally broadcast radio programs reaching youth and parents. This project will encourage making science, mathematics, and technology a conscious part of the everyday life experiences of Hispanic youth and families. The SRF in collaboration with the Hispanic Radio Network (HRN) produces and broadcasts radio programs to address the topics and meet the objectives as outlined in the Environmental Literacy Plan and DOE-EM Communications Plan in this document. The SRF has in place a toll-free ''800'' number Information and Resource Referral (I and RR) service that national radio program listeners can call to obtain information and resource referrals as well as give their reactions to the radio programs that will air. HRN uses this feature to put listeners in touch with local organizations and resources that can provide them with further information and assistance on the related program topics.

  7. HISPANIC ENVIRONMENTAL AND WASTE MANAGEMENT OUTREACH PROJECT

    International Nuclear Information System (INIS)

    Sebastian Puente

    1998-01-01

    The Department of Energy Office of Environmental Management (DOE-EM) in cooperation with the Self Reliance Foundation (SRF) is conducting the Hispanic Environmental and Waste Management Outreach Project (HEWMO) to increase science and environmental literacy, specifically that related to nuclear engineering and waste management in the nuclear industry, among the US Hispanic population. The project will encourage Hispanic youth and young adults to pursue careers through the regular presentation of Spanish-speaking scientists and engineers and other role models, as well as career information on nationally broadcast radio programs reaching youth and parents. This project will encourage making science, mathematics, and technology a conscious part of the everyday life experiences of Hispanic youth and families. The SRF in collaboration with the Hispanic Radio Network (HRN) produces and broadcasts radio programs to address the topics and meet the objectives as outlined in the Environmental Literacy Plan and DOE-EM Communications Plan in this document. The SRF has in place a toll-free ''800'' number Information and Resource Referral (I and RR) service that national radio program listeners can call to obtain information and resource referrals as well as give their reactions to the radio programs that will air. HRN uses this feature to put listeners in touch with local organizations and resources that can provide them with further information and assistance on the related program topics

  8. Radioactive dumping in the Arctic Ocean

    International Nuclear Information System (INIS)

    Lamb, J.; Gizewski, P.

    1993-01-01

    Recent revelations concerning the possible environmental hazards posed by the sunken Soviet nuclear submarine Komsomolets and the disposal of radioactive materials in the Arctic and North Atlantic oceans have generated much controversy and debate. Too often, however, the key scientific and policy issues that the dumping raises are treated as two solitudes. In reality, decisions taken by national governments and international agencies in connection with remediation, regulation, and even research must be based on both science and policy. Indeed, a sound approach to the dumping issue must integrate scientific evidence and policy considerations relating to legal, political, social, and economic matters. Radioactive waste disposal is an exceedingly difficult problem. Information detailing the Soviet Navy's past dumping practices, and increasing awareness of the problems that Russia and other states may encounter in the future disposal of radioactive waste, indicate that the global inventory of radioactive wastes requiring storage and disposal is large and growing

  9. Trace element geochemistry of self-burning and weathering of a mineralized coal waste dump: The Novátor mine, Czech Republic

    Czech Academy of Sciences Publication Activity Database

    Kříbek, B.; Sýkorová, Ivana; Veselovský, F.; Laufek, F.; Malec, J.; Knésl, I.; Majer, V.

    2017-01-01

    Roč. 173, MAR 15 (2017), s. 158-175 ISSN 0166-5162 R&D Projects: GA ČR(CZ) GA15-11674S Institutional support: RVO:67985891 Keywords : coal wastes * organic matter * uranium * mineralization * self-heating * biomarkers Subject RIV: DD - Geochemistry OBOR OECD: Geology Impact factor: 4.783, year: 2016

  10. The international arctic seas assessment project: Progress report

    International Nuclear Information System (INIS)

    Sjoeblom, K.L.; Linsley, G.S.

    1995-01-01

    The article provides some background information on wastes dumped into the Arctic Seas and describes the progress made within the framework of International Arctic Seas Assessment Project (IASAP) lunched to assess the health and environmental implications of the dumping. 1 tab

  11. Catalytic hydrotreatment of refinery waste: Demonstration project

    Energy Technology Data Exchange (ETDEWEB)

    1989-01-01

    The object of this project and report is to produce liquid hydrocarbons by the catalytic hydroprocessing of solid refinery wastes (hard pitches) in order to improve the profitability of deep conversion processes and reduce the excess production of heavy fuels. The project was mostly carried out on the ASVAHL demonstration platform site, at Solaize, and hard pitches were produced primarily by deasphalting of atmospheric or vacuum distillation residues. The project includes two experimental phases and an economic evaluation study phase. In Phase 1, two granular catalysts were used to transform pitch into standard low sulfur fuel oil: a continuously moving bed, with demetallation and conversion catalyst; a fixed bed, with hydrorefining catalyst. In Phase 2 of the project, it was proven that a hydrotreatment process using a finely dispersed catalyst in the feedstock, can, under realistic operating conditions, transform with good yields hard pitch into distillates that can be refined through standard methods. In Phase 3 of the project, it was shown that the economics of such processes are tightly linked to the price differential between white'' and black'' oil products, which is expected to increase in the future. Furthermore, the evolution of environmental constraints will impel the use of such methods, thus avoiding the coproduction of polluting solid residues. 11 figs., 1 tab.

  12. Waste-isolation projects, FY 1978

    International Nuclear Information System (INIS)

    Ramspott, L.D.

    1979-01-01

    This report describes Lawrence Livermore Laboratory (LLL) activities during FY 1978 in support of the National Waste Terminal Storage Program. Current projects at LLL fall into three categories: (1) field testing, (2) laboratory rock mechanics measurements, and (3) laboratory studies of sorption and leaching. Field test activities conducted in the Climax granite at the Nevada Test Site included electrical heater tests, preparation for a spent-fuel-storage test, and planning for a series of rock mechanics tests. The heater tests determined the in situ thermal properties of Climax granite and its in situ permeability as a function of rock temperature. The two main laboratory rock mechanics projects involved (1) measurement of the permeability, electrical conductivity, and acoustic velocity of 15-cm-diam cores of granitic rocks over a range of confining pressure, pore (water) pressure, and deviatoric stress, and (2) measurement of rock thermal properties as a function of temperature and confining pressure in the presence of pore fluids to 770 0 K and 200 Mpa. The leaching studies made use of an LLL-designed, single-pass leaching apparatus with three solutions, two leach temperatures, and three flow rates. The material evaluated was Np--Pu-doped simulated waste glass from Battelle Pacific Northwest Laboratories. The sorption studies involved standard static measurements of the equilibrium distribution coefficient (K/sub d/) for various radionuclides on a variety of rocks, and flow-through-core studies of dynamic sorption

  13. Remediation measures at the former hazardous waste dump at Malsch near Heidelberg; Sanierung der ehemaligen Sonderabfalldeponie Malsch. Hydrogeologische Bewertung

    Energy Technology Data Exchange (ETDEWEB)

    Hanstein, P.; Hoetzl, H. [Karlsruhe Univ. (T.H.) (Germany). Lehrstuhl fuer Angewandte Geologie

    1998-12-31

    The former hazardous waste deposit of Malsch is located south of Heidelberg at the eastern margin of the Upper Rhine Graben. Using a former clay pit about 700.000 m{sup 3} of partly high toxic organic and inorganic wastes were deposited from 1971 to 1984. A leakage from the deposit was first recognised in 1984. Detailed investigation showed that thin channel-like conglomerate layers intercalated in the clays and marls as well as faults are cropping out into the base of the deposit and cause a direct seepage of leachate. Contaminants pollute the downstream area over a distance of 500 m. Remediation measures adding up to 100 Mio. DM were carried out including the construction of a slurry wall encircling laterally the whole site, a surface cover with a multi-liner system as well as a pump and treat system for the leachate was installed and are now in operation. Model studies of the ground water flow including a 3-dimensional site model and a 2-dimensional regional model started during the remediation work. According to the complex geological situation specific procedures was applied to transform the heterogeneous tectonical structure into the numerical models. The balance of water flowing through the deposit was calculated by the piezometric heads to assess different remediation stages. In spite of the missing impervious base the calculation could prove that in connection of a certain pumping rate of the leachate the environment and especially the groundwater can be protected from further leakage. (orig.) [Deutsch] Die fruehere Sonderabfalldeponie Malsch wurde 1971 in einer stillgelegten Tongrube suedlich von Heidelberg am oestlichen Rand des Oberrheingrabens angelegt und bis 1984 betrieben. Insgesamt wurden ueber 700.000 m{sup 3} zum Teil hochtoxische organische und anorganische Sonderabfaelle abgelagert. Mit Abschluss der Deponierungsphase wurden Sickerwasseraustritte im westlichen Deponievorfeld festgelstellt. Ursache fuer die Undichtigkeiten waren geringmaechtige

  14. Corrective Action Decision Document for Corrective Action Unit 140: Waste Dumps, Burn Pits, and Storage Area, Nevada Test Site, Nevada: Revision No. 0

    Energy Technology Data Exchange (ETDEWEB)

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

    2003-10-17

    This Corrective Action Decision Document identifies and rationalizes the U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office's selection of a recommended corrective action alternative appropriate to facilitate the closure of Corrective Action Unit (CAU) 140: Waste Dumps, Burn Pits, and Storage Area, Nevada Test Site (NTS), Nevada, under the Federal Facility Agreement and Consent Order. Located in Areas 5, 22, and 23 of the NTS, CAU 140 consists of nine corrective action sites (CASs). Investigation activities were performed from November 13 through December 11, 2002, with additional sampling to delineate the extent of contaminants of concern (COCs) conducted on February 4 and March 18 and 19, 2003. Results obtained from the investigation activities and sampling indicated that only 3 of the 9 CASs at CAU 140 had COCs identified. Following a review of existing data, future land use, and current operations at the NTS, the following preferred alternatives were developed for consideration: (1) No Further Action - six CASs (05-08-02, 05-17-01, 05-19-01, 05-35-01, 05-99-04, and 22-99-04); (2) Clean Closure - one CAS (05-08-01), and (3) Closure-in-Place - two CASs (05-23-01 and 23-17-01). These alternatives were judged to meet all requirements for the technical components evaluated. Additionally, the alternatives meet all applicable state and federal regulations for closure of the site and will eliminate potential future exposure pathways to the contaminated media at CAU 140.

  15. The Los Alamos National Laboratory Transuranic Waste Retireval Project

    International Nuclear Information System (INIS)

    Montoya, G.M.; Christensen, D.V.; Stanford, A.R.

    1997-01-01

    This paper presents the status of the Los Alamos National Laboratory (LANL) project for remediation of transuranic (TRU) and TRU mixed waste from Pads 1, 2, and 4. Some of the TRU waste packages retrieved from Pad I are anticipated to be part of LANL's initial inventory to be shipped to the Waste Isolation Pilot Plant (WIPP) in April 1998. The TRU Waste Inspectable Storage Project (TWISP) was initiated in February 1993 in response to the New Mexico Environment Department's (NMED's) Consent Agreement for Compliance Order, ''New Mexico Hazardous Waste Agreement (NMHWA) 93-03.'' The TWISP involves the recovery of approximately 16,865 TRU and TRU-mixed waste containers currently under earthen cover on Pads 1, 2, and 4 at Technical Area 54, Area G, and placement of that waste into inspectable storage. All waste will be moved into inspectable storage by September 30, 2003. Waste recovery and storage operations emphasize protection of worker safety, public health, and the environment

  16. Conceptual Model for Systematic Construction Waste Management

    OpenAIRE

    Abd Rahim Mohd Hilmi Izwan; Kasim Narimah

    2017-01-01

    Development of the construction industry generated construction waste which can contribute towards environmental issues. Weaknesses of compliance in construction waste management especially in construction site have also contributed to the big issues of waste generated in landfills and illegal dumping area. This gives sign that construction projects are needed a systematic construction waste management. To date, a comprehensive criteria of construction waste management, particularly for const...

  17. Final Hanford Site Transuranic (TRU) Waste Characterization QA Project Plan

    International Nuclear Information System (INIS)

    GREAGER, T.M.

    2000-01-01

    The Quality Assurance Project Plan (QAPjP) has been prepared for waste characterization activities to be conducted by the Transuranic (TRU) Project at the Hanford Site to meet requirements set forth in the Waste Isolation Pilot Plan (WIPP) Hazardous Waste Facility Permit, 4890139088-TSDF, Attachment B, including Attachments B1 through B6 (WAP) (DOE, 1999a). The QAPjP describes the waste characterization requirements and includes test methods, details of planned waste sampling and analysis, and a description of the waste characterization and verification process. In addition, the QAPjP includes a description of the quality assurance/quality control (QA/QC) requirements for the waste characterization program. Before TRU waste is shipped to the WIPP site by the TRU Project, all applicable requirements of the QAPjP shall be implemented. Additional requirements necessary for transportation to waste disposal at WIPP can be found in the ''Quality Assurance Program Document'' (DOE 1999b) and HNF-2600, ''Hanford Site Transuranic Waste Certification Plan.'' TRU mixed waste contains both TRU radioactive and hazardous components, as defined in the WLPP-WAP. The waste is designated and separately packaged as either contact-handled (CH) or remote-handled (RH), based on the radiological dose rate at the surface of the waste container. RH TRU wastes are not currently shipped to the WIPP facility

  18. Perspectives on past and Present Waste Disposal Practices: A community-Based Participatory Research Project in Three Saskatchewan First Nations Communities

    Directory of Open Access Journals (Sweden)

    Rebecca Zagozewski

    2011-01-01

    Full Text Available The impact of current and historical waste disposal practices on the environment and human health of Indigenous people in First Nations communities has yet to be adequately addressed. Solid waste disposal has been identified as a major environmental threat to First Nations Communities. A community-based participatory research project (CBPR was initiated by the Saskatoon Tribal Council Health and Family Services Incorporated to investigate concerns related to waste disposal in three Saskatchewan First Nations Communities. Utilizing a qualitative approach, we aimed to gain an understanding of past and present waste disposal practices and to identify any human and environmental health concerns related to these practices. One to one interviews and sharing circles were conducted with Elders. Elders were asked to share their perspectives on past and present waste disposal practices and to comment on the possible impacts these practices may have on the environment and community health. Historically waste disposal practices were similar among communities. The homeowner generated small volumes of waste, was exclusively responsible for disposal and utilized a backyard pit. Overtime waste disposal evolved to weekly pick-up of un-segregated garbage with waste disposal and open trash burning in a community dump site. Dump site locations and open trash burning were identified as significant health issues related to waste disposal practices in these communities. This research raises issues of inequity in the management of waste in First Nations Communities. It highlights the need for long-term sustainable funding to support community-based waste disposal and management strategies and the development of First Nations centered and delivered educational programs to encourage the adoption and implementation of waste reduction, reutilization and recycling activities in these communities.

  19. Perspectives on past and present waste disposal practices: a community-based participatory research project in three Saskatchewan first nations communities.

    Science.gov (United States)

    Zagozewski, Rebecca; Judd-Henrey, Ian; Nilson, Suzie; Bharadwaj, Lalita

    2011-04-28

    The impact of current and historical waste disposal practices on the environment and human health of Indigenous people in First Nations communities has yet to be adequately addressed. Solid waste disposal has been identified as a major environmental threat to First Nations Communities. A community-based participatory research project (CBPR) was initiated by the Saskatoon Tribal Council Health and Family Services Incorporated to investigate concerns related to waste disposal in three Saskatchewan First Nations Communities. Utilizing a qualitative approach, we aimed to gain an understanding of past and present waste disposal practices and to identify any human and environmental health concerns related to these practices. One to one interviews and sharing circles were conducted with Elders. Elders were asked to share their perspectives on past and present waste disposal practices and to comment on the possible impacts these practices may have on the environment and community health. Historically waste disposal practices were similar among communities. The homeowner generated small volumes of waste, was exclusively responsible for disposal and utilized a backyard pit. Overtime waste disposal evolved to weekly pick-up of un-segregated garbage with waste disposal and open trash burning in a community dump site. Dump site locations and open trash burning were identified as significant health issues related to waste disposal practices in these communities. This research raises issues of inequity in the management of waste in First Nations Communities. It highlights the need for long-term sustainable funding to support community-based waste disposal and management strategies and the development of First Nations centered and delivered educational programs to encourage the adoption and implementation of waste reduction, reutilization and recycling activities in these communities.

  20. Management of the solid waste in perforation projects exploratory hydrocarbons

    International Nuclear Information System (INIS)

    Rodriguez Miranda, J.P.

    2010-01-01

    This paper describes de considerations for solid waste management in hydrocarbons exploration projects, as the serious environmental affectation as a function of soil contamination by leachate form the temporary storage of contaminated industrial waste hydrocarbons, altered by the presence of deposits landscaping waste materials, pollution of water and vegetation and the production of odors.

  1. Old dumps of uranium mining

    International Nuclear Information System (INIS)

    Gatzweiler, R.; Mager, D.

    1993-01-01

    The production of natural uranium through mining and milling results in large volumes of low-level radioactive waste, mainly in mine dumps and mill tailings. Hazards which relate to abandoned uranium production sites and environmental remediation approaches are described in reference to the Wismut case. During the period 1947 to 1990 the former Soviet-German Wismut Corporation produced about 200 000 t of uranium from several deposits in Thuringia and Saxonia within a relatively small and densely populated area. These activities resulted in major land disturbance and other environmental damage. Restoration problems are highlighted. (orig.)

  2. Spent fuel and radioactive waste inventories, projections, and characteristics

    International Nuclear Information System (INIS)

    1984-09-01

    Current inventories and characteristics of commercial spent fuels and both commercial and US Department of Energy (DOE) radioactive wastes were compiled through December 31, 1983, based on the most reliable information available from government sources and the open literature, technical reports, and direct contacts. Future waste and spent fuel to be generated over the next 37 years and characteristics of these materials are also presented, consistent with the latest DOE/Energy Information Administration (EIA) or projection of US commercial nuclear power growth and expected defense-related and private industrial and institutional activities. Materials considered, on a chapter-by-chapter basis, are: spent fuel, high-level waste, transuranic waste, low-level waste, commercial uranium mill tailings, airborne waste, remedial action waste, and decommissioning waste. For each category, current and projected inventories are given through the year 2020, and the radioactivity and thermal power are calculated, based on reported or calculated isotopic compositions. 48 figures, 107 tables

  3. Los Alamos National Laboratory TRU waste sampling projects

    International Nuclear Information System (INIS)

    Yeamans, D.; Rogers, P.; Mroz, E.

    1997-01-01

    The Los Alamos National Laboratory (LANL) has begun characterizing transuranic (TRU) waste in order to comply with New Mexico regulations, and to prepare the waste for shipment and disposal at the Waste Isolation Pilot Plant (WIPP), near Carlsbad, New Mexico. Sampling consists of removing some head space gas from each drum, removing a core from a few drums of each homogeneous waste stream, and visually characterizing a few drums from each heterogeneous waste stream. The gases are analyzed by GC/MS, and the cores are analyzed for VOC's and SVOC's by GC/MS and for metals by AA or AE spectroscopy. The sampling and examination projects are conducted in accordance with the ''DOE TRU Waste Quality Assurance Program Plan'' (QAPP) and the ''LANL TRU Waste Quality Assurance Project Plan,'' (QAPjP), guaranteeing that the data meet the needs of both the Carlsbad Area Office (CAO) of DOE and the ''WIPP Waste Acceptance Criteria, Rev. 5,'' (WAC)

  4. Dump truck-related deaths in construction, 1992-2007.

    Science.gov (United States)

    McCann, Michael; Cheng, Mei-Tai

    2012-05-01

    Dump trucks are universally used in construction and other industries to haul materials to the location and to remove waste materials. The source for dump truck-related fatality data was the Bureau of Labor Statistics Census of Fatal Occupational Injuries (CFOI) Research File. From 1992 to 2007, 829 construction workers were killed in dump truck-related incidents nationwide. Of those, 336 were dump truck operators with 215 deaths occurring in street and highway incidents. Another 343 deaths involved workers on foot, three-quarters struck by dump trucks. Sixty-four of the construction workers killed were maintaining dump trucks, 22 when caught between the truck frame and a falling dump truck bed. Of the 86 other deaths, 55 involved streets and highways. Recommendations include: (i) improving the reporting of seat belt usage in fatality reports; (ii) requiring use of seat belts; (iii) requiring the use of backup alarms, spotters, or other methods to alert dump truck operators to workers in their blind spots; (iv) prohibiting direct dumping at river banks and embankments; (v) using cameras or radar to enforce stopping at railway crossings; and (xi) enforcing worker safety practices (e.g., lockout/tagout procedures on elevated dump truck beds). Copyright © 2011 Wiley Periodicals, Inc.

  5. Analysis of the London dumping convention

    International Nuclear Information System (INIS)

    Nauke, M.K.

    1983-05-01

    This report gives an in-depth review of the provisions of the London Dumping Convention and of its origins in the context of the international legal framework for controlling all aspects of marine pollution. Particular attention is paid to the provisions concerning radioactive waste. (NEA) [fr

  6. Waste management - nuclear style

    International Nuclear Information System (INIS)

    McCall, P.

    1977-01-01

    Possible ways of disposing of highly radioactive wastes arising from the United Kingdom nuclear industry are briefly reviewed: projecting into outer space, dumping in containers in the ocean, or storage on land. The problems in each case and, in particular, the risks of environmental contamination from marine or land disposal, are discussed. (U.K.)

  7. The quality and quantity of runoff and groundwater in two overburden dumps undergoing pyritic oxidation

    International Nuclear Information System (INIS)

    Daniel, J.A.; Harries, J.R.; Ritchie, A.I.M.

    1983-01-01

    The quality and quantity of runoff and seepage water from two waste rock dumps at the abandoned uranium mine at Rum Jungle, N.T., have been monitored over various time intervals since 1975. Both dumps contain pyrite which is oxidising and solubilising trace metals within the dumps. Results are presented for the quality and quantity of runoff from both dumps measured in the 1980-81 wet season. The rainfall/runoff characteristics of the two dumps measured during this wet season are similar and in good agreement with measurements made in previous wet seasons. Pollution loads in runoff were only a few per cent of pollution loads in water percolating through to the base of the dumps. The rainfall/runoff characteristics and the dominance of pollution loads in water percolating through the dumps are likely to apply to other similar waste rock dumps

  8. The beam dump tunnels

    CERN Multimedia

    Patrice Loïez

    2002-01-01

    In these images workers are digging the tunnels that will be used to dump the counter-circulating beams. Travelling just a fraction under the speed of light, the beams at the LHC will each carry the energy of an aircraft carrier travelling at 12 knots. In order to dispose of these beams safely, a beam dump is used to extract the beam and diffuse it before it collides with a radiation shielded graphite target.

  9. Project Plan for the evaluation of REDC waste for TRU-waste radionuclides

    International Nuclear Information System (INIS)

    Nguyen, L.; Yong, L.; Chapman, J.

    1996-09-01

    This project plan describes the plan to determine whether the solid radioactive wastes generated by the Radiochemical Engineering Development Center (REDC) meet the Department of Energy's definition of transuranic wastes. Existing waste characterization methods will be evaluated, as well as historical data, and recommendations will be made as necessary

  10. Preliminary waste acceptance requirements - Konrad repository project

    International Nuclear Information System (INIS)

    Brennecke, P.W.; Warnecke, E.H.

    1991-01-01

    In Germany, the planned Konrad repository is proposed for the disposal of all types of radioactive wastes whose thermal influence upon the host rock is negligible. The Bundesamt fuer Strahlenschutz has established Preliminary Waste Acceptance Requirements (as of April 1990) for this facility. The respective requirements were developed on the basis of the results of site-specific safety assessments. They include general requirements on the waste packages to be disposed of as well as more specific requirements on the waste forms, the packaging and the radionuclide inventory per waste package. In addition, the delivery of waste packages was regulated. An outline of the structure and the elements of the Preliminary Waste Acceptance Requirements of April 1990 is given including comments on their legal status. (Author)

  11. Radiation- and self-ignition induced alterations of Permian uraniferous coal from the abandoned Novátor mine waste dump (Czech Republic)

    Czech Academy of Sciences Publication Activity Database

    Sýkorová, Ivana; Kříbek, B.; Havelcová, Martina; Machovič, Vladimír; Špaldoňová, Alexandra; Lapčák, L.; Knésl, I.; Blažek, Jaroslav

    2016-01-01

    Roč. 168, NOV (2016), s. 162-178 ISSN 0166-5162. [Annual Meeting of the International Committee for Coal and Organic Petrology /67./ – Symposium on Coal &Organic Petrology - New perspectives and Applications: atribute to Marlies Teichmüller (1914 – 2000). Potsdam, 05.09.2015-11.09.2015] R&D Projects: GA ČR(CZ) GA15-11674S Grant - others:OPPK(XE) CZ.2.16/3.1.00/21538 Program:OPPK Institutional support: RVO:67985891 Keywords : coal wastes * organic matter * uranium * mineralization * self-heating * biomarkers Subject RIV: DD - Geochemistry Impact factor: 4.783, year: 2016

  12. Flowsheets and source terms for radioactive waste projections

    International Nuclear Information System (INIS)

    Forsberg, C.W.

    1985-03-01

    Flowsheets and source terms used to generate radioactive waste projections in the Integrated Data Base (IDB) Program are given. Volumes of each waste type generated per unit product throughput have been determined for the following facilities: uranium mining, UF 6 conversion, uranium enrichment, fuel fabrication, boiling-water reactors (BWRs), pressurized-water reactors (PWRs), and fuel reprocessing. Source terms for DOE/defense wastes have been developed. Expected wastes from typical decommissioning operations for each facility type have been determined. All wastes are also characterized by isotopic composition at time of generation and by general chemical composition. 70 references, 21 figures, 53 tables

  13. Waste management for Shippingport Station Decommissioning Project: Extended summary

    International Nuclear Information System (INIS)

    Mullee, G.R.; Schulmeister, A.R.

    1987-01-01

    The Shippingport Station (SSDP) is demonstrating that the techniques and methodologies of waste management, which are currently employed by the nuclear industry, provide adequate management and control of waste activities for the decommissioning of a large scale nuclear plant. The SSDP has some unique aspects in that as part of the objective to promote technology transfer, multiple subcontractors are being utilized in the project. The interfaces resulting from multiple subcontractors require additional controls. Effective control has been accomplished by the use of a process control and inventory system, coupled with personnel training in waste management activities. This report summarizes the waste management plan and provides a status of waste management activities for SSDP

  14. Main results of the 2012 joint Norwegian-Russian expedition to the dumping sites of the nuclear submarine K-27 and solid radioactive waste in Stepovogo Fjord, Novaya Zemlya.

    Science.gov (United States)

    Gwynn, Justin P; Nikitin, Aleksander; Shershakov, Viacheslav; Heldal, Hilde Elise; Lind, Bjørn; Teien, Hans-Christian; Lind, Ole Christian; Sidhu, Rajdeep Singh; Bakke, Gunnar; Kazennov, Alexey; Grishin, Denis; Fedorova, Anastasia; Blinova, Oxana; Sværen, Ingrid; Lee Liebig, Penny; Salbu, Brit; Wendell, Cato Christian; Strålberg, Elisabeth; Valetova, Nailja; Petrenko, Galina; Katrich, Ivan; Logoyda, Igor; Osvath, Iolanda; Levy, Isabelle; Bartocci, Jean; Pham, Mai Khanh; Sam, Adam; Nies, Hartmut; Rudjord, Anne Liv

    2016-01-01

    This paper reports the main results of the 2012 joint Norwegian-Russian expedition to investigate the radioecological situation of the Stepovogo Fjord on the eastern coast of Novaya Zemlya, where the nuclear submarine K-27 and solid radioactive waste was dumped. Based on in situ gamma measurements and the analysis of seawater and sediment samples taken around the submarine, there was no indication of any leakage from the reactor units of K-27. With regard to the radioecological status of Stepovogo Fjord, activity concentrations of all radionuclides in seawater, sediment and biota in 2012 were in general lower than reported from the previous investigations in the 1990s. However in 2012, the activity concentrations of (137)Cs and, to a lesser extent, those of (90)Sr remained elevated in bottom water from the inner part of Stepovogo Fjord compared with surface water and the outer part of Stepovogo Fjord. Deviations from expected (238)Pu/(239,240)Pu activity ratios and (240)Pu/(239)Pu atom ratios in some sediment samples from the inner part of Stepovogo Fjord observed in this study and earlier studies may indicate the possibility of leakages from dumped waste from different nuclear sources. Although the current environmental levels of radionuclides in Stepovogo Fjord are not of immediate cause for concern, further monitoring of the situation is warranted. Copyright © 2015 Elsevier Ltd. All rights reserved.

  15. Convention on the Prevention of Marine Pollution by Dumping of Wastes and Other Matter; Convenio Sobre la Prevencion de la Contaminacion del mar por Vertimiento de Desechos y Otras Materias

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1974-06-11

    The Convention on the Prevention of Marine Pollution by Dumping of Wastes and Other Matter was drawn up at the Inter-Governmental Conference on the Dumping of Wastes at Sea, held in London from 30 October to 10 November 1972. The Governments of Mexico, the Union of Soviet Socialist Republics, the United Kingdom of Great Britain and Northern Ireland and the United States of America are the Depository Governments for instruments of ratification of, and accession to, the Convention, pursuant to Articles XVII and XVIII respectively [Spanish] El Convenio sobre la Prevencion de la Contaminacion del Mar por Vertimiento de Desechos y otras Materias fue elaborado en la Conferencia Intergubernamental para el Convenio sobre Vertimiento de Desechos en el Mar, celebrada en Londres del 30 de octubre al 10 de noviembre de 1972. Los Gobiernos de los Estados Unidos de America, Mexico, Reino Unido de Gran Bretana e Irlanda del Norte y Union de Republicas Socialistas Sovieticas son los Gobiernos depositarios de los instrumentos de ratificacion del Convenio y de adhesion al mismo, en conformidad con los Articulos XVII y XVIII, respectivamente.

  16. Low-level radioactive waste in the northeast: revised waste volume projections

    International Nuclear Information System (INIS)

    1984-06-01

    The volume of low-level radioactive waste generated in the eleven Northeast states has undergone significant change since the inital 1982 analysis and projection. These revised projections incorporate improved data reporting and evidence of sharp declines in certain categories of waste. Volumes in the 1982-1983 period reflect waste shipped for disposal as reported by disposal site operators. Projected waste volumes represent waste intended for disposal. The recent dramatic changes in source reduction and waste management practices underscore the need for annual review of waste volume projections. The volume of waste shipped for off-site disposal has declined approximately 12% in two years, from an average 1,092,500 ft 3 annually in 1979 to 1981 to an average annual 956,500 ft 3 in 1982 to 1983; reactor waste disposal volumes declined by about 39,000 ft 3 or 7% during this period. Non-reactor waste volumes shipped for disposal declined by over 70,000 ft 3 or 15% during this period. The data suggest that generators increased their use of such management practices as source reduction, compaction, or, for carbon-14 and tritium, temporary storage followed by disposal as non-radioactive waste under the NRC de minimus standard effective March 1981. Using the Technical Subcommittee projection methodology, the volume of low-level waste produced annually in the eleven states, individually and collectively, is expected to increase through the year 2000, but at a significantly lower rate of increase than initially projected. By the year 2000, the Northeast is projected to generate 1,137,600 ft 3 of waste annually, an increase of about 20% over 1982 to 1983 average volume

  17. Hanford tank waste operation simulator operational waste volume projection verification and validation procedure

    International Nuclear Information System (INIS)

    HARMSEN, R.W.

    1999-01-01

    The Hanford Tank Waste Operation Simulator is tested to determine if it can replace the FORTRAN-based Operational Waste Volume Projection computer simulation that has traditionally served to project double-shell tank utilization. Three Test Cases are used to compare the results of the two simulators; one incorporates the cleanup schedule of the Tri Party Agreement

  18. Major Components of the National TRU Waste System Optimization Project

    International Nuclear Information System (INIS)

    Moody, D.C.; Bennington, B.; Sharif, F.

    2002-01-01

    The National Transuranic (TRU) Program (NTP) is being optimized to allow for disposing of the legacy TRU waste at least 10 years earlier than originally planned. This acceleration will save the nation an estimated $713. The Department of Energy's (DOE'S) Carlsbad Field Office (CBFO) has initiated the National TRU Waste System Optimization Project to propose, and upon approvaI, implement activities that produce significant cost saving by improving efficiency, thereby accelerating the rate of TRU waste disposal without compromising safety. In its role as NTP agent of change, the National TRU Waste System Optimization Project (the Project) (1) interacts closely with all NTP activities. Three of the major components of the Project are the Central Characterization Project (CCP), the Central Confirmation Facility (CCF), and the MobiIe/Modular Deployment Program.

  19. Mixed and Low-Level Waste Treatment Facility project

    International Nuclear Information System (INIS)

    1992-04-01

    Mixed and low-level wastes generated at the Idaho National Engineering Laboratory (INEL) are required to be managed according to applicable State and Federal regulations, and Department of Energy Orders that provide for the protection of human health and the environment. The Mixed and Low-Level Waste Treatment Facility Project was chartered in 1991, by the Department of Energy to provide treatment capability for these mixed and low-level waste streams. The first project task consisted of conducting engineering studies to identify the waste streams, their potential treatment strategies, and the requirements that would be imposed on the waste streams and the facilities used to process them. The engineering studies, initiated in July 1991, identified 37 mixed waste streams, and 55 low-level waste streams. This report documents the waste stream information and potential treatment strategies, as well as the regulatory requirements for the Department of Energy-owned treatment facility option. The total report comprises three volumes and two appendices. This report consists of Volume 1, which explains the overall program mission, the guiding assumptions for the engineering studies, and summarizes the waste stream and regulatory information, and Volume 2, the Waste Stream Technical Summary which, encompasses the studies conducted to identify the INEL's waste streams and their potential treatment strategies

  20. Comments on conceptual questions concerning the clearance of wastes for disposal on a dump site during the decommissioning and dismantling of the nuclear power plant Obrigheim (KWO); Stellungnahme zu konzeptionellen Fragen der Freigabe zur Beseitigung auf einer Deponie bei Stilllegung und Abbau des Kernkraftwerks Obrigheim (KWO)

    Energy Technology Data Exchange (ETDEWEB)

    Kueppers, Christian

    2015-08-03

    The comments on conceptual questions concerning the clearance of wastes for disposal on a dump site during the decommissioning and dismantling of the nuclear power plant Obrigheim (KWO) cover the following issues: fundamentals of the 10 micro-Sv concept for clearance; specific regulations for the clearance of wastes from the dismantling of KWO for disposal on a dump site; disposal concept at shutdown and dismantling of KWO; measurements and control during clearance for disposal during shutdown and dismantling of KWO; documentation and reports.

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

    Energy Technology Data Exchange (ETDEWEB)

    Alfred Wickline

    2008-04-01

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

  2. SELENIUM TREATMENT/REMOVAL ALTERNATIVES DEMONSTRATION PROJECT - MINE WASTE TECHNOLOGY PROGRAM ACTIVITY III, PROJECT 20

    Science.gov (United States)

    This document is the final report for EPA's Mine WAste Technology Program (MWTP) Activity III, Project 20--Selenium Treatment/Removal Alternatives Demonstration project. Selenium contamination originates from many sources including mining operations, mineral processing, abandoned...

  3. Spent fuel and radioactive waste inventories, projections, and characteristics

    International Nuclear Information System (INIS)

    1983-09-01

    Current inventories and characteristics of commercial spent fuels and both commercial and US Department of Energy radioactive wastes were compiled through December 31, 1982, based on the most reliable information available from government sources and the open literature, technical reports, and direct contacts. Future waste and spent fuel to be generated over the next 40 years and characteristics of these materials are also presented, based on the latest DOE/EIA projection of US commercial nuclear power growth and expected defense-related and industrial and institutional activities. Materials considered, on a chapter-by-chapter bases, are: spent fuel, high-level waste, transuranic waste, low-level waste, active uranium mill tailings, airborne waste, remedial action waste, and decommissioning waste. For each category, current and projected inventories are given through the year 2020, and the radioactivity and thermal power are calculated, based on reported or calculated isotopic compositions. One chapter gives broad, summary data on the costs of spent fuel and radioactive waste management and disposal to provide an economic perspective. This chapter is not intended as a definitive guide, but it is a source of reasonable, order-of-magnitude costs and also provides references to more-detailed and scenario-specific studies. An appendix on generic flowsheets and source terms used for the projections is also included

  4. Conceptual project of waste treatment plant of CDTN

    International Nuclear Information System (INIS)

    Gabriel, J.L.; Astolfi, D.

    1983-01-01

    This paper presents the conceptual project of the waste treatment plant of CDTN. Several areas, such as: process area, material entrance and exit area are studied. The treatment processes are: evaporation, filtration, cementation, cutting and processing of solid wastes. (C.M.)

  5. Tunnel Boring Machine for nuclear waste repository research project

    International Nuclear Information System (INIS)

    Janzon, H.A.

    1994-01-01

    A description is presented of a Tunnel Boring Machine and its intended use on a research project underway in Sweden for demonstrating and testing methods for rock investigation at a suitable depth for a deep repository for nuclear waste

  6. Quality Assurance Program Plan (QAPP) Waste Management Project

    Energy Technology Data Exchange (ETDEWEB)

    VOLKMAN, D.D.

    1999-10-27

    This document is the Quality Assurance Program Plan (QAPP) for Waste Management Federal Services of Hanford, Inc. (WMH), that implements the requirements of the Project Hanford Management Contract (PHMC), HNF-MP-599, Project Hanford Quality Assurance Program Description (QAPD) document, and the Hanford Federal Facility Agreement with Consent Order (Tri-Party Agreement), Sections 6.5 and 7.8. WHM is responsible for the treatment, storage, and disposal of liquid and solid wastes generated at the Hanford Site as well as those wastes received from other US Department of Energy (DOE) and non-DOE sites. WMH operations include the Low-Level Burial Grounds, Central Waste Complex (a mixed-waste storage complex), a nonradioactive dangerous waste storage facility, the Transuranic Storage Facility, T Plant, Waste Receiving and Processing Facility, 200 Area Liquid Effluent Facility, 200 Area Treated Effluent Disposal Facility, the Liquid Effluent Retention Facility, the 242-A Evaporator, 300 Area Treatment Effluent Disposal Facility, the 340 Facility (a radioactive liquid waste handling facility), 222-S Laboratory, the Waste Sampling and Characterization Facility, and the Hanford TRU Waste Program.

  7. Spent fuel and radioactive-waste inventories, projections, and characteristics

    International Nuclear Information System (INIS)

    1982-10-01

    Current inventories and characteristics of commercial spent fuels and both commercial and US Department of Energy radioactive wastes were compiled, based on the most reliable information available from government sources and the open literature, technical reports, and direct contacts. Future waste and spent fuel to be generated over the next 40 years, and characteristics of these materials are also presented, based on a present DOE/EIA projection of US commercial nuclear power growth and expected defense-related and industrial and institutional activities. Materials considered, on a chapter-by-chapter basis, are: spent fuel, high-level waste, transuranic waste, low-level waste, remedial action waste, active uranium mill tailings, airborne waste, and decommissioning. For each category, current and projected inventories are given through the year 2020. The land usage requirements are given for storage/disposal of low-level and transuranic wastes, and for the present inventories of inactive uranium mill tailings. For each waste category the radioactivity and thermal power are calculated. Isotopic compositions and cost data are given for each waste type and for spent fuel

  8. Optimized application of systems engineering to nuclear waste repository projects

    International Nuclear Information System (INIS)

    Miskimin, P.A.; Shepard, M.

    1986-01-01

    The purpose of this presentation is to describe a fully optimized application of systems engineering methods and philosophy to the management of a large nuclear waste repository project. Knowledge gained from actual experience with the use of the systems approach on two repository projects is incorporated in the material presented. The projects are currently evaluating the isolation performance of different geologic settings and are in different phases of maturity. Systems engineering methods were applied by the principal author at the Waste Isolation Pilot Plant (WIPP) in the form of a functional analysis. At the Basalt Waste Isolation Project (BWIP), the authors assisted the intergrating contractor with the development and application of systems engineering methods. Based on this experience and that acquired from other waste management projects, an optimized plan for applying systems engineering techniques was developed. The plan encompasses the following aspects: project organization, developing and defining requirements, assigning work responsibilities, evaluating system performance, quality assurance, controlling changes, enhancing licensability, optimizing project performance, and addressing regulatory issues. This information is presented in the form of a roadmap for the practical application of system engineering principles to a nuclear waste repository project

  9. Spoil dump design and rehabilitation management practices (Australia)

    International Nuclear Information System (INIS)

    Goh, E.K.H.; Aspinall, T.O.; Kuszmaul, J.S.

    1998-01-01

    The environmental impact of mining and evolving environmental legislation has been receiving increased attention worldwide in the last two decades. The potential impacts associated with unstable spoil dumps from mine operations is the focus of concern both by the mining industry, environmental legislative agencies and members of the public. Engineered slopes of mine spoils may be stable at the end of construction, but they can deteriorate over time. There is thus the need to increase the base of knowledge on the existing practices of spoil dump design and rehabilitation. Information concluded from the analysis of the industrial survey carried out on Australian spoil dump management practices at coal, gold and ore mines are presented in this paper. The questionnaire asked for details of soil type of spoils, and factors influencing the design of spoil dumps (climate, rate of erosion, height of dumps, slope gradient and length, overburden handling equipment, soil characteristics, legislation and wastes). 10 refs., 5 figs., 5 tabs

  10. The SGHWR decommissioning project-waste strategy

    International Nuclear Information System (INIS)

    Graham, G.; Napper, M.

    1999-01-01

    Every facility must reach a stage in the decommissioning process where low-level waste (LLW) becomes the major factor in the decommissioning costs, therefore a cost-effective strategy for dealing with the waste must be sought. This paper describes the waste management strategy process that was carried out at the steam generating heavy water reactor (SGHWR) at Winfrith in Dorset. Obviously, each facility will have its own specific radiological problems, with its own unique fingerprint, which will have to be addressed, and, therefore, the optimum waste management strategy will differ for each facility. However, from the work done at SGHWR, it can be seen that it is possible to formulate a structured approach for dealing with LLW which meets the requirements of all stake holders, is safe, technically acceptable, cost-effective, and, furthermore, is equally applicable to other plants. (author)

  11. Economic analysis of radioactive waste storage and disposal projects

    International Nuclear Information System (INIS)

    Kleinen, P.J.; Starnes, R.B.

    1995-01-01

    Radioactive waste storage and disposal efforts present challenging issues for cost and economic analyses. In particular, legal requirements for states and compact areas to develop radioactive waste disposal sites, combined with closure of some sites, have placed urgency on planning, locating, and constructing storage and disposal sites. Cost analyses of potential projects are important to the decision processes. Principal objectives for cost analyses for projects are to identify all activities, covering the entire project life cycle, and to develop costs for those activities using methods that allow direct comparisons between competing project alternatives. For radioactive waste projects, long project lives ranging from tens of years to 100 or more years must be considered. Alternative, and competing, technologies, designs, and operating plans must be evaluated. Thorough base cost estimates must be made for all project phases: planning, development, licensing/permitting, construction, operations, and maintenance, closure, and post-closure/institutional care. Economic analysis procedures need to accommodate the specific features of each project alternative and facilitate cost comparisons between differing alternatives. Economic analysis assumptions must be developed to address the unusually long project lives involved in radioactive waste projects

  12. The flooded pit at Aznalcollar (Seville, Spain) and its use as a dumping site for mine waste; La corta inundada de Aznalcollar y su uso como vertedero de residuos mineros (Sevilla, Espana)

    Energy Technology Data Exchange (ETDEWEB)

    Santofimia Pastor, E.; Lopez Pamo, E.; Montero Gonzalez, E.

    2011-07-01

    Since its closure in 1995 and the subsequent failure of the slurry deposit dam in 1998, the Aznalcollar pit has been used as a disposal site for diverse metal-rich materials, such as the polluted soils removed during the cleaning-up of areas along the Guadiamar river together with waste rock, pyrite sludge and ashes deriving from pyrite roasting. At present the pit is partly flooded with a highly acidic (pH 2.7) lake holding some 6 Mm{sup 3} of metal- and sulphate-rich water. Detailed research undertaken in the area during recent years has proved that the dumping of wastes and the inflow of acidic mine waters are having a dramatic effect on the quality of the water in the lake. The greatest effect upon the Aznalcollar lake water was due to the dumping of 1.4 Mm{sup 3} of pyritic wastes during 2005 and 2006. The oxidative dissolution of this mineral has resulted firstly in the total consumption of dissolved oxygen, secondly, a notable increase in electric conductivity (from 8.6 to 12 mS/cm), thirdly, considerable acidification (from pH 4.2 to 2.7) and finally, heating due to the exothermic character of pyrite oxidation. Despite the almost total lack of oxidizing agents such as O{sub 2} and Fe(III) (Fe(III)<5% Fetotal) in the pit lake, pyrite continues to oxidize, producing a concomitant increase in SO{sub 4}{sup 2}- and Fe. (Author) 32 refs.

  13. Hanford Waste Vitrification Plant - the project and process systems

    International Nuclear Information System (INIS)

    Swenson, L.D.; Miller, W.C.; Smith, R.A.

    1990-01-01

    The Hanford Waste Vitrification Plant (HWVP) project is scheduled to start construction on the Hanford reservation in southeastern Washington State in 1991. The project will immobilize the liquid high-level defense waste stored there. The HWVP represents the third phase of the U.S. Department of Energy (DOE) activities that are focused on the permanent disposal of high-level radioactive waste, building on the experience of Defense Waste Processing Facility (DWPF) at the Savannah River site, South Carolina, and of the West Valley Demonstration Plant (WVDP), New York. This sequential approach to disposal of the country's commercial and defense high-level radioactive waste allows HWVP to make extensive use of lessons learned from the experience of its predecessors, using mature designs from the earlier facilities to achieve economies in design and construction costs while enhancing operational effectiveness

  14. Dump evaluation for landscape restoration of an ancient cacareous quarry

    International Nuclear Information System (INIS)

    Paredes, R.; Ayala, R.; Trevisiol, S.

    2010-01-01

    This work is about the geological - mining study in the limestone quarry in the west of Valle Hermoso town - Cordoba - Argentina. The generation of dump material is considered a waste but is inherent to the process of rocks and minerals extraction. The dump stocks evaluation take into account the different types of rocks with physical and chemical characteristics. The dump has several carbonatic qualities and can be given useful to uncover material originally dismissed as to be used as crushed stone for concrete and others.The reuse of this waste can be allocated primarily to the construction industry, and explore other potential uses, would rehabilitate these lands, and thus eliminate an environmental liability .This work is about the geological - mining study in the limestone quarry in the west of Valle Hermoso town - Cordoba - Argentina. The generation of dump material is considered a waste but is inherent to the process of rocks and minerals extraction. The dump stocks evaluation take into account the different types of rocks with physical and chemical characteristics. The dump has several carbonatic qualities and can be given useful to uncover material originally dismissed as to be used as crushed stone for concrete and others.The reuse of this waste can be allocated primarily to the construction industry, and explore other potential uses, would rehabilitate these lands, and thus eliminate an environmental liability

  15. Allegheny County Illegal Dump Sites

    Data.gov (United States)

    Allegheny County / City of Pittsburgh / Western PA Regional Data Center — The Illegal Dump Site dataset includes information on illegal dump sites, their type of trash, and the estimate tons of trash at each site. The information was...

  16. Waste management CDM projects barriers NVivo 10® qualitative dataset.

    Science.gov (United States)

    Bufoni, André Luiz; de Sousa Ferreira, Aracéli Cristina; Oliveira, Luciano Basto

    2017-12-01

    This article contains one NVivo 10® file with the complete 432 projects design documents (PDD) of seven waste management sector industries registered as Clean Development Mechanism (CDM) under United Nations Framework Convention on Climate Change (UNFCCC) Kyoto Protocol Initiative from 2004 to 2014. All data analyses and sample statistics made during the research remain in the file. We coded PDDs in 890 fragments of text, classified in five categories of barriers (nodes): technological, financial, human resources, regulatory, socio-political. The data supports the findings of author thesis [1] and other two indexed publication in Waste Management Journal: "The financial attractiveness assessment of large waste management projects registered as clean development mechanism" and "The declared barriers of the large developing countries waste management projects: The STAR model" [2], [3]. The data allows any computer assisted qualitative content analysis (CAQCA) on the sector and it is available at Mendeley [4].

  17. Use of a Knowledge Management System in Waste Management Projects

    International Nuclear Information System (INIS)

    Gruendler, D.; Boetsch, W.U.; Holzhauer, U.; Nies, R.A.

    2006-01-01

    In Germany the knowledge management system 'WasteInfo' about waste management and disposal issues has been developed and implemented. Beneficiaries of 'WasteInfo' are official decision makers having access to a large information pool. The information pool is fed by experts, so called authors This means compiling of information, evaluation and assigning of appropriate properties (metadata) to this information. The knowledge management system 'WasteInfo' has been introduced at the WM04, the operation of 'WasteInfo' at the WM05. The recent contribution describes the additional advantage of the KMS being used as a tool for the dealing with waste management projects. This specific aspect will be demonstrated using a project concerning a comparative analysis of the implementation of repositories in six countries using nuclear power as examples: The information of 'WasteInfo' is assigned to categories and structured according to its origin and type of publication. To use 'WasteInfo' as a tool for the processing the projects, a suitable set of categories has to be developed for each project. Apart from technical and scientific aspects, the selected project deals with repository strategies and policies in various countries, with the roles of applicants and authorities in licensing procedures, with safety philosophy and with socio-economic concerns. This new point of view has to be modelled in the categories. Similar to this, new sources of information such as local and regional dailies or particular web-sites have to be taken into consideration. In this way 'WasteInfo' represents an open document which reflects the current status of the respective repository policy in several countries. Information with particular meaning for the German repository planning is marked and by this may influence the German strategy. (authors)

  18. Mixed and Low-Level Waste Treatment Facility Project

    International Nuclear Information System (INIS)

    1992-04-01

    Mixed and low-level wastes generated at the Idaho National Engineering Laboratory (INEL) are required to be managed according to applicable State and Federal regulations, and Department of Energy Orders that provide for the protection of human health and the environment. The Mixed and Low-Level Waste Treatment Facility Project was chartered in 1991, by the Department of Energy to provide treatment capability for these mixed and low-level waste streams. The first project task consisted of conducting engineering studies to identify the waste streams, their potential treatment strategies, and the requirements that would be imposed on the waste streams and the facilities used to process them. This report documents those studies so the project can continue with an evaluation of programmatic options, system tradeoff studies, and the conceptual design phase of the project. This report, appendix B, comprises the engineering design files for this project study. The engineering design files document each waste steam, its characteristics, and identified treatment strategies

  19. Remedial Action and Waste Disposal Project Manager's Implementing Instructions

    International Nuclear Information System (INIS)

    Dronen, V.R.

    1998-01-01

    These Project Manager's Implementing Instructions provide the performance standards required of all Environmental Restoration Contractor personnel in their work during operation and administration of the Remedial Action and Waste Disposal Project. The instructions emphasize technical competency, workplace discipline, and personal accountability to ensure a high level of safety and performance during operations activities

  20. The Hanford Site solid waste treatment project; Waste Receiving and Processing (WRAP) Facility

    International Nuclear Information System (INIS)

    Roberts, R.J.

    1991-01-01

    The Waste Receiving and Processing (WRAP) Facility will provide treatment and temporary storage (consisting of in-process storage) for radioactive and radioactive/hazardous mixed waste. This facility must be constructed and operated in compliance with all appropriate US Department of Energy (DOE) orders and Resource Conservation and Recovery Act (RCRA) regulations. The WRAP Facility will examine and certify, segregate/sort, and treat for disposal suspect transuranic (TRU) wastes in drums and boxes placed in 20-yr retrievable storage since 1970; low-level radioactive mixed waste (RMW) generated and placed into storage at the Hanford Site since 1987; designated remote-handled wastes; and newly generated TRU and RMW wastes from high-level waste (HLW) recovery and processing operations. In order to accelerated the WRAP Project, a partitioning of the facility functions was done in two phases as a means to expedite those parts of the WRAP duties that were well understood and used established technology, while allowing more time to better define the processing functions needed for the remainder of WRAP. The WRAP Module 1 phase one, is to provide the necessary nondestructive examination and nondestructive assay services, as well as all transuranic package transporter (TRUPACT-2) shipping for both WRAP Project phases, with heating, ventilation, and air conditioning; change rooms; and administrative services. Phase two of the project, WRAP Module 2, will provide all necessary waste treatment facilities for disposal of solid wastes. 1 tab

  1. Dumping of solid packaged radioactivity in the deep oceans

    International Nuclear Information System (INIS)

    Forster, Wm. O.; Van As, D.

    1980-01-01

    With the increasing use of nuclear energy, the quantity of radioactive wastes which are generated is also increasing. Their treatment and disposal is causing a concern in further development of nuclear energy. World's oceans are considered as a possible location for these wastes. A convention on the prevention of marine pollution caused by dumping of wastes and other matter into oceans was adopted at the Intergovernmental Conference held at London in November 1972. The convention prohibits dumping of high-level radioactive wastes in the oceans and has entrusted the IAEA the tasks of defining the high level radioactive wastes and providing recommendations for the issue of special permits for dumping of the radioactive materials which do not fall into the category of high-level wastes. A provisional definition and recommendations formulated by the IAEA and adopted by contractin.o. parties in 1976 are outlined. On the basis of an oceanographic model developed by Shepherd (1976) and considered to be the best available, a revised definition and revised recommendations were formulated. Their salient features are mentioned. The key parameters for specific site assessments are mentioned. The Nuclear Energy Agency also formulated guidelines on sea-disposal packages for radioactive wastes in 1974 and revised them in 1978. Finally it is noted that criteria have not been established for dumping of non-radioactive wastes in the ocean, though such criteria are contained in the IAEA recommendations in case of radioactive wastes. (M.G.B.)

  2. Waste management for the Shippingport Station Decommissioning Project

    International Nuclear Information System (INIS)

    Mullee, G.R.; Schulmeister, A.R.

    1987-01-01

    The Shippingport Station Decommissioning Project (SSDP) is being performed by the US Department of Energy (DOE) with the objectives of placing the station in a radiologically safe condition, demonstrating safe and cost effective dismantlement and providing useful data for future decommissioning projects. This paper describes the development of the Waste Management Plan which is being used for the accomplishment of the SSDP. Significant aspects of the Plan are described, such as the use of a process control and inventory system. The current status of waste management activities is reported. It is concluded that SSDP has some unique aspects which will provide useful information for future decommissioning projects

  3. The Stripa project in a Swedish waste management perspective

    International Nuclear Information System (INIS)

    Bjurstroem, S.

    1994-01-01

    This publication deals with the Swedish nuclear waste management program till the 60s; it also consists of a presentation of the Stripa Project, that played a important role in the research development work in Sweden. This project was carried out in collaboration with the United States, and an international participation was organized. The primary goals of this project were to develop scientific techniques to characterize a granite rock. The issues of such studies were of common concern to many countries that had research and development programs on the disposal of high-level radioactive wastes. (TEC)

  4. Salt Repository Project waste emplacement mode decision paper: Revison 1

    International Nuclear Information System (INIS)

    1987-08-01

    This paper provides a recommendation as to the mode of waste emplacement to be used as the current basis for site characterization activity for the Deaf Smith County, Texas, high level nuclear waste repository site. It also presents a plan for implementing the recommendation so as to provide a high level of confidence in the project's success. Since evaluations of high-level waste disposal in geologic repositories began in the 1950s, most studies emplacement in salt formations employed the vertical orientation for emplacing waste packages in boreholes in the floor of the underground facility. This orientation was used in trials at Project Salt Vault in the 1960s. The Waste Isolation Pilot Plant (WIPP) has recently settled on a combination of vertical and horizontal modes for various waste types. This paper analyzes the information available and develops a project position upon which to base current site characterization activities. The position recommended is that the SRP should continue to use the vertical waste emplacement mode as the reference design and to carry the horizontal mode as a ''passive'' alternative. This position was developed based upon the conclusions of a decision analysis, risk assessment, and cost/schedule impact assessment. 52 refs., 6 figs., 1 tab

  5. Solid Waste Projection Model: Database (Version 1.4)

    International Nuclear Information System (INIS)

    Blackburn, C.; Cillan, T.

    1993-09-01

    The Solid Waste Projection Model (SWPM) system is an analytical tool developed by Pacific Northwest Laboratory (PNL) for Westinghouse Hanford Company (WHC). The SWPM system provides a modeling and analysis environment that supports decisions in the process of evaluating various solid waste management alternatives. This document, one of a series describing the SWPM system, contains detailed information regarding the software and data structures utilized in developing the SWPM Version 1.4 Database. This document is intended for use by experienced database specialists and supports database maintenance, utility development, and database enhancement. Those interested in using the SWPM database should refer to the SWPM Database User's Guide. This document is available from the PNL Task M Project Manager (D. L. Stiles, 509-372-4358), the PNL Task L Project Manager (L. L. Armacost, 509-372-4304), the WHC Restoration Projects Section Manager (509-372-1443), or the WHC Waste Characterization Manager (509-372-1193)

  6. Overview of the waste/barrier/rock interactions program of the basalt waste isolation project

    International Nuclear Information System (INIS)

    Salter, P.F.; Burnell, J.R.; Lane, D.L.

    1986-01-01

    The waste package waste/barrier/rock interactions testing program of the Basalt Waste Isolation Project is designed to assess the interactions between nuclear waste forms, other waste package components, and the environment in order to evaluate long-term waste package isolation (radionuclide release) behavior. The program involves reacting fully radioactive waste forms with combinations of steel or copper container material and basalt/bentonite packing material in site-specific ground water under anticipated repository conditions to obtain the steady state radionuclide concentrations required to predictively model waste package radionuclide concentrations required to predictively model waste package radionuclide releases. Both static and flow-through autoclaves are being used in the test program to determine radionuclide concentrations as a function of time and groundwater flow rate, and to evaluate the solid phase and water chemistry changes that control those concentrations. This test program, when combined with project hydrologic and geochemical testing and modeling efforts, and natural analog studies, provides the information required to evaluate long-term radionuclide mobility within a waste package emplaced in a basalt repository

  7. Reclamation of the illegal dump for sustainable development the environment in Sverdlovo of Leningrad Oblast’, Russia

    Directory of Open Access Journals (Sweden)

    Bukova Maria

    2016-01-01

    Full Text Available Illegal dumping is dumping of any waste such as oil, furniture, appliances, trash, litter or landscaping cuttings, upon any land of state, city, village or private ownership without consent of the owner. Illegal dumping has a great negative and fatal impact on our environment and all living organisms both fauna and flora. It also exposes people to various risks of chemicals (fluids or dust and is a big threat to all under-ground and surface water resources. Illegal dumps also attract all kinds of bugs such as rodents and insects. For example, illegal dumps with waste tires provide a practically perfect place for mosquitoes to breed. Mosquitoes can multiply 100 times faster than normal in the warm, stagnant water in waste tires. Exemplary for the illegal dump in Sverdlovo of Leningrad Oblast’ the main purpose of this article is to offer a possible option for the remediation of contaminated area.

  8. The refined of waste oil as sustainable solution: Ecoroil project; El re-refinamiento como solucion sostenible para el aceite usado: proyecto Ecoril

    Energy Technology Data Exchange (ETDEWEB)

    Torras, J. M.

    1999-11-01

    Waste oil must be re-refined at all? Or simply burn it all and forget about it? Today`s waste oil is burnt and dumped, thus causing serious and unnecessary pollution of the environment, contamination of the rivers, seas, water sources, soil and atmosphere. Industry and government, both, have fundamental responsibility to use every option to them to reduce pollution and to re-use and recycle before producing more. One of the most effective recycling possibilities is the re-refining. The lubricating oil business is large, profitable and complex. The new technologies in re-refining produce base oils of highest quality which can equal the performance of virgin oil. The ECOROIL Project carried forward by three companies from different sectors, F. L. Iberia - Infineum -Cator, S. A. - has demonstrated it. The paper also provides some light aspects about waste oil and re-refined oils in the last years in Spain. (Author) 4 refs.

  9. Mixed Waste Treatment Project: Computer simulations of integrated flowsheets

    International Nuclear Information System (INIS)

    Dietsche, L.J.

    1993-12-01

    The disposal of mixed waste, that is waste containing both hazardous and radioactive components, is a challenging waste management problem of particular concern to DOE sites throughout the United States. Traditional technologies used for the destruction of hazardous wastes need to be re-evaluated for their ability to handle mixed wastes, and in some cases new technologies need to be developed. The Mixed Waste Treatment Project (MWTP) was set up by DOE's Waste Operations Program (EM30) to provide guidance on mixed waste treatment options. One of MWTP's charters is to develop flowsheets for prototype integrated mixed waste treatment facilities which can serve as models for sites developing their own treatment strategies. Evaluation of these flowsheets is being facilitated through the use of computer modelling. The objective of the flowsheet simulations is to provide mass and energy balances, product compositions, and equipment sizing (leading to cost) information. The modelled flowsheets need to be easily modified to examine how alternative technologies and varying feed streams effect the overall integrated process. One such commercially available simulation program is ASPEN PLUS. This report contains details of the Aspen Plus program

  10. Development plan. High activity-long living wastes project. Abstract

    International Nuclear Information System (INIS)

    2007-01-01

    This brochure presents the actions that the ANDRA (the French national agency of radioactive wastes) has to implement in the framework of the project of high activity-long living (HALL) radioactive wastes (HAVL project) conformably to the requirements of the program defined in the law from June 28, 2006 (law no 2006-739). This law precises the three, complementary, research paths to explore for the management of this type of wastes: separation and transmutation of long-living radioactive elements, reversible disposal in deep geologic underground, and long duration storage. The ANDRA's action concerns the geologic disposal aspect. The following points are presented: the HALL wastes and their containers, the reversible disposal procedure, the HAVL project: financing of researches, storage concepts, development plan of the project (dynamics, information and dialogue approach, input data, main steps, schedule); the nine programs of the HAVL project (laboratory experiments and demonstration tests, surface survey, scientific program, simulation program, surface engineering studies and technological tests, information and communication program, program of environment and facilities surface observation and monitoring, waste packages management, monitoring and transport program, disposal program); the five transverse technical and scientific activities (safety, reversibility, cost, health and occupational safety, impact study). (J.S.)

  11. Waste management - sewage - special wastes

    International Nuclear Information System (INIS)

    1987-01-01

    The 27 papers represent a cross-section of the subject waste management. Particular attention is paid to the following themes: waste avoidance, waste product utilization, household wastes, dumping technology, sewage sludge treatments, special wastes, seepage from hazardous waste dumps, radioactive wastes, hospital wastes, purification of flue gas from waste combustion plants, flue gas purification and heavy metals, as well as combined sewage sludge and waste product utilization. The examples given relate to plants in Germany and other European countries. 12 papers have been separately recorded in the data base. (DG) [de

  12. The Dutch geologic radioactive waste disposal project

    International Nuclear Information System (INIS)

    Hamstra, J.; Verkerk, B.

    1981-01-01

    The Final Report reviews the work on geologic disposal of radioactive waste performed in the Netherlands over the period 1 January 1978 to 31 December 1979. The attached four topical reports cover detailed subjects of this work. The radionuclide release consequences of an accidental flooding of the underground excavations during the operational period was studied by the institute for Atomic Sciences in Agriculture (Italy). The results of the quantitative examples made for different effective cross-sections of the permeable layer connecting the mine excavations with the boundary of the salt dome, are that under all circumstances the concentration of the waste nuclides in drinking water will remain well within the ICRP maximum permissible concentrations. Further analysis work was done on what minima can be achieved for both the maximum local rock salt temperatures at the disposal borehole walls and the maximum global rock salt temperatures halfway between a square of disposal boreholes. Different multi-layer disposal configurations were analysed and compared. A more detailed description is given of specific design and construction details of a waste repository such as the shaft sinking and construction, the disposal mine development, the mine ventilation and the different plugging and sealing procedures for both the disposal boreholes and the shafts. Thanks to the hospitality of the Gesellschaft fuer Strahlenforschung, an underground working area in the Asse mine became available for performing a dry drilling experiment, which resulted successfully in the drilling of a 300 m deep disposal borehole from a mine room at the -750 m level

  13. Projected legislation on radioactive waste management

    International Nuclear Information System (INIS)

    Wagner, H.

    1992-01-01

    Should be regulatory proposals contained in the draft of a law to change the legal regulations concerning nuclear power (as of September 1, 1992) be put into effect, this would mean an essential conceptual change concerning radioactive waste management. The contribution examines the essential changes and comes to the following conclusion: 1. At present there is a need for concretization of regulations concerning reactor decommissioning by means of amendments of laws, legal regulations and administrative regulations. The set of rules concerning nuclear technology must be adapted to the specific situation in which reactor decommissioning, reactor dismantling and confinement are involved. 2. No convincing reacons for privatizing the construction and operation of radwaste repositories exist. The advantages of such a change in course are not apparent. 3. Direct radwaste disposal should be legally defined in clear terms as an independent and cumulative process of waste disposal (in addition to and apart from radwaste repositing and re-processing). Hereby the utilization of radioactive waste products should continue to be given priority. (orig./HSCH) [de

  14. Salt Repository Project Waste Package Program Plan: Draft

    International Nuclear Information System (INIS)

    Carr, J.A.; Cunnane, J.C.

    1986-01-01

    Under the direction of the Office of Civilian Radioactive Waste Management (OCRWM) created within the DOE by direction of the Nuclear Waste Policy Act of 1982 (NWPA), the mission of the Salt Repository Project (SRP) is to provide for the development of a candidate salt repository for disposal of high-level radioactive waste (HLW) and spent reactor fuel in a manner that fully protects the health and safety of the public and the quality of the environment. In consideration of the program needs and requirements discussed above, the SRP has decided to develop and issue this SRP Waste Package Program Plan. This document is intended to outline how the SRP plans to develop the waste package design and to show, with reasonable assurance, that the developed design will satisfy applicable requirements/performance objectives. 44 refs., 16 figs., 16 tabs

  15. Processing the THOREX waste at the West Valley demonstration project

    International Nuclear Information System (INIS)

    Barnes, S.M.; Schiffhauer, M.A.

    1994-01-01

    This paper focuses on several options for neutralizing the THOREX and combining it with the PUREX wastes. Neutralization testing with simulated wastes (nonradioactive chemicals) was performed to evaluate the neutralization reactions and the reaction product generation. Various methods for neutralizing the THOREX solution were examined to determine their advantages and disadvantages relative to the overall project objectives and compatibility with the existing process. The primary neutralization process selection criteria were safety and minimizing the potential delays prior to vitrification. The THOREX neutralization method selected was direct addition to the high pH PUREX wastes within Tank 8D-2. Laboratory testing with simulated waste has demonstrated rapid neutralization of the THOREX waste acid. Test results for various direct addition scenarios has established the optimum process operating conditions which provide the largest safety margins

  16. Yucca Mountain Site Characterization Project Waste Package Plan

    International Nuclear Information System (INIS)

    Harrison-Giesler, D.J.; Jardine, L.J.

    1991-02-01

    The goal of the US Department of Energy's (DOE) Yucca Mountain Site Characterization Project (YMP) waste package program is to develop, confirm the effectiveness of, and document a design for a waste package and associated engineered barrier system (EBS) for spent nuclear fuel and solidified high-level nuclear waste (HLW) that meets the applicable regulatory requirements for a geologic repository. The Waste Package Plan describes the waste package program and establishes the technical approach against which overall progress can be measured. It provides guidance for execution and describes the essential elements of the program, including the objectives, technical plan, and management approach. The plan covers the time period up to the submission of a repository license application to the US Nuclear Regulatory Commission (NRC). 1 fig

  17. LLNL/YMP Waste Container Fabrication and Closure Project

    International Nuclear Information System (INIS)

    1990-10-01

    The Department of Energy's Office of Civilian Radioactive Waste Management (OCRWM) Program is studying Yucca Mountain, Nevada as a suitable site for the first US high-level nuclear waste repository. Lawrence Livermore National Laboratory (LLNL) has the responsibility for designing and developing the waste package for the permanent storage of high-level nuclear waste. This report is a summary of the technical activities for the LLNL/YMP Nuclear Waste Disposal Container Fabrication and Closure Development Project. Candidate welding closure processes were identified in the Phase 1 report. This report discusses Phase 2. Phase 2 of this effort involved laboratory studies to determine the optimum fabrication and closure processes. Because of budget limitations, LLNL narrowed the materials for evaluation in Phase 2 from the original six to four: Alloy 825, CDA 715, CDA 102 (or CDA 122) and CDA 952. Phase 2 studies focused on evaluation of candidate material in conjunction with fabrication and closure processes

  18. Waste-to-energy technologies and project implementation

    CERN Document Server

    Rogoff, Marc J

    2011-01-01

    This book covers in detail programs and technologies for converting traditionally landfilled solid wastes into energy through waste-to-energy projects. Modern Waste-to-Energy plants are being built around the world to reduce the levels of solid waste going into landfill sites and contribute to renewable energy and carbon reduction targets. The latest technologies have also reduced the pollution levels seen from early waste incineration plants by over 99 per cent. With case studies from around the world, Rogoff and Screve provide an insight into the different approaches taken to the planning and implementation of WTE. The second edition includes coverage of the latest technologies and practical engineering challenges as well as an exploration of the economic and regulatory context for the development of WTE.

  19. Refuse Dumps And The Environment: A Case Study Of Some ...

    African Journals Online (AJOL)

    Refuse Dumps And The Environment: A Case Study Of Some Selected Cities In Nigeria. ... International Journal of Emotional Psychology and Sport Ethics ... This study assessed the level of environmental pollution in the nation by focusing on the degree of accumulation of house – hold wastes, industrial scraps or wastes, ...

  20. A model for quantifying construction waste in projects according to the European waste list.

    Science.gov (United States)

    Llatas, C

    2011-06-01

    The new EU challenge is to recover 70% by weight of C&D waste in 2020. Literature reveals that one major barrier is the lack of data. Therefore, this paper presents a model which allows technicians to estimate C&D waste during the design stage in order to promote prevention and recovery. The types and quantities of CW are estimated and managed according to EU guidelines, by building elements and specifically for each project. The model would allow detection of the source of the waste and to adopt other alternative procedures which delete hazardous waste and reduce CW. Likewise, it develops a systematic structure of the construction process, a waste classification system and some analytical expressions which are based on factors. These factors depend on technology and represent a standard on site. It would allow to develop a database of waste anywhere. A Spanish case study is covered. Factors were obtained by studying over 20 dwellings. The source and types of packaging waste, remains, soil and hazardous waste were estimated in detail and were compared with other studies. Results reveal that the model can be implemented in projects and the chances of reducing and recovery C&D waste could be increased, well above the EU challenge. Copyright © 2011 Elsevier Ltd. All rights reserved.

  1. Solid waste integrated cost analysis model: 1991 project year report

    Energy Technology Data Exchange (ETDEWEB)

    1991-01-01

    The purpose of the City of Houston's 1991 Solid Waste Integrated Cost Analysis Model (SWICAM) project was to continue the development of a computerized cost analysis model. This model is to provide solid waste managers with tool to evaluate the dollar cost of real or hypothetical solid waste management choices. Those choices have become complicated by the implementation of Subtitle D of the Resources Conservation and Recovery Act (RCRA) and the EPA's Integrated Approach to managing municipal solid waste;. that is, minimize generation, maximize recycling, reduce volume (incinerate), and then bury (landfill) only the remainder. Implementation of an integrated solid waste management system involving all or some of the options of recycling, waste to energy, composting, and landfilling is extremely complicated. Factors such as hauling distances, markets, and prices for recyclable, costs and benefits of transfer stations, and material recovery facilities must all be considered. A jurisdiction must determine the cost impacts of implementing a number of various possibilities for managing, handling, processing, and disposing of waste. SWICAM employs a single Lotus 123 spreadsheet to enable a jurisdiction to predict or assess the costs of its waste management system. It allows the user to select his own process flow for waste material and to manipulate the model to include as few or as many options as he or she chooses. The model will calculate the estimated cost for those choices selected. The user can then change the model to include or exclude waste stream components, until the mix of choices suits the user. Graphs can be produced as a visual communication aid in presenting the results of the cost analysis. SWICAM also allows future cost projections to be made.

  2. The Waste Isolation Pilot Plant (WIPP) integrated project management system

    International Nuclear Information System (INIS)

    Olona, D.; Sala, D.

    1993-01-01

    The Waste Isolation Pilot Plant (WIPP), located 26 miles east of Carlsbad, New Mexico, is a research and development project of the Department of Energy (DOE), tasked with the mission of demonstrating the safe disposal of transuranic (TRU) radioactive wastes. This unique project was authorized by Congress in 1979 in response to the national need for long-term, safe methods for disposing of radioactive by-products from our national defense programs. The WIPP was originally established in December of 1979, by Public Law 96-164, DOE National Security and Military Applications of Nuclear Energy Authorization Act of 1980. Since the inception of the WIPP Project, work has continued to prepare the facility to receive TRU wastes. Studies continue to be conducted to demonstrate the safety of the WIPP facility in accordance with federal and state laws, state agreements, environmental regulations, and DOE Orders. The objectives of implementing an integrated project management system are to assure compliance with all regulatory and federal regulations, identify areas of concern, provide justification for funding, provide a management tool for control of program workscope, and establish a project baseline from which accountability and performance will be assessed. Program management and project controls are essential for the success of the WIPP Project. The WIPP has developed an integrated project management system to establish the process for the control of the program which has an expected total dollar value of $2B over the ten-year period from 1990-2000. The implementation of this project management system was motivated by the regulatory requirements of the project, the highly public environment in which the project takes place, limited funding and resources, and the dynamic nature of the project. Specific areas to be addressed in this paper include strategic planning, project organization, planning and scheduling, fiscal planning, and project monitoring and reporting

  3. Swiss projects for the final disposal of radioactive wastes

    International Nuclear Information System (INIS)

    McCombie, C.

    1987-01-01

    At present, the major part of the discussion does not focus on technical assessment methodology and data, but rather on interpretation of the available geologic data for high-level waste disposal planning. Meanwhile, plans for the implementation of repositories have to be developed. Accordingly, the longer-term studies on high-level waste disposal are proceeding at a pace appropriate for their relatively far-future timescales, and intensified efforts are being put into projects for design, siting, safety assessment and construction of the more urgently required repository for low and intermediate level waste. (orig./PW) [de

  4. Defense waste processing facility project at the Savannah River Plant

    International Nuclear Information System (INIS)

    Baxter, R.G.; Maher, R.; Mellen, J.B.; Shafranek, L.F.; Stevens, W.R. III.

    1984-01-01

    The Du Pont Company is building for the Department of Energy a facility to vitrify high-level waste at the Savannah River Plant near Aiken, South Carolina. The Defense Waste Processing Facility (DWPF) will solidify existing and future radioactive wastes produced by defense activities at the site. At the present time engineering and design are 45% complete, the site has been cleared, and startup is expected in 1989. This paper will describe project status as well as features of the design. 9 figures

  5. Mixed and Low-Level Waste Treatment Facility project

    International Nuclear Information System (INIS)

    1992-04-01

    Mixed and low-level wastes generated at the Idaho National Engineering Laboratory (INEL) are required to be managed according to applicable State and Federal regulations, and Department of Energy Orders that provide for the protection of human health and the environment. The Mixed and Low-Level Waste Treatment Facility Project was chartered in 1991, by the Department of Energy to provide treatment capability for these mixed and low-level waste streams. The first project task consisted of conducting engineering studies to identify the waste streams, their potential treatment strategies, and the requirements that would be imposed on the waste streams and the facilities used to process them. This report, Appendix A, Environmental ampersand Regulatory Planning ampersand Documentation, identifies the regulatory requirements that would be imposed on the operation or construction of a facility designed to process the INEL's waste streams. These requirements are contained in five reports that discuss the following topics: (1) an environmental compliance plan and schedule, (2) National Environmental Policy Act requirements, (3) preliminary siting requirements, (4) regulatory justification for the project, and (5) health and safety criteria

  6. The upper Rhine waste heat project

    International Nuclear Information System (INIS)

    Schikarski, W.

    1977-03-01

    The tasks and targets of the project are: 1) Determination of the parameters relevant for an assessment of consequences, e.g.: General influences on weather and climate, anthropogenic influences on weather and climate, effects, affected systems, boundary conditions, anthropogenic changes in boundary conditions. 2) Developing a method of evaluation. 3) Establishing a sensitivity model and carrying out analyses. 4) Determining interface parameters which relate this project to other projects. 5) Summary of the findings and preparation of the main study. The cooperating institutions are: UBA, GfK, KFA, Deutscher Wetterdienst, University Bonn (Inst. f. Meteorology), Bonnenberg + Drescher GmbH, ISI (FhG Karlsruhe). (orig./HP) [de

  7. Nevada Nuclear Waste Storage Investigations. FY 1979 project plan

    International Nuclear Information System (INIS)

    1979-03-01

    This document presents the management and cost for the Nevada Nuclear Waste Storage Investigations (disposal of high-level wastes at Nevada Test Site) and provides a complete description of the overall project, management structure, technical approach, and work breakdown structure. The document is organized into five major sections. Section I summarizes the history of the project and indicates a potential future course of action. FY 1979 project work is briefly described in Section II. Section III outlines the delegated responsibilities of all project management functions. A list of critical questions that guide the technical approach of the project are presented in Section IV. Section V contains subtask work plans which outline the work in detail for this fiscal year

  8. Impact of waste dump on surface water quality and aquatic insect diversity of Deepor Beel (Ramsar site), Assam, North-east India.

    Science.gov (United States)

    Choudhury, Dharitri; Gupta, Susmita

    2017-10-06

    Water and aquatic insects were collected seasonally from site 1, the low-lying area of the dump near Deepor Beel, and from sites 2 and 3 of the main wetland and analysed. While dissolved oxygen (DO) increased from site 1 to site 3 in each season, electrical conductivity (EC), total dissolved solid (TDS), total alkalinity (TA) and free CO 2 (F-CO 2 ) decreased. Pb and Cd were found to exceed the limits set for drinking water in all the sites and seasons. Species richness (SpR) was found highest (23) at site 2 and lowest (14) at site 1. Sensitive species was absent. The Shannon (H') values at site 1 were  1 in most of the seasons. Biological monitoring scores (Biological Monitoring Working Party and Stream Invertebrate Grade Number-Average Level) in different sites and seasons inferred severely poor to moderate water quality. At site 1, significant negative correlations were seen for Pb and Cr with SpR while Ni and Cu with insect density (ID). At site 2, TA had highly significant positive correlations with SpR and ID while Cu showed negative correlation with SpR. At site 3, ID had significant negative relationships with air temperature, water temperature, depth, TA, F-CO 2 , PO 4 3- and Cr. Canonical correspondence analysis triplot has clearly separated site 1 associated with tolerant species and highly influenced by TA, TDS, EC, F-CO 2, Cr, Ni, Cd and Zn confirming high anthropogenic activities on that site. Tolerant and semitolerant species were present at site 2 (influenced by depth and transparency) and site 3 (influenced by Pb and WT) both. Results of this study discerned that the dump site is the point source of pollution.

  9. Determinants of sustainability in solid waste management – The Gianyar Waste Recovery Project in Indonesia

    International Nuclear Information System (INIS)

    Zurbrügg, Christian; Gfrerer, Margareth; Ashadi, Henki; Brenner, Werner; Küper, David

    2012-01-01

    Highlights: ► Our assessment tool helps evaluate success factors in solid waste projects. ► Success of the composting plant in Indonesia is linked to its community integration. ► Appropriate technology is not a main determining success factor for sustainability. ► Structured assessment of “best practices” can enhance replication in other cities. - Abstract: According to most experts, integrated and sustainable solid waste management should not only be given top priority, but must go beyond technical aspects to include various key elements of sustainability to ensure success of any solid waste project. Aside from project sustainable impacts, the overall enabling environment is the key feature determining performance and success of an integrated and affordable solid waste system. This paper describes a project-specific approach to assess typical success or failure factors. A questionnaire-based assessment method covers issues of: (i) social mobilisation and acceptance (social element), (ii) stakeholder, legal and institutional arrangements comprising roles, responsibilities and management functions (institutional element); (iii) financial and operational requirements, as well as cost recovery mechanisms (economic element). The Gianyar Waste Recovery Project in Bali, Indonesia was analysed using this integrated assessment method. The results clearly identified chief characteristics, key factors to consider when planning country wide replication but also major barriers and obstacles which must be overcome to ensure project sustainability. The Gianyar project consists of a composting unit processing 60 tons of municipal waste per day from 500,000 inhabitants, including manual waste segregation and subsequent composting of the biodegradable organic fraction.

  10. Determinants of sustainability in solid waste management - The Gianyar Waste Recovery Project in Indonesia

    Energy Technology Data Exchange (ETDEWEB)

    Zurbruegg, Christian, E-mail: zurbrugg@eawag.ch [Eawag: Swiss Federal Institute of Aquatic Science and Technology, Department of Water and Sanitation in Developing Countries (Sandec), Ueberlandstrasse 133, P.O. Box 611, 8600 Duebendorf (Switzerland); Gfrerer, Margareth, E-mail: margareth.gfrerer@gmx.net [Faculty of Engineering, University of Indonesia, Depok Campus, 16424 Jakarta (Indonesia); Ashadi, Henki, E-mail: henki@eng.ui.ac.id [Faculty of Engineering, University of Indonesia, Depok Campus, 16424 Jakarta (Indonesia); Brenner, Werner, E-mail: werner.brenner@gmx.at [Faculty of Engineering, University of Indonesia, Depok Campus, 16424 Jakarta (Indonesia); Kueper, David, E-mail: dkuper@indo.net.id [Yayasan Pemilahan Sampah Temesi, Temsi-Gianyar, Bali (Indonesia)

    2012-11-15

    Highlights: Black-Right-Pointing-Pointer Our assessment tool helps evaluate success factors in solid waste projects. Black-Right-Pointing-Pointer Success of the composting plant in Indonesia is linked to its community integration. Black-Right-Pointing-Pointer Appropriate technology is not a main determining success factor for sustainability. Black-Right-Pointing-Pointer Structured assessment of 'best practices' can enhance replication in other cities. - Abstract: According to most experts, integrated and sustainable solid waste management should not only be given top priority, but must go beyond technical aspects to include various key elements of sustainability to ensure success of any solid waste project. Aside from project sustainable impacts, the overall enabling environment is the key feature determining performance and success of an integrated and affordable solid waste system. This paper describes a project-specific approach to assess typical success or failure factors. A questionnaire-based assessment method covers issues of: (i) social mobilisation and acceptance (social element), (ii) stakeholder, legal and institutional arrangements comprising roles, responsibilities and management functions (institutional element); (iii) financial and operational requirements, as well as cost recovery mechanisms (economic element). The Gianyar Waste Recovery Project in Bali, Indonesia was analysed using this integrated assessment method. The results clearly identified chief characteristics, key factors to consider when planning country wide replication but also major barriers and obstacles which must be overcome to ensure project sustainability. The Gianyar project consists of a composting unit processing 60 tons of municipal waste per day from 500,000 inhabitants, including manual waste segregation and subsequent composting of the biodegradable organic fraction.

  11. Waste-to-Energy Cogeneration Project, Centennial Park

    Energy Technology Data Exchange (ETDEWEB)

    Johnson, Clay; Mandon, Jim; DeGiulio, Thomas; Baker, Ryan

    2014-04-29

    The Waste-to-Energy Cogeneration Project at Centennial Park has allowed methane from the closed Centennial landfill to export excess power into the the local utility’s electric grid for resale. This project is part of a greater brownfield reclamation project to the benefit of the residents of Munster and the general public. Installation of a gas-to-electric generator and waste-heat conversion unit take methane byproduct and convert it into electricity at the rate of about 103,500 Mwh/year for resale to the local utility. The sale of the electricity will be used to reduce operating budgets by covering the expenses for streetlights and utility bills. The benefits of such a project are not simply financial. Munster’s Waste-to Energy Cogeneration Project at Centennial Park will reduce the community’s carbon footprint in an amount equivalent to removing 1,100 cars from our roads, conserving enough electricity to power 720 homes, planting 1,200 acres of trees, or recycling 2,000 tons of waste instead of sending it to a landfill.

  12. Tank Waste Remediation System Characterization Project Programmatic Risk Management Plan

    International Nuclear Information System (INIS)

    Baide, D.G.; Webster, T.L.

    1995-12-01

    The TWRS Characterization Project has developed a process and plan in order to identify, manage and control the risks associated with tank waste characterization activities. The result of implementing this process is a defined list of programmatic risks (i.e. a risk management list) that are used by the Project as management tool. This concept of risk management process is a commonly used systems engineering approach which is being applied to all TWRS program and project elements. The Characterization Project risk management plan and list are subset of the overall TWRS risk management plan and list

  13. Role of quality assurance vs project manager's responsibility for waste projects

    International Nuclear Information System (INIS)

    Solecki, J.

    1989-01-01

    This paper takes a project manager's perspective and discusses the role of the quality assurance organization in the development, implementation and interface related to the QA program for waste projects. The author describes the role which the QA program plays in allowing project management to assure that the project manager knows what is placed in the repository and the characteristics of the surrounding environment meet closure requirements

  14. State of Nevada, Agency for Nuclear Projects/Nuclear Waste Project Office narrative report, January 1992

    International Nuclear Information System (INIS)

    1992-01-01

    The Agency for Nuclear Projects/Nuclear Waste Project Office (NWPO) is the State of Nevada agency designated by State law to monitor and oversee US Department of Energy (DOE) activities relative to the possible siting, construction, operation and closure of a high-level nuclear waste repository at Yucca Mountain and to carry out the State of Nevada's responsibilities under the Nuclear Waste Policy Act of 1982. During the reporting period the NWPO continued to work toward the five objectives designed to implement the Agency's oversight responsibilities: (1) Assure that the health and safety of Nevada's citizens are adequately protected with regard to any federal high-level radioactive waste program within the State; (2) Take the responsibilities and perform the duties of the State of Nevada as described in the Nuclear Waste Policy Act of 1982 (Public Law 97-425) and the Nuclear Waste Policy Amendments Act of 1987; (3) Advise the Governor, the State Commission on Nuclear Projects and the Nevada State Legislature on matters concerning the potential disposal of high-level radioactive waste in the State; (4) Work closely and consult with affected local governments and State agencies; (5) Monitor and evaluate federal planning and activities regarding high-level radioactive waste disposal. Plan and conduct independent State studies regarding the proposed repository

  15. Overview of hydrothermal testing of waste-package barrier materials at the Basalt Waste Isolation Project

    International Nuclear Information System (INIS)

    1982-01-01

    The current Waste Package Department (WPD) hydrothermal testing program for the Basalt Waste Isolation Project (BWIP) has followed a systematic approach for the testing of waste-barrier-basalt interactions based on sequential penetration of barriers by intruding groundwaters. Present test activities in the WPD program have focused on determining radionuclide solubility limits (or steady-state conditions) of simulated waste forms and the long-term stability of waste package barriers under site-specific hydrothermal conditions. The resulting data on solution compositions and solid alteration products have been used to evaluate waste form degradation under conditions specific to a nuclear waste repository located in basalt (NWRB). Isothermal, time-invariant compositional data on sampled solutions have been coupled with realistic hydrologic flow data for near-field and far-field modeling for the calculation of meaningful radionuclide release rates. Radionuclides that are not strongly sorbed or precipitated from solution and that, therefore, may require special attention to ensure their isolation within the waste package have been identified. Taken together, these hydrothermal test data have been used to establish design requirements for waste packages located in basalt

  16. INEL Waste and Environmental Information Integration Project approach and concepts

    International Nuclear Information System (INIS)

    Dean, L.A.; Fairbourn, P.J.; Randall, V.C.; Riedesel, A.M.

    1994-06-01

    The Idaho National Engineering, Laboratory (INEL) Waste and Environmental Information integration Project (IWEIIP) was established in December 1993 to address issues related to INEL waste and environmental information including: Data quality; Data redundancy; Data accessibility; Data integration. This effort includes existing information, new development, and acquisition activities. Existing information may not be a database record; it may be an entire document (electronic, scanned, or hard-copy), a video clip, or a file cabinet of information. The IWEIIP will implement an effective integrated information framework to manage INEL waste and environmental information as an asset. This will improve data quality, resolve data redundancy, and increase data accessibility; therefore, providing more effective utilization of the dollars spent on waste and environmental information

  17. Experience with dose limitation during preparations for sea dumping operations

    International Nuclear Information System (INIS)

    Fieuw, G.; Voorde, N. van de; Baekelandt, L.

    1982-01-01

    Since 1967 low-level radioactive wastes from operational nuclear facilities in Belgium have been dumped into the sea. The dumping is carried out in accordance with the recommendations issued by the IAEA under the London Convention. All these dumping operations have taken place under the surveillance of the Nuclear Energy Agency of the OECD. To limit the doses received by workers and the public during the various phases leading up to sea dumping, appropriate measures are required in connection with waste treatment and packaging, limitation of radiation levels, storage and handling, organization and selection of the means of transport and organization and means of monitoring. Although treatment and handling at the nuclear sites are entrusted to occupationally exposed workers, temporary labour is used for the transport and handling operations. Effective treatment and packaging reduce the risk of internal exposure to a negligible value. Meticulous planning and permanent personnel monitoring reduce the doses received by the workers to acceptable values not exceeding the statutory dose limits. The doses received by personnel involved in the preparations for sea dumping operations from 1967 to 1980 are given and a relationship is established between these doses and the activities handled. Experience shows that sea dumping operations do not entail unacceptable risks either for the workers concerned or for the population and allows us to optimize the methods used for loading, handling and transport. (author)

  18. Premature beam dumps in 2011

    CERN Document Server

    Albert, Markus

    2012-01-01

    The statistical analysis of all non-programmed beam dumps during the 2011 proton run is presented. The selection criteria of fills that got considered were that the beam intensity of each of the two beams exceeded at least 1e12 particles per beam in order to exclude all probe beam dumps and most of the MPS test dumps. A distribution of beam dump causes by system is shown, as well as the time it took to re-establish injection after a non-programmed dump for fills which made it into STABLE BEAMS. This was done in an attempt to evaluate the cost of those non-programmed dumps in terms of time.

  19. CONRRAD Project: how CNEA is managing radioactive waste knowledge

    International Nuclear Information System (INIS)

    Vetere, Claudia L.; Gomiz, Pablo R.

    2009-01-01

    The aim of this paper is to introduce CONRRAD Project, which is an initiative of the Knowledge Management Group (GesCon) belonged to the Nuclear Safety and Environment Area, for knowledge preservation of Radioactive Waste Management. It discusses the methodology and the results that have been achieved at present. (author)

  20. Reducing construction waste: A study of urban infrastructure projects.

    Science.gov (United States)

    de Magalhães, Ruane Fernandes; Danilevicz, Ângela de Moura Ferreira; Saurin, Tarcisio Abreu

    2017-09-01

    The construction industry is well-known for producing waste detrimental to the environment, and its impacts have increased with the development process of cities. Although there are several studies focused on the environmental impact of residential and commercial buildings, less knowledge is available regarding decreasing construction waste (CW) generation in urban infrastructure projects. This study presents best practices to reduce waste in the said projects, stressing the role of decision-making in the design stage and the effective management of construction processes in public sector. The best practices were identified from literature review, document analysis in 14 projects of urban infrastructure, and both qualitative and quantitative survey with 18 experts (architects and engineers) playing different roles on those projects. The contributions of these research are: (i) the identification of the main building techniques related to the urban design typologies analyzed; (ii) the identification of cause-effect relationships between the design choices and the CW generation diagnosis; (iii) the proposal of a checklist to support the decision-making process, that can be used as a control and evaluation instrument when developing urban infrastructure designs, focused on the construction waste minimization (CWM). Copyright © 2017 Elsevier Ltd. All rights reserved.

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

    International Nuclear Information System (INIS)

    Slaybaugh, R.R.

    1997-08-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

    Slaybaugh, R.R.

    1997-08-29

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

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

    International Nuclear Information System (INIS)

    Duncan, David

    2011-01-01

    This preliminary project execution plan (PEP) defines U.S. Department of Energy (DOE) project objectives, roles and responsibilities of project participants, project organization, and controls to effectively manage acquisition of capital funds for construction of a proposed remote-handled low-level waste (LLW) disposal facility at the Idaho National Laboratory (INL). The plan addresses the policies, requirements, and critical decision (CD) responsibilities identified in DOE Order 413.3B, 'Program and Project Management for the Acquisition of Capital Assets.' This plan is intended to be a 'living document' that will be periodically updated as the project progresses through the CD process to construction and turnover for operation.

  4. Challenges and Plans for Injection and Beam Dump

    Science.gov (United States)

    Barnes, M.; Goddard, B.; Mertens, V.; Uythoven, J.

    The injection and beam dumping systems of the LHC will need to be upgraded to comply with the requirements of operation with the HL-LHC beams. The elements of the injection system concerned are the fixed and movable absorbers which protect the LHC in case of an injection kicker error and the injection kickers themselves. The beam dumping system elements under study are the absorbers which protect the aperture in case of an asynchronous beam dump and the beam absorber block. The operational limits of these elements and the new developments in the context of the HL-LHC project are described.

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

    International Nuclear Information System (INIS)

    Jacobsen, P.H.

    1997-01-01

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

  6. Geology beneath and beside the notorious Payatas open dump, Metro Manila, Philippines

    Science.gov (United States)

    Tomarong, C.; Arcilla, C.; de Sales, L.; Chua, S.; Garcia, E.; Pamintuan, G.

    2003-04-01

    With a minimum of 6000 tonnes/day municipal waste output, and with NO existing operational sanitary landfill and with incineration illegal, Metro Manila has a very serious solid waste disposal problem. Unsorted municipal waste are being piled in open dumps, the most notorious of which is the Payatas open dump. A recent, tragic garbage-slide in this open dump caused dozens of deaths, news of which were broadcast internationally. Political expediency laced with a lot of corruption, rather than sound science, was the main basis for selecting this site as an open dump. As an example, this dump is situated plastics. Several cross-sections cut across the dump show that the side slopes of the dump are on the average steeper than the pre-dump slopes. The “bedrock” of the Payatas dump are conglomerate members of the Pleistocene volcaniclastic Guadualupe Formation. Studies are still to be done on the extent of pollution on surface and groundwater in the Payatas environs.

  7. Radioactive Waste Management System: Draft Project Decision Schedule. Revision

    International Nuclear Information System (INIS)

    1985-07-01

    The Nuclear Waste Policy Act (NWPA) of 1982 (Pub. L. 97-425) requires that the Secretary of Energy prepare, in cooperation with affected Federal agencies, a Project Decision Schedule that portrays the optimum way to attain the operation of geologic repositories. The Draft Project Decision Schedule portrays the major milestones of the Radioactive Waste Management System. It also depicts the set of activities for which Federal agencies have responsibility and the deadlines for taking the required action that are associated with the activities. The NWPA also requires that Federal agencies having determined that they: (1) cannot comply with a deadline for taking a required action; or (2) fail to comply with a deadline contained in the Project Decision Schedule; submit a comprehensive report to the Secretary of Energy and Congress to explain their failure or expected failure. The Secretary, in turn, is required to submit to Congress a response to the agency's report. 7 figs., 13 tabs

  8. TWRS privatization support project waste characterization database development

    International Nuclear Information System (INIS)

    1995-11-01

    Pacific Northwest National Laboratory requested support from ICF Kaiser Hanford Company in assembling radionuclide and chemical analyte sample data and inventory estimates for fourteen Hanford underground storage tanks: 241-AN-102, -104, -105, -106, and -107, 241-AP-102, -104, and -105, 241-AW-101, -103, and -105, 241 AZ-101 and -102; and 241-C-109. Sample data were assembled for sixteen radionuclides and thirty-five chemical analytes. The characterization data were provided to Pacific Northwest National Laboratory in support of the Tank Waste Remediation Services Privatization Support Project. The purpose of this report is to present the results and document the methodology used in preparing the waste characterization information data set to support the Tank Waste Remediation Services Privatization Support Project. This report describes the methodology used in assembling the waste characterization information and how that information was validated by a panel of independent technical reviewers. Also, contained in this report are the various data sets created: the master data set, a subset, and an unreviewed data set. The master data set contains waste composition information for Tanks 241-AN-102 and -107, 241-AP-102 and -105, 241-AW-101; and 241-AZ-101 and -102. The subset contains only the validated analytical sample data from the master data set. The unreviewed data set contains all collected but unreviewed sample data for Tanks 241-AN-104, -105, and -106; 241-AP-104; 241-AW-103 and-105; and 241-C-109. The methodology used to review the waste characterization information was found to be an accurate, useful way to separate the invalid or questionable data from the more reliable data. In the future, this methodology should be considered when validating waste characterization information

  9. Projecting future solid waste management requirements on the Hanford Site

    International Nuclear Information System (INIS)

    Shaver, S.R.; Stiles, D.L.; Holter, G.M.; Anderson, B.C.

    1990-09-01

    The problem of treating and disposing of hazardous transuranic (TRU), low-level radioactive, and mixed waste has become a major concern of the public and the government. At the US Department of Energy's Hanford Site in Washington state, the problem is compounded by the need to characterize, retrieve, and treat the solid waste that was generated and stored for retrieval during the past 20 years. This paper discusses the development and application of a Solid Waste Projection Model that uses forecast volumes and characteristics of existing and future solid waste to address the treatment, storage, and disposal requirements at Hanford. The model uses a data-driven, object-oriented approach to assess the storage and treatment throughout requirements for each operation for each of the distinct waste classes and the accompanying cost of the storage and treatment operations. By defining the elements of each alternative for the total waste management system, the same database can be used for numerous analyses performed at different levels of detail. This approach also helps a variety of users with widely varying information requirements to use the model and helps achieve the high degree of flexibility needed to cope with changing regulations and evolving treatment and disposal technologies. 2 figs

  10. Solid Waste Projection Model: Database (Version 1.3)

    International Nuclear Information System (INIS)

    Blackburn, C.L.

    1991-11-01

    The Solid Waste Projection Model (SWPM) system is an analytical tool developed by Pacific Northwest Laboratory (PNL) for Westinghouse Hanford Company (WHC). The SWPM system provides a modeling and analysis environment that supports decisions in the process of evaluating various solid waste management alternatives. This document, one of a series describing the SWPM system, contains detailed information regarding the software and data structures utilized in developing the SWPM Version 1.3 Database. This document is intended for use by experienced database specialists and supports database maintenance, utility development, and database enhancement

  11. ''Project Crystal'' for ultimate storage of highly radioactive waste

    International Nuclear Information System (INIS)

    Anon.

    1983-01-01

    NAGRA (The National Association for storage of radioactive waste) in Baden has launched in North Switzerland an extensive geological research program. The current research program, under the title of ''Project Crystal'', aims at providing the scientific knowledge which is required for the assessment of the suitability of the crystalline sub-soil of North Switzerland for the ultimate storage of highly radioactive waste. Safety and feasibility of such ultimate storage are in the forefront of preoccupations. Scientific institutes of France, Germany, USA and Canada are cooperating more particularly on boring research and laboratory analyses. Technical data are given on the USA and German installations used. (P.F.K.)

  12. Industrial Program of Waste Management - Cigeo Project - 13033

    Energy Technology Data Exchange (ETDEWEB)

    Butez, Marc [Agence nationale pour la gestion des dechets radioactifs - Andra, 1-7, rue Jean Monnet 92298 Chatenay-Malabry (France); Bartagnon, Olivier; Gagner, Laurent [AREVA NC Tour AREVA 1 place de la Coupole 92084 Paris La Defense (France); Advocat, Thierry; Sacristan, Pablo [Commissariat a l' energie atomique et aux energies alternatives - CEA, CEA-SACLAY 91191 Gif sur Yvette Cedex (France); Beguin, Stephane [Electricite de France - EDF, Division Combustible Nucleaire, 1, Place Pleyel Site Cap Ampere93282 Saint Denis (France)

    2013-07-01

    The French Planning Act of 28 June 2006 prescribed that a reversible repository in a deep geological formation be chosen as the reference solution for the long-term management of high-level and intermediate-level long-lived radioactive waste. It also entrusted the responsibility of further studies and design of the repository (named Cigeo) upon the French Radioactive Waste Management Agency (Andra), in order for the review of the creation-license application to start in 2015 and, subject to its approval, the commissioning of the repository to take place in 2025. Andra is responsible for siting, designing, implementing, operating the future geological repository, including operational and long term safety and waste acceptance. Nuclear operators (Electricite de France (EDF), AREVA NC, and the French Commission in charge of Atomic Energy and Alternative Energies (CEA) are technically and financially responsible for the waste they generate, with no limit in time. They provide Andra, on one hand, with waste packages related input data, and on the other hand with their long term industrial experiences of high and intermediate-level long-lived radwaste management and nuclear operation. Andra, EDF, AREVA and CEA established a cooperation agreement for strengthening their collaborations in these fields. Within this agreement Andra and the nuclear operators have defined an industrial program for waste management. This program includes the waste inventory to be taken into account for the design of the Cigeo project and the structural hypothesis underlying its phased development. It schedules the delivery of the different categories of waste and defines associated flows. (authors)

  13. Industrial Program of Waste Management - Cigeo Project - 13033

    International Nuclear Information System (INIS)

    Butez, Marc; Bartagnon, Olivier; Gagner, Laurent; Advocat, Thierry; Sacristan, Pablo; Beguin, Stephane

    2013-01-01

    The French Planning Act of 28 June 2006 prescribed that a reversible repository in a deep geological formation be chosen as the reference solution for the long-term management of high-level and intermediate-level long-lived radioactive waste. It also entrusted the responsibility of further studies and design of the repository (named Cigeo) upon the French Radioactive Waste Management Agency (Andra), in order for the review of the creation-license application to start in 2015 and, subject to its approval, the commissioning of the repository to take place in 2025. Andra is responsible for siting, designing, implementing, operating the future geological repository, including operational and long term safety and waste acceptance. Nuclear operators (Electricite de France (EDF), AREVA NC, and the French Commission in charge of Atomic Energy and Alternative Energies (CEA) are technically and financially responsible for the waste they generate, with no limit in time. They provide Andra, on one hand, with waste packages related input data, and on the other hand with their long term industrial experiences of high and intermediate-level long-lived radwaste management and nuclear operation. Andra, EDF, AREVA and CEA established a cooperation agreement for strengthening their collaborations in these fields. Within this agreement Andra and the nuclear operators have defined an industrial program for waste management. This program includes the waste inventory to be taken into account for the design of the Cigeo project and the structural hypothesis underlying its phased development. It schedules the delivery of the different categories of waste and defines associated flows. (authors)

  14. National Conversion Pilot Project Waste Management Program

    International Nuclear Information System (INIS)

    Engelmann, G.G.; Simmons, M.S.

    1995-01-01

    The U.S. Department of Energy facilities are in the process of downsizing. Most plans for downsizing focus on the decontamination and decommissioning of excess production facilities. A different approach for downsizing is taken at Rocky Flats Environmental Technology Site (RFETS), which has four production buildings. These buildings were used for the production of weapons components from uranium and beryllium and contain unique and valuable equipment, such as rolling mills, furnaces, and high-capacity presses, which could be utilized for stage-III metal recycling. The mission of this National Conversion Pilot Project (NCPP) open-quotes is to explore and demonstrate, at the Rocky Flats Environmental Technology Site (RFETS), the feasibility of economic conversion at Department of Energy facilities.close quotes The NCPP has been divided into three stages: 1. Stage I-planning and feasibility determination 2. Stage II-facility cleanup for reuse and operational assessment 3. Stage III-metals recycling. The NCPP has recently been approved to begin stage II. The objective of the NCPP stage II is to prepare the four NCPP buildings for stage III, to remove unwanted equipment, and to decontaminate buildings and essential equipment to levels consistent with those that commercial industrial operations must meet pursuant to applicable Occupational Safety and Health Administration, U.S. Environmental Protection Agency, U.S. Nuclear Regulatory Commission, and state workplace regulations

  15. Dumping in a Global World

    NARCIS (Netherlands)

    J.L. Moraga-Gonzalez (José Luis); J.M.A. Viaene (Jean-Marie)

    2004-01-01

    textabstractAnti-dumping actions are now the trade policy of choice of developing and transition economies. To understand why these economies have increasingly applied anti-dumping laws, we build a simple theoretical model of vertical intra-industry trade and investigate the strategic incentives of

  16. Alpha waste incineration prototype incinerator and industrial project

    International Nuclear Information System (INIS)

    Caramelle, D.; Meyere, A.

    1988-01-01

    To meet our requirements with respect to the processing of solid alpha wastes, a pilot cold incinerator has been used for R and D. This unit has a capacity of 5 kg/hr. The main objectives assigned to this incineration process are: a good reduction factor, controlled combustion, ash composition compatible with plutonium recovery, limited secondary solid and fluid wastes, releases within the nuclear and chemical standards, and in strict observance of the confinement and criticality safety rules. After describing the process we will discuss the major results of the incineration test campaigns with representative solid wastes (50 % PVC). We will then give a description of an industrial project with a capacity of 7 kg/hr, followed by a cost estimate

  17. Remote-Handled Low Level Waste Disposal Project Alternatives Analysis

    Energy Technology Data Exchange (ETDEWEB)

    David Duncan

    2010-10-01

    This report identifies, evaluates, and compares alternatives for meeting the U.S. Department of Energy’s mission need for management of remote-handled low-level waste generated by the Idaho National Laboratory and its tenants. Each alternative identified in the Mission Need Statement for the Remote-Handled Low-Level Waste Treatment Project is described and evaluated for capability to fulfill the mission need. Alternatives that could meet the mission need are further evaluated and compared using criteria of cost, risk, complexity, stakeholder values, and regulatory compliance. The alternative for disposal of remote-handled low-level waste that has the highest confidence of meeting the mission need and represents best value to the government is to build a new disposal facility at the Idaho National Laboratory Site.

  18. Environmental Management Integration Project/Mixed Waste Focus Area Partnership

    International Nuclear Information System (INIS)

    Gombert, D.; Kristofferson, K.; Cole, L.

    1999-01-01

    On January 16, 1998, the Assistant Secretary for the Environmental Management (EM) Program at the Department of Energy, issued DOE-Idaho the Program Integration and Systems Engineering Guidance for Fiscal Year 1998, herein called Guidance, which directed that program integration tasks be performed for all EM program areas. This guidance directed the EM Integration team, as part of the Task 1, to develop baseline waste and material disposition maps which are owned by the site Project Baseline Summary (PBS) manager. With these baselines in place Task 2 gave direction to link Science and Technology activities to the waste and material stream supported by that technology. This linkage of EM Program needs with the OST activities supports the DOE goal of maximizing cleanup at DOE sites by 2006 and provides a defensible science and technology program. Additionally, this linkage is a valuable tool in the integration of the waste and material disposition efforts for the DOE complex

  19. Prioritization of proposed waste management construction projects for the Waste Management program within the Department of Energy

    International Nuclear Information System (INIS)

    Johnson, J.V.

    1995-01-01

    A prioritization process is used to evaluate and rank proposed construction projects within the Department of Energy's Waste Management program. The process is used to determine which projects should proceed with conceptual design activities. The proposed construction projects are evaluated against a set of criteria which reflect Waste Management priorities. A management review team ranks and scores the projects thereby generating a prioritized list of projects. Despite decreasing budgets and changing political climates, the process has been a successful decision-aiding tool for selecting construction projects to carry out the Waste Management mission within the Department of Energy

  20. River Protection Project (RPP) Dangerous Waste Training Plan

    International Nuclear Information System (INIS)

    POHTO, R.E.

    2000-01-01

    This supporting document contains the training plan for dangerous waste management at River Protection Project TSD Units. This document outlines the dangerous waste training program developed and implemented for all Treatment, Storage, and Disposal (TSD) Units operated by River Protection Project (RPP) in the Hanford 200 East, 200 West and 600 Areas and the <90 Day Accumulation Area at 209E. Operating TSD Units managed by RPP are: the Double-Shell Tank (DST) System, 204-AR Waste Unloading Facility, Grout, and the Single-Shell Tank (SST) System. The program is designed in compliance with the requirements of Washington Administrative Code (WAC) 173-303-330 and Title 40 Code of Federal Regulations (CFR) 265.16 for the development of a written dangerous waste training program and the Hanford Facility Permit. Training requirements were determined by an assessment of employee duties and responsibilities. The RPP training program is designed to prepare employees to operate and maintain the Tank Farms in a safe, effective, efficient, and environmentally sound manner. In addition to preparing employees to operate and maintain the Tank Farms under normal conditions, the training program ensures that employees are prepared to respond in a prompt and effective manner should abnormal or emergency conditions occur. Emergency response training is consistent with emergency responses outlined in the following Building Emergency Plans: HNF-IP-0263-TF and HNF-=IP-0263-209E

  1. River Protection Project (RPP) Dangerous Waste Training Plan

    Energy Technology Data Exchange (ETDEWEB)

    POHTO, R.E.

    2000-03-09

    This supporting document contains the training plan for dangerous waste management at River Protection Project TSD Units. This document outlines the dangerous waste training program developed and implemented for all Treatment, Storage, and Disposal (TSD) Units operated by River Protection Project (RPP) in the Hanford 200 East, 200 West and 600 Areas and the <90 Day Accumulation Area at 209E. Operating TSD Units managed by RPP are: the Double-Shell Tank (DST) System, 204-AR Waste Unloading Facility, Grout, and the Single-Shell Tank (SST) System. The program is designed in compliance with the requirements of Washington Administrative Code (WAC) 173-303-330 and Title 40 Code of Federal Regulations (CFR) 265.16 for the development of a written dangerous waste training program and the Hanford Facility Permit. Training requirements were determined by an assessment of employee duties and responsibilities. The RPP training program is designed to prepare employees to operate and maintain the Tank Farms in a safe, effective, efficient, and environmentally sound manner. In addition to preparing employees to operate and maintain the Tank Farms under normal conditions, the training program ensures that employees are prepared to respond in a prompt and effective manner should abnormal or emergency conditions occur. Emergency response training is consistent with emergency responses outlined in the following Building Emergency Plans: HNF-IP-0263-TF and HNF-=IP-0263-209E.

  2. TWRS privatization support project waste characterization database development. Volume 1

    International Nuclear Information System (INIS)

    Brevick, C.H.

    1995-11-01

    Pacific Northwest National Laboratory requested support from ICF Kaiser Hanford Company in assembling radionuclide and chemical analyte sample data and inventory estimates for fourteen Hanford under-ground storage tanks: 241-AN-102, -104, -105, -106, and -107, 241-AP-102, -104, and -105; 241-AW-101, -103, and -105, 241-AZ-101 and-102; and 241-C-109. Sample data were assembled for sixteen radio nuclides and thirty five chemical analytes. The characterization data were provided to Pacific Northwest National Laboratory in support of the Tank Waste Remediation Services Privatization Support Project. The purpose of this report is to present the results and document the methodology used in preparing the waste characterization information data set to support the Tank Waste Remediation Services Privatization Support Project. This report describes the methodology used in assembling the waste characterization information and how that information was validated by a panel of independent technical reviewers. Also, contained in this report are the various data sets created., the master data set, a subset, and an unreviewed data set

  3. Basalt Waste Isolation Project. Annual report, fiscal year 1980

    International Nuclear Information System (INIS)

    1980-11-01

    During this fiscal year the information available in the fields of geology and hydrology of the Columbia Plateau was consolidated and two reports were issued summarizing this information. In addition, the information on engineered barriers was consolidated and a report summarizing the research to date on waste package development and design of borehole seals was prepared. The waste package studies, when combined with the hydrologic integration, revealed that even under extreme disruptive conditions, a repository in basalt with appropriately designed waste packages can serve as an excellent barrier for containment of radionuclides for the long periods of time required for waste isolation. On July 1, 1980, the first two heater tests at the Near-Surface Test Facility were started and have been successfully operated to this date. The papers on the Near-Surface Test Facility section of this report present the results of the equipment installed and the preliminary results of the testing. In October 1979, the US Department of Energy selected the joint venture of Kaiser Engineers/Parsons Brinckerhoff Quade and Douglas, Inc., to be the architect-engineer to produce a conceptual design of a repository in basalt. During the year, this design has progressed and concept selection has now been completed. This annual report presents a summary of the highlights of the work completed during fiscal year 1980. It is intended to supplement and summarize the nearly 200 papers and reports that have been distributed to date as a part of the Basalt Waste Isolation Project studies

  4. Radioactive waste management. International projects on biosphere modelling

    International Nuclear Information System (INIS)

    Carboneras, P.; Cancio, D.

    1993-01-01

    The paper presents a general overview and discussion on the state of art concerning the biospheric transfer and accumulation of contaminants. A special emphasis is given to the progress achieved in the field of radioactive contaminants and particularly to those implied in radioactive waste disposal. The objectives and advances of the international projects BIOMOVS and VAMP on validation of model predictions are also described. (Author)

  5. Design a Solid Waste Management Course for Primary School focus on Reduce-Reuse-Recycle : Project: WastED – Export of Education, Waste Management - Target market: Vietnam

    OpenAIRE

    Pham, Linh

    2014-01-01

    This product-oriented Bachelor’s thesis looks at waste-management education in primary schools. The primary objective of the study was to design a basic wastemanagement course, concisely packed in a booklet, ready-to-use for teachers and trainers. The outcome of the thesis, the booklet (content of the course) is expected to be used as one of the materials for the WastED project – Export of Education in Waste Management. The study is made up of theory sections and a product design se...

  6. Basalt Waste Isolation Project exploratory shaft site: Final reclamation report

    International Nuclear Information System (INIS)

    Brandt, C.A.; Rickard, W.H. Jr.

    1990-06-01

    The restoration of areas disturbed by activities of the Basalt Waste Isolation Project (BWIP) constitutes a unique operation at the US Department of Energy's (DOE) Hanford Site, both from the standpoint of restoration objectives and the time frame for accomplishing these objectives. The BWIP reclamation program comprises three separate projects: borehole reclamation, Near Surface Test Facility (NSTF) reclamation, and Exploratory Shaft Facility (ESF) reclamation. The main focus of this report is on determining the success of the revegetation effort 1 year after work was completed. This report also provides a brief overview of the ESF reclamation program. 21 refs., 7 figs., 14 tabs

  7. Midwestern High-Level Radioactive Waste Transportation Project

    International Nuclear Information System (INIS)

    1993-01-01

    On February 17,1989, the Midwestern Office of The Council of State Governments and the US Department of Energy entered into a cooperative agreement authorizing the initiation of the Midwestern High-Level Radioactive Waste Transportation Project. The transportation project continued to receive funding from DOE through amendments to the original cooperative agreement, with December 31, 1993, marking the end of the initial 5-year period. This progress report reflects the work completed by the Midwestern Office from February 17,1989, through December 31,1993. In accordance with the scopes of work governing the period covered by this report, the Midwestern Office of The Council of State Governments has worked closely with the Midwestern High-Level Radioactive Waste Committee. Project staff have facilitated all eight of the committee's meetings and have represented the committee at meetings of DOE's Transportation Coordination Group (TCG) and Transportation External Coordination Working Group (TEC/WG). Staff have also prepared and submitted comments on DOE activities on behalf of the committee. In addition to working with the committee, project staff have prepared and distributed 20 reports, including some revised reports (see Attachment 1). Staff have also developed a library of reference materials for the benefit of committee members, state officials, and other interested parties. To publicize the library, and to make it more accessible to potential users, project staff have prepared and distributed regular notices of resource availability

  8. Feasibility of In-Situ Aeration of Old Dumping Ground for Land Reclamation

    Directory of Open Access Journals (Sweden)

    Huan-Huan Tong

    2013-12-01

    Full Text Available Dumping grounds are characterized by the absence of engineering controls such as base liners and cover layer. Consequently, these dumping grounds present risks for surrounding resources such as soil, groundwater and air. The concern for groundwater contamination by leachate from tropical dumping grounds is heightened due to the greater amounts of rainfall and subsequent infiltration and percolation through the waste mass. The emergent demand for old dumping grounds reclamation drives the need to employ remediation technologies. Generally, in-situ aeration is a remediation method that promotes aerobic conditions in the later stage of dumping ground. It accelerates carbon transfer, reduces remaining organic load, and generally shortens the post closure period. However, high rainfall in tropical areas straitens this technique. For example, pollutants could be easily flushed out and more energy should be required to overcome hydrostatic pressure. Although heavy rainfall could supply sufficient water to the substrate and accelerate degradation of organic matter, it may inhibit aerobic activities due to limited air transfer. The waste characterization from Lorong Halus Dumping Ground (closed dumping ground in Singapore showed that the waste materials were stabilized after 22 years closure. According to the Waste Acceptance Criteria set by European Communities Council, the waste materials could be classified as inert wastes. One interesting finding was that leachate layer detected was about of 5 - 8 meter depth, which entirely soaked the waste materials. Hence, the reclamation design and operation should be carefully adjusted according to these characters. Lorong Halus Dumping Ground case study can provide a guideline for other tropical closed landfills or dumping grounds.

  9. Marine disposal of radioactive wastes - the debate

    International Nuclear Information System (INIS)

    Palmer, R.

    1985-01-01

    The paper presents arguments against the marine disposal of radioactive wastes. Results of American studies of deep-water dump-sites, and strontium levels in fish, are cited as providing evidence of the detrimental effects of marine dumping. The London Dumping Convention and the British dumping programme, are briefly discussed. (U.K.)

  10. COIN Project: Towards a zero-waste technology for concrete aggregate production in Norway

    Science.gov (United States)

    Cepuritis, Rolands; Willy Danielsen, Svein

    2014-05-01

    COIN Project: Towards a zero-waste technology for concrete aggregate production in Norway Rolands Cepuritis, Norcem/NTNU and Svein Willy Danielsen, SINTEF Aggregate production is a mining operation where no purification of the "ore" is necessary. Still it is extremely rare that an aggregate production plant is operating on the basis of zero-waste concept. This is since historically the fine crushed aggregate (particles with a size of less than 2, 4 or sometimes 8 mm) has been regarded as a by-product or waste of the more valuable coarse aggregate production. The reason is that the crushed coarse aggregates can easily replace coarse rounded natural stones in almost any concrete composition; while, the situation with the sand is different. The production of coarse aggregate normally yields fine fractions with rough surface texture, flaky or elongated particles an inadequate gradation. When such a material replaces smooth and rounded natural sand grains in a concrete mix, the result is usually poor and much more water and cement has to be used to achieve adequate concrete flow. The consequences are huge stockpiles of the crushed fine fractions that can't be sold (mass balance problems) for the aggregate producers, sustainability problems for the whole industry and environmental issues for society due to dumping and storing of the fine co-generated material. There have been attempts of utilising the material in concrete before; however, they have mostly ended up in failure. There have been attempts to adjust the crushed sand to the properties of the natural sand, which would still give a lot of waste, especially if the grading would have to be adjusted and the high amounts of fines abundantly present in the crushed sand would have to be removed. Another fundamental reason for failure has been that historically such attempts have mainly ended up in a research carried out by people (both industrial and academic) with aggregate background (= parties willing to find market

  11. Corrective Action Investigation Plan for Corrective Action Unit 168: Areas 25 and 26 Contaminated Materials and Waste Dumps, Nevada Test Site, Nevada (Rev. 0) includes Record of Technical Change No. 1 (dated 8/28/2002), Record of Technical Change No. 2 (dated 9/23/2002), and Record of Technical Change No. 3 (dated 6/2/2004)

    Energy Technology Data Exchange (ETDEWEB)

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

    2001-11-21

    This Corrective Action Investigation Plan contains the U.S. Department of Energy, National Nuclear Security Administration Nevada Operations Office's approach to collect data necessary to evaluate corrective action alternatives appropriate for the closure of Corrective Action Unit 168 under the Federal Facility Agreement and Consent Order. Corrective Action Unit 168 consists of a group of twelve relatively diverse Corrective Action Sites (CASs 25-16-01, Construction Waste Pile; 25-16-03, MX Construction Landfill; 25-19-02, Waste Disposal Site; 25-23-02, Radioactive Storage RR Cars; 25-23-18, Radioactive Material Storage; 25-34-01, NRDS Contaminated Bunker; 25-34-02, NRDS Contaminated Bunker; CAS 25-23-13, ETL - Lab Radioactive Contamination; 25-99-16, USW G3; 26-08-01, Waste Dump/Burn Pit; 26-17-01, Pluto Waste Holding Area; 26-19-02, Contaminated Waste Dump No.2). These CASs vary in terms of the sources and nature of potential contamination. The CASs are located and/or associated wit h the following Nevada Test Site (NTS) facilities within three areas. The first eight CASs were in operation between 1958 to 1984 in Area 25 include the Engine Maintenance, Assembly, and Disassembly Facility; the Missile Experiment Salvage Yard; the Reactor Maintenance, Assembly, and Disassembly Facility; the Radioactive Materials Storage Facility; and the Treatment Test Facility Building at Test Cell A. Secondly, the three CASs located in Area 26 include the Project Pluto testing area that operated from 1961 to 1964. Lastly, the Underground Southern Nevada Well (USW) G3 (CAS 25-99-16), a groundwater monitoring well located west of the NTS on the ridgeline of Yucca Mountain, was in operation during the 1980s. Based on site history and existing characterization data obtained to support the data quality objectives process, contaminants of potential concern (COPCs) for CAU 168 are primarily radionuclide; however, the COPCs for several CASs were not defined. To address COPC

  12. PERUBAHAN FISIK KERUANGAN DAN SOSIAL EKONOMI MASYARAKAT DI KAWASAN SEKITAR TEMPAT PEMBUANGAN AKHIR SAMPAH BANTARGEBANG KOTA BEKASI (Physical Environmental and Social Economic Changing in Bantargebang Solid Waste Dumping Site Area Surrounding Bekasi City

    Directory of Open Access Journals (Sweden)

    Nila Kesuma

    2003-07-01

    Full Text Available ABSTRAK Penelitian ini bertujuan untuk mengidentifikasi dan menjelaskan perubahan fisik keruangan dan sosial ekonomi masyarakat di kawasan sekitar TPA Sampah Bantargebang. Metode penelitian yang digunakan adalah gabungan metode kualitatif dengan metode kuantitatif dengan pendekatan rasionalitas, yaitu data dan informasi dilapangan dikomparasikan dengan teori dan konsep yang berhubungan dengan masalah yang diteliti. Hasil penelitian dan pembahasan menunjukkan bahwa: (1 terdapat perubahan fisik keruangan di walayah penelitian yang ditandai dengan bertambahnya area terbangun, yaitu tumbuhnya tempat-tempat permukiman pemulung warung-warung, rumah-rumah penduduk, bertambah panjang dan lebarnya jalan, serta menurunnya kualitas air tanah, udara dan kesuburan lahan; (2 terdapat perubahan pada kondis; sosial masyarakat yang ditandai dengan bertambahnya jumlah penduduk, kegiatan ekonomi atau lapangan kerja, rendahnya angka partisipasi kasar pada setiap tingkat pendidikan, menurunnya derajat kesehatan masyarakat, serta terganggunya kenyamanan lingkungan yang akhirnya mengurangi kesejahteraan masyarakat; (3 terdapat perubahan pada ekonomi penduduk ke arah yang lebih baik, yang ditandai dengan meningkatnya jumlah pendapatan dan terbukanya peluang mengembangkan usaha sampingan. Berdasarkan hal tersebut dapat disimpulkan bahwa bagi lingkungan sekitar dan masyarakat di wilayah penelitian sebara umum keberadaan TPA Sampah Bantargebang lebih memberikan pengaruh negatif daripada positif.   ABSTRACT This research aims to identify and to explain physical spatial and social economic community changing in the Bantargebang Solid Waste Dumping site area  and it surroundings. The research used deductive rational approach, with a combination of quantitative and qualitative methods, i.e. comparison between data and information collected in the field, and the concept and theory related to the subject. The research identified physical, social, and economic changes. The

  13. Progress and Lessons Learned in Transuranic Waste Disposition at The Department of Energy's Advanced Mixed Waste Treatment Project

    International Nuclear Information System (INIS)

    J.D. Mousseau; S.C. Raish; F.M. Russo

    2006-01-01

    This paper provides an overview of the Department of Energy's (DOE) Advanced Mixed Waste Treatment Project (AMWTP) located at the Idaho National Laboratory (INL) and operated by Bechtel BWXT Idaho, LLC(BBWI) It describes the results to date in meeting the 6,000-cubic-meter Idaho Settlement Agreement milestone that was due December 31, 2005. The paper further describes lessons that have been learned from the project in the area of transuranic (TRU) waste processing and waste certification. Information contained within this paper would be beneficial to others who manage TRU waste for disposal at the Waste Isolation Pilot Plant (WIPP)

  14. Project characteristics monitoring report: BWIP (Basalt Waste Isolation Program) repository project

    Energy Technology Data Exchange (ETDEWEB)

    Friedli, E.A.; Herborn, D.I.; Taylor, C.D.; Tomlinson, K.M.

    1988-03-01

    This monitoring report has been prepared to show compliance with provisions of the Nuclear Waste Policy Act of 1982 (NWPA) and to provide local and state government agencies with information concerning the Basalt Waste Isolation Program (BWIP). This report contains data for the time period May 26, 1986 to February 1988. The data include employment figures, salaries, project purchases, taxes and fees paid, worker survey results, and project closedown personal interview summaries. This information has become particularly important since the decision in December 1987 to stop all BWIP activities except those for site reclamation. The Nuclear Waste Policy Amendments Act of 1987 requires nonreclamation work at the Hanford Site to stop as of March 22, 1988. 7 refs., 6 figs., 28 tabs.

  15. Project characteristics monitoring report: BWIP [Basalt Waste Isolation Program] repository project

    International Nuclear Information System (INIS)

    Friedli, E.A.; Herborn, D.I.; Taylor, C.D.; Tomlinson, K.M.

    1988-03-01

    This monitoring report has been prepared to show compliance with provisions of the Nuclear Waste Policy Act of 1982 (NWPA) and to provide local and state government agencies with information concerning the Basalt Waste Isolation Program (BWIP). This report contains data for the time period May 26, 1986 to February 1988. The data include employment figures, salaries, project purchases, taxes and fees paid, worker survey results, and project closedown personal interview summaries. This information has become particularly important since the decision in December 1987 to stop all BWIP activities except those for site reclamation. The Nuclear Waste Policy Amendments Act of 1987 requires nonreclamation work at the Hanford Site to stop as of March 22, 1988. 7 refs., 6 figs., 28 tabs

  16. Project on effects of gas in underground storage facilities for radioactive waste (Pegasus project)

    International Nuclear Information System (INIS)

    Haijtink, B.; McMenamin, T.

    1993-01-01

    Whereas the subject of gas generation and gas release from radioactive waste repositories has gained in interest on the international scene, the Commission of the European Communities has increased its research efforts on this issue. In particular, in the fourth five-year R and D programme on management and storage of radioactive waste (1990-94), a framework has been set up in which research efforts on the subject of gas generation and migration, supported by the CEC, are brought together and coordinated. In this project, called Pegasus, about 20 organizations and research institutes are involved. The project covers theoretical and experimental studies of the processes of gas formation and possible gas release from the different waste types, LLW, ILW and HLW, under typical repository conditions in suitable geological formations such as clay, salt and granite. In this report the present status of the various research activities are described and 13 papers have been selected

  17. Project management plan, Waste Receiving and Processing Facility, Module 1, Project W-026

    Energy Technology Data Exchange (ETDEWEB)

    Starkey, J.G.

    1993-05-01

    The Hanford Waste Receiving and Processing Facility Module 1 Project (WRAP 1) has been established to support the retrieval and final disposal of approximately 400K grams of plutonium and quantities of hazardous components currently stored in drums at the Hanford Site.

  18. Project management plan, Waste Receiving and Processing Facility, Module 1, Project W-026

    International Nuclear Information System (INIS)

    Starkey, J.G.

    1993-05-01

    The Hanford Waste Receiving and Processing Facility Module 1 Project (WRAP 1) has been established to support the retrieval and final disposal of approximately 400K grams of plutonium and quantities of hazardous components currently stored in drums at the Hanford Site

  19. Remaining Sites Verification Package for the 126-B-3, 184-B Coal Pit Dumping Area, Waste Site Reclassification Form 2005-028

    Energy Technology Data Exchange (ETDEWEB)

    L. M. Dittmer

    2006-08-07

    The 126-B-3 waste site is the former coal storage pit for the 184-B Powerhouse. During demolition operations in the 1970s, the site was used for disposal of demolition debris from 100-B/C Area facilities. The site has been remediated by removing debris and contaminated soils. The results of verification sampling demonstrated that residual contaminant concentrations do not preclude any future uses and allow for unrestricted use of shallow zone soils. The results also showed that residual contaminant concentrations are protective of groundwater and the Columbia River.

  20. Remaining Sites Verification Package for the 126-B-3, 184-B Coal Pit Dumping Area. Attachment to Waste Site Reclassification Form 2005-028

    International Nuclear Information System (INIS)

    Dittmer, L.M.

    2006-01-01

    The 126-B-3 waste site is the former coal storage pit for the 184-B Powerhouse. During demolition operations in the 1970s, the site was used for disposal of demolition debris from 100-B/C Area facilities. The site has been remediated by removing debris and contaminated soils. The results of verification sampling demonstrated that residual contaminant concentrations do not preclude any future uses and allow for unrestricted use of shallow zone soils. The results also showed that residual contaminant concentrations are protective of groundwater and the Columbia River

  1. Underground engineering at the Basalt Waste Isolation Project

    International Nuclear Information System (INIS)

    1987-01-01

    A special task group was organized by the US National Committee for Rock Mechanics and the Board on Radioactive Waste Management of the National Research Council to address issues relating to the geotechnical site characterization program for an underground facility to house high-level radioactive waste of the Basalt Waste Isolation Project (BWIP). Intended to provide an overview of the geotechnical program, the study was carried out by a task group consisting of ten members with expertise in the many disciplines required to successfully complete such a project. The task group recognized from the outset that the short time frame of this study would limit its ability to address all geotechnical issues in detail. Geotechnical issues were considered to range from specific technical aspects such as in-situ testing for rock mass permeability; rock hardness testing in the laboratory; or geologic characterizations and quantification of joints, to broader aspects of design philosophy, data collection, and treatment of uncertainty. The task group chose to focus on the broader aspects of underground design and construction, recognizing that the BWIP program utilizes a peer review group on a regular basis which reviews the specific technical questions related to geotechnical engineering. In this way, it was hoped that the review provided by the task group would complement those prepared by the BWIP peer review group

  2. Management of uranium mining and processing wastes at Turamdih project

    International Nuclear Information System (INIS)

    Puri, R.C.; Verma, R.P.

    1991-01-01

    Based on environmental impact assessment, comprehensive plan for management of wastes has been drawn up. No solid waste from the mine is being disposed off outside the project area. The quantity of waste generated after processing of ore is large because of low content of uranium in the ore. A big tailings pond has been planned in specially selected suitable valley near the plant. No liquid effluents are to be discharged into general surrounding environment. Mine water is to be fed to the process plant. Effluents from tailings pond will be collected in a storage cum evaporation pond. All water from different zones of the project shall be collected in zonal ponds and then pumped to tailings effluent storage pond. All the ponds will be provided with requisite impervious liners. The effluents of the storage pond will be treated for removal of radium and manganese and discharged into monitoring pond. Large surface areas for various ponds are envisaged to take advantage of evaporation with aim for zero discharge. To reduce impact from gaseous emissions, high efficiency dust suppression and extraction systems shall be provided. High stacks have been incorporated for DG set, boiler plants, sulphuric acid plant and dust extraction systems for crushing and grinding section and the quality of discharges will be very much within the prescribed limits. The paper describes the management plan in detail. (author)

  3. The Plasma Hearth Process demonstration project for mixed waste treatment

    International Nuclear Information System (INIS)

    Geimer, R.; Dwight, C.; McClellan, G.

    1994-01-01

    The Plasma Hearth Process (PHP) demonstration project is one of the key technology projects in the Department of Energy (DOE) Office of Technology Development (OTD) Mixed Waste Integrated Program (MWIP). Testing to date has yielded encouraging results in displaying potential applications for the PHP technology. Early tests have shown that a wide range of waste materials can be readily processed in the PHP and converted to a vitreous product. Waste materials can be treated in their original container as received at the treatment facility, without pretreatment. The vitreous product, when cooled, exhibits excellent performance in leach resistance, consistently exceeding the Environmental Protection Agency (EPA) Toxicity Characteristic Leaching Procedure (TCLP) requirements. Performance of the Demonstration System during test operations has been shown to meet emission requirements. An accelerated development phase, being conducted at both bench- and pilot-scale on both nonradioactive and radioactive materials, will confirm the viability of the process. It is anticipated that, as a result of this accelerated technology development and demonstration phase, the PHP will be ready for a final field-level demonstration within three years

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

    Energy Technology Data Exchange (ETDEWEB)

    David Duncan

    2011-05-01

    This preliminary project execution plan (PEP) defines U.S. Department of Energy (DOE) project objectives, roles and responsibilities of project participants, project organization, and controls to effectively manage acquisition of capital funds for construction of a proposed remote-handled low-level waste (LLW) disposal facility at the Idaho National Laboratory (INL). The plan addresses the policies, requirements, and critical decision (CD) responsibilities identified in DOE Order 413.3B, 'Program and Project Management for the Acquisition of Capital Assets.' This plan is intended to be a 'living document' that will be periodically updated as the project progresses through the CD process to construction and turnover for operation.

  5. Projection and enterprises controlling in domestic waste water econom

    Directory of Open Access Journals (Sweden)

    Schröder Reinhard

    2000-03-01

    Full Text Available The development of the cost of communal waste water disposal is widely discussed among the population, among politicians and experts. Not only the absolute amount of the charged fees are the cause of concern, but also their increase over the last few years. As part of this thesis, the PC software SloVaKon, which facilitates project and operation decision, will be designed to apply the experience gained during the building and expansion of the waste water industry in Germany´s five new federal states to the conditions in the Slovak republic. For this, a comparison of both country´s topographical, technical, legal and economical conditions proved necessary.

  6. Waste Package Project quarterly report, July 1, 1995--September 30, 1995

    International Nuclear Information System (INIS)

    Ladkany, S.G.

    1995-01-01

    The following tasks are reported: overview and progress of nuclear waste package project and container design; nuclear waste container design considerations; structural investigation of multi purpose nuclear waste package canister; and design requirements of rock tunnel drift for long-term storage of high-level waste (faulted tunnel model study by photoelasticity/finite element analysis)

  7. Functional design criteria radioactive liquid waste line replacement, Project W-087. Revision 3

    International Nuclear Information System (INIS)

    McVey, C.B.

    1994-01-01

    This document provides the functional design criteria for the 222-S Laboratory radioactive waste drain piping and transfer pipeline replacement. The project will replace the radioactive waste drain piping from the hot cells in 222-S to the 219-S Waste Handling Facility and provide a new waste transfer route from 219-S to the 244-S Catch Station in Tank Farms

  8. Mixed and Low-Level Treatment Facility Project. Appendix B, Waste stream engineering files, Part 1, Mixed waste streams

    Energy Technology Data Exchange (ETDEWEB)

    1992-04-01

    This appendix contains the mixed and low-level waste engineering design files (EDFS) documenting each low-level and mixed waste stream investigated during preengineering studies for Mixed and Low-Level Waste Treatment Facility Project. The EDFs provide background information on mixed and low-level waste generated at the Idaho National Engineering Laboratory. They identify, characterize, and provide treatment strategies for the waste streams. Mixed waste is waste containing both radioactive and hazardous components as defined by the Atomic Energy Act and the Resource Conservation and Recovery Act, respectively. Low-level waste is waste that contains radioactivity and is not classified as high-level waste, transuranic waste, spent nuclear fuel, or 11e(2) byproduct material as defined by DOE 5820.2A. Test specimens of fissionable material irradiated for research and development only, and not for the production of power or plutonium, may be classified as low-level waste, provided the concentration of transuranic is less than 100 nCi/g. This appendix is a tool that clarifies presentation format for the EDFS. The EDFs contain waste stream characterization data and potential treatment strategies that will facilitate system tradeoff studies and conceptual design development. A total of 43 mixed waste and 55 low-level waste EDFs are provided.

  9. Waste Tank Vapor Characterization Project: Annual status report for FY 1995

    International Nuclear Information System (INIS)

    Ligotke, M.W.; Fruchter, J.S.; Huckaby, J.L.; Birn, M.B.; McVeety, B.D.; Evans, J.C. Jr.; Pool, K.H.; Silvers, K.L.; Goheen, S.C.

    1995-11-01

    This report compiles information collected during the Fiscal Year 1995 pertaining to the waste tank vapor characterization project. Information covers the following topics: project management; organic sampling and analysis; inorganic sampling and analysis; waste tank vapor data reports; and the waste tanks vapor database

  10. Ecological and human health risk assessment of heavy metal contamination in soil of a municipal solid waste dump in Uyo, Nigeria.

    Science.gov (United States)

    Ihedioha, J N; Ukoha, P O; Ekere, N R

    2017-06-01

    The study assessed the levels of some heavy metals in soils in the vicinity of a municipal solid waste dumpsite with a view to providing information on the extent of contamination, ecological risk of metals in the soils and human health risk to the residents in Uyo. Soil samples were collected in rainy and dry seasons and analyzed for metals (Pb, Cd, Zn, Mn, Cr, Ni and Fe) using atomic absorption spectrometry. The concentrations of heavy metals (mg/kg) at the dumpsite in rainy season were Pb (9.90), Zn (137), Ni (12.56), Cr (3.60), Cd (9.05) and Mn (94.00), while in dry season, the concentrations were Pb (11.80), Zn (146), Ni (11.82), Cr (4.05), Cd (12.20) and Mn (91.20). The concentrations of metals in the studied sites were higher than that of the control site (P contamination than adult.

  11. Radioactive waste management: a series of bibliographies. Radioactive waste inventories and projections. Supplement 1

    International Nuclear Information System (INIS)

    McLaren, L.H.

    1986-01-01

    This bibliography contains information on radioactive waste inventories and projections included in the Department of Energy's Energy Data Base from October 1982 through December 1984. The arrangement is by report number for reports, followed by nonreports in reverse chronological order. These citations are to research reports, journal articles, books, patents, theses, and conference papers from worldwide sources. Five indexes, each preceded by a brief description, are provided: Corporate Author, Personal Author, Subject, Contract Number, and Report Number. 31 abstracts

  12. Mine subsidence control projects associated with solid waste disposal facilities

    International Nuclear Information System (INIS)

    Wood, R.M.

    1994-01-01

    Pennsylvania environmental regulations require applicant's for solid waste disposal permits to provide information regarding the extent of deep mining under the proposed site, evaluations of the maximum subsidence potential, and designs of measures to mitigate potential subsidence impact on the facility. This paper presents three case histories of deep mine subsidence control projects at solid waste disposal facilities. Each case history presents site specific mine grouting project data summaries which include evaluations of the subsurface conditions from drilling, mine void volume calculations, grout mix designs, grouting procedures and techniques, as well as grout coverage and extent of mine void filling evaluations. The case studies described utilized basic gravity grouting techniques to fill the mine voids and fractured strata over the collapsed portions of the deep mines. Grout mixtures were designed to achieve compressive strengths suitable for preventing future mine subsidence while maintaining high flow characteristics to penetrate fractured strata. Verification drilling and coring was performed in the grouted areas to determine the extent of grout coverage and obtain samples of the in-place grout for compression testing. The case histories presented in this report demonstrate an efficient and cost effective technique for mine subsidence control projects

  13. Idaho Nuclear Technology and Engineering Center Newly Generated Liquid Waste Demonstration Project Feasibility Study

    International Nuclear Information System (INIS)

    Herbst, A.K.

    2000-01-01

    A research, development, and demonstration project for the grouting of newly generated liquid waste (NGLW) at the Idaho Nuclear Technology and Engineering Center is considered feasible. NGLW is expected from process equipment waste, decontamination waste, analytical laboratory waste, fuel storage basin waste water, and high-level liquid waste evaporator condensate. The potential grouted waste would be classed as mixed low-level waste, stabilized and immobilized to meet RCRA LDR disposal in a grouting process in the CPP-604 facility, and then transported to the state

  14. Chevron beam dump for ITER edge Thomson scattering system

    International Nuclear Information System (INIS)

    Yatsuka, E.; Hatae, T.; Bassan, M.; Itami, K.; Vayakis, G.

    2013-01-01

    This paper contains the design of the beam dump for the ITER edge Thomson scattering system and mainly concerns its lifetime under the harsh thermal and electromagnetic loads as well as tight space allocation. The lifetime was estimated from the multi-pulse laser-induced damage threshold. In order to extend its lifetime, the structure of the beam dump was optimized. A number of bent sheets aligned parallel in the beam dump form a shape called a chevron which enables it to avoid the concentration of the incident laser pulse energy. The chevron beam dump is expected to withstand thermal loads due to nuclear heating, radiation from the plasma, and numerous incident laser pulses throughout the entire ITER project with a reasonable margin for the peak factor of the beam profile. Structural analysis was also carried out in case of electromagnetic loads during a disruption. Moreover, detailed issues for more accurate assessments of the beam dump's lifetime are clarified. Variation of the bi-directional reflection distribution function (BRDF) due to erosion by or contamination of neutral particles derived from the plasma is one of the most critical issues that needs to be resolved. In this paper, the BRDF was assumed, and the total amount of stray light and the absorbed laser energy profile on the beam dump were evaluated

  15. Chevron beam dump for ITER edge Thomson scattering system

    Energy Technology Data Exchange (ETDEWEB)

    Yatsuka, E.; Hatae, T.; Bassan, M.; Itami, K. [Japan Atomic Energy Agency, 801-1 Mukoyama, Naka, Ibaraki 311-0193 (Japan); Vayakis, G. [ITER Organization, 13115 St Paul Lez Durance Cedex (France)

    2013-10-15

    This paper contains the design of the beam dump for the ITER edge Thomson scattering system and mainly concerns its lifetime under the harsh thermal and electromagnetic loads as well as tight space allocation. The lifetime was estimated from the multi-pulse laser-induced damage threshold. In order to extend its lifetime, the structure of the beam dump was optimized. A number of bent sheets aligned parallel in the beam dump form a shape called a chevron which enables it to avoid the concentration of the incident laser pulse energy. The chevron beam dump is expected to withstand thermal loads due to nuclear heating, radiation from the plasma, and numerous incident laser pulses throughout the entire ITER project with a reasonable margin for the peak factor of the beam profile. Structural analysis was also carried out in case of electromagnetic loads during a disruption. Moreover, detailed issues for more accurate assessments of the beam dump's lifetime are clarified. Variation of the bi-directional reflection distribution function (BRDF) due to erosion by or contamination of neutral particles derived from the plasma is one of the most critical issues that needs to be resolved. In this paper, the BRDF was assumed, and the total amount of stray light and the absorbed laser energy profile on the beam dump were evaluated.

  16. Chevron beam dump for ITER edge Thomson scattering system.

    Science.gov (United States)

    Yatsuka, E; Hatae, T; Vayakis, G; Bassan, M; Itami, K

    2013-10-01

    This paper contains the design of the beam dump for the ITER edge Thomson scattering system and mainly concerns its lifetime under the harsh thermal and electromagnetic loads as well as tight space allocation. The lifetime was estimated from the multi-pulse laser-induced damage threshold. In order to extend its lifetime, the structure of the beam dump was optimized. A number of bent sheets aligned parallel in the beam dump form a shape called a chevron which enables it to avoid the concentration of the incident laser pulse energy. The chevron beam dump is expected to withstand thermal loads due to nuclear heating, radiation from the plasma, and numerous incident laser pulses throughout the entire ITER project with a reasonable margin for the peak factor of the beam profile. Structural analysis was also carried out in case of electromagnetic loads during a disruption. Moreover, detailed issues for more accurate assessments of the beam dump's lifetime are clarified. Variation of the bi-directional reflection distribution function (BRDF) due to erosion by or contamination of neutral particles derived from the plasma is one of the most critical issues that needs to be resolved. In this paper, the BRDF was assumed, and the total amount of stray light and the absorbed laser energy profile on the beam dump were evaluated.

  17. From waste to traffic fuel -projects. Final report

    Energy Technology Data Exchange (ETDEWEB)

    Rasi, S; Lehtonen, E; Aro-Heinilae, E [and others

    2012-11-01

    The main objective of the project was to promote biogas production and its use as traffic fuel. The aims in the four Finnish and two Estonian case regions were to reduce the amount and improve the sustainable use of waste and sludge, to promote biogas production, to start biogas use as traffic fuel and to provide tools for implementing the aims. The results of this study show that achieving the food waste prevention target will decrease greenhouse gas emissions by 415 000 CO{sub 2}-eq tons and result in monetary savings for the waste generators amounting to almost 300 euro/ capita on average in all case regions in 2020. The results show that waste prevention should be the first priority in waste management and the use of waste materials as feedstock for energy production the second priority. In total 3 TWh energy could be produced from available biomass in the studied case regions. This corresponds to the fuel consumption of about 300 000 passenger cars. When a Geographical Information System (GIS) was used to identify suitable biogas plant site locations with particular respect to the spatial distribution of available biomass, it was found that a total of 50 biogas plants with capacity varying from 2.1 to 14.5 MW could be built in the case regions. This corresponds to 2.2 TWh energy and covers from 5 to 40% of the passenger car fuel consumption in these regions. Using all produced biogas (2.2 TWh energy) for vehicle fuel GHG emissions would lead to a 450 000 t CO{sub 2}-eq reduction. The same effect on emissions would be gained if more than 100 000 passenger cars were to be taken off the roads. On average, the energy consumed by biogas plants represents approximately 20% of the produced energy. The results also show that biomethane production from waste materials is profitable. In some cases the biomethane production costs can be covered with the gained gate fees. The cost of biomethane production from agricultural materials is less than 96 euro/MWh{sub th

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

    International Nuclear Information System (INIS)

    1998-01-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1998-05-21

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

  20. Modelling reactive transport in a phosphogypsum dump, Venezia, Italia

    Science.gov (United States)

    Calcara, Massimo; Borgia, Andrea; Cattaneo, Laura; Bartolo, Sergio; Clemente, Gianni; Glauco Amoroso, Carlo; Lo Re, Fabio; Tozzato, Elena

    2013-04-01

    We develop a reactive-transport porous media flow model for a phosphogypsum dump located on the intertidal deposits of the Venetian Lagoon: 1. we construct a complex conceptual and geologic model from field data using the GMS™ graphical user interface; 2. the geological model is mapped onto a rectangular MODFLOW grid; 3. using the TMT2 FORTRAN90 code we translate this grid into the MESH, INCON and GENER input files for the TOUGH2 series of codes; 4. we run TOUGH-REACT to model flow and reactive transport in the dump and the sediments below it. The model includes 3 different dump materials (phosphogypsum, bituminous and hazardous wastes) with the pores saturated by specific fluids. The sediments below the dump are formed by an intertidal sequence of calcareous sands and silts, in addition to clays and organic deposits, all of which are initially saturated with lagoon salty waters. The recharge rain-water dilutes the dump fluids. In turn, the percolates from the dump react with the underlying sediments and the sea water that saturates them. Simulation results have been compared with chemical sampled analyses. In fact, in spite of the simplicity of our model we are able to show how the pH becomes neutral at a short distance below the dump, a fact observed during aquifer monitoring. The spatial and temporal evolution of dissolution and precipitation reactions occur in our model much alike reality. Mobility of some elements, such as divalent iron, are reduced by specific and concurrent conditions of pH from near-neutrality to moderately high values and positive redox potential; opposite conditions favour mobility of potentially toxic metals such as Cr, As Cd and Pb. Vertical movement are predominant. Trend should be therefore heavily influenced by pH and Eh values. If conditions are favourable to mobility, concentration of these substances in the bottom strata could be high. However, simulation suggest that the sediments tend to reduce the transport potential of

  1. Radioactive waste management in Spain: co-ordination and projects

    International Nuclear Information System (INIS)

    2007-01-01

    The sixth workshop of the OECD/NEA Forum on Stakeholder Confidence (FSC) was hosted by ENRESA, the Spanish agency responsible for the management of radioactive waste and the dismantling of nuclear power plants, and the Council of Nuclear Safety (CSN), with the support of the Association of Spanish Municipalities in Areas Surrounding Nuclear Power Plants (AMAC). The workshop took place at L'Hospitalet de l'Infant, Catalonia, Spain, on 21-23 November 2005. At this workshop, Spanish stakeholders and delegates from 14 countries discussed current co-ordination of radioactive waste management decision making in Spain. Findings were shared from Cowam-Spain, a co-operative research project on the involvement of local stakeholders, the relationship between national and local levels of decision making, and the long-term sustainability of decisions regarding the siting of a centralized interim storage facility for high-level waste. These proceedings include the workshop presentations and discussions, as well as the rapporteurs' reflections on what was learned about policy making and participative decision making. (author)

  2. The waste isolation pilot plant project: a changing paradigm

    International Nuclear Information System (INIS)

    Sheppard, L.E.; McFadden, M.H.

    1996-01-01

    The Waste Isolation Pilot Plant (WIPP) is a US Department of Energy (DOE) repository that has been developed to demonstrate the safe and permanent isolation of transuranic radioactive wastes in a deep geologic site. It is located in 650 m below the surface in a bedded salt formation, and is designed to hold approximately 175,500 cubic meters of waste. Compliance with the regulations has become the principal focus for the Project. The scientific baseline is an important and integral part of the CCA, as it provides the foundation for conducting total system performance assessment calculations for comparison with applicable standards. The activities required to support the scientific baseline are being pursued in parallel to minimize the time required to collect, analyze, interpret and fully incorporate the results into the CCA. The DOE has shifted its approach to demonstrating compliance with the applicable regulations from a paradigm of a series of broad investigations to a new paradigm of highly focused activities conducted in parallel. The success of this approach will be assessed by the EPA when the application is critically reviewed

  3. Radiological aspects of sea bed dumping in the deep oceans

    International Nuclear Information System (INIS)

    Templeton, W.L.

    1979-01-01

    In order to control coastal discharges or ocean dumping of any kind of material, it is necessary to determine a release rate. This can only come from a knowledge of the composition and chemical form of the source materials, the distribution and bioavailability of these materials in the ocean ecosystem, the degree and rates of bioaccumulation and the actual or potential use of the ocean resources. With this information release rates within acceptable limits for man and the ecosystem can then be determined. Today, probably the only situations which apply this approach are the controlled disposal of radioactive wastes. In this paper a recent radiological assessment of the dumping of packaged radioactive wastes on the seabed is discussed and some environmental aspects of the United States Department of Energy program are described examining the feasibility of the emplacement of contained radioactive wastes within the deep ocean sediments

  4. Combustion of Waste Wood. Second phase of the collaboration project on waste wood combustion

    International Nuclear Information System (INIS)

    Andersson, Annika; Andersson, Christer; Eriksson, Jan; Hemstroem, Bengt; Jungstedt, Jenny; Kling, Aasa; Bahr, Bo von; Ekvall, Annika; Eskilsson, David; Tullin, Claes; Harnevie, Henrik; Sieurin, Jan; Keihaes, Juha; Mueller, Christian; Berg, Magnus; Wikman, Karin

    2003-08-01

    Combustion of waste wood has during the last decade increased dramatically and this has resulted in a number of Swedish plants using this fuel, e.g. Handeloe P11 (Norrkoeping) and ldbaecken P3 (Nykoeping), and yet other plants that are under construction (e.g. Nynaeshamn). The experience from these plants are that waste wood combustion results in a number of operational problems. To some extent these problems are different compared with the problems related to combustion of other biofuels but the situation is not directly comparable to waste incinerators. The problems are mainly related to slagging and fouling of heat exchanger surfaces and accelerated corrosion at relatively low temperature compared to the situation for ordinary biofuels. In some cases an increase in the emissions of specific substances can also result in difficulties to fulfil the EC-directive on waste combustion. Within previous projects the main problems related to combustion of waste wood have been identified and to some extent the cause of these problems has been clarified. One result of this reported investigation is a deeper understanding of the actual causes of these problems. However, the most important result is a number of recommendations for different measures on how to achieve disturbance-free combustion of waste wood. These recommendations actually summarises the most important possible solutions on how to achieve a disturbance-free operation and a lower maintenance cost for boilers combusting waste wood and can thereby be regarded as a short summery of the whole project: 1) Improving fuel quality by Improved sorting at the source and Sieving of the fuel -> Reducing the amount of metals and chlorine and Separation of fines and thereby reducing the amount of metals. 2) Combustion modifications by Avoiding reducing conditions at the heat exchanger surfaces -> Minimising slagging, fouling and corrosion. 3) Additives or co-combustion by Addition of sulphur with the fuel; Injection of

  5. Agency for Nuclear Projects/Nuclear Waste Project Office final progress report

    International Nuclear Information System (INIS)

    1992-01-01

    The Nevada Agency for Nuclear Projects/Nuclear Waste Project Office (NWPO) was formally established by Executive Policy in 1983 following passage of the federal Nuclear Waste Policy Act of 1982 (Act). That Act provides for the systematic siting, construction, operation, and closure of high-level radioactive defense and research by-products and other forms of high-level radioactive waste from around the country which will be stored at such repositories. In 1985 the Nevada legislature formally established the NWPO as a distinct and statutorily authorized agency to provide support to the Governor and State Legislature on matters concerning the high-level nuclear waste programs. The NWPO utilized a small, central staff supplemented by contractual services for needed technical and specialized expertise in order to provide high quality oversight and monitoring of federal activities, to conduct necessary independent studies, and to avoid unnecessary duplication of efforts. This report summarizes the results of this ongoing program to ensure that risks to the environment and to human safety are minimized. It includes findings in the areas of hydrogeology, geology, quality assurance activities, repository engineering, legislature participation, socioeconomic affects, risk assessments, monitoring programs, public information dissemination, and transportation activities. The bulk of the reporting deals with the Yucca Mountain facility

  6. Process Knowledge Characterization of Radioactive Waste at the Classified Waste Landfill Remediation Project Sandia National Laboratories, Albuquerque, New Mexico

    International Nuclear Information System (INIS)

    DOTSON, PATRICK WELLS; GALLOWAY, ROBERT B.; JOHNSON JR, CARL EDWARD

    1999-01-01

    This paper discusses the development and application of process knowledge (PK) to the characterization of radioactive wastes generated during the excavation of buried materials at the Sandia National Laboratories/New Mexico (SNL/NM) Classified Waste Landfill (CWLF). The CWLF, located in SNL/NM Technical Area II, is a 1.5-acre site that received nuclear weapon components and related materials from about 1950 through 1987. These materials were used in the development and testing of nuclear weapon designs. The CWLF is being remediated by the SNL/NM Environmental Restoration (ER) Project pursuant to regulations of the New Mexico Environment Department. A goal of the CWLF project is to maximize the amount of excavated materials that can be demilitarized and recycled. However, some of these materials are radioactively contaminated and, if they cannot be decontaminated, are destined to require disposal as radioactive waste. Five major radioactive waste streams have been designated on the CWLF project, including: unclassified soft radioactive waste--consists of soft, compatible trash such as paper, plastic, and plywood; unclassified solid radioactive waste--includes scrap metal, other unclassified hardware items, and soil; unclassified mixed waste--contains the same materials as unclassified soft or solid radioactive waste, but also contains one or more Resource Conservation and Recovery Act (RCRA) constituents; classified radioactive waste--consists of classified artifacts, usually weapons components, that contain only radioactive contaminants; and classified mixed waste--comprises radioactive classified material that also contains RCRA constituents. These waste streams contain a variety of radionuclides that exist both as surface contamination and as sealed sources. To characterize these wastes, the CWLF project's waste management team is relying on data obtained from direct measurement of radionuclide activity content to the maximum extent possible and, in cases where

  7. The new Wallula CO2 project may revive the old Columbia River Basalt (western USA) nuclear-waste repository project

    Science.gov (United States)

    Schwartz, Michael O.

    2018-02-01

    A novel CO2 sequestration project at Wallula, Washington, USA, makes ample use of the geoscientific data collection of the old nuclear waste repository project at the Hanford Site nearby. Both projects target the Columbia River Basalt (CRB). The new publicity for the old project comes at a time when the approach to high-level nuclear waste disposal has undergone fundamental changes. The emphasis now is on a technical barrier that is chemically compatible with the host rock. In the ideal case, the waste container is in thermodynamic equilibrium with the host-rock groundwater regime. The CRB groundwater has what it takes to represent the ideal case.

  8. Can we talk? Communications management for the Waste Isolation Pilot Plant, a complex nuclear waste management project

    Energy Technology Data Exchange (ETDEWEB)

    Goldstein, S.A.; Pullen, G.M.; Brewer, D.R.

    1995-07-01

    Sandia Nuclear Waste Management Program is pursuing for DOE an option for permanently disposing radioactive waste in deep geologic repositories. Included in the Program are the Waste Isolation Pilot Plant (WIPP) Project for US defense program mixed waste the Yucca Mountain Project (YMP) for spent power reactor fuel and vitrified high-level waste, projects for other waste types, and development efforts in environmental decision support technologies. WIPP and YMP are in the public arena, of a controversial nature, and provide significant management challenges. Both projects have large project teams, multiple organization participants, large budgets, long durations, are very complex, have a high degree of programmatic risk, and operate in an extremely regulated environment requiring legal defensibility. For environmental projects like these to succeed, SNL`s Program is utilizing nearly all areas in PMI`s Project Management Body of Knowledge (PMBOK) to manage along multiple project dimensions such as the physical sciences (e.g., geophysics and geochemistry; performance assessment; decision analysis) management sciences (controlling the triple constraint of performance, cost and schedule), and social sciences (belief systems; public participation; institutional politics). This discussion focuses primarily on communication challenges active on WIPP. How is the WIPP team meeting the challenges of managing communications?`` and ``How are you approaching similar challenges?`` will be questions for a dialog with the audience.

  9. Can we talk? Communications management for the Waste Isolation Pilot Plant, a complex nuclear waste management project

    International Nuclear Information System (INIS)

    Goldstein, S.A.; Pullen, G.M.; Brewer, D.R.

    1995-01-01

    Sandia Nuclear Waste Management Program is pursuing for DOE an option for permanently disposing radioactive waste in deep geologic repositories. Included in the Program are the Waste Isolation Pilot Plant (WIPP) Project for US defense program mixed waste the Yucca Mountain Project (YMP) for spent power reactor fuel and vitrified high-level waste, projects for other waste types, and development efforts in environmental decision support technologies. WIPP and YMP are in the public arena, of a controversial nature, and provide significant management challenges. Both projects have large project teams, multiple organization participants, large budgets, long durations, are very complex, have a high degree of programmatic risk, and operate in an extremely regulated environment requiring legal defensibility. For environmental projects like these to succeed, SNL's Program is utilizing nearly all areas in PMI's Project Management Body of Knowledge (PMBOK) to manage along multiple project dimensions such as the physical sciences (e.g., geophysics and geochemistry; performance assessment; decision analysis) management sciences (controlling the triple constraint of performance, cost and schedule), and social sciences (belief systems; public participation; institutional politics). This discussion focuses primarily on communication challenges active on WIPP. How is the WIPP team meeting the challenges of managing communications?'' and ''How are you approaching similar challenges?'' will be questions for a dialog with the audience

  10. Large scale waste combustion projects. A study of financial structures and sensitivities

    International Nuclear Information System (INIS)

    Brandler, A.

    1993-01-01

    The principal objective of the study was to determine the key contractual and financial aspects of large scale energy-from-waste projects, and to provide the necessary background information on financing to appreciate the approach lenders take when they consider financing waste combustion projects. An integral part of the study has been the preparation of a detailed financial model, incorporating all major financing parameters, to assess the economic and financial viability of typical waste combustion projects. (author)

  11. 324 Building liquid waste handling and removal system project plan

    Energy Technology Data Exchange (ETDEWEB)

    Ham, J.E.

    1998-07-29

    This report evaluates the modification options for handling radiological liquid waste generated during decontamination and cleanout of the 324 Building. Recent discussions indicate that the Hanford site railroad system will be closed by the end of FY 1998 necessitating the need for an alternate transfer method. The issue of handling of Radioactive Liquid Waste (RLW) from the 324 Building (assuming the 340 Facility is not available to accept the RLW) has been examined in at least two earlier engineering studies (Parsons 1997a and Hobart 1997). Each study identified a similar preferred alternative that included modifying the 324 Building RLWS to allow load-out of wastewater to a truck tanker, while making maximum use of existing piping, tanks, instrumentation, controls and other features to minimize costs and physical changes to the building. This alternative is accepted as the basis for further discussion presented in this study. The goal of this engineering study is to verify the path forward presented in the previous studies and assure that the selected alternative satisfies the 324 Building deactivation goals and objectives as currently described in the project management plan. This study will also evaluate options available to implement the preferred alternative and select the preferred option for implementation of the entire system. Items requiring further examination will also be identified. Finally, the study will provide a conceptual design, schedule and cost estimate for the required modifications to the 324 Building to allow removal of RLW. Attachment 5 is an excerpt from the project baseline schedule found in the Project Management Plan.

  12. Otter Brook Lake, New Hampshire Connecticut River Basin, Flood Control Project, Solid Waste Management Plan

    National Research Council Canada - National Science Library

    1996-01-01

    .... This plan provides guidance to establish policies, and responsibilities, procedures, and instructions for proper handling, storage, disposal and recycling of solid waste generated at the flood control project...

  13. Pioneer vegetation on ash dumps in Oswiecim (southern Poland)

    Energy Technology Data Exchange (ETDEWEB)

    Bojarczuk, T.; Kuczynski, B.

    1972-01-01

    The authors found fifty-three plant species growing on the ash dumps in Oswiecim, while in 1963 twenty-two species only were encountered there. Most of the self-sown plants belong to calciphilous, ruderal and xerophilous species. The pH of the ashes amounts to 9.5. Some of them, e.g. Matricaria chamomilla are index plants for acid habitats; others were hitherto encountered in wet habitats, e.g. Rumex obtusifolias, Myricaria germanica, Epilobium roseum, and others. Their occurrence on ash dumps is possible thanks to the considerable amount of precipitation (465 mm) during the vegetative period. The mosses are the pioneers of these dumps, e.g. Funaria hygromertrica and Bryum argenteum, which usually appear on the site of fire. The authors are of the opinion that a better knowledge of the plants appearing spontaneously on dumps and waste heaps may provide many useful conclusions which will help to obtain positive results at the recultivation of spoil heaps and industrial wastes. 9 references, 3 tables.

  14. Beam-dump kicker magnets

    International Nuclear Information System (INIS)

    Bulos, F.; Odian, A.; Tomlin, B.

    1983-01-01

    The beam-dump kicker magnets are located in the final focus region and, in conjunction with septum magnets, extract the beams after they have passed the interaction point (IP) and direct them to their respective dumps. Two schemes for these kickers have been under consideration; ferrite transmission line magnets utilizing technology common with damping rings and positron target kickers, and current loop magnets which are possible only for the dump kickers, where the rise time of the magnetic pulse can be comparatively longer; approximately 400 nanoseconds as compared with 50 nanoseconds for the others. A prototype ferrite kicker has been built and is undergoing tests. Since the current loop requires lower voltage and power plus some additional savings in cost, we decided to build and test a prototype. This note describes in detail an optimized design for the current loop magnets and their associated pulse circuitry

  15. Efficiency of Low-Profile External Dumping at Open Pit Coal Mining in Kemerovo Region

    Science.gov (United States)

    Selyukov, Alexey; Ermolaev, Vyacheslav; Kostinez, Irina

    2017-11-01

    Kemerovo region is one of the largest industrial regions of Russia, with a raw material specialization. The rapid growth of the coal industry in recent years has been greatly facilitated by the expansion and development of open pit mining for coal seams extraction, accompanied by an increase in the volumes of overburden and the height of the dumps. There are about 400 objects in the Russian Federation Government Register of Waste Disposal Facilities 80% of which are dumps. Approaches both to external dumping and to the technical stage of reclamation currently contribute to the growth of geomorphic system's instability. Thus, it is proposed to slightly change the approaches to external dumping: the essence consists in the formation of an external dump of overburden, which in future would represent a favorable landscape unit of a flat surface relief used for subsequent differently directed purposes.

  16. Efficiency of Low-Profile External Dumping at Open Pit Coal Mining in Kemerovo Region

    Directory of Open Access Journals (Sweden)

    Selyukov Alexey

    2017-01-01

    Full Text Available Kemerovo region is one of the largest industrial regions of Russia, with a raw material specialization. The rapid growth of the coal industry in recent years has been greatly facilitated by the expansion and development of open pit mining for coal seams extraction, accompanied by an increase in the volumes of overburden and the height of the dumps. There are about 400 objects in the Russian Federation Government Register of Waste Disposal Facilities 80% of which are dumps. Approaches both to external dumping and to the technical stage of reclamation currently contribute to the growth of geomorphic system's instability. Thus, it is proposed to slightly change the approaches to external dumping: the essence consists in the formation of an external dump of overburden, which in future would represent a favorable landscape unit of a flat surface relief used for subsequent differently directed purposes.

  17. Hanford Waste Simulants Created to Support the Research and Development on the River Protection Project - Waste Treatment Plant

    Energy Technology Data Exchange (ETDEWEB)

    Eibling, R.E.

    2001-07-26

    The development of nonradioactive waste simulants to support the River Protection Project - Waste Treatment Plant bench and pilot-scale testing is crucial to the design of the facility. The report documents the simulants development to support the SRTC programs and the strategies used to produce the simulants.

  18. Waste hydrogen utilization project receives $12 M in federal support

    Energy Technology Data Exchange (ETDEWEB)

    Anon.

    2005-10-01

    This article announced that $12.2 million dollars in federal funding support, over a 3 year period, will be made available to Sacre-Davey Innovations to support the development and demonstration of the Integrated Waste Hydrogen Utilization Project (IWHUP). The IWHUP is a clean energy project that will develop and demonstrate the feasibility of using hydrogen generated as a byproduct of a sodium chlorate manufacturing plant in North Vancouver. Greenhouse gas emissions and fossil fuels will be reduced by using purified hydrogen to fuel vehicles. The full hydrogen value chain will also be demonstrated by the IWHUP. This includes the supply, storage, distribution and use of hydrogen. Eight light-duty trucks running on hydrogen will be included in the demonstration, along with 4 public transit buses converted to run on a combination of compressed natural gas and hydrogen, and a fuel cell system operating on hydrogen while providing electrical power to a car wash. The newsletter article discussed the funding leveraged from various sources as well as the names of project participants. The article also mentioned that the IWHUP fuel station in North Vancouver will play a key role in sustainable transportation demonstrations during the 2010 Olympic and Paralympic Winter Games in Vancouver.

  19. Grouts and concretes for the Waste Isolation Pilot Project (WIPP)

    International Nuclear Information System (INIS)

    Wakeley, L.D.

    1990-01-01

    The Structures Laboratory of the U.S. Army Engineer Waterways Experiment Station has conducted research on cement-based composites for the Waste Isolation Pilot Project (WIPP) since 1977, in cooperation with Sandia National Laboratories. Field testing requirements guided initial development of grouts. Concurrent and later laboratory studies explored the chemical stability and probable durability of these mixtures. Beginning in 1985, a series of small-scale seal performance tests at the WIPP prompted development of an expansive salt-saturated concrete. Important lessons learned from this ongoing work include: (1) carefully tailored mixtures can tolerate phase changes involving Ca, Al, and SO 4 , without loss of structural integrity; (2) handling and placement properties are probably more crucial to the mixtures than is exact phase composition; and (3) for the environment of a geologic repository, demonstrated chemical durability will be the best indicator of long-term performance

  20. Projected transuranic waste loads requiring treatment, storage, and disposal

    International Nuclear Information System (INIS)

    Hong, K.; Kotek, T.

    1996-01-01

    This paper provides information on the volume of TRU waste loads requiring treatment, storage, and disposal at DOE facilities for three siting configurations. Input consisted of updated inventory and generation data from. Waste Isolation Pilot plant Transuranic Waste Baseline Inventory report. Results indicate that WIPP's design capacity is sufficient for the CH TRU waste found throughout the DOE Complex

  1. Final Hanford Site Transuranic (TRU) Waste Characterization Qualit Assurance Project Plan

    International Nuclear Information System (INIS)

    GREAGER, T.M.

    1999-01-01

    The Transuranic Waste Characterization Quality Assurance Program Plan required each U.S. Department of Energy (DOE) site that characterizes transuranic waste to be sent the Waste Isolation Pilot Plan that addresses applicable requirements specified in the quality assurance project plan (QAPP)

  2. Capacity building in solid waste management in Argentina

    Energy Technology Data Exchange (ETDEWEB)

    McBean, E. A.; Del Rosso, E.; Schoemaker, H.

    2002-03-01

    To assist in climate change protection and to improve solid waste management practices, a project in being undertaken in Tucuman, Argentina's fifth largest city, with funding from the Climate Change Early Action Fund, the Government of Canada and from Conestoga-Rovers and Associates. The demonstration project covers the wastes for purposes of accelerating landfill gas production, thereby improving options for utilizing landfill gas as an energy source, and providing climate change protection by transforming methane to carbon dioxide, which is substantially less powerful as a global warming gas. Prior to the project, refuse was dumped directly into an uncontrolled dump or the adjacent Sali River, or burnt, releasing noxious gases to the atmosphere. The primary objective of the energy cell project involved the collection of refuse and placement in energy cells. The energy cells are operated as bioreactors to accelerate the generation of landfill gas. The project included placement of a comprehensive bottom liner system, leachate collection, preparation of the refuse, a leachate recirculation system, a gas collection system, and a flexible top membrane liner. The emphasis of the energy cell project is to demonstrate the opportunities available, which could influence the viability of energy recovery and possible greenhouse gas credits. After only a few months of direct learning from the energy cell project, solid waste management in Tucuman has been decisively reversed. There is no longer any uncontrolled dumping and implementation of a modern solid waste management system is well under way.

  3. Biohydrogen production by anaerobic fermentation of waste. Final project report

    Energy Technology Data Exchange (ETDEWEB)

    Karakashev, D.; Angelidaki, I.

    2009-01-15

    The objective of this project was to investigate and increase dark fermentative hydrogen production from organic wastes by optimizing important process parameters (reactor type, pH, temperature, organic loading, retention time, inoculation strategy, microbial composition). Labscale experiments were carried out at the Department of Environmental Engineering, Technical University of Denmark. A two steps process for hydrogen production in the first step and methane production in the second step in serial connected fully mixed reactors was developed and could successfully convert organic matter to approx. 20-25 % hydrogen and 15-80 % to methane. Sparging with methane produced in the second stage could significantly increase the hydrogen production. Additionally it was shown that upflow anaerobic sludge blanket (UASB) reactor system was very promising for high effective biohydrogen production from glucose at 70 deg C. Glucose-fed biofilm reactors filled with plastic carriers demonstrated high efficient extreme thermophilic biohydrogen production with mixed cultures. Repeated batch cultivations via exposure of the cultures to increased concentrations of household solid waste was found to be most useful method to enhance hydrogen production rate and reduce lag phase of extreme thermophilic fermentation process. Low level of pH (5.5) at 3-day HRT was enough to inhibit completely the methanogenesis and resulted in stable extreme thermophilic hydrogen production. Homoacetogenisis was proven to be an alternative competitor to biohydrogen production from organic acids under thermophilic (55 deg. C) conditions. With respect to microbiology, 16S rRNA targeted oligonucleotide probes were designed to monitor the spatial distribution of hydrogen producing bacteria in sludge and granules from anaerobic reactors. An extreme thermophilic (70 deg. C), strict anaerobic, mixed microbial culture with high hydrogen producing potential was enriched from digested household waste. Culture

  4. Project report for the commercial disposal of mixed low-level waste debris

    International Nuclear Information System (INIS)

    Andrews, G.; Balls, V.; Shea, T.; Thiesen, T.

    1994-05-01

    This report summarizes the basis for the commercial disposal of Idaho National Engineering Laboratory (INEL) mixed low-level waste (MLLW) debris and the associated activities. Mixed waste is radioactive waste plus hazardous waste as defined by the Resource Conservation and Recovery Act (RCRA). The critical factors for this project were DOE 5820.2A exemption, contracting mechanism, NEPA documentation, sampling and analysis, time limitation and transportation of waste. This report also will provide a guide or a starting place for future use of Envirocare of Utah or other private sector disposal/treatment facilities, and the lessons learned during this project

  5. Project report for the commercial disposal of mixed low-level waste debris

    Energy Technology Data Exchange (ETDEWEB)

    Andrews, G.; Balls, V.; Shea, T.; Thiesen, T.

    1994-05-01

    This report summarizes the basis for the commercial disposal of Idaho National Engineering Laboratory (INEL) mixed low-level waste (MLLW) debris and the associated activities. Mixed waste is radioactive waste plus hazardous waste as defined by the Resource Conservation and Recovery Act (RCRA). The critical factors for this project were DOE 5820.2A exemption, contracting mechanism, NEPA documentation, sampling and analysis, time limitation and transportation of waste. This report also will provide a guide or a starting place for future use of Envirocare of Utah or other private sector disposal/treatment facilities, and the lessons learned during this project.

  6. Status of Pantex Plant Waste Management Project/program control system

    International Nuclear Information System (INIS)

    Price, Wesley J.; Matthews, William L.

    1992-01-01

    During a December 1990 Waste Management Program Review held in Albuquerque, New Mexico, the Waste Management and Operational Surety Division (WMOSD) introduced the project control system to be used for the Waste Management (WM) Operations Program. The system was entitled 'TRAC-WM' (Tracking and Control for Waste Management). The stated objective for this system was to establish a frame work for planning, managing, and controlling work within the WM program. As a result Mason and Hanger (the operating contractor at the Pantex Plant) initiated the development of a computerized waste management project tracking system. (author)

  7. Expedited technology demonstration project (Revised mixed waste management facility project) Project baseline revision 4.0 and FY98 plan

    International Nuclear Information System (INIS)

    Adamson, M. G.

    1997-01-01

    The re-baseline of the Expedited Technology Demonstration Project (Revised Mixed Waste Facility Project) is designated as Project Baseline Revision 4.0. The last approved baseline was identified as Project Baseline Revision 3.0 and was issued in October 1996. Project Baseline Revision 4.0 does not depart from the formal DOE guidance followed by, and contained in, Revision 3.0. This revised baseline document describes the MSO and Final Forms testing activities that will occur during FY98, the final year of the ETD Project. The cost estimate for work during FY98 continues to be $2.OM as published in Revision 3.0. However, the funds will be all CENRTC rather than the OPEX/CENTRC split previously anticipated. LLNL has waived overhead charges on ETD Project CENRTC funds since the beginning of project activities. By requesting the $2.OM as all CENTRC a more aggressive approach to staffing and testing can be taken. Due to a cost under- run condition during FY97 procurements were made and work was accomplished, with the knowledge of DOE, in the Feed Preparation and Final Forms areas that were not in the scope of Revision 3.0. Feed preparation activities for FY98 have been expanded to include the drum opening station/enclosure previously deleted

  8. Environmental impact of differently remediated hard coal overburden and tailings dumps a few decades after remediation

    International Nuclear Information System (INIS)

    Willscher, S.; Felix, M.; Sohr, A.

    2010-01-01

    Coal mining in the Saxony region of Germany has caused heavy metal and arsenic pollution in adjacent groundwater and surface waters. Coal waste dumping sites are leaching heavy metals and metalloids in the form of fine precipitates into local rivers. This paper studied the different remediation strategies used at 3 different dump sites in the area. The aim of the study was to determine the environmental impact of the dumps and evaluate the long-term effects of remediation measures. The dumps consisted of coarse to fine-grained materials from former processing activities, and contained pyrite in varying concentrations. Samples from different depth as well as groundwater samples were taken from the sites and investigated for their mechanical, geological, geochemical, biogeochemical, and physico-chemical characteristics. Seepage formation rates and contaminant loads at the dump sites were compared. The study showed that the revegetation of dump surfaces can help to prevent against erosion, but cannot prevent acid mine drainage (AMD) generation. The additional seals and covers placed at 2 of the dumps resulted in a high reduction of seepage waters, and almost no acidification of dump materials. 5 refs., 1 fig.

  9. Down in the dumps - cheerfully

    International Nuclear Information System (INIS)

    Ruhmer, W.T.

    1984-01-01

    Scavenging gold and uranium from the sands dumps and slimes dams is a highly profitable operation. In a few pages the author summarises some of the permutations and combinations of the various processes employed by South African concerns to achieve economic results

  10. Egg dumping by predatory insects

    Czech Academy of Sciences Publication Activity Database

    Corbani, A. C.; Ferrer, A.; Dixon, Anthony F. G.; Hemptinne, J. L.

    2011-01-01

    Roč. 36, č. 3 (2011), s. 290-293 ISSN 0307-6962 Institutional research plan: CEZ:AV0Z60870520 Keywords : Egg dumping * ladybird beetles * oocyte resorption * trophic egg Subject RIV: EH - Ecology, Behaviour Impact factor: 1.330, year: 2011

  11. Spent fuel and radioactive waste inventories and projections as of December 31, 1980

    International Nuclear Information System (INIS)

    1981-09-01

    Current inventories and characteristics of commercial spent fuels and both commercial and US Department of Energy radioactive wastes were compiled, based on the most reliable information available from Government sources and the open literature, technical reports, and direct contacts. Future waste generation rates and characteristics of these materials to be accumulated over the remainder of this century are also presented, based on a present DOE/EIA projection of US commercial nuclear power growth and expected defense-related and industrial and institutional activities. Materials considered, on a chapter-by-chapter basis, are: spent fuel, high-level wastes, transuranic waste, low-level waste, remedial action waste, active uranium mill tailings, and airborne waste. For each category, current and projected inventories are given through the year 2000. The land usage requirements are given for storage/disposal of low-level and transuranic wastes, and for the present inventories of inactive uranium mill tailings

  12. Los Alamos National Laboratory transuranic waste quality assurance project plan. Revision 1

    International Nuclear Information System (INIS)

    1997-01-01

    This Transuranic (TRU) Waste Quality Assurance Project Plan (QAPjP) serves as the quality management plan for the characterization of transuranic waste in preparation for certification and transportation. The Transuranic Waste Characterization/Certification Program (TWCP) consists of personnel who sample and analyze waste, validate and report data; and provide project management, quality assurance, audit and assessment, and records management support, all in accordance with established requirements for disposal of TRU waste at the Waste Isolation Pilot Plant (WIPP) facility. This QAPjP addresses how the TWCP meets the quality requirements of the Carlsbad Area Office (CAO) Quality Assurance Program Description (QAPD) and the technical requirements of the Transuranic Waste Characterization Quality Assurance Program Plan (QAPP). The TWCP characterizes and certifies retrievably stored and newly generated TRU waste using the waste selection, testing, sampling, and analytical techniques and data quality objectives (DQOs) described in the QAPP, the Los Alamos National Laboratory Transuranic Waste Certification Plan (Certification Plan), and the CST Waste Management Facilities Waste Acceptance Criteria and Certification [Los Alamos National Laboratory (LANL) Waste Acceptance Criteria (WAC)]. At the present, the TWCP does not address remote-handled (RH) waste

  13. 30 CFR 77.1608 - Dumping facilities.

    Science.gov (United States)

    2010-07-01

    ... 30 Mineral Resources 1 2010-07-01 2010-07-01 false Dumping facilities. 77.1608 Section 77.1608 Mineral Resources MINE SAFETY AND HEALTH ADMINISTRATION, DEPARTMENT OF LABOR COAL MINE SAFETY AND HEALTH... Haulage § 77.1608 Dumping facilities. (a) Dumping locations and haulage roads shall be kept reasonably...

  14. Solid waste information and tracking system server conversion project management plan

    International Nuclear Information System (INIS)

    MAY, D.L.

    1999-01-01

    The Project Management Plan governing the conversion of Solid Waste Information and Tracking System (SWITS) to a client-server architecture. The Solid Waste Information and Tracking System Project Management Plan (PMP) describes the background, planning and management of the SWITS conversion. Requirements and specification documentation needed for the SWITS conversion will be released as supporting documents

  15. Basalt waste isolation project. Quarterly report, April 1, 1981-June 30, 1981

    Energy Technology Data Exchange (ETDEWEB)

    Deju, R.A.

    1981-08-01

    This document reports progress made in the Basalt Waste Isolation Project during the third quarter of fiscal year 1981. Efforts are described for the following programs of the project work breakdown structure: systems; waste package; site; repository; regulatory and institutional; test facilities; in situ test facilities.

  16. Electric Energy production through Municipal solid wastes

    International Nuclear Information System (INIS)

    Agorio Comas, M.; Chediak Nunez, M.; Galan Prado, A.

    2010-01-01

    The main objective in this investment Project is to improve the integral management of urban solid waste in the city of Salto, Uruguay, obtaining favorable results for the environment and society, contributing moreover in Sustainable Development.First of all, it is recommended the remediation of the current Open air Municipal dumping site. Simultaneously with the Remediation process, a controlled dumping site with daily covers of the compacted solid waste has been designed, as a transition methodology with a lifetime of 3 years approximately.In addition to this, two sanitary landfills are designed wits29h a total lifetime of 7 years, for the operation after the controlled dumping site is closed. There is also a leachate treatment system to process the effluents of the landfills. In order to optimize the use of the landfills, is proposed the simultaneous implementation of a Separated Urban Solid Waste Collection System (SisRReVa). This consist in separating the Valuable Waste (VW) from wet or organic solid waste in origin (home, stores,etc)and collecting it separately.The VW are separated by type (paper, board, glass, plastic and metal) in a Valuable Waste Classification Plant. This plant is designed to process the VW generated in Salto and collected by the SisRReVa for about ten years from now on. (Author)

  17. Characterization of low-level waste from the industrial sector, and near-term projection of waste volumes and types

    International Nuclear Information System (INIS)

    MacKenzie, D.R.

    1988-01-01

    A telephone survey of low-level waste generators has been carried out in order to make useful estimates of the volume and nature of the waste which the generators will be shipping for disposal when the compacts and states begin operating new disposal facilities. Emphasis of the survey was on the industrial sector, since there has been little information available on characteristics of industrial LLW. Ten large industrial generators shipping to Richland, ten shipping to Barnwell, and two whose wastes had previously been characterized by BNL were contacted. The waste volume shipped by these generators accounted for about two-thirds to three-quarters of the total industrial volume. Results are given in terms of the categories of LLW represented and of the chemical characteristics of the different wastes. Estimates by the respondents of their near-term waste volume projections are presented

  18. Characterization of low-level waste from the industrial sector, and near-term projection of waste volumes and types

    International Nuclear Information System (INIS)

    MacKenzie, D.R.

    1988-01-01

    A telephone survey of low-level waste generators has been carried out in order to make useful estimates of the volume and nature of the waste which the generators are shipping for disposal when the compacts and states begin operating new disposal facilities. Emphasis of the survey was on the industrial sector, since there has been little information available on characteristics of industrial LLW. Ten large industrial generators shipping to Richland, ten shipping to Barnwell, and two whose wastes had previously been characterized by BNL were contacted. The waste volume shipped by these generators accounted for about two-thirds to three-quarters of the total industrial volume. Results are given in terms of the categories of LLW represented and of the chemical characteristics of the different wastes. Estimates by the respondents of their near-term waste volume projections are presented

  19. River Protection Project Mission Analysis Waste Blending Study

    International Nuclear Information System (INIS)

    Shuford, D.H.; Stegen, G.

    2010-01-01

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

  20. MANAGEMENT OF TRANSURANIC (TRU) WASTE RETRIEVAL PROJECT RISKS SUCCESSES IN THE STARTUP OF THE HANFORD 200 AREA TRU WASTE RETRIEVAL PROJECT

    International Nuclear Information System (INIS)

    GREENWLL, R.D.

    2005-01-01

    A risk identification and mitigation method applied to the Transuranic (TRU) Waste Retrieval Project performed at the Hanford 200 Area burial grounds is described. Retrieval operations are analyzed using process flow diagramming. and the anticipated project contingencies are included in the Authorization Basis and operational plans. Examples of uncertainties assessed include degraded container integrity, bulged drums, unknown containers, and releases to the environment. Identification and mitigation of project risks contributed to the safe retrieval of over 1700 cubic meters of waste without significant work stoppage and below the targeted cost per cubic meter retrieved. This paper will be of interest to managers, project engineers, regulators, and others who are responsible for successful performance of waste retrieval and other projects with high safety and performance risks

  1. Modelling sequential Biosphere systems under Climate change for radioactive waste disposal. Project BIOCLIM

    International Nuclear Information System (INIS)

    Texier, D.; Degnan, P.; Loutre, M.F.; Lemaitre, G.; Paillard, D.; Thorne, M.

    2000-01-01

    The BIOCLIM project (Modelling Sequential Biosphere systems under Climate change for Radioactive Waste Disposal) is part of the EURATOM fifth European framework programme. The project was launched in October 2000 for a three-year period. It is coordinated by ANDRA, the French national radioactive waste management agency. The project brings together a number of European radioactive waste management organisations that have national responsibilities for the safe disposal of radioactive wastes, and several highly experienced climate research teams. Waste management organisations involved are: NIREX (UK), GRS (Germany), ENRESA (Spain), NRI (Czech Republic) and ANDRA (France). Climate research teams involved are: LSCE (CEA/CNRS, France), CIEMAT (Spain), UPMETSIMM (Spain), UCL/ASTR (Belgium) and CRU (UEA, UK). The Environmental Agency for England and Wales provides a regulatory perspective. The consulting company Enviros Consulting (UK) assists ANDRA by contributing to both the administrative and scientific aspects of the project. This paper describes the project and progress to date. (authors)

  2. Mapping of information and identification of construction waste at project life cycle

    Science.gov (United States)

    Wibowo, Mochamad Agung; Handayani, Naniek Utami; Nurdiana, Asri; Sholeh, Moh Nur; Pamungkas, Gita Silvia

    2018-03-01

    The development of construction project towards green construction is needed in order to improve the efficiency of construction projects. One that needs to be minimized is construction waste. Construction waste is waste generated from construction project activities, both solid waste and non solid waste. More specifically, the waste happens at every phase of the project life cycle. Project life cycle are the stage of idea, design, construction, and operation/maintenance. Each phase is managed by different stakeholders. Therefore it requires special handling from the involved stakeholders. The objective of the study is to map the information and identify the waste at each phase of the project life cycle. The purpose of mapping is to figure out the process of information and product flow and with its timeline. This mapping used Value Stream Mapping (VSM). Identification of waste was done by distributing questionnaire to respondents to know the waste according to owner, consultant planner, contractor, and supervisory consultant. The result of the study is the mapping of information flow and product flow at the phases of idea, design, construction, and operation/ maintenance.

  3. Waste Tank Vapor Project: Tank vapor database development

    International Nuclear Information System (INIS)

    Seesing, P.R.; Birn, M.B.; Manke, K.L.

    1994-09-01

    The objective of the Tank Vapor Database (TVD) Development task in FY 1994 was to create a database to store, retrieve, and analyze data collected from the vapor phase of Hanford waste tanks. The data needed to be accessible over the Hanford Local Area Network to users at both Westinghouse Hanford Company (WHC) and Pacific Northwest Laboratory (PNL). The data were restricted to results published in cleared reports from the laboratories analyzing vapor samples. Emphasis was placed on ease of access and flexibility of data formatting and reporting mechanisms. Because of time and budget constraints, a Rapid Application Development strategy was adopted by the database development team. An extensive data modeling exercise was conducted to determine the scope of information contained in the database. a A SUN Sparcstation 1000 was procured as the database file server. A multi-user relational database management system, Sybase reg-sign, was chosen to provide the basic data storage and retrieval capabilities. Two packages were chosen for the user interface to the database: DataPrism reg-sign and Business Objects trademark. A prototype database was constructed to provide the Waste Tank Vapor Project's Toxicology task with summarized and detailed information presented at Vapor Conference 4 by WHC, PNL, Oak Ridge National Laboratory, and Oregon Graduate Institute. The prototype was used to develop a list of reported compounds, and the range of values for compounds reported by the analytical laboratories using different sample containers and analysis methodologies. The prototype allowed a panel of toxicology experts to identify carcinogens and compounds whose concentrations were within the reach of regulatory limits. The database and user documentation was made available for general access in September 1994

  4. EU Lobbying and Anti-Dumping Policy

    DEFF Research Database (Denmark)

    Nielsen, Jørgen Ulff-Møller; Svendsen, Gert Tinggaard

    2012-01-01

    of petitioning firms and Council voting in the case of anti-dumping policy. If the political position of countries in anti-dumping cases is influenced by domestic lobbying efforts, we expect that the empirical pattern of country distribution of petitioning firms in EU anti-dumping cases corresponds closely...... to the empirical pattern of EU country distribution in Council voting. Our results show a low petitioning intensity for anti-dumping investigations and a high voting intensity against anti-dumping measures in Northern Europe. Thus, it seems likely that domestic lobbying efforts have influenced the political...

  5. Treatment of organic radioactive waste in decommissioning project

    International Nuclear Information System (INIS)

    Dimovic, S.; Plecas, I.

    2003-01-01

    This paper describes methods of treatment of organic radioactive waste in the aspect of its integral part of radioactive waste which will arise during decommissioning process of nuclear power reactor RA (author)

  6. International Arctic Seas Assessment Project (IASAP)

    International Nuclear Information System (INIS)

    Sjoeblom, K.L.; Linsley, G.S.

    1995-01-01

    The purpose of this paper was to give an overall view of the International Arctic Seas Assessment Project (IASAP). The IASAP project was initiated in 1993 to address concerns about the possible health and environmental impacts of radioactive wastes dumped in the shallow waters of the Arctic seas by the former Soviet Union. The project is being executed as a part of the IAEA's responsibilities under the Convention on the Prevention of Marine Pollution by Dumping of Wastes and Other Matter (London Convention 1972). The results and conclusions of the project are expected to be reported to the London Convention in late 1996. The objectives of the project are: 1) to assess the risks to human health and to the environment associated with the radioactive waste dumped in the Kara and Barents Seas; and 2) to examine possible remedial actions related to the dumped wastes and to advise on whether they are necessary and justified. The project is organized in five working areas: source terms, existing environmental concentrations, transfer mechanisms and models, impact assessment and remedial measures. Progress made in all working areas of IASAP is reviewed each year by a group of senior scientists (IASAP Advisory Group Meeting). During the first two years of the IASAP project, a considerable amount of new information has been produced and published as IASAP working documents. Experts from 15 countries and several international organizations are involved in the different Working Groups and Advisory Group Meetings of the project. It is planned that in addition to the report to the London Convention, which will be prepared by the Advisory Group, detailed technical reports covering the work of all areas of the IASAP will be produced. 12 refs., 3 figs., 1 tab

  7. Distribution, ecology and inhibition of Thiobacillus ferrooxidans in relation to acid drainage from Witwatersrand gold mine dumps

    International Nuclear Information System (INIS)

    Whillier, P.A.

    1987-03-01

    The distribution and ecology of Thiobacillus ferrooxidans in gold mine dumps and possible means for its inhibition were investigated. A literature survey of the micro-ecology of mine waste dumps in various parts of the world was undertaken. A linear alkylbenzene sulphonate (LAS), NANSA 80/S, and a cetyl pyridinium chloride, Ceepryn, were tested as possible inhibitors for mine dump application. The LAS was rejected because it is poorly soluble in water and required higher concentrations than SLS for the inhibition of T.ferrooxidans. Ceepryn was an efficient inhibitor, but its efficiency was dramatically impeded in the presence of mine dump sand making it unsuitable for application on dumps. The SLS and LAS were tested against a mixed population of T.ferrooxidans from gold mine dumps and these bacteria were shown to be marginally more resistant to the inhibitors than the pure T.ferrooxidans culture. Sampling from mine dumps on the Witwatersrand suggested that the major T.ferrooxidans populations occurred in the moist sand of the drainage areas at the base of dumps, with few viable iron-oxidising bacteria located on the surfaces or in the centre of dumps. Sites of low moisture in dumps contained few or no viable bacteria. In the laboratory the bacterial viability decreased rapidly with loss of moisture from the sand. Moisture was shown to be important to bacterial activity and should be considered with respect to acid drainage control. Experimental sand columns showed that iron was leached with water from mine dump sand in the absence and presence of bacteria. In this study substrates, moisture, oxygen and carbon dioxide availability, ph, temperature, microorganisms and metal pollutants of uranium waste dumps are also covered

  8. Systems Engineering Plan and project record Configuration Management Plan for the Mixed Waste Disposal Initiative

    International Nuclear Information System (INIS)

    Bryan, W.E.; Oakley, L.B.

    1993-04-01

    This document summarizes the systems engineering assessment that was performed for the Mixed Waste Disposal Initiative (MWDI) Project to determine what types of documentation are required for the success of the project. The report also identifies the documents that will make up the MWDI Project Record and describes the Configuration Management Plan describes the responsibilities and process for making changes to project documentation

  9. Low-level radioactive waste in the northeast: disposal volume projections

    International Nuclear Information System (INIS)

    1982-10-01

    The northeastern states, with support of the Coalition of Northeastern Governors (CONEG), are developing compact(s) for the disposal and management of low-level radioactive waste (LLRW) generated in the eleven northeastern states (Connecticut, Delaware, Maine, Maryland, Massachusetts, New Hampshire, New Jersey, New York, Pennsylvania, Rhode Island, and Vermont). The Technical Subcommittee has made a projection of future low-level radioactive waste to the year 2000 based on existing waste volume data and anticipated growth in the Northeast states. Aware of the difficulties involved with any long range projection - unforeseen events can drastically change projections based on current assumptions - the Technical Subcommittee believes that waste volume projections should be reviewed annually as updated information becomes available. The Technical Subcommittee made the following findings based upon a conservative projection methodology: volumes of low-level waste produced annually in the eleven states individually and collectively are expected to grow continually through the year 2000 with the rate of increase varying by state; by the year 2000, the Northeast is projected to generate 58,000 m 3 of low-level waste annually, about 1.9 times the current average; and based on current estimates, 47% of the total projected waste volume in the year 2000 will be produced by nuclear power plants, compared to the current average of 54%. Non-reactor wastes will equal 53% of the total in the year 2000 compared to the current 46%

  10. Powershift transmission for dump trucks; Neues Lastschaltgetriebe fuer Dump Trucks

    Energy Technology Data Exchange (ETDEWEB)

    Rebholz, Wolfgang; Geis, Joerg; Riedhammer, Michael [ZF Friedrichshafen AG, Friedrichshafen (Germany)

    2012-04-15

    Articulated dumpers (also called dump trucks) are used in many locations where large quantities of earth, spoil, gravel or other materials have to be moved on construction sites or in quarries. ZF has developed a new transmission with eight forward and four reverse gears up to production standard specifically for use in these vehicles. The integrated primary retarder is continuously controllable and provides maximum braking torque of up to 1800 Nm. (orig.)

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

    Energy Technology Data Exchange (ETDEWEB)

    Danny Anderson

    2014-07-01

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

  12. Upgrading of oil palm wastes by radiation processing - project review

    International Nuclear Information System (INIS)

    Nahrul Khair Alang Md Rashid

    1998-01-01

    Early works on oil palm waste treatment at MINT started in 1984 with the objective of degrading EFB (Empty Fruit Bunches) by radiation. This idea was shared by JAERI that adopted the research project with MINT in 1986 under the Japanese Science and Technology Agency (STA) programme. The results of these preliminary works show that EFB can be degraded using gamma radiation at a dose of ranging from 500 to 1000 kGy - 50 to 100 times higher than what is considered to be the economic dose. It is generally accepted that the economics of radiation treatment process could only be realised if the treatment dose can be kept below 10 kGy, which was incidentally, during the course of this early works, found to be the pasteurisation dose for oil palm by - products. With these information, MINT and JAERI agreed to pursue further research in this area and formulated a bilateral research co-operation in radiation pasteurisation of EFB and subsequent degradation by cellulolytic fungi or mushrooms. The research has the objective of upgrading EFB, which was not considered as suitable for feed due to its known physical properties as coarse and highly fibrous, to animal feed as well as substrate for mushroom cultivation and enzyme production. In addition to the desire to provide an environment friendly method for waste disposal to a growing industry, the possibility of catalysing the development of livestock industry by commercial farming in the process is another motivation for this project. Malaysia is estimated to be only about 40% self-sufficient in beef production. Thus there is great opportunity for the growth and expansion of this industry in Malaysia. However, growth in ruminant population should not result in the alienation of land for pastures. Among the reasons for the lack of interest in livestock production through commercial farming is the unavailability of local feed material which could be cheaper than imported feed grains, particularly maize. Feed is one the main cost

  13. Upgrading of oil palm wastes by radiation processing - project review

    Energy Technology Data Exchange (ETDEWEB)

    Alang Md Rashid, Nahrul Khair [Malaysian Institute for Nuclear Technology Research (MINT), Bangi (Malaysia)

    1998-07-01

    Early works on oil palm waste treatment at MINT started in 1984 with the objective of degrading EFB (Empty Fruit Bunches) by radiation. This idea was shared by JAERI that adopted the research project with MINT in 1986 under the Japanese Science and Technology Agency (STA) programme. The results of these preliminary works show that EFB can be degraded using gamma radiation at a dose of ranging from 500 to 1000 kGy - 50 to 100 times higher than what is considered to be the economic dose. It is generally accepted that the economics of radiation treatment process could only be realised if the treatment dose can be kept below 10 kGy, which was incidentally, during the course of this early works, found to be the pasteurisationdose for oil palm by - products. With these information, MINT and JAERI agreed to pursue further research in this area and formulated a bilateral research co-operation in radiation pasteurisation of EFB and subsequent degradation by cellulolytic fungi or mushrooms. The research has the objective of upgrading EFB, which was not considered as suitable for feed due to its known physical properties as coarse and highly fibrous, to animal feed as well as substrate for mushroom cultivation and enzyme production. In addition to the desire to provide an environment friendly method for waste disposal to a growing industry, the possibility of catalysing the development of livestock industry by commercial farming in the process is another motivation for this project. Malaysia is estimated to be only about 40% self-sufficient in beef production. Thus there is great opportunity for the growth and expansion of this industry in Malaysia. However, growth in ruminant population should not result in the alienation of land for pastures. Among the reasons for the lack of interest in livestock production through commercial farming is the unavailability of local feed material which could be cheaper than imported feed grains, particularly maize. Feed is one the main cost

  14. Conceptual Design of the RHIC Dump Core

    Energy Technology Data Exchange (ETDEWEB)

    Stevens, A. J. [Brookhaven National Lab. (BNL), Upton, NY (United States)

    1995-09-26

    Conceptually, the internal dump consists of a "core" whose purpose is to absorb the energy of the beam, and surrounding shielding whose purpose is to attenuate radiation. Design of the core for an internal dump has two problems which must be overcome. The first problem is preserving the integrity of the dump core. The bunches must be dispersed laterally an amount sufficient to keep the energy density from cracking the dump core material. Since the dump kickers in RHIC are only ~25m upstream of the entrance face of the dump, this is i a difficult problem. The second problem, not addressed in this note, is that dumping the beam should not quench downstream magnets. Preliminary calculations related to both of these problems have been presented in earlier notes.

  15. Waste compatibility assessments to support project W-320

    International Nuclear Information System (INIS)

    BLAAK, T.M.

    1999-01-01

    The intent of this internal memo is to provide a recommendation for the transfer of tank 241-C-106 waste, Attachment 2, to tank 241-AY-102. This internal memo also identifies additional requirements which have been deemed necessary for safely receiving and storing the waste documented in Attachment 2 from tank 241-C-106 in tank 241-AY-102. This waste transfer is planned in support of tank 241-C-106 solids sluicing activities. Approximately 200,000 gallons of waste and flush water are expected to be pumped from tank 241-C-106 into tank 241-AY-102. Several transfers will be necessary to complete the sluicing of tank 241-C-106 solids. To assure ourselves that this waste transfer will not create any compatibility concerns, a waste compatibility assessment adhering to current waste compatibility requirements has been performed

  16. Waste Management Project Quality Assurance Program Plan (QAPP)

    International Nuclear Information System (INIS)

    HORHOTA, M.J.

    2000-01-01

    The Waste Management Project (WMP) is committed to excellence in our work and to delivering quality products and services to our customers, protecting our employees and the public and to being good stewards of the environment. We will continually strive to understand customer requirements, perform services, and activities that meet or exceed customer expectations, and be cost-effective in our performance. The WMP maintains an environment that fosters continuous improvement in our processes, performance, safety and quality. The achievement of quality will require the total commitment of all WMP employees to our ethic that Quality, Health and Safety, and Regulatory Compliance must come before profits. The successful implementation of this policy and ethic requires a formal, documented management quality system to ensure quality standards are established and achieved in all activities. The following principles are the foundation of our quality system. Senior management will take full ownership of the quality system and will create an environment that ensures quality objectives are met, standards are clearly established, and performance is measured and evaluated. Line management will be responsible for quality system implementation. Each organization will adhere to all quality system requirements that apply to their function. Every employee will be responsible for their work quality, to work safely and for complying with the policies, procedures and instructions applicable to their activities. Quality will be addressed and verified during all phases of our work scope from proposal development through closeout including contracts or projects. Continuous quality improvement will be an ongoing process. Our quality ethic and these quality principles constantly guide our actions. We will meet our own quality expectations and exceed those of our customers with vigilance, commitment, teamwork, and persistence

  17. Quality Assurance Program Plan (QAPP) Waste Management Project

    Energy Technology Data Exchange (ETDEWEB)

    HORHOTA, M.J.

    2000-12-21

    The Waste Management Project (WMP) is committed to excellence in our work and to delivering quality products and services to our customers, protecting our employees and the public and to being good stewards of the environment. We will continually strive to understand customer requirements, perform services, and activities that meet or exceed customer expectations, and be cost-effective in our performance. The WMP maintains an environment that fosters continuous improvement in our processes, performance, safety and quality. The achievement of quality will require the total commitment of all WMP employees to our ethic that Quality, Health and Safety, and Regulatory Compliance must come before profits. The successful implementation of this policy and ethic requires a formal, documented management quality system to ensure quality standards are established and achieved in all activities. The following principles are the foundation of our quality system. Senior management will take full ownership of the quality system and will create an environment that ensures quality objectives are met, standards are clearly established, and performance is measured and evaluated. Line management will be responsible for quality system implementation. Each organization will adhere to all quality system requirements that apply to their function. Every employee will be responsible for their work quality, to work safely and for complying with the policies, procedures and instructions applicable to their activities. Quality will be addressed and verified during all phases of our work scope from proposal development through closeout including contracts or projects. Continuous quality improvement will be an ongoing process. Our quality ethic and these quality principles constantly guide our actions. We will meet our own quality expectations and exceed those of our customers with vigilance, commitment, teamwork, and persistence.

  18. 327 Building liquid waste handling options modification project plan

    International Nuclear Information System (INIS)

    Ham, J.E.

    1998-01-01

    This report evaluates the modification options for handling radiological liquid waste (RLW) generated during decontamination and cleanout of the 327 Building. The overall objective of the 327 Facility Stabilization Project is to establish a passively safe and environmentally secure configuration of the 327 Facility. The issue of handling of RLW from the 327 Facility (assuming the 34O Facility is not available to accept the RLW) has been conceptually examined in at least two earlier engineering studies (Parsons 1997a and Hobart l997). Each study identified a similar preferred alternative that included modifying the 327 Facility RLWS handling systems to provide a truck load-out station, either within the confines of the facility or exterior to the facility. The alternatives also maximized the use of existing piping, tanks, instrumentation, controls and other features to minimize costs and physical changes. An issue discussed in each study involved the anticipated volume of the RLW stream. Estimates ranged between 113,550 and 387,500 liters in the earlier studies. During the development of the 324/327 Building Stabilization/Deactivation Project Management Plan, the lower estimate of approximately 113,550 liters was confirmed and has been adopted as the baseline for the 327 Facility RLW stream. The goal of this engineering study is to reevaluate the existing preferred alternative and select a new preferred alternative, if appropriate. Based on the new or confirmed preferred alternative, this study will also provide a conceptual design and cost estimate for required modifications to the 327 Facility to allow removal of RLWS and treatment of the RLW generated during deactivation

  19. The role of intergenerational influence in waste education programmes: The THAW project

    International Nuclear Information System (INIS)

    Maddox, P.; Doran, C.; Williams, I.D.; Kus, M.

    2011-01-01

    Highlights: → Children can be effective advocates in changing their parents' lifestyles. → We investigated the role of intergenerational influence in waste education programmes. → Waste Watch's Take Home Action on Waste project worked with 6705 children in 39 schools. → The results showed increased participation in recycling and declines in residual waste. → The study shows that recycling behaviour is positively impacted by intergenerational influence. - Abstract: Whilst the education of young people is often seen as a part of the solution to current environmental problems seeking urgent attention, it is often forgotten that their parents and other household members can also be educated/influenced via home-based educational activities. This paper explores the theory of intergenerational influence in relation to school based waste education. Waste Watch, a UK-based environmental charity ( (www.wastewatch.org.uk)), has pioneered a model that uses practical activities and whole school involvement to promote school based action on waste. This methodology has been adopted nationally. This paper outlines and evaluates how effective school based waste education is in promoting action at a household level. The paper outlines Waste Watch's 'Taking Home Action on Waste (THAW)' project carried out for two and half years in Rotherham, a town in South Yorkshire, England. The project worked with 6705 primary age children in 39 schools (44% of primary schools in the project area) to enable them to take the 'reduce, reuse and recycle message' home to their families and to engage these (i.e. families) in sustainable waste management practices. As well as substantial increases in students' knowledge and understanding of waste reduction, measurement of the impact of the project in areas around 12 carefully chosen sample schools showed evidence of increased participation in recycling and recycling tonnages as well as declining levels of residual waste. Following delivery of

  20. Design requirements document for project W-520, immobilized low-activity waste disposal

    International Nuclear Information System (INIS)

    Ashworth, S.C.

    1998-01-01

    This design requirements document (DRD) identifies the functions that must be performed to accept, handle, and dispose of the immobilized low-activity waste (ILAW) produced by the Tank Waste Remediation System (TWRS) private treatment contractors and close the facility. It identifies the requirements that are associated with those functions and that must be met. The functional and performance requirements in this document provide the basis for the conceptual design of the Tank Waste Remediation System Immobilized Low-Activity Waste disposal facility project (W-520) and provides traceability from the program-level requirements to the project design activity

  1. Design requirements document for project W-520, immobilized low-activity waste disposal

    Energy Technology Data Exchange (ETDEWEB)

    Ashworth, S.C.

    1998-08-06

    This design requirements document (DRD) identifies the functions that must be performed to accept, handle, and dispose of the immobilized low-activity waste (ILAW) produced by the Tank Waste Remediation System (TWRS) private treatment contractors and close the facility. It identifies the requirements that are associated with those functions and that must be met. The functional and performance requirements in this document provide the basis for the conceptual design of the Tank Waste Remediation System Immobilized Low-Activity Waste disposal facility project (W-520) and provides traceability from the program-level requirements to the project design activity.

  2. Underground disposal of hazardous waste - state of the art and R and D projects

    International Nuclear Information System (INIS)

    Pitterich, H.; Brueckner, C.

    1998-01-01

    The project management group Entsorgung (PTE) coordinates R and D activities on deep geological disposal of hazardous waste besides other activities in the field of nuclear disposal. R and D projects aim at the improvement of tools used to predict the long-term behaviour of underground disposal facilities and the threat for man and environment associated with these facilities. The current German situation on deep geological disposal of hazardous waste is described and some results from the fields waste-anaylsis, geochemical modelling and geotechnical barriers for the sealing of waste disposal sites are presented. (orig.)

  3. An approach for sampling solid heterogeneous waste at the Hanford Site waste receiving and processing and solid waste projects

    International Nuclear Information System (INIS)

    Sexton, R.A.

    1993-03-01

    This paper addresses the problem of obtaining meaningful data from samples of solid heterogeneous waste while maintaining sample rates as low as practical. The Waste Receiving and Processing Facility, Module 1, at the Hanford Site in south-central Washington State will process mostly heterogeneous solid wastes. The presence of hazardous materials is documented for some packages and unknown for others. Waste characterization is needed to segregate the waste, meet waste acceptance and shipping requirements, and meet facility permitting requirements. Sampling and analysis are expensive, and no amount of sampling will produce absolute certainty of waste contents. A sampling strategy is proposed that provides acceptable confidence with achievable sampling rates

  4. Changes in some physical properties of soils in the chronosequence of self-overgrown dumps of the Sokolov quarry-dump complex, Czechia

    Czech Academy of Sciences Publication Activity Database

    Kuráž, V.; Frouz, Jan; Kuráž, M.; Mako, A.; Šustr, Vladimír; Cejpek, J.; Romanov, O.V.; Abakumov, E.V.

    2012-01-01

    Roč. 45, č. 3 (2012), s. 266-272 ISSN 1064-2293 R&D Projects: GA MŠk 2B08023 Grant - others:Russian Foundation for Basic Research(RU) 08-04-01128 Institutional support: RVO:60077344 Keywords : physical properties of soil s * chronosequence of self-overgrown dumps * Sokolov quarry-dump complex Subject RIV: EH - Ecology, Behaviour Impact factor: 0.216, year: 2012

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

    International Nuclear Information System (INIS)

    Deffenbaugh, M.L.

    1997-01-01

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

  6. Regularities of restoration of plant cover on the dumps of the Kuznetsk Basin

    Directory of Open Access Journals (Sweden)

    A. N. Kupriyanov

    2016-04-01

    Full Text Available The article considers the issues of the restoration vegetation on the dumps of the coal enterprises of the Kuznetsk Basin. Studies have shown that the dumps have a wide range of environmental conditions and are potentially suitable for establishment of plants. To negative environmental factors at the mine dumps include the lack of productive moisture, failed penetration, contrasting temperature regime on the different elements of the relief, and low potential fertility of the embryonic soils. Positive – high humidity in the depressions, the high content of fine-grained deposits in the lower part of the elephant dumps, excessive accumulation of snow in the winter on separate dumping sites. On disturbed lands identified eight technogenic ecotopes, characterized by various microrelief, moisture level, amount of fine fractions of technogenic eluvium determining favorable, moderately favorable and unfavorable conditions for vegetation of disturbed land. Selected three stages of syngenesis: pioneer stage, simple plant communities and complex plant communities. The stage of zonal phytocenosis on the dumps was not detected. The basis of diagnostic signs consists of the projective cover, the nature of the host plants, the number of species part of the zonal species. The selected criteria are universal and can be applicable to most dumps. Speed of syngenetic succession does not depend on calendar age of the dumps, and environmental conditions, which are formed on separate sites.

  7. Mobilization and transport of pollutants in an abandoned dump in tropical conditions

    Science.gov (United States)

    Pelinson, Natalia; Shinzato, Marjolly; Wendland, Edson

    2017-04-01

    The valuation and treatment techniques of municipal solid waste (MSW) in developing countries are not sufficiently developed, and therefore, the volume of waste destined for disposal still presents significant amounts. In Brazil, the more common practice of final destination is the deposition on the soil, due to its simple operation and low cost compared to other techniques. One of the most serious negative environmental impacts in the irregular disposal of solid waste is the contamination of soil and groundwater by waste leachates. The final disposal in dumps is forbidden by Brazilian law since 2010, nevertheless, the public administration is not prepared to monitor waste disposal areas and the risk of contamination of water. In this sense, a research has been developed in an abandoned dump installed over an outcrop of the Botucatu Formation, which is part of the Guarani Aquifer System (SAG) and therefore, is an area of high water vulnerability. In this dump, an old gully was used as a final waste disposal area for urban, construction and demolition, medical and industrial waste from 1980 to 1996. Since the end of the deposition, the waste body is kept with inefficient hydraulic control. The water infiltration due to rainfall promotes the mobility of contaminant in the deposit. The present water quality in the dump has been monitored through physical and chemical analysis of samples collected in the unsaturated zone (inside the waste mass using vacuum lysimeters) and in the saturated zone (monitoring wells). The rainfall variation observed in the years 2014 (dry year) and 2015 (wet year) contributed significantly to evaluate the mobilization of pollutants within the dump. The reduction of the water volume that infiltrates the waste mass affected the quality of the leachate collected in the lysimeters. The groundwater collected in monitoring wells outside the dump area presents low turbidity values (1000 µS.cma-1 in leachate) and chlorides values (>800 mg.L-1

  8. Technical solutions for waste treatment in the Belene project

    International Nuclear Information System (INIS)

    Büttner, K.; Eichhorn, H.

    2011-01-01

    Outline: In June 2010 NUKEM Technologies GmbH was awarded a contract from ATOMSTROYEXPORT JSC to perform the complete work package related to designing and completion of the equipment for treatment of radioactive waste on the turn-key basis for Belene NPP. Technical Solutions: Waste Streams and Technologies at UKC and UKS; Concentration Plant; Thermal Treatment of Resins Sorting Facility; Biological Waste Water Treatment; Conditioning – Cementation • Sorting of Radwaste; Plasma Facility; Grouting; Filter Press; Monitoring and Tracking

  9. Project plans for transuranic waste at small quantity sites in the Department of Energy comples-10522

    International Nuclear Information System (INIS)

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

    2009-01-01

    Los Alamos National Laboratory, Carlsbad Office (LANL-CO), has been tasked to write Project Plans for all of the Small Quantity Sites (SQS) with defense related Transuranic (TRU) waste in the Department of Energy (DOE) complex. Transuranic Work-Off Plans were precursors to the Project Plans. LANL-CO prepared a Work-Off Plan for each small quantity site. The Work-Off Plan that identified issues, drivers, schedules, and inventory. Eight sites have been chosen to deinventory their legacy TRU waste; Bettis Atomic Power Laboratory, General Electric-Vallecitos Nuclear Center, Lawrence Berkeley National Laboratory, Lawrence Livermore National Laboratory-Area 300, Nevada Test Site, Nuclear Radiation Development, Sandia National Laboratory, and the Separations Process Research Unit. Each plan was written for contact and/or remote handled waste if present at the site. These project plans will assist the small quantity sites to ship legacy TRU waste offsite and de-inventory the site of legacy TRU waste. The DOE is working very diligently to reduce the nuclear foot print in the United States. Each of the eight SQSs will be de-inventoried of legacy TRU waste during a campaign that ends September 2011. The small quantity sites have a fraction of the waste that large quantity sites possess. During this campaign, the small quantity sites will package all of the legacy TRU waste and ship to Idaho or directly to the Waste Isolation Pilot Plant (WIPP) in Carlsbad, New Mexico. The sites will then be removed from the Transuranic Waste Inventory if they are de-inventoried of all waste. Each Project Plan includes the respective site inventory report, schedules, resources, drivers and any issues. These project plans have been written by the difficult waste team and will be approved by each site. Team members have been assigned to each site to write site specific project plans. Once the project plans have been written, the difficult team members will visit the sites to ensure nothing has

  10. Accelerator Production of Tritium project process waste assessment

    International Nuclear Information System (INIS)

    Carson, S.D.; Peterson, P.K.

    1995-09-01

    DOE has made a commitment to compliance with all applicable environmental regulatory requirements. In this respect, it is important to consider and design all tritium supply alternatives so that they can comply with these requirements. The management of waste is an integral part of this activity and it is therefore necessary to estimate the quantities and specific wastes that will be generated by all tritium supply alternatives. A thorough assessment of waste streams includes waste characterization, quantification, and the identification of treatment and disposal options. The waste assessment for APT has been covered in two reports. The first report was a process waste assessment (PWA) that identified and quantified waste streams associated with both target designs and fulfilled the requirements of APT Work Breakdown Structure (WBS) Item 5.5.2.1. This second report is an expanded version of the first that includes all of the data of the first report, plus an assessment of treatment and disposal options for each waste stream identified in the initial report. The latter information was initially planned to be issued as a separate Waste Treatment and Disposal Options Assessment Report (WBS Item 5.5.2.2)

  11. Accelerator Production of Tritium project process waste assessment

    Energy Technology Data Exchange (ETDEWEB)

    Carson, S.D.; Peterson, P.K.

    1995-09-01

    DOE has made a commitment to compliance with all applicable environmental regulatory requirements. In this respect, it is important to consider and design all tritium supply alternatives so that they can comply with these requirements. The management of waste is an integral part of this activity and it is therefore necessary to estimate the quantities and specific wastes that will be generated by all tritium supply alternatives. A thorough assessment of waste streams includes waste characterization, quantification, and the identification of treatment and disposal options. The waste assessment for APT has been covered in two reports. The first report was a process waste assessment (PWA) that identified and quantified waste streams associated with both target designs and fulfilled the requirements of APT Work Breakdown Structure (WBS) Item 5.5.2.1. This second report is an expanded version of the first that includes all of the data of the first report, plus an assessment of treatment and disposal options for each waste stream identified in the initial report. The latter information was initially planned to be issued as a separate Waste Treatment and Disposal Options Assessment Report (WBS Item 5.5.2.2).

  12. Waste Vitrification Projects Throughout the US Initiated by SRS

    International Nuclear Information System (INIS)

    Jantzen, C.M.; Whitehouse, J.C.; Smith, M.E.; Pickett, J.B.; Peeler, D.K.

    1998-05-01

    Technologies are being developed by the U. S. Department of Energy's (DOE) Nuclear Facility sites to convert high-level, low-level, and mixed wastes to a solid stabilized waste form for permanent disposal. Vitrification is one of the most important and environmentally safest technologies being developed. The Environmental Protection Agency (EPA) has declared vitrification the best demonstrated available technology for high-level radioactive waste and produced a Handbook of Vitrification Technologies for Treatment of Hazardous and Radioactive Waste. The Defense Waste Processing Facility being tested at will soon start vitrifying the high-level waste at. The DOE Office of Technology Development has taken the position that mixed waste needs to be stabilized to the highest level reasonably possible to ensure that the resulting waste forms will meet both current and future regulatory specifications. Vitrification produces durable waste forms at volume reductions up to 97%. Large reductions in volume minimize long-term storage costs making vitrification cost effective on a life cycle basis

  13. ANALYSIS OF REMEDIATION PROCESS OF THE GROUDWATER COTAMINATION IN AN ILLEGAL DUMPING SITE

    Science.gov (United States)

    Nishida, Norikazu; Furuichi, Toru; Ishii, Kazuei

    Among on-site remediation technologies applied to illegal dumping sites, a technology to remedy contaminated groundwater without removal of the dumped waste is expected to provide a great opportunity to fulfill a societal need due to its economic advantage compared to removal of all waste. However heterogeneously-distributed waste makes the remedial process difficult. In this study, an in situflushing technology was applied to an illegal dumping site in Kuwana city, Mie, in order to remedy groundwater contaminated with several volatile organic compounds (VOCs) within five years. The key to successfully achieve the target was to conduct a series of advanced remediation processes; introducing a new indicator by which multiple VOCs can be estimated integratelly, monitoring the progress of remediation with a contour map of VOC concentration as well as the weighted averages of the concentration derived from the indicator, pinpointing residual contaminants area, reexamining the plan, and taking additional steps that promote further remediation.

  14. An overview of waste management systems at the West Valley demonstration project

    International Nuclear Information System (INIS)

    McIntosh, T.W.; Bixby, W.W.; Krauss, J.E.; Leap, D.R.

    1988-01-01

    In 1980, the United States Congress passed into law the West Valley Demonstration Project Act authorizing the Department of Energy (DOE) to conduct a nuclear waste management project at a former commercial nuclear fuel reprocessing facility located in West Valley, New York. The Project's main objective is to solidify approximately two million litres of high-level radioactive liquid waste into a form suitable for transport to a federal repository for final disposal. The majority of the liquid waste was produced as a by-product of the PUREX extraction process and is stored in an underground steel tank. A waste characterization program has shown that the neutralized waste has settled into two distinct layers: a clear alkaline liquid (supernatant) layer and a dense precipitate (sludge) layer. The principle radioactive elements in the waste are cesium 137 (supernatant) and strontium 90 (sludge). This paper describes the overall project strategy, the waste management systems, the present project engineering and construction status and the project schedule leading to radioactive operation

  15. Project Guarantee 1985. Radioactive wastes: Properties and allocation to final repository types

    International Nuclear Information System (INIS)

    Anon.

    1985-01-01

    An overview of waste-specific data, as input into constructional engineering studies and safety analyses of Project Guarantee, is presented which describes the activity inventory of the radioactive waste to be disposed of, classified according to origin, the quantitative spezifications of the waste, the concept of classifying waste into appropriate categories, grouping into major categories and distribution of these between the different repository types, and finally, control measures which ensure observance of the specifications of the waste to be disposed of. It is expedient, for conceptional considerations and for the operational phase of the repository, to split the waste up into several suitably specified waste categories according to the practical aspects of origin and conditioning. This can be done in such a way that the waste within a specific category is sufficiently homogeneous with regard to its radiological properties and chemical composition for the requirements of safety analysis. The present volume contains base-data for around 30 waste types. Two waste types are documented with more detailed data as an example of the practicability of the comprehensive waste characterisation contained in reference report NTB 84-47. It is shown that waste-specific data which go into safety analysis and constructional engineering project studies are available in an appropriate degree of detail. The method of distributing the waste between repositories with differing degrees of protection and procedures for controlling adherence to admission specifications are developed and documented. It can be ensured that no waste with an impermissibly high radiotoxicity level will later be emplaced in a repository for low- and intermediate-level waste

  16. Waste management aspects of decontamination and decommissioning (D ampersand D) projects

    International Nuclear Information System (INIS)

    Becker, B.D.

    1993-01-01

    History shows that waste management concepts have generally been overlooked during the planning stages of most projects and experiments. This is resulting,in the generation of vast amounts of waste during the clean up or D ampersand D of these facilities. Managers are not only being frustrated in their waste minimization efforts (a relatively new concept) but are also facing the prospect of not being able to dispose of the waste materials at all. At the least, managers are having to budget extraordinary amounts of time, money, and effort in defending their positions that the waste materials are not only humanly and environmentally safe, but that the waste materials are in fact what management says they are. The following discussion will attempt to provide some guidance to D ampersand D managers to help them avoid many of the common pitfalls associated with the ultimate disposal of the materials generated during these projects

  17. Advanced mixed waste treatment project draft environmental impact statement

    International Nuclear Information System (INIS)

    1998-07-01

    The AMWTP DEIS assesses the potential environmental impacts associated with four alternatives related to the construction and operation of a proposed waste treatment facility at the INEEL. Four alternatives were analyzed: The No Action Alternative, the Proposed Action, the Non-Thermal Treatment Alternative, and the Treatment and Storage Alternative. The proposed AMWTP facility would treat low-level mixed waste, alpha-contaminated low-level mixed waste, and transuranic waste in preparation for disposal. Transuranic waste would be disposed of at the Waste isolation Pilot Plant in New Mexico. Low-level mixed waste would be disposed of at an approval disposal facility depending on decisions to be based on DOE's Final Waste Management Programmatic Environmental Impact Statement. Evaluation of impacts on land use, socio-economics, cultural resources, aesthetic and scenic resources, geology, air resources, water resources, ecological resources, noise, traffic and transportation, occupational and public health and safety, INEEL services, and environmental justice were included in the assessment. The AMWTP DEIS identifies as the Preferred Alternative the Proposed Action, which is the construction and operation of the AMWTP facility

  18. The IAEA project on nuclear and non-nuclear wastes

    International Nuclear Information System (INIS)

    Seitz, Roger

    1998-01-01

    Radioactive and chemotoxic agents are common in electricity generation waste. Data and assessments illustrate that nuclear and non-nuclear fuel chains result in waste posing potential long-term hazards. Efforts are focussed on filling data gaps and approaches for comparing impacts of radioactive and chemotoxic agents

  19. Market for small waste gasification projects - preliminary scoping study

    International Nuclear Information System (INIS)

    1999-01-01

    This report presents the findings of a market analysis for small waste gasification/pyrolysis plant in the UK. The overall objectives of the study are to assess the potential merits in establishing a demonstration plant in the UK, and to identify the size, profile and characteristics of the potential market based on municipal solid waste (MSW) feedstock. (author)

  20. Projected Salt Waste Production from a Commercial Pyroprocessing Facility

    Directory of Open Access Journals (Sweden)

    Michael F. Simpson

    2013-01-01

    Full Text Available Pyroprocessing of used nuclear fuel inevitably produces salt waste from electrorefining and/or oxide reduction unit operations. Various process design characteristics can affect the actual mass of such waste produced. This paper examines both oxide and metal fuel treatment, estimates the amount of salt waste generated, and assesses potential benefit of process options to mitigate the generation of salt waste. For reference purposes, a facility is considered in which 100 MT/year of fuel is processed. Salt waste estimates range from 8 to 20 MT/year from considering numerous scenarios. It appears that some benefit may be derived from advanced processes for separating fission products from molten salt waste, but the degree of improvement is limited. Waste form production is also considered but appears to be economically unfavorable. Direct disposal of salt into a salt basin type repository is found to be the most promising with respect to minimizing the impact of waste generation on the economic feasibility and sustainability of pyroprocessing.

  1. Project of the century. Nuclear waste disposal; Jahrhundertprojekt Endlagerung

    Energy Technology Data Exchange (ETDEWEB)

    Brunnengraeber, Achim [Freie Univ. Berlin (Germany). Forschungszentrum fuer Umweltpolitik (FFU)

    2017-09-01

    In Germany - as worldwide - no final repository for radioactive wastes from nuclear power plants exists. The interdisciplinary contribution is focused on the question how the new political developments based on the work of the final repository commission will proceed with respect to the site selection. Possible challenges arising on the way to final waste disposal are discussed.

  2. Waste receiving and processing facility module 1 data management system software project management plan

    International Nuclear Information System (INIS)

    Clark, R.E.

    1994-01-01

    This document provides the software development plan for the Waste Receiving and Processing (WRAP) Module 1 Data Management System (DMS). The DMS is one of the plant computer systems for the new WRAP 1 facility (Project W-026). The DMS will collect, store, and report data required to certify the low level waste (LLW) and transuranic (TRU) waste items processed at WRAP 1 as acceptable for shipment, storage, or disposal

  3. 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)

  4. West Valley Demonstration Project low-level and transuranic waste assay and methodology

    International Nuclear Information System (INIS)

    McVay, C.W.

    1987-03-01

    In the decontamination and decommissioning of the West Valley Nuclear Facility, waste materials are being removed and packaged in a variety of waste containers which require classification in accordance with USNRC 10 CFR 61 and DOE 5820.2 criteria. Low-Level and Transuranic waste assay systems have been developed to efficiently assay and classify the waste packages. The waste is assayed by segmented gamma scanning, passive neutron techniques, dose rate conversion, and/or radiochemical laboratory analysis. The systems are capable of handling all the waste forms currently packaged as part of the Project. The above systems produce a list of nuclides present with their concentrations and determines the classification of the waste packages based on criteria outlined in DOE Order 5820.2 and USNRC 10 CFR 61.55. 9 refs., 12 figs., 8 tabs

  5. Law project on the radioactive materials and wastes management 2006 recommendations presented by Anne Duthilleul

    International Nuclear Information System (INIS)

    2006-01-01

    This document provides recommendations on the law project concerning the radioactive material and wastes management. It precises the law objectives, the french particularities concerning the radioactive wastes and materials management, the public debate in France, the evaluation of the researches, the recommendations of the economic and social council. (A.L.B.)

  6. The Savannah River Site Replacement High Level Radioactive Waste Evaporator Project

    International Nuclear Information System (INIS)

    Presgrove, S.B.

    1992-01-01

    The Replacement High Level Waste Evaporator Project was conceived in 1985 to reduce the volume of the high level radioactive waste Process of the high level waste has been accomplished up to this time using Bent Tube type evaporators and therefore, that type evaporator was selected for this project. The Title I Design of the project was 70% completed in late 1990. The Department of Energy at that time hired an independent consulting firm to perform a complete review of the project. The DOE placed a STOP ORDER on purchasing the evaporator in January 1991. Essentially, no construction was to be done on this project until all findings and concerns dealing with the type and design of the evaporator are resolved. This report addresses two aspects of the DOE design review; (1) Comparing the Bent Tube Evaporator with the Forced Circulation Evaporator, (2) The design portion of the DOE Project Review - concentrated on the mechanical design properties of the evaporator. 1 ref

  7. Results of evaluation of tailing dumps dust intensity

    Directory of Open Access Journals (Sweden)

    Masloboev V. A.

    2016-03-01

    Full Text Available A set of most acceptable and well-known methods of dust intensity evaluation has been defined and tested (dependence of Westphal D. L. et al. and DEAD scheme based on the analysis of exiting approaches (deserts, tailing dumps, etc.. The description of the chosen methods has been given. The determination of dynamic velocity u* and velocity at the height of +10 m above the dusting surface u10 which are necessary to evaluate the dust intensity has been demonstrated. The method is based on two-dimensional numerical model of atmosphere aerodynamics in the area of "tailing dumps of ANOF-2 ‒ the town of Apatity". The study provides calculations of horizontal velocity at the height of +10 m above the dusting surface at the wind speed varying from 5 to 23 m/sec. The work also suggests the results of graphical data processing related to tailing grain size distribution from the surface of the firmly established surface of the tailing dumps of ANOF-2. Comparative analysis has been given and the peculiarities of interval (based on grains sizes dust intensity of the tailing dumps of ANOF-2 have been shown using the dependence of Westphal D. L. et al. and DEAD scheme within the wind speed range. The received values of dust intensity at the lower range limit are close to the "maximum specific dust off" value which is used by project specialists for documentation development

  8. DQO Summary Report for 105-N/109-N Interim Safe Storage Project Waste Characterization

    Energy Technology Data Exchange (ETDEWEB)

    T. A. Lee

    2005-09-15

    The DQO summary report provides the results of the DQO process completed for waste characterization activities for the 105-N/109-N Reactor Interim Safe Storage Project including decommission, deactivate, decontaminate, and demolish activities for six associated buildings.

  9. Foaming in Hanford River Protection Project Waste Treatment Plant LAW Evaporation Processes - FY01 Summary Report

    International Nuclear Information System (INIS)

    Calloway, T.B.

    2002-01-01

    The LAW evaporation processes currently being designed for the Hanford River Protection Project Waste Treatment Plant are subject to foaming. Experimental simulant studies have been conducted in an effort to achieve an effective antifoam agent suitable to mitigate such foaming

  10. DQO Summary Report for 105-N/109-N Interim Safe Storage Project Waste Characterization

    International Nuclear Information System (INIS)

    Lee, T.A.

    2005-01-01

    The DQO summary report provides the results of the DQO process completed for waste characterization activities for the 105-N/109-N Reactor Interim Safe Storage Project including decommission, deactivate, decontaminate, and demolish activities for six associated buildings.

  11. A post-contract project analysis of material waste and cost overrun ...

    African Journals Online (AJOL)

    In Malaysia, 28.34% of the total waste sent to landfills originates from ..... by comparing the opinions of the first two interviewees. The process continued .... the causes of delay and cost overrun in Uganda's public sector construction projects.

  12. The 2016-2018 National Plan of Management of Radioactive Materials and Wastes - Project

    International Nuclear Information System (INIS)

    Gazzo, Alexis; Robert, Jean-Gabriel; Abraham, Christophe; Benaze, Manon de

    2015-01-01

    A first document contains the project of the National Plan of Management of Radioactive Materials and Wastes (PNGMDR) for the period 2016-2018: principles and objectives (presentation of radioactive materials and wastes, principles to be taken into account to define pathways of management of radioactive wastes, legal and institutional framework, information transparency), the management of radioactive materials (context and challenges, management pathways, works on fast breeder reactors of fourth generation), assessment and perspectives of existing pathways of management of radioactive wastes (management of historical situations, management of residues of mining and sterile processing, management of waste with a high natural radioactivity, management of very short life waste, of very low activity wastes, and low and medium activity wastes), needs and perspectives regarding management processes to be implemented for the different types of radioactive wastes. Appendices to this document contain a recall of the content of previous PNGMDR since 2007, a synthesis of realisations and researches performed abroad, research orientations for the concerned period, and international agreement on spent fuel and radioactive waste management. A second document, released by the ASN, proposes an environmental and strategic assessment of the plan. A third one and a fourth one contain the opinion of the Environmental Authority, respectively on the plan preliminary focus, and on the plan itself. An answer to this last one is then proposed, followed by a synthesis of the plan project and the text of the corresponding decree

  13. Nuclear waste: the political realities

    International Nuclear Information System (INIS)

    Arnott, D.

    1983-01-01

    The land dumping of nuclear waste has again come to the attention of anti-nuclear groups, environmentalists and the media, following the announcement of the proposed sites for intermediate-level nuclear waste at Billingham and Bedford. Opposition has already surfaced on a large scale, with public meetings in both areas and a revitalisation of the waste dumping network. This article explains some of the political realities in the nuclear debate, and suggests how we can tackle the issue of waste dumping, remembering that, even if the industry closes tomorrow, there are vast quantities of waste which must be safely and democratically dealt with. (author)

  14. ENGINEERING STUDY FOR THE 200 AREA EFFLUENT TREATMENT FACILITY (ETF) SECONDARY WASTE TREATMENT OF PROJECTED FUTURE WASTE FEEDS

    International Nuclear Information System (INIS)

    LUECK, K.J.

    2004-01-01

    This report documents an engineering study conducted to evaluate alternatives for treating secondary waste in the secondary treatment train (STT) of the Hanford Site 200 Area Effluent Treatment Facility (ETF). The study evaluates ETF STT treatment alternatives and recommends preferred alternatives for meeting the projected future missions of the ETF. The preferred alternative(s) will process projected future ETF influents to produce a solid waste acceptable for final disposal on the Hanford Site. The main text of this report summarizes the ETF past and projected operations, lists the assumptions about projected operations that provide the basis for the engineering evaluation, and summarizes the evaluation process. The evaluation process includes identification of available modifications to the current ETF process, screens those modifications for technical viability, evaluates the technically viable alternatives, and provides conclusions and recommendations based on that evaluation

  15. TWRS privatization support project waste characterization resource dictionary

    International Nuclear Information System (INIS)

    Patello, G.K.; Wiemers, K.D.

    1996-09-01

    A single estimate of waste characteristics for each underground storage tanks at the Hanford Site is not available. The information that is available was developed for specific programmatic objectives and varies in format and level of descriptive detail, depending on the intended application. This dictionary reflects an attempt to define what waste characterization information is available. It shows the relationship between the identified resource and the original data source and the inter-relationships among the resources; it also provides a brief description of each resource. Developed as a general dictionary for waste characterization information, this document is intended to make the user aware of potenially useful resources

  16. Construction and Demolition Waste Characteristics in Tanzania ...

    African Journals Online (AJOL)

    The construction industry generates a lot of construction and demolition (C&D) waste which puts some challenges to its management. For example, currently, in many towns in Tanzania, there are no landfill sites for solid waste disposal; and as a consequence open air dumping sites are used. Dumping C&D waste puts ...

  17. International intercomparison and harmonization projects for demonstrating the safety of radioactive waste management, decommissioning and radioactive waste disposal

    International Nuclear Information System (INIS)

    Metcalf, Phil; O'Donnell, Patricio; Jova Sed, Luis; Batandjieva, Borislava; Rowat, John; Kinker, Monica

    2008-01-01

    Full text: The Joint Convention on the safety of spent fuel management and the safety of radioactive waste management and the international safety standards on radioactive waste management, decommissioning and radioactive waste disposal call for assessment and demonstration of the safety of facilities and activities; during siting, design and construction prior to operation, periodically during operation and at the end of lifetime or upon closure of a waste disposal facility. In addition, more recent revisions of the international safety standards require the development of a safety case for such facilities and activities, documentation presenting all the arguments supporting the safety of the facilities and activities covering site and engineering features, quantitative safety assessment and management systems. Guidance on meeting these safety requirements also indicates the need for a graded approach to safety assessment, with the extent and complexity of the assessment being proportional to the complexity of the activity or facility, and its propensity for radiation hazard. Safety assessment approaches and methodologies have evolved over several decades and international interest in these developments has been considerable as they can be complex and often subjective, which has led to international projects being established aimed at harmonization. The IAEA has sponsored a number of such initiatives, particularly in the area of disposal facility safety, but more recently in the areas of pre disposal waste management and decommissioning, including projects known as ISAM, ASAM, SADRWMS and DeSa. The projects have a number of common aspects including development of standardized methodological approaches, application on test cases and assessment review; they also have activity and facility specific elements. The paper presents an overview of the projects, the outcomes from the projects to date and their future direction aimed very much at practical application of

  18. Community interviews task report: Working draft: BWIP [Basalt Waste Isolation Project] Repository Project

    International Nuclear Information System (INIS)

    Bolton, P.A.

    1987-11-01

    The socioeconomic program for the Basalt Waste Isolation Project (BWIP) requires the collection of information about economic, social and cultural conditions, demographic, housing and settlement patterns, and the provision of public services and facilities in order to monitor and assess the impacts of the project on the study area. Much of the information needed by the socioeconomic program is compiled, maintained, and used by officials or staff members of local, regional, state, or tribal agencies or organizations. Because much of this information is prepared for internal use, the documents are often not published or advertised and it can be difficult for researchers to identify many obscure, yet useful, sources of information. In order to identify and gain access to this information, it is often most efficient to talk directly with officials and staff members of pertinent agencies or organizations who may have knowledge of these documents or who may have useful information themselves. Consequently, interviews in the study communities with persons knowledgeable about the socioeconomic or sociocultural characteristics of the area constitute an important source of data for the socioeconomic program. In addition to identifying various data sources, these interviews provide a mechanism for understanding and interpreting those data. Knowledge of specific local conditions is often necessary to correctly interpret quantitative data. The purpose of this paper is to summarize the objectives of the community interviews task and the general methods that will be used in conducting the community interviews. 3 refs

  19. Surrogate formulations for thermal treatment of low-level mixed waste, Part II: Selected mixed waste treatment project waste streams

    Energy Technology Data Exchange (ETDEWEB)

    Bostick, W.D.; Hoffmann, D.P.; Chiang, J.M.; Hermes, W.H.; Gibson, L.V. Jr.; Richmond, A.A. [Martin Marietta Energy Systems, Inc., Oak Ridge, TN (United States); Mayberry, J. [Science Applications International Corp., Idaho Falls, ID (United States); Frazier, G. [Univ. of Tennessee, Knoxville, TN (United States)

    1994-01-01

    This report summarizes the formulation of surrogate waste packages, representing the major bulk constituent compositions for 12 waste stream classifications selected by the US DOE Mixed Waste Treatment Program. These waste groupings include: neutral aqueous wastes; aqueous halogenated organic liquids; ash; high organic content sludges; adsorbed aqueous and organic liquids; cement sludges, ashes, and solids; chloride; sulfate, and nitrate salts; organic matrix solids; heterogeneous debris; bulk combustibles; lab packs; and lead shapes. Insofar as possible, formulation of surrogate waste packages are referenced to authentic wastes in inventory within the DOE; however, the surrogate waste packages are intended to represent generic treatability group compositions. The intent is to specify a nonradiological synthetic mixture, with a minimal number of readily available components, that can be used to represent the significant challenges anticipated for treatment of the specified waste class. Performance testing and evaluation with use of a consistent series of surrogate wastes will provide a means for the initial assessment (and intercomparability) of candidate treatment technology applicability and performance. Originally the surrogate wastes were intended for use with emerging thermal treatment systems, but use may be extended to select nonthermal systems as well.

  20. Surrogate formulations for thermal treatment of low-level mixed waste, Part II: Selected mixed waste treatment project waste streams

    International Nuclear Information System (INIS)

    Bostick, W.D.; Hoffmann, D.P.; Chiang, J.M.; Hermes, W.H.; Gibson, L.V. Jr.; Richmond, A.A.; Mayberry, J.; Frazier, G.

    1994-01-01

    This report summarizes the formulation of surrogate waste packages, representing the major bulk constituent compositions for 12 waste stream classifications selected by the US DOE Mixed Waste Treatment Program. These waste groupings include: neutral aqueous wastes; aqueous halogenated organic liquids; ash; high organic content sludges; adsorbed aqueous and organic liquids; cement sludges, ashes, and solids; chloride; sulfate, and nitrate salts; organic matrix solids; heterogeneous debris; bulk combustibles; lab packs; and lead shapes. Insofar as possible, formulation of surrogate waste packages are referenced to authentic wastes in inventory within the DOE; however, the surrogate waste packages are intended to represent generic treatability group compositions. The intent is to specify a nonradiological synthetic mixture, with a minimal number of readily available components, that can be used to represent the significant challenges anticipated for treatment of the specified waste class. Performance testing and evaluation with use of a consistent series of surrogate wastes will provide a means for the initial assessment (and intercomparability) of candidate treatment technology applicability and performance. Originally the surrogate wastes were intended for use with emerging thermal treatment systems, but use may be extended to select nonthermal systems as well