WorldWideScience

Sample records for waste transfer station

  1. Waste Transfer Stations

    DEFF Research Database (Denmark)

    Christensen, Thomas Højlund

    2011-01-01

    tion and transport is usually the most costly part of any waste management system; and when waste is transported over a considerable distance or for a long time, transferring the waste from the collection vehicles to more efficient transportation may be economically beneficial. This involves...... a transfer station where the transfer takes place. These stations may also be accessible by private people, offering flexibility to the waste system, including facilities for bulky waste, household hazardous waste and recyclables. Waste transfer may also take place on the collection route from small...... describes the main features of waste transfer stations, including some considerations about the economical aspects on when transfer is advisable....

  2. Research on Layout Optimization of Urban Circle Solid Waste Transfer and Disposal Stations

    OpenAIRE

    Xuhui Li; Gangyan Li; Guowen Sun; Huiping Shi; Bao’an Yang

    2013-01-01

    Based on the Systematic Layout Planning theory and the analysis of transfer stations’ technological processes, a layout optimization model for solid waste transfer and disposal stations was made. The operating units’ layout of the solid waste transfer and disposal stations was simulated and optimized using the genetic algorithm, which could achieve reasonable technological processes, the smallest floor space and the lowest construction cost. The simulation result can also direct t...

  3. The Solid Waste Transfer Pit an FFTF [Fast Flux Test Facility] station for fuel and reflector transfer

    International Nuclear Information System (INIS)

    Milewski, A.J.; Thomson, J.D.

    1985-01-01

    This paper describes the design aspects of a proposed FFTF facility called the Solid Waste Transfer Pit (SWTP). This new facility will be used as a transfer station for reflectors and/or low decay heat fuel assemblies when movement from the Fuel Storage Facility for sodium removal and subsequent reprocessing is to be accomplished. The SWTP utilizes a shielded cell cover with an integral manually-operated gate valve for top loading of a transfer vessel. The cost-effective design discussed herein provides a practical approach using state-of-the-art concepts while assuring safe and reliable operation

  4. Pump station for radioactive waste water

    Science.gov (United States)

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

    2003-11-18

    A pump station for transferring radioactive particle containing waste water, includes: (a.) an enclosed sump having a vertically elongated right frusto conical wall surface and a bottom surface and (b.) a submersible volute centrifugal pump having a horizontally rotating impeller and a volute exterior surface. The sump interior surface, the bottom surface and the volute exterior surface are made of stainless steel having a 30 Ra or finer surface finish. A 15 Ra finish has been found to be most cost effective. The pump station is used for transferring waste water, without accumulation of radioactive fines.

  5. Transfer Stations for urban solid wastes. Design; Transferencia ferroviaria de residuos solidos domiciliarios. Alternativas para el diseno

    Energy Technology Data Exchange (ETDEWEB)

    Dussuel Jurado, E.

    2004-07-01

    On the basis of experience in the design of projects promoted by Spanish companies for Transfer Stations for Solid Domestic Waste (RSD) using the railway, aspects regarding location, technological alternatives, restrictions and dimensions are considered. The equipment necessary for the different options is described. The paper is concerned with the Metropolitan Area of Santiago (Chile) and comments on and discusses the regulatory restrictions laid down by the PRMS (Metropolitan Regulatory Plan for Santiago) affecting decisions on location, dimensions and design. Last of all, the costs of Transfer Stations are analysed depending on the distance from the sanitary landfill nd in comparison with the alternative by road, laying down convenience kerbs. Also analysed are the environmental advantages of the railway option as opposed to roads. (Author)

  6. Solid waste treatment processes for space station

    Science.gov (United States)

    Marrero, T. R.

    1983-01-01

    The purpose of this study was to evaluate the state-of-the-art of solid waste(s) treatment processes applicable to a Space Station. From the review of available information a source term model for solid wastes was determined. An overall system is proposed to treat solid wastes under constraints of zero-gravity and zero-leakage. This study contains discussion of more promising potential treatment processes, including supercritical water oxidation, wet air (oxygen) oxidation, and chemical oxidation. A low pressure, batch-type treament process is recommended. Processes needed for pretreatment and post-treatment are hardware already developed for space operations. The overall solid waste management system should minimize transfer of wastes from their collection point to treatment vessel.

  7. BATCH ANAEROBIC TREATMENT OF FRESH LEACHATE FROM TRANSFER STATION

    Directory of Open Access Journals (Sweden)

    SEYED MOHAMMAD DARA GHASIMI

    2008-12-01

    Full Text Available Leachate from transfer station requires treatment before being discharged into the environment to avoid surface and underground water contamination. Various factors such as waste composition, availability of oxygen and moisture, designing and controlling of transfer station operations have been shown to affect the composition of the leachate. The high COD, BOD, ammonia nitrogen (NH3-N and heavy metals contents of fresh leachate are the main problems faced by leachate treatment operators. The result of the present study indicated that this process reduced the COD content by 43%.The average removal efficiencies of BOD5, TS, TSS, and VSS were 80, 49, 37 and 39 %, respectively.

  8. 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

  9. Material Flow and Stakeholder Analysis for a Transfer & Recycling Station in Gaborone, Botswana

    OpenAIRE

    Andersson, Emil

    2014-01-01

    Landfilling waste material is still one of the most common methods to take care of waste in a big part of the world. Gaborone, the capital of Botswana located in the southern part of Africa is no different in this way. The major part of all waste is landfilled in Gaborone and there is only a minor part of all collected material that is recycled. One solution that earlier studies suggest is to build a transfer and recycling station in the city of Gaborone that can contribute to a more sustaina...

  10. Dealing with operational power station wastes

    Energy Technology Data Exchange (ETDEWEB)

    Pepper, R B [Central Electricity Generating Board, London (UK). Nuclear Health and Safety Dept.

    1981-08-01

    The disposal of wastes from nuclear power stations is discussed. Liquid and gaseous wastes, from magnox stations, which are of low level activity, are dispersed to the sea or estuaries on coastal sites or for the case of Trawfynyeld, to the nearby lake. Low activity solid wastes are either disposed of on local authority tips or in shallow land burial sites. Intermediate level wastes, consisting mainly of wet materials such as filter sludges and resins from cooling ponds, are at present stored in shielded storage tanks either dry or under water. Only one disposal route for intermediate waste is used by Britain, namely, sea-dumping. Materials for sea dumping have to be encapsulated in a durable material for example, concrete.

  11. Pumped energy transfer stations (STEP)

    International Nuclear Information System (INIS)

    Tournery, Jean-Francois

    2015-12-01

    As objectives of development are high for renewable energies (they are supposed to cover 50 per cent of new energy needs by 2035), pumped energy transfer stations are to play an important role in this respect. The author first discusses the consequences of the development of renewable energies on the exploitation of electric grids: issue of intermittency for some of them, envisaged solutions. Then, he addresses one of the solutions: the storage of electric power. He notices that increasing the potential energy of a volume of water is presently the most mature solution to face massive needs of the power system. Dams and pumped energy transfer stations represent now almost the whole installed storage power in the world. The author then presents these pumped energy transfer stations: principle, brief history (the first appeared in Italy and Switzerland at the end of the 1890's). He indicates the various parameters of assessment of such stations: maximum stored energy, installed power in pumping mode and turbine mode, time constant, efficiency, level of flexibility. He discusses economic issues. He describes and comments the operation of turbine-pump groups: ternary groups, reversible binary groups. He discusses barriers to be overcome and technical advances to be made for varying speed groups and for marine stations. He finally gives an overview (table with number of stations belonging to different power ranges, remarkable installations) of existing stations in China, USA, Japan, Germany, Austria, Spain, Portugal, Italy, Switzerland, France and UK, and indicate predictions regarding storage needs at the world level. Some data are finally indicated for the six existing French installations

  12. Self Calibrating Flow Estimation in Waste Water Pumping Stations

    DEFF Research Database (Denmark)

    Kallesøe, Carsten Skovmose; Knudsen, Torben

    2016-01-01

    Knowledge about where waste water is flowing in waste water networks is essential to optimize the operation of the network pumping stations. However, installation of flow sensors is expensive and requires regular maintenance. This paper proposes an alternative approach where the pumps and the waste...... water pit are used for estimating both the inflow and the pump flow of the pumping station. Due to the nature of waste water, the waste water pumps are heavily affected by wear and tear. To compensate for the wear of the pumps, the pump parameters, used for the flow estimation, are automatically...... calibrated. This calibration is done based on data batches stored at each pump cycle, hence makes the approach a self calibrating system. The approach is tested on a pumping station operating in a real waste water network....

  13. An optimization model for collection, haul, transfer, treatment and disposal of infectious medical waste: Application to a Greek region.

    Science.gov (United States)

    Mantzaras, Gerasimos; Voudrias, Evangelos A

    2017-11-01

    The objective of this work was to develop an optimization model to minimize the cost of a collection, haul, transfer, treatment and disposal system for infectious medical waste (IMW). The model calculates the optimum locations of the treatment facilities and transfer stations, their design capacities (t/d), the number and capacities of all waste collection, transport and transfer vehicles and their optimum transport path and the minimum IMW management system cost. Waste production nodes (hospitals, healthcare centers, peripheral health offices, private clinics and physicians in private practice) and their IMW production rates were specified and used as model inputs. The candidate locations of the treatment facilities, transfer stations and sanitary landfills were designated, using a GIS-based methodology. Specifically, Mapinfo software with exclusion criteria for non-appropriate areas was used for siting candidate locations for the construction of the treatment plant and calculating the distance and travel time of all possible vehicle routes. The objective function was a non-linear equation, which minimized the total collection, transport, treatment and disposal cost. Total cost comprised capital and operation costs for: (1) treatment plant, (2) waste transfer stations, (3) waste transport and transfer vehicles and (4) waste collection bins and hospital boxes. Binary variables were used to decide whether a treatment plant and/or a transfer station should be constructed and whether a collection route between two or more nodes should be followed. Microsoft excel software was used as installation platform of the optimization model. For the execution of the optimization routine, two completely different software were used and the results were compared, thus, resulting in higher reliability and validity of the results. The first software was Evolver, which is based on the use of genetic algorithms. The second one was Crystal Ball, which is based on Monte Carlo

  14. Estimating Pedestrian flows at train stations using the Station Transfer Model

    NARCIS (Netherlands)

    Van den Heuvel, J.P.A.; Dekkers, K.; De Vos, S.

    2012-01-01

    Train stations play a vital role in the door to door travel experience of train passengers. From the passengers’ value of time perspective, the station is the weakest link in total time value of the journey. Within the station the transfer function – moving between the various transport modes and

  15. Waste Feed Delivery Transfer System Analysis

    Energy Technology Data Exchange (ETDEWEB)

    JULYK, L.J.

    2000-05-05

    This document provides a documented basis for the required design pressure rating and pump pressure capacity of the Hanford Site waste-transfer system in support of the waste feed delivery to the privatization contractor for vitrification. The scope of the analysis includes the 200 East Area double-shell tank waste transfer pipeline system and the associated transfer system pumps for a11 Phase 1B and Phase 2 waste transfers from AN, AP, AW, AY, and A2 Tank Farms.

  16. Waste Feed Delivery Transfer System Analysis

    International Nuclear Information System (INIS)

    JULYK, L.J.

    2000-01-01

    This document provides a documented basis for the required design pressure rating and pump pressure capacity of the Hanford Site waste-transfer system in support of the waste feed delivery to the privatization contractor for vitrification. The scope of the analysis includes the 200 East Area double-shell tank waste transfer pipeline system and the associated transfer system pumps for a11 Phase 1B and Phase 2 waste transfers from AN, AP, AW, AY, and A2 Tank Farms

  17. Hanford Waste Transfer Planning and Control - 13465

    Energy Technology Data Exchange (ETDEWEB)

    Kirch, N.W.; Uytioco, E.M.; Jo, J. [Washington River Protection Solutions, LLC, Richland, Washington (United States)

    2013-07-01

    Hanford tank waste cleanup requires efficient use of double-shell tank space to support single-shell tank retrievals and future waste feed delivery to the Waste Treatment and Immobilization Plant (WTP). Every waste transfer, including single-shell tank retrievals and evaporator campaign, is evaluated via the Waste Transfer Compatibility Program for compliance with safety basis, environmental compliance, operational limits and controls to enhance future waste treatment. Mixed radioactive and hazardous wastes are stored at the Hanford Site on an interim basis until they can be treated, as necessary, for final disposal. Implementation of the Tank Farms Waste Transfer Compatibility Program helps to ensure continued safe and prudent storage and handling of these wastes within the Tank Farms Facility. The Tank Farms Waste Transfer Compatibility Program is a Safety Management Program that is a formal process for evaluating waste transfers and chemical additions through the preparation of documented Waste Compatibility Assessments (WCA). The primary purpose of the program is to ensure that sufficient controls are in place to prevent the formation of incompatible mixtures as the result of waste transfer operations. The program defines a consistent means of evaluating compliance with certain administrative controls, safety, operational, regulatory, and programmatic criteria and specifies considerations necessary to assess waste transfers and chemical additions. Current operations are most limited by staying within compliance with the safety basis controls to prevent flammable gas build up in the tank headspace. The depth of solids, the depth of supernatant, the total waste depth and the waste temperature are monitored and controlled to stay within the Compatibility Program rules. Also, transfer planning includes a preliminary evaluation against the Compatibility Program to assure that operating plans will comply with the Waste Transfer Compatibility Program. (authors)

  18. Intervention assessments in the control of PM10 emissions from an urban waste transfer station.

    Science.gov (United States)

    Barratt, B M; Fuller, G W

    2014-05-01

    While vehicle emissions present the most widespread cause of breaches of EU air quality standards in urban areas of the UK, the greatest PM10 concentrations are often recorded close to small industrial sites with significant and long-term public exposure within close proximity. This is particularly the case in London, where monitoring in densely populated locations, adjacent to waste transfer stations (WTS), routinely report the highest PM10 concentrations in the city. This study aims to assess the impact of dust abatement measures taken at a WTS in west London and, in so doing, develop analysis techniques transferrable to other similar industrial situations. The study was performed in a 'blinded fashion', i.e., no details of operating times, activities or remediation measures were provided prior to the analysis. The study established that PM10 concentrations were strongly related to the industrial area's working hours and atmospheric humidity. The primary source of local particulate matter during working hours was found to be from the industrial area itself, not from the adjacent road serving the site. CUSUM analysis revealed a strong, sustained change point coinciding with a number of modifications at the WTS. Analysis suggested that introducing a vehicle washer bay, leading to a less dry and dusty yard, and ceasing stock piling and waste handling activities outside of the open shed had the greatest effect on PM10 concentrations. The techniques developed in this study should empower licensing authorities to more effectively characterise and mitigate particulate matter generated by urban industrial activities, thereby improving the health and quality of life of the local population.

  19. What Makes Urban Transportation Efficient? Evidence from Subway Transfer Stations in Korea

    Directory of Open Access Journals (Sweden)

    Changhee Kim

    2017-11-01

    Full Text Available Subway stations have been proliferating underneath cosmopolitan metropolises with subway lines forming complex webs connected in strategic transfer stations. The efficiency of the subway system thus heavily weighs on the efficiency at these transfer stations. However, few studies have been conducted on transfer efficiency at transfer stations due to the complexities involved. As the first study of its kind in the subway context, we analyze the transfer efficiency of the subway transfer stations in Seoul, one of the megacities in the world, and demonstrate how transfer efficiency can be analyzed using bootstrap-based DEA technique. Based on the results, we discuss the reasons behind the inefficiency of subway transfer stations and possible ways to improve them into efficient decision-making units.

  20. Apparatus and method for treating waste material

    International Nuclear Information System (INIS)

    Allison, W.

    1981-01-01

    Apparatus is described for the packaging of waste material in a vessel, comprising: a vessel entry station having inlet and outlet doors; a filling station downstream of the vessel entry station and having a filling position to which vessels are transferred from the entry station through the outlet door, the filling station having filling means for introducing radioactive waste into the vessel; a mixing station having a mixing position to which a vessel is transferred from the filling position; a capping station having a capping position to which a vessel is transferred from the mixing position; and means for effecting transfer of a vessel through the apparatus. Radiation shielding is provided. (U.K.)

  1. Incinerators for radioactive wastes in Japanese nuclear power stations

    International Nuclear Information System (INIS)

    Karita, Yoichi

    1983-01-01

    As the measures of treatment and disposal of radioactive wastes in nuclear power stations, the development of the techniques to decrease wastes, to reduce the volume of wastes, to treat wastes by solidification and to dispose wastes has been advanced energetically. In particular, efforts have been exerted on the volume reduction treatment from the viewpoint of the improvement of storage efficiency and the reduction of transport and disposal costs. Incineration as one of the volume reduction techniques has been regarded as the most effective method with large reduction ratio, but it was not included in waste treatment system. NGK Insulators Ltd. developed NGK type miscellaneous solid incinerators, and seven incinerators were installed in nuclear power stations. These incinerators have been operated smoothly, and the construction is in progress in six more plants. The necessity of incinerators in nuclear power stations and the problems in their adoption, the circumstance of the development of NGK type miscellaneous solid incinerators, the outline of the incinerator of Karlsruhe nuclear power station and the problems, the contents of the technical development in NGK, the outline of NGK type incinerators and the features, the outline of the pretreatment system, incinerator system, exhaust gas treatment system, ash taking out system and accessory equipment, the operational results and the performance are described. (Kako, I.)

  2. PLUGGING AND UNPLUGGING OF WASTE TRANSFER PIPELINES

    International Nuclear Information System (INIS)

    Ebadian, M.A.

    1999-01-01

    This project, which began in FY97, involves both the flow loop research on plugging and unplugging of waste transfer pipelines, and the large-scale industrial equipment test of plugging locating and unplugging technologies. In FY98, the related work was performed under the project name ''Mixing, Settling, and Pipe Unplugging of Waste Transfer Lines.'' The mixing, settling, and pipeline plugging and unplugging are critical to the design and maintenance of a waste transfer pipeline system, especially for the High-Level Waste (HLW) pipeline transfer. The major objective of this work is to recreate pipeline plugging conditions for equipment testing of plug locating and removal and to provide systematic operating data for modification of equipment design and enhancement of performance of waste transfer lines used at DOE sites. As the waste tank clean-out and decommissioning program becomes active at the DOE sites, there is an increasing potential that the waste slurry transfer lines will become plugged and unable to transport waste slurry from one tank to another or from the mixing tank to processing facilities. Transfer systems may potentially become plugged if the solids concentration of the material being transferred increases beyond the capability of the prime mover or if upstream mixing is inadequately performed. Plugging can occur due to the solids' settling in either the mixing tank, the pumping system, or the transfer lines. In order to enhance and optimize the slurry's removal and transfer, refined and reliable data on the mixing, sampling, and pipe unplugging systems must be obtained based on both laboratory-scale and simulated in-situ operating conditions

  3. Heat transfer in high-level waste management

    International Nuclear Information System (INIS)

    Dickey, B.R.; Hogg, G.W.

    1979-01-01

    Heat transfer in the storage of high-level liquid wastes, calcining of radioactive wastes, and storage of solidified wastes are discussed. Processing and storage experience at the Idaho Chemical Processing Plant are summarized for defense high-level wastes; heat transfer in power reactor high-level waste processing and storage is also discussed

  4. 77 FR 69769 - Solid Waste Rail Transfer Facilities

    Science.gov (United States)

    2012-11-21

    ...] Solid Waste Rail Transfer Facilities AGENCY: Surface Transportation Board, DOT. ACTION: Final rules. SUMMARY: These final rules govern land-use-exemption permits for solid waste rail transfer facilities. The... Transportation Board over solid waste rail transfer facilities. The Act also added three new statutory provisions...

  5. Waste Transfer Leaks Control Decision Record

    International Nuclear Information System (INIS)

    RYAN, G.W.

    2000-01-01

    Control decision meetings for Waste Transfer Leaks were held on April 24,25,26, and 27, 2000. The agenda for the control decision meetings is included in Appendix A, and attendee lists are included in Appendix B. The purpose of the control decision meetings was to review and revise previously selected controls for the prevention or mitigation of waste transfer leak accidents. Re-evaluation of the controls is warranted due to revisions in the hazard and accident analysis for these Tank Farm events. In particular, calculated radiological consequences are significantly reduced from those currently reported in the Final Safety Analysis Report (FSAR). Revised hazard and accident analysis and a revised control recommendation will be reflected in an Authorization Basis Amendment to be submitted at the Department of Energy, Office of River Protection's (ORP's) request by June 30, 2000 to satisfy ORP Performance Incentive (PI) 2.1.1, Revision 1, ''Authorization Basis Management Process Efficiency Improvement''. The scope of the control decision meetings was to address all waste transfer leak-related hazardous conditions identified in the Tank Farm hazard analysis database, excluding those associated with the use of the Replacement Cross-Site Transfer System (RCSTS) slurry line and sluicing of Tank 241-C-106, which is addressed in FSAR Addendum 1. The scope of this control decision process does include future waste feed delivery waste transfer operations

  6. Corrosion control for the Hanford site waste transfer system

    International Nuclear Information System (INIS)

    Haberman, J.H.

    1995-01-01

    Processing large volumes of spent reactor fuel and other related waste management activities produced radioactive wastes which have been stored in underground high-level waste storage tanks since the 1940s. The effluent waste streams from the processing facilities were stored underground in high-level waste storage tanks. The waste was transferred between storage tanks and from the tanks to waste processing facilities in a complex network of underground piping. The underground waste transfer system consists of process piping, catch tanks, lift tanks, diversion boxes, pump pits, valves, and jumpers. Corrosion of the process piping from contact with the soil is a primary concern. The other transfer system components are made of corrosion-resistant alloys or they are isolated from the underground environment and experience little degradation. Corrosion control of the underground transfer system is necessary to ensure that transfer routes will be available for future waste retrieval, processing,a nd disposal. Today, most waste transfer lines are protected by an active impressed-current cathodic protection (CP) system. The original system has been updated. Energization surveys and a recent base-line survey demonstrate that system operational goals are met

  7. 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

  8. Radioactive waste management at nuclear electric power stations

    International Nuclear Information System (INIS)

    Gordelier, S.C.

    1993-01-01

    After suitable treatment, gaseous and liquid wastes are routinely discharged from Nuclear Electric's stations and are diluted and dispersed in the environment. The discharges are controlled and authorized under UK legislation and the environmental impact is minimal. Most solid wastes were originally accumulated at the site of origin, but since 1978 low level wastes (LLW) have been send to the UK's main disposal site at Drigg. Recent changes at Drigg have resulted in changed arrangements for the transport and disposal of low-level wastes, including volume reduction by supercompaction. Small amounts of intermediate-level waste (ILW) have been conditioned and disposed of in the sea but this route is now effectively closed and there is currently no disposal route for ILW in the UK. Spent ion exchange resins at one power station have been conditioned and are stored pending the availability of a disposal route. Most ILW will continue to be stored in retrievable form on the site of origin until a mobile waste treatment plant can be brought into use. The timing of this will be subject to agreement with the regulators. In the case of Magnox fuel element debris, a demonstration dissolution plant has been constructed and this will significantly reduce the volume of waste being stored while retaining the bulk of the activity on site for later treatment. A further development has been the construction of a new facility which will hold Magnox fuel element debris in 500 liter drums

  9. Shippingport station decommissioning project technology transfer program

    International Nuclear Information System (INIS)

    McKernan, M.L.

    1989-01-01

    The US Department of Energy (DOE) Shippingport Station Decommissioning Project (SSDP) decontaminated and dismantled the world's first nuclear-fueled, commercial-size electric power plant. The SSDP programmatic goal direction for technology transfer is documentation of project management and operations experience. The objective is to provide future nuclear facility decommissioning projects with pertinent SSDP performance data for project assessment, planning, and operational implementation. This paper sets out access and availability directions for SSDP technology acquisition. Discusses are technology transfer definition; technology transfer products including topical and other project reports, professional-technical society presentations, other project liaison and media relations, visual documentation, and technology transfer data base; and retrieving SSDP information

  10. Nevada test site defense waste acceptance criteria, certification, and transfer requirements

    International Nuclear Information System (INIS)

    1988-10-01

    The Nevada Test Site (NTS) Defense Waste Acceptance Criteria, Certification and Transfer Requirements establishes procedures and criteria for safe transfer, disposal, and storage of defense transuranic, low-level, and mixed waste at the NTS. Included are an overview of the NTS defense waste management program; the NTS waste acceptance criteria for transuranic, low-level, and mixed wastes; waste certification requirements and guidance; application to submit waste; and requirements for waste transfer and receipt. 5 figs., 16 tabs

  11. Soluble pig for radioactive waste transfer lines

    International Nuclear Information System (INIS)

    Ohl, P.C.; Pezeshki, C.

    1997-01-01

    Flushing transfer pipe after radioactive waste transfers generates thousands of gallons of additional radioactive waste each year at the Hanford site. The use of pneumatic pigging with waste soluble pigs as a means to clear transfer piping may be an effective alternative to raw water flushes. A feasibility study was performed by a group of senior mechanical engineering students for their senior design project as part of their curriculum at Washington State University. The students divided the feasibility study into three sub-projects involving: (1) material research, (2) delivery system design, and (3) mockup fabrication and testing. The students screened through twenty-three candidate materials and selected a thermoplastic polymer combined 50:50 wt% with sucrose to meet the established material performance criteria. The students also prepared a conceptual design of a remote pneumatic delivery system and constructed a mockup section of transfer pipe for testing the prototype pigs

  12. 75 FR 26268 - Agency Information Collection Activities: Permit To Transfer Containers to a Container Station

    Science.gov (United States)

    2010-05-11

    ... Activities: Permit To Transfer Containers to a Container Station AGENCY: U.S. Customs and Border Protection... information collection requirement concerning the: Permit to Transfer Containers to a Container Station. This... information collection: Title: Permit to Transfer Containers to a Container Station. OMB Number: 1651-0049...

  13. Shippingport station decommissioning project technology transfer program

    International Nuclear Information System (INIS)

    Pasquini, L.A.

    1986-01-01

    The purpose of the Shippingport Station Decommissioning Project (SSDP) is to place the Shippingport Atomic Power Station in a long-term radiologically safe condition following defueling of the reactor, to perform decommissioning in such a manner as to demonstrate to the nuclear industry the application of decommissioning procedures to a large scale nuclear power plant, and to provide useful planning data for future decommissioning projects. This paper describes the Technology Transfer Program for collecting and archiving the decommissioning data base and its availability to the nuclear industry

  14. Material Balance Assessment for Double-Shell Tank Waste Pipeline Transfer

    International Nuclear Information System (INIS)

    Onishi, Yasuo; Wells, Beric E; Hartley, Stacey A; Enderlin, Carl W

    2001-01-01

    PNNL developed a material balance assessment methodology based on conservation of mass for detecting leaks and mis-routings in pipeline transfer of double-shell tank waste at Hanford. The main factors causing uncertainty in these transfers are variable property and tank conditions of density, existence of crust, and surface disturbance due to mixer pump operation during the waste transfer. The methodology was applied to three waste transfers from Tanks AN-105 and AZ-102

  15. Optimization of waste transportation route at waste transfers point in Lowokwaru District, Malang City

    Science.gov (United States)

    Hariyani, S.; Meidiana, C.

    2018-04-01

    Increasing population led to the emergence of the urban infrastructure services issue including waste problems especially waste transportation system. Data in 2016 shows that the amount of waste in Malang was 659.21 tons / day. The amount of waste transported to landfill only reached 464.74 tons / day. This indicates that not all waste can be transported to the landfill Supiturang because Level of Service (LoS) reached 70.49%. This study aims to determine the effectiveness of waste transportation system and determine the fastest route from waste transfers point in Lowokwaru district to the landfill Supiturang. The data collection method in this research were 1) primary survey by interview officials from the Sanitation and Gardening Agency which questions related to the condition of the waste transportation system in waste transfer point, 2) Secondary survey related to data of waste transportation system in Malang City i.e the amount of waste generation in waste transfer point, number of garbage trucks and other data related to the garbage transportation system. To determine the fastest route analyzed by network analyst using ArcGIS software. The results of network analyst show that not all routes are already using the fastest route to the landfill Supiturang.

  16. Shippingport station decommissioning project technology transfer program

    International Nuclear Information System (INIS)

    McKernan, M.L.

    1988-01-01

    US Department of Energy (DOE) Shippingport Station Decommissioning Project (SSDP) decommissioned, decontaminated, and dismantled the world's first, nuclear fueled, commercial size, electric power plant. SSDP programmatic goal direction for technology transfer is documentation of project management and operations experience. Objective is to provide future nuclear facility decommissioning projects with pertinent SSDP performance data for project assessment, planning, and operational implementation. This paper presents a working definition for technology transfer. Direction is provided for access and availability for SSDP technology acquisition

  17. Radioactive waste management at Narora atomic power station in India

    International Nuclear Information System (INIS)

    Prasad, P.N.; Gupta, J.P.; Mittal, S.

    2001-01-01

    Modern society creates waste material, which have to be disposed of in nature without disturbing the ecological equilibrium. Hence effective waste management in all industries is a major concern today. Narora Atomic Power Station (NAPS) generates low and intermediate level liquid, solid and gaseous wastes during its operation and maintenance. The generation of wastes is controlled at the source itself. The wastes are managed by adequate and appropriate treatment before being released into the environment. Different types of liquid wastes are treated by chemical co-precipitation, ion exchange, evaporation, filtration, and dilution techniques. For handling and conditioning of solid wastes, volume reduction techniques such as incineration and baling are employed. The treated wastes are immobilised by incorporation into cement and polymer matrices. Gaseous waste is cleaned by passing through pre-filters and high efficiency particulate (HEPA) filters and diluted with inactive air prior to release to the atmosphere through a 145 m high stack to get further atmospheric dilution. Regular monitoring up to 30 km radius is carried out by fully equipped Environmental Survey and Micrometeorological Laboratory which functions independently under the Directorate of Health and Safety, Bhabha Atomic Research Centre (BARC), Mumbai. So far, the annual maximum dose to the public around NAPS is reported to be 0.2 to 0.3% of limit of 1 mSv/year recommended by the International Commission on Radiological Protection (ICRP). A decade of experience has proved that present practices of nuclear waste management at Narora Atomic Power Station are quite safe and effective with respect to ecological equilibrium. (author)

  18. Radioactive waste treatment system for Tsuruga Nuclear Power Station

    International Nuclear Information System (INIS)

    Taniguchi, Takashi; Takeshima, Masaki; Saito, Toru; Kikkawa, Ryozo

    1978-01-01

    The augmentation of the radioactive waste treatment system in the Tsuruga Nuclear Power Station was planned in 1973, and this enlarged facility was completed in June, 1977. The object of this augmentation is to increase the storage capacity for wastes and to enlarge the treating capacity utilizing the newly installed facility. The operating experience in the facility having been already constructed was fed back for the engineering of this new facility. This new facility contains the newly developed vacuum forced circulation type concentrator, the exclusive storage pool for solid wastes, etc. At the design stage of this new system, the pilot plant test of slurry transportation and the corrosion test of long hours were carried out as the research and developmental works for the confirmation of correct design condition. The measures for augmenting this radioactive waste treatment system are the installation of a long time storage tank with the capacity of 350 m 3 , the sit bunker facility and the drum storage as the storage facility, and the vacuum forced circulation type concentrator with the circulating flow rate more than 200 times as much as the treating flow rate and vacuum level of 0.255 ata. The augmented system is shown with the flow sheet of whole waste disposal system. The flow sheet of the concentrator is separately shown, and the relating research and developmental works, for example, the test of the cause of corrosion, the surface finishing test, the material test, the blockage test for heat transfer tubes and the inhibiter test, are explained with the test results. The ion exchange resin is transported by air and water as the slurry state, and the long distance transport of about 250 m is required in this new system. As clogging has to be avoided in this transportation, the experimental work was conducted to obtain the flow characteristics of slurry, and the test result is outlined. (Nakai, Y.)

  19. Ways of solving the problems of radiation safety and environmental protection in handling radioactive waste at atomic power stations in the USSR

    International Nuclear Information System (INIS)

    Gusev, D.I.; Belitskij, A.S.; Turkin, A.D.; Kozlov, V.M.

    1977-01-01

    Requirements of the State Sanitary Supervision on radiation safety of the personnel and population and on protection of the environment in handling radioactive wastes from nuclear power stations in the USSR are regulated by the Standards of Radiation Safety, the Main Sanitary Rules for Handling Radioactive Materials and by the Sanitary Rules for Designing Nuclear Power Stations. The regulations contained in these documents are obligatory for all the establishments at the stages of design, building and operation of nuclear power stations. The main requirement for handling radioactive wastes from nuclear power stations in the USSR is to dispose of them near the place of their production. In nuclear power station siting and designing the special territory is provided for liquid and solid radioactive wastes storage taking into account the whole period of nuclear power station operation. These storage sites are located within the controlled area. They are built as required, usually for five years. The report contains hygienic and hydrological requirements to the radiation waste burial sites and data on the accepted system of controlling leak-proof qualities of the disposal cavities and radioactivity of the ground water in this region. The results of long-term studies on radionuclide leaching from the bituminic blocks are given and it is shown that the bituminizing method used for solidification of intermediate activity wastes is very promising. In the USSR much attention is given to the problem of sanitary protection of the cooling ponds at nuclear power stations. No limits to the national-economic use of these ponds outside the nuclear power station site are established. Therefore in determining the requirements to the discharge of effluents into the cooling ponds of nuclear power stations the possibility of radionuclide transfer to the population through the aquaeous and terrestrial biological chains is taken into account. The possibility of human diet contamination

  20. Shippingport station decommissioning project irradiated components transfer: Topical report

    International Nuclear Information System (INIS)

    1988-01-01

    This topical report is a synopsis of the transfer of irradiated components into the Shippingport Reactor Pressure Vessel (RPV) performed at the Shippingport Station Decommissioning Project (SSDP). The information is provided as a part of the Technology Transfer Program to document the preparation activities for the decommissioning of a nuclear power reactor to be removed in one piece

  1. Removing radio-active wastes from nuclear power stations by the STEAG system

    International Nuclear Information System (INIS)

    Baatz, H.

    1978-01-01

    The mobile STEAG System for conditioning radio-active wastes from nuclear power stations represents a particularly safe and economic method of removing them in present day conditions. Cementation by the FAFNIR System is used for the greater part of the waste, the liquid concentrate (evaporator concentrate and filter slurry). For the special case of the medium active resin balls from the primary circuits, embedding in plastic by the FAMA process has proved to be the only available successful process so far. The highly active solid waste from the reactor core is decomposed by the MOSAIK System, is packed in transportable and storable containers and is removed from the fuel element storage pond. The systems are so safe that faults or interruptions of power station operation due to faults in removing radio-active wastes can be excluded. (orig.) [de

  2. Waste minimization successes at McGuire Nuclear Station

    International Nuclear Information System (INIS)

    Correll, J.C.; Johnson, G.T.

    1995-01-01

    McGuire Nuclear Station is a two unit, 1125 MWe PWR located 25 miles north of Charlotte, North Carolina. It is a Westinghouse Ice Condenser plant that is owned and operated by Duke Power Company. At Duke Power, open-quotes Culture Changeclose quotes is a common term that we have used to describe the incredible transformation that we are making to become a cost conscious, customer driven, highly competitive business. Nowhere has this change been more evident then in the way we process and disposed of our solid radioactive waste. With top-down management support, we have used team-based, formalized, problem solving methods and have implemented many successful waste minimization programs. Through these programs, we have dramatically increased employees close-quote awareness of the importance of waste minimization. As a result, we have been able to reduce both our burial volumes and our waste processing and disposal costs

  3. Process for treating waste water containing hydrazine from power stations

    International Nuclear Information System (INIS)

    Hoffmann, W.

    1982-01-01

    A process for treating waste water containing hydrazine from nuclear power stations is proposed, characterized by the fact that the water is taken continuously through a water decomposition cell. If the water does not have sufficient conductivity itself, a substance raising the electrical conductivity is added to the water to be treated. The electrolysis is situated in the waste water tank. (orig./RB) [de

  4. Technology transfer and the management of radioactive waste

    International Nuclear Information System (INIS)

    Bonne, A.; Chan-Sands, C.

    1998-01-01

    One of the IAEA's fundamental roles is to act as a centre for the transfer of nuclear technologies, including those for managing radioactive wastes. In the area of waste management technology, the Agency is actively working to improve and develop new and efficient means to fulfill that responsibility. Recognizing its responsibilities and challenges, IAEA efforts related to radioactive waste management technologies into the next century are framed around three major areas: the development and implementation of mechanisms for better technology transfer and information exchange; the promotion of sustainable and safer processes and procedures; and the provision of peer reviews and direct technical assistance that help facilitate bilateral and multinational efforts. To illustrate some specific elements of the overall programme, this article reviews selected technology-transfer activities that have been initiated in the field

  5. Radiological risk curves for the liquid radioactive waste transfer from Angra 1 to Angra 2 nuclear power plants by a container tank

    International Nuclear Information System (INIS)

    Alves, A.S.M.; Passos, E.M. dos; Duarte, J.P.

    2013-01-01

    Eletrobras Termonuclear has a radiowaste management program focused on reducing the produced volumes, for which it has considered to transfer Angra 1 liquid radioactive waste by a container tank to be processed and packed in Angra 2. This paper presents a radiological risk study for providing the necessary technical foundations to obtain the license from the regulatory agency for implementing this transfer operation. Out of the 92 accident scenarios identified with the help of a preliminary hazard analysis, the greatest risk of fatal cancer for members of the public was equal to 6.9 x 10 -13 fatalities/yr, which refers to the accident scenario involving intrinsic failures of valves, hoses, flanges, seals, gaskets and instrumentation lines, while filling the container tank at Angra 1 filling station. This risk figure is about ten million times less than the one adopted by Eletronuclear for such a waste transfer. The highest frequency was also associated with this type of scenario, and its value was equal to 1.4 x 10 -6 yr -1 . This paper also presents and discusses the radiological risk curves for the three possible in-plant transfer routes, the Angra 1 filling station and Angra 2 discharging station and the overall risk curve in order to allow for a broader perspective of the results obtained. These risk curves display the accident scenarios frequencies against radiation doses by considering relevant in-plant and surroundings release paths. In these curves, the extreme scenarios mentioned earlier can be clearly identified in terms of occurrence frequencies and radiation doses. (author)

  6. Recycling by coverting organic waste to fertilize at Ikata Nuclear Power Station

    International Nuclear Information System (INIS)

    Kubota, T.; Matsuoka, H.

    2008-01-01

    In order to cope with global- warming and Dioxin issue, we started the Project in which all kinds of organic wastes originated on site are fermented to organic fertilizer with the help of YM bacteria in 2001. And in 2006 our product was officially approved as fertilizer by regulatory body, and then we started to sell these fertilizers to farmers near-by. Among many power stations in Japan, Ikata Nuclear Power Station may be the first plant where organic wastes are totally reused as commercial-based fertilizer. (author)

  7. 75 FR 43536 - Agency Information Collection Activities: Permit To Transfer Containers to a Container Station

    Science.gov (United States)

    2010-07-26

    ... Activities: Permit To Transfer Containers to a Container Station AGENCY: U.S. Customs and Border Protection... Transfer Containers to a Container Station. This is a proposed extension of an information collection that... other technological techniques or other forms of information. Title: Permit to Transfer Containers to a...

  8. Using geographic information system (GIS) to determine waste ...

    African Journals Online (AJOL)

    lyndon

    could be used as waste transfer stations in relation to location of landfill sites using Geographic. Information ... Coast, bounded to the east by the Ga East Municipal Assembly, to the west by the .... Solid Waste and the Hierarchy in Solid Waste.

  9. Evaluation of tank waste transfers at 241-AW tank farm

    International Nuclear Information System (INIS)

    Willis, W.L.

    1998-01-01

    A number of waste transfers are needed to process and feed waste to the private contractors in support of Phase 1 Privatization. Other waste transfers are needed to support the 242-A Evaporator, saltwell pumping, and other ongoing Tank Waste Remediation System (TWRS) operations. The purpose of this evaluation is to determine if existing or planned equipment and systems are capable of supporting the Privatization Mission of the Tank Farms and continuing operations through the end of Phase 1B Privatization Mission. Projects W-211 and W-314 have been established and will support the privatization effort. Equipment and system upgrades provided by these projects (W-211 and W-314) will also support other ongoing operations in the tank farms. It is recognized that these projects do not support the entire transfer schedule represented in the Tank Waste Remediation system Operation and Utilization Plan. Additionally, transfers surrounding the 241-AW farm must be considered. This evaluation is provided as information, which will help to define transfer paths required to complete the Waste Feed Delivery (WFD) mission. This document is not focused on changing a particular project, but it is realized that new project work in the 241-AW Tank Farm is required

  10. Solid waste processing experience at Susquehanna Steam Electric Station

    International Nuclear Information System (INIS)

    Phillips, J.W.; Granus, M.W.

    1984-01-01

    This paper reviews the first year's operation at the Susquehanna Steam Electric Station (SSES) with respect to the Westinghouse Hittman Nuclear Incorporated (Hittman) mobile solidification system and the dry activated waste generation, handling and processing. Experiences pertinent to the mobile solidification system are reviewed with emphasis on the integration of the system into the plant, problems associated with unexpected waste properties and the myriad of operating procedures that had to be prepared. The processing history for 1983 is reviewed in terms of the volume of waste, including solidified wastes, dewatered wastes an DAW. Factors that must be considered in evaluating processing alternatives, i.e., dewatering vs. solidification; steel liners vs. HICs, are discussed. Actions taken by Hittman and SSES to maximize the processing economics are also discussed. Finally, recommendations are provided to the utility considering implementing mobile solification services to ensure a smooth and timely integration of services into the plant

  11. Mixed Wastes Vitrification by Transferred Plasma

    International Nuclear Information System (INIS)

    Tapia-Fabela, J.; Pacheco-Pacheco, M.; Pacheco-Sotelo, J.; Torres-Reyes, C.; Valdivia-Barrientos, R.; Benitez-Read, J.; Lopez-Callejas, R.; Ramos-Flores, F.; Boshle, S.; Zissis, G.

    2007-01-01

    Thermal plasma technology provides a stable and long term treatment of mixed wastes through vitrification processes. In this work, a transferred plasma system was realized to vitrify mixed wastes, taking advantage of its high power density, enthalpy and chemical reactivity as well as its rapid quenching and high operation temperatures. To characterize the plasma discharge, a temperature diagnostic is realized by means of optical emission spectroscopy (OES). To typify the morphological structure of the wastes samples, scanning electron microscopy (SEM), and X-ray diffraction (XRD) techniques were applied before and after the plasma treatment

  12. Development of bagless transfer system for standard waste boxes

    International Nuclear Information System (INIS)

    Presgrove, S.B.; Patel, K.

    1991-01-01

    At several DOE site, substantial volumes of Transuranic (TRU) waste has been handled on a daily basis. Usually, the waste has been transferred from the facilities to the Waste Isolation Pilot Plant (WIPP) or to an on site storage facility using the ''bag-out'' technique. This process begins in the most contaminated area by placing the waste in a strong plastic bag, twisting closed the neck of the bag, then taping the closed neck. This reduces the exposed TRU waste and the resulting contamination. However, even though that the contamination is reduced, it remains high enough to prevent direct transfer into the environment. In order to reduce the contamination to acceptable levels, the ''bag-out'' process is repeated until the outside contamination on the plastic bag is acceptable. This procedure has been affective, however, it also generates organic waste in the process. During the design of the Transuranic Waste Facility (TWF) at the Savannah River Site, a conceptual alternative was developed using the Standard Waste Box (SWB)

  13. Treatment of alpha-bearing combustible wastes using acid digestion

    International Nuclear Information System (INIS)

    Lerch, R.E.; Allen, C.R.; Blasewitz, A.G.

    1978-01-01

    Acid digestion has been developed at the Hanford Engineering Development Laboratory (HEDL) in Richland, Washington to reduce the volume of combustible nuclear waste materials, while converting them to an inert, noncombustible residue. A 100 kg/day test unit has recently been constructed to demonstrate the process using radioactively contaminated combustible wastes. The unit, called the Radioactive Acid Digestion Test Unit (RADTU) was completed in September 1977 and is currently undergoing cold shakedown tests. Hot operation is expected in May 1978. Features of RADTU include: storage and transfer station for incoming wastes, a feed preparation station, an extrusion feed mechanism for transfer of the waste to the acid digester, the acid digester a residue recovery system, and an off-gas treatment system

  14. Treatment of alpha-bearing combustible wastes using acid digestion

    International Nuclear Information System (INIS)

    Lerch, R.E.; Allen, C.R.; Blasewitz, A.G.

    1977-11-01

    Acid digestion has been developed at the Hanford Engineering Development Laboratory (HEDL) in Richland, Washington to reduce the volume of combustible nuclear waste materials, while converting them to an inert, noncombustible residue. A 100 kg/day test unit has recently been constructed to demonstrate the process using radioactively contaminated combustible wastes. The unit, called the Radioactive Acid Digestion Test Unit (RADTU) was completed in September 1977 and is currently undergoing cold shakedown tests. Hot operation is expected in May 1978. Features of RADTU include: storage and transfer station for incoming wastes, a feed preparation station, an extrusion feed mechanism for transfer of the waste to the acid digester, the acid digester, a residue recovery system, and an off-gas treatment system

  15. Shippingport Station Decommissioning Project

    International Nuclear Information System (INIS)

    1989-01-01

    This Topical Report is a synopsis of the decontamination of plant components and structures at the Shippingport Station Decommissioning Project (SSDP). The information is provided as a part of the Technology Transfer Program to document the preparation activities in support of the shipment of radioactive wastes and the unconditional release of the site and structural materials. 1 ref., 16 figs., 4 tabs

  16. Control Decisions for Flammable Gas Hazards in Waste Transfer Systems

    International Nuclear Information System (INIS)

    KRIPPS, L.J.

    2000-01-01

    This report describes the control decisions for flammable gas hazards in waste transfer systems (i.e., waste transfer piping and waste transfer-associated structures) made at control decision meetings on November 30, 1999a and April 19, 2000, and their basis. These control decisions, and the analyses that support them, will be documented in an amendment to the Final Safety Analysis Report (FSAR) (CHG 2000a) and Technical Safety Requirements (TSR) (CHG 2000b) to close the Flammable Gas Unreviewed Safety Question (USQ) (Bacon 1996 and Wagoner 1996). Following the Contractor Tier I review of the FSAR and TSR amendment, it will be submitted to the US. Department of Energy (DOE), Office of River Protection (ORP) for review and approval. The control decision meeting on November 30, 1999 to address flammable gas hazards in waste transfer systems followed the control decision process and the criteria for control decisions described in Section 3.3.1.5 of the FSAR. The control decision meeting agenda, attendance list, and introductory and background presentations are included in Attachments 1 through 4. The control decision discussions on existing and other possible controls for flammable gas hazards in waste transfer systems and the basis for selecting or not selecting specific controls are summarized in this report

  17. 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

  18. Ariane transfer vehicle scenario

    Science.gov (United States)

    Deutscher, Norbert; Cougnet, Claude

    1990-10-01

    ESA's Ariane Transfer Vehicle (ATV) is a vehicle design concept for the transfer of payloads from Ariane 5 launch vehicle orbit insertion to a space station, on the basis of the Ariane 5 program-developed Upper Stage Propulsion Module and Vehicle Equipment Bay. The ATV is conceived as a complement to the Hermes manned vehicle for lower cost unmanned carriage of logistics modules and other large structural elements, as well as waste disposal. It is also anticipated that the ATV will have an essential role in the building block transportation logistics of any prospective European space station.

  19. Purification and solidification of reactor wastes at a Canadian nuclear generating station

    International Nuclear Information System (INIS)

    Buckley, L.P.; Burt, D.A.

    1981-06-01

    Chalk River Nuclear Laboratories are developing methods to condition power reactor wastes and to immobilize their radionuclides. Evaporation alone and combined with bituminization has been an important part of the program. After testing at the laboratories a 0.5 m 2 wiped-film evaporator was sent to the Douglas Point Nuclear Generating Station (220 MWe) to demonstrate its suitability to handle typical reactor liquid wastes. Two specific tasks undertaken with the wiped-film evaporator were successfully completed. The first was purification of contaminated heavy water which had leaked from the moderator circuit. The heavy water is normally recovered, cleaned by filters and ion-exchange resin and then upgraded by electrolysis. Cleaning the heavy water with the wiped-film evaporator produced better quality water for upgrading than had been achieved by any previous method and at much lower operating cost. The second task was to concentrate and immobilize a decontamination waste. The waste was generated from the decontamination of pump bowls used in the primary heat transport circuit. The simultaneous addition of the liquid waste and bitumen emulsion to the wiped-film evaporator produced a solid containing 30 wt% waste solids in a bitumen matrix. The volume reduction achieved was 16:1 based on the volumes of initial liquid waste and the final product generated. The quantity sent to storage was 20 times less than had the waste been immobilized in a cement matrix. The successful demonstration has resulted in a proposal to install a wiped-film evaporator at the station to clean heavy water and immobilize decontamination wastes. (author)

  20. International Space Station USOS Waste and Hygiene Compartment Development

    Science.gov (United States)

    Link, Dwight E., Jr.; Broyan, James Lee, Jr.; Gelmis, Karen; Philistine, Cynthia; Balistreri, Steven

    2007-01-01

    The International Space Station (ISS) currently provides human waste collection and hygiene facilities in the Russian Segment Service Module (SM) which supports a three person crew. Additional hardware is planned for the United States Operational Segment (USOS) to support expansion of the crew to six person capability. The additional hardware will be integrated in an ISS standard equipment rack structure that was planned to be installed in the Node 3 element; however, the ISS Program Office recently directed implementation of the rack, or Waste and Hygiene Compartment (WHC), into the U.S. Laboratory element to provide early operational capability. In this configuration, preserved urine from the WHC waste collection system can be processed by the Urine Processor Assembly (UPA) in either the U.S. Lab or Node 3 to recover water for crew consumption or oxygen production. The human waste collection hardware is derived from the Service Module system and is provided by RSC-Energia. This paper describes the concepts, design, and integration of the WHC waste collection hardware into the USOS including integration with U.S. Lab and Node 3 systems.

  1. Analysis of the effects of explosion of a hydrogen cylinder on the transfer of radioactive liquid wastes at nuclear power stations

    International Nuclear Information System (INIS)

    Lopes, Karina B.; Melo, Paulo Fernando F.F. e

    2011-01-01

    This work presents a study of explosion effects of a stored hydrogen cylinder on the transfer of radioactive liquid wastes at nuclear power plants. The peak overpressure is calculated, as well as the strength of resulting fragments, thus confirming the main harmful effect of an explosion of flammable vapor cloud, based on the TNT equivalent method. The scenarios identified are calculated and compared with the overpressure ranges of 1%, 50% and 99% of structural damages, which were determined by the Eisenberg's vulnerability model. The results show that the overpressure and the resulting fragments from the explosion of a hydrogen gas cylinder are not able to cause the overturning of the tanker under study, and also show that a minimum distance of 30 meters between the hydrogen cylinder and the tanker can be considered a safe distance to the passage of this tanker during the transfer of radioactive liquid waste, in which the likelihood of occurrence of structural damages is less than 1%. (author)

  2. Design assessment for Melton Valley liquid low-level waste collection and transfer system upgrade project at Oak Ridge National Laboratory, Oak Ridge, Tennessee

    International Nuclear Information System (INIS)

    1994-10-01

    This project is designed for collecting liquid low level waste (LLLW) from generating points inside the Radioisotope Engineering and Development Center (Buildings 7920 and 7930) facility and transferring this waste to the Collection Tank (F-1800) in the new Monitoring and Control Station (MCS) facility. The LLLW is transferred to the MCS in a new, underground, jacketed, stainless steel piping system. The LLLW will then be transferred from Tank F-1800 through a new, underground, jacketed, stainless steel piping system that connects the existing Bethel Valley LLLW Collection System and the Evaporator Facility Service Tanks. The interface for the two systems will be at the existing Interconnecting Pipe Line (ICPL) Valve Box adjacent to the Nonradiological Wastewater Treatment Plant. The project scope consists of the following systems: (1) Building 7920 LLLW Collection System; (2) Building 7930 LLLW Collection System; (3) LLLW Underground Transfer System to MCS; (4) MCS Building (including all equipment contained therein); (5) LLLW Underground Transfer System to ICPL Valve Box; and (6) Leak detection system for jacketed piping systems (3) and (5)

  3. Radiological safety evaluation for a Waste Transfer Facility at Savannah River Site

    International Nuclear Information System (INIS)

    Ades, M.J.

    1993-01-01

    This paper provides a review of the radiological safety evaluation performed for a Waste Transfer Facility (WTF) located at the Savannah River Site (SRS). This facility transfers liquid radioactive waste between various waste processing facilities and waste storage facilities. The WTF includes functional components such as the diversion box and the pump pits, waste transfer lines, and the outside yard service piping and electrical services. The WSRC methodology is used to evaluate the consequences of postulated accidents that result in the release of radioactive material. Such accidents include transfer line breaks, underground liquid pathway release, fire in pump tank cells and HEPA filters, accidents due to natural phenomena, and externally induced events. Chemical hazards accidents are not considered. The analysis results indicate that the calculated mean onsite and offsite radiological consequences are bounded by the corresponding WSRC dose limits for each accident considered. Moreover, the results show that the maximum onsite and offsite doses calculated for the WTF are lower than the maximum doses determined for the whole radioactive waste facility where the WTF is located

  4. 77 FR 21579 - Agency Information Collection Activities: Transfer of Cargo to a Container Station

    Science.gov (United States)

    2012-04-10

    ... Activities: Transfer of Cargo to a Container Station AGENCY: U.S. Customs and Border Protection, Department... a Container Station. This is a proposed extension of an information collection that was previously... Container Station. OMB Number: 1651-0096. Form Number: None. Abstract: Before the filing of an entry of...

  5. A concept for a station for the encapsulation of vitrified highly radioactive waste into containers for final disposal

    International Nuclear Information System (INIS)

    Anon

    1984-09-01

    The report presents a concept and plans for a station for the encapsulation of vitrified highly radioactive waste into containers for final disposal. The process steps, the layout of the station, the main components of equipment and the sequence of operations under normal conditions are described. The station is designed for vitrified waste from reprocessing. The volume of the waste packages is 150 l, and each package contains the equivalent of 1.33 tonne HM of fuel. The radionuclide activity of the waste corresponds to spent fuel with a decay time of 40 years from discharge from the reactor. It is assumed that after transport under normal conditions the steel shell enclosing the waste is gastight and its surface is free of contamination. The containers for final disposal are made of cast steel and have the form of hollow cylinders with hemispherical ends; their overall length is 2 m and their overall diameter 0.94 m. The station is so designed that the whole procedure, from supply of the transport containers containing the waste to the delivery of the full final disposal containers, is carried out by remote control behind radiation screens in an area isolated from the environment. Containers that do not fulfill the quality control requirements can be improved or repaired in a special rework cell without interfering with the further normal operation of the plant. (author)

  6. Purification and solidification of reactor wastes at a Canadian nuclear generating station

    International Nuclear Information System (INIS)

    Buckley, L.P.; Burt, D.A.

    1981-01-01

    The study aimed at development and demonstration of volume reduction and solidification of CANDU reactor wastes has been underway at Chalk River Nuclear Laboratories in the Province of Ontario, Canada. The study comprises membrane separation processes, evaporator appraisal and immobilization of concentrated wastes in bitumen. This paper discusses the development work with a wiped-film evaporator and the successful completion of demonstration tests at Douglas Point Nuclear Generating Station. Heavy water from the moderator system was purified and wastes arising from pump bowl decontamination were immobilized in bitumen with the wiped-film evaporator that was used in the development tests at Chalk River

  7. Discussion about the application of treatment process for dehydrated wet waste at nuclear power station

    International Nuclear Information System (INIS)

    Li Guanghua; Wu Qiang

    2009-01-01

    In nuclear power station, the most popular treatment about low level radioactive wet waste generated during the unit operating and maintenance is embedded by cement. For radioactive waste minimization, this article introduces a new treatment process to dehydrate and compress wet waste. According to the development and application of the treatment process for the wet waste, and comparing with the formerly treatment-the cement embedding, prove that the new treatment can meet the purpose for volume reduction of wet waste. (authors)

  8. Space Station Environmental Control and Life Support Systems: An Update on Waste Water Reclamation

    Science.gov (United States)

    Ferner, Kathleen M.

    1994-01-01

    Since the mid-1980's, work has been ongoing In the development of the various environmental control and life support systems (ECLSS) for the space station. Part of this effort has been focused on the development of a new subsystem to reclaim waste water that had not been previously required for shuttle missions. Because of the extended manned missions proposed, reclamation of waste water becomes imperative to avoid the weight penalties associated with resupplying a crew's entire water needs for consumption and daily hygiene. Hamilton Standard, under contract to Boeing Aerospace and Electronics, has been designing the water reclamation system for space station use. Since June of 1991, Hamilton Standard has developed a combined water processor capable of reclaiming potable quality water from waste hygiene water, used laundry water, processed urine, Shuttle fuel cell water, humidity condensate and other minor waste water sources. The system was assembled and then tested with over 27,700 pounds of 'real' waste water. During the 1700 hours of system operation required to process this waste water, potable quality water meeting NASA and Boeing specifications was produced. This paper gives a schematic overview of the system, describes the test conditions and test results and outlines the next steps for system development.

  9. Toxicity regulation of radioactive liquid waste effluent from CANDU stations - lessons from Ontario's MISA program

    International Nuclear Information System (INIS)

    Rodgers, D.W.

    2009-01-01

    Toxicity testing became an issue for Ontario's CANDU stations, when it was required under Ontario's MISA regulations for the Electricity Generation Sector. In initial tests, radioactive liquid waste (RLW) effluent was intermittently toxic to both rainbow trout and Daphnia. Significant differences in RLW toxicity were apparent among stations and contributing streams. Specific treatment systems were designed for three stations, with the fourth electing to use existing treatment systems. Stations now use a combination of chemical analysis and treatment to regulate RLW toxicity. Studies of Ontario CANDU stations provide a basis for minimizing costs and environmental effects of new nuclear stations. (author)

  10. Utilization of waste heat from electricity generating stations

    International Nuclear Information System (INIS)

    Robertson, R.F.S.

    1977-06-01

    Historically the nuclear power station has been designed solely as an electricity producer. But in Canada today only 15 percent of our energy consumption is as electricity. The non-electrical needs today are supplied almost entirely by natural gas and oil. There is an incentive to see whether a nuclear station could supply energy for some of these non-electrical needs, thus freeing gas and oil for uses for which they may be more valuable and suitable, especially in transportation. A group located at the Whiteshell Nuclear Research Establishment undertook a series of studies to examine this problem. These studies were done in sufficient depth to provide technological and economic answers, and as a result several reports have been published on various topics. In this report, the findings from these studies are drawn together in an assessment of the potential in Canada for using waste heat. (author)

  11. Railcar waste transfer system hydrostatic test

    International Nuclear Information System (INIS)

    Ellingson, S.D.

    1997-01-01

    Recent modifications have been performed on the T-Plant Railcar Waste Transfer System, This Acceptance Test Procedure (ATP) has been prepared to demonstrate that identified piping welds and mechanical connections incorporated during the modification are of high integrity and are acceptable for service. This will be achieved by implementation of a hydrostatic leak test

  12. Mathematical modeling in municipal solid waste management: case study of Tehran.

    Science.gov (United States)

    Akbarpour Shirazi, Mohsen; Samieifard, Reza; Abduli, Mohammad Ali; Omidvar, Babak

    2016-01-01

    Solid Waste Management (SWM) in metropolises with systematic methods and following environmental issues, is one of the most important subjects in the area of urban management. In this regard, it is regarded as a legal entity so that its activities are not overshadowed by other urban activities. In this paper, a linear mathematical programming model has been designed for integrated SWM. Using Lingo software and required data from Tehran, the proposed model has been applied for Tehran SWM system as a case study. To determine the optimal status of the available system for Tehran's Solid Waste Management System (SWMS), a novel linear programming model is applied. Tehran has 22 municipal regions with 11 transfer stations and 10 processing units. By running of the model, the transfer stations and processing units are decreased to 10 and 6 units, respectively. The proposed model is an alternative method for improvement the SWMS by decreasing the transfer stations and processing units.

  13. Waste disposal technology transfer matching requirement clusters for waste disposal facilities in China.

    Science.gov (United States)

    Dorn, Thomas; Nelles, Michael; Flamme, Sabine; Jinming, Cai

    2012-11-01

    Even though technology transfer has been part of development aid programmes for many decades, it has more often than not failed to come to fruition. One reason is the absence of simple guidelines or decision making tools that help operators or plant owners to decide on the most suitable technology to adopt. Practical suggestions for choosing the most suitable technology to combat a specific problem are hard to get and technology drawbacks are not sufficiently highlighted. Western counterparts in technology transfer or development projects often underestimate or don't sufficiently account for the high investment costs for the imported incineration plant; the differing nature of Chinese MSW; the need for trained manpower; and the need to treat flue gas, bunker leakage water, and ash, all of which contain highly toxic elements. This article sets out requirements for municipal solid waste disposal plant owner/operators in China as well as giving an attribute assessment for the prevalent waste disposal plant types in order to assist individual decision makers in their evaluation process for what plant type might be most suitable in a given situation. There is no 'best' plant for all needs and purposes, and requirement constellations rely on generalisations meaning they cannot be blindly applied, but an alignment of a type of plant to a type of owner or operator can realistically be achieved. To this end, a four-step approach is suggested and a technology matrix is set out to ease the choice of technology to transfer and avoid past errors. The four steps are (1) Identification of plant owner/operator requirement clusters; (2) Determination of different municipal solid waste (MSW) treatment plant attributes; (3) Development of a matrix matching requirement clusters to plant attributes; (4) Application of Quality Function Deployment Method to aid in technology localisation. The technology transfer matrices thus derived show significant performance differences between the

  14. Railcar waste transfer system hydrostatic test report

    International Nuclear Information System (INIS)

    Ellingson, S.D.

    1997-01-01

    This Acceptance Test Report (ATR) documents for record purposes the field results, acceptance, and approvals of the completed acceptance test per HNF-SD-W417-ATP-001, ''Rail car Waste Transfer System Hydrostatic Test''. The test was completed and approved without any problems or exceptions

  15. Optimization of municipal solid waste collection and transportation routes

    Energy Technology Data Exchange (ETDEWEB)

    Das, Swapan, E-mail: swapan2009sajal@gmail.com; Bhattacharyya, Bidyut Kr., E-mail: bidyut53@yahoo.co.in

    2015-09-15

    Graphical abstract: Display Omitted - Highlights: • Profitable integrated solid waste management system. • Optimal municipal waste collection scheme between the sources and waste collection centres. • Optimal path calculation between waste collection centres and transfer stations. • Optimal waste routing between the transfer stations and processing plants. - Abstract: Optimization of municipal solid waste (MSW) collection and transportation through source separation becomes one of the major concerns in the MSW management system design, due to the fact that the existing MSW management systems suffer by the high collection and transportation cost. Generally, in a city different waste sources scatter throughout the city in heterogeneous way that increase waste collection and transportation cost in the waste management system. Therefore, a shortest waste collection and transportation strategy can effectively reduce waste collection and transportation cost. In this paper, we propose an optimal MSW collection and transportation scheme that focus on the problem of minimizing the length of each waste collection and transportation route. We first formulize the MSW collection and transportation problem into a mixed integer program. Moreover, we propose a heuristic solution for the waste collection and transportation problem that can provide an optimal way for waste collection and transportation. Extensive simulations and real testbed results show that the proposed solution can significantly improve the MSW performance. Results show that the proposed scheme is able to reduce more than 30% of the total waste collection path length.

  16. Optimization of municipal solid waste collection and transportation routes

    International Nuclear Information System (INIS)

    Das, Swapan; Bhattacharyya, Bidyut Kr.

    2015-01-01

    Graphical abstract: Display Omitted - Highlights: • Profitable integrated solid waste management system. • Optimal municipal waste collection scheme between the sources and waste collection centres. • Optimal path calculation between waste collection centres and transfer stations. • Optimal waste routing between the transfer stations and processing plants. - Abstract: Optimization of municipal solid waste (MSW) collection and transportation through source separation becomes one of the major concerns in the MSW management system design, due to the fact that the existing MSW management systems suffer by the high collection and transportation cost. Generally, in a city different waste sources scatter throughout the city in heterogeneous way that increase waste collection and transportation cost in the waste management system. Therefore, a shortest waste collection and transportation strategy can effectively reduce waste collection and transportation cost. In this paper, we propose an optimal MSW collection and transportation scheme that focus on the problem of minimizing the length of each waste collection and transportation route. We first formulize the MSW collection and transportation problem into a mixed integer program. Moreover, we propose a heuristic solution for the waste collection and transportation problem that can provide an optimal way for waste collection and transportation. Extensive simulations and real testbed results show that the proposed solution can significantly improve the MSW performance. Results show that the proposed scheme is able to reduce more than 30% of the total waste collection path length

  17. Wireless Power Transfer and Data Collection in Wireless Sensor Networks

    OpenAIRE

    Li, Kai; Ni, Wei; Duan, Lingjie; Abolhasan, Mehran; Niu, Jianwei

    2017-01-01

    In a rechargeable wireless sensor network, the data packets are generated by sensor nodes at a specific data rate, and transmitted to a base station. Moreover, the base station transfers power to the nodes by using Wireless Power Transfer (WPT) to extend their battery life. However, inadequately scheduling WPT and data collection causes some of the nodes to drain their battery and have their data buffer overflow, while the other nodes waste their harvested energy, which is more than they need...

  18. Waste disposal technology transfer matching requirement clusters for waste disposal facilities in China

    International Nuclear Information System (INIS)

    Dorn, Thomas; Nelles, Michael; Flamme, Sabine; Jinming, Cai

    2012-01-01

    Highlights: ► We outline the differences of Chinese MSW characteristics from Western MSW. ► We model the requirements of four clusters of plant owner/operators in China. ► We examine the best technology fit for these requirements via a matrix. ► Variance in waste input affects result more than training and costs. ► For China technology adaptation and localisation could become push, not pull factors. - Abstract: Even though technology transfer has been part of development aid programmes for many decades, it has more often than not failed to come to fruition. One reason is the absence of simple guidelines or decision making tools that help operators or plant owners to decide on the most suitable technology to adopt. Practical suggestions for choosing the most suitable technology to combat a specific problem are hard to get and technology drawbacks are not sufficiently highlighted. Western counterparts in technology transfer or development projects often underestimate or don’t sufficiently account for the high investment costs for the imported incineration plant; the differing nature of Chinese MSW; the need for trained manpower; and the need to treat flue gas, bunker leakage water, and ash, all of which contain highly toxic elements. This article sets out requirements for municipal solid waste disposal plant owner/operators in China as well as giving an attribute assessment for the prevalent waste disposal plant types in order to assist individual decision makers in their evaluation process for what plant type might be most suitable in a given situation. There is no ‘best’ plant for all needs and purposes, and requirement constellations rely on generalisations meaning they cannot be blindly applied, but an alignment of a type of plant to a type of owner or operator can realistically be achieved. To this end, a four-step approach is suggested and a technology matrix is set out to ease the choice of technology to transfer and avoid past errors. The four

  19. Solid Waste Land Applications with Permits by the Iowa DNR

    Data.gov (United States)

    Iowa State University GIS Support and Research Facility — All types of facilities that handle solid waste, including: sanitary landfills, appliance demanufacturing facilities, transfer stations, land application sites,...

  20. Solid Waste Management Facilities with Permits by the Iowa DNR

    Data.gov (United States)

    Iowa State University GIS Support and Research Facility — All types of facilities that handle solid waste, including: sanitary landfills, appliance demanufacturing facilities, transfer stations, land application sites,...

  1. Solar-assisted MED treatment of Eskom power station waste water

    Science.gov (United States)

    Roos, Thomas H.; Rogers, David E. C.; Gericke, Gerhard

    2017-06-01

    The comparative benefits of multi-effect distillation (MED) used in conjunction with Nano Filtration (NF), Reverse Osmosis (RO) and Eutectic Freeze Crystallization (EFC) are determined for waste water minimization for inland coal fired power stations for Zero Liquid Effluent Discharge (ZLED). A sequence of technologies is proposed to achieve maximal water recovery and brine concentration: NF - physico-chemical treatment - MED - EFC. The possibility of extending the concentration of RO reject arising from minewater treatment at the Lethabo power station with MED alone is evaluated with mineral formation modelling using the thermochemical modelling software Phreeq-C. It is shown that pretreatment is essential to extend the amount of water that can be recovered, and this can be beneficially supported by NF.

  2. Double-shell tank waste transfer facilities integrity assessment plan

    International Nuclear Information System (INIS)

    Hundal, T.S.

    1998-01-01

    This document presents the integrity assessment plan for the existing double-shell tank waste transfer facilities system in the 200 East and 200 West Areas of Hanford Site. This plan identifies and proposes the integrity assessment elements and techniques to be performed for each facility. The integrity assessments of existing tank systems that stores or treats dangerous waste is required to be performed to be in compliance with the Washington State Department of Ecology Dangerous Waste Regulations, Washington Administrative Code WAC-173-303-640 requirements

  3. Status of the International Space Station Waste and Hygiene Compartment

    Science.gov (United States)

    Walker, Stephanie; Zahner, Christopher

    2010-01-01

    The Waste and Hygiene Compartment (WHC) serves as the primary system for removal and containment of metabolic waste and hygiene activities on board the United States segment of the International Space Station (ISS). The WHC was launched on ULF 2 and is currently in the U.S. Laboratory and is integrated into the Water Recovery System (WRS) where pretreated urine is processed by the Urine Processor Assembly (UPA). The waste collection part of the WHC system is derived from the Service Module system and was provided by RSC-Energia along with additional hardware to allow for urine delivery to the UPA. The System has been integrated in an ISS standard equipment rack structure for use on the U.S. segment of the ISS. The system has experienced several events of interest during the deployment, checkout, and operation of the system during its first year of use and these will be covered in this paper. Design and on-orbit performance will also be discussed.

  4. Volume reduction/solidification of liquid radioactive waste using bitumen at Ontario Hydro's Bruce Nuclear Generating Station 'A'

    International Nuclear Information System (INIS)

    Day, J.E.; Baker, R.L.

    1995-01-01

    Ontario Hydro at the Bruce Nuclear Generating Station 'A' has undertaken a program to render the station's liquid radioactive waste suitable for discharge to Lake Huron by removing sufficient radiological and chemical contaminants to satisfy regulatory requirements for emissions. The system will remove radionuclide and chemical contaminants from five different plant waste streams. The contaminants will be immobilized and stored at on-site radioactive waste storage facilities and the purified streams will be discharged. The discharge targets established by Ontario Hydro are set well below the limits established by the Ontario Ministry of Environment (MOE) and are based on the Best Available Technology Economically Achievable Approach (B.A.T.E.A.). ADTECHS Corporation has been selected by Ontario Hydro to provide volume reduction/solidification technology for one of the five waste streams. The system will dry and immobilize the contaminants from a liquid waste stream in emulsified asphalt using thin film evaporation technology

  5. Hinkley Point 'C' power station public inquiry: proof of evidence on on-site radioactive waste management and decommissioning

    International Nuclear Information System (INIS)

    Passant, F.H.

    1988-09-01

    A public inquiry has been set up to examine the planning application made by the Central Electricity Generating Board (CEGB) for the construction of a 1200 MW Pressurized Water Reactor power station at Hinkley Point (Hinkley Point ''C'') in the United Kingdom. The CEGB evidence to the Inquiry presented here provides information on the on-site management of solid, liquid and gaseous radioactive wastes both during station operation and during decommissioning. Estimates are given of current and projected future discharges of liquid and gaseous wastes from the site and packaging and transport arrangements for solid radioactive wastes are described. The framework of waste management policy, disposal strategy and legislation in the United Kingdom which will determine procedure at Hinkley Point ''C'' is given. (UK)

  6. Municipal solid waste management in Africa: Strategies and livelihoods in Yaounde, Cameroon

    International Nuclear Information System (INIS)

    Parrot, Laurent; Sotamenou, Joel; Dia, Bernadette Kamgnia

    2009-01-01

    This paper provides an overview of the state of municipal solid waste (MSW) management in the capital of Cameroon, Yaounde, and suggests some possible solutions for its improvement. The institutional, financial, and physical aspects of MSW management, as well as the livelihoods of the population, were analyzed. Our study revealed that distances and lack of infrastructure have a major impact on waste collection. Garbage bins are systematically mentioned as the primary infrastructure needed by the population in all quarters, whether it be a high or low standard community. The construction of transfer stations and the installation of garbage bins are suggested as a solution to reduce distances between households and garbage bins, thus improving waste collection vehicle accessibility. Transfer stations and garbage bins would enable the official waste collection company to expand its range of services and significantly improve waste collection rates. Several transfer stations have already been set up by non-governmental organizations (NGOs) and community-based organizations (CBOs), but they require technical, institutional and funding support. Research is needed on the quality and safety of community-made compost, as well as on soil fertility in urban and peri-urban areas. Most of the stakeholders, municipalities, the official waste collection company and households acknowledge the need for better monitoring and regulation of MSW management. The urban community of Yaounde also needs to maintain its support of MSW management and promote the sustainability of NGOs and CBOs operating in underserved areas not yet covered by adequate infrastructures. A major opportunity for implementation of such waste policy is the heavily indebted poor countries (HIPC) program dedicated to urban planning and good governance

  7. 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)

  8. Study on Evaluation Indicators System of Crowd Management for Transfer Stations Based on Pedestrian Simulation

    Directory of Open Access Journals (Sweden)

    Guanghou Zhang

    2011-12-01

    Full Text Available Improving safety and convenience of transfer is one of the most vital tasks in subway system planning, design and operation management. Because of complicated space layout and crowded pedestrian, crowd control is a big challenge for management of transfer stations. Thus, a quantitative evaluation should be done before improvement measures are carried out. Literature review showed that present evaluation indicators about crowd management in subway system were all based on fixed value or experience. Dynamic effect caused by pedestrian congestion and various facility combination cannot be represented based on these indicators. Thus, in this paper, based on the pedestrian simulation tool, dynamic evaluation indicators system of crowd management was established from the point of safety, cost-effectiveness and comfort. In order to aid decision makers to identify the most appropriate scenario to improve the effectiveness of crowd management, Matter-Element Analysis (MEA was used to rate different scenarios. A pedestrian simulation model of a designing intermodal transfer station was built and four different scenarios were tested to demonstrate how to use this indicators system. Simulation results were evaluated based on the dynamic indicators system and MEA. The application results show that the dynamic evaluation indicators system is operational and can reflect level of the crowd management in transfer station comprehensively and precisely.

  9. A mathematical model for the municipal solid waste location-routing problem with intermediate transfer stations

    Directory of Open Access Journals (Sweden)

    Hossein Asefi

    2015-09-01

    Full Text Available Municipal solid waste management is one of the challenging issues in mega cities due to various interrelated factors such as operational costs and environmental concerns. Cost as one of the most significant constraints of municipal solid waste management can be effectively economized by efficient planning approaches. Considering diverse waste types in an integrated municipal solid waste system, a mathematical model of the location-routing problem is formulated and solved in this study in order to minimize the total cost of transportation and facility establishment.

  10. Heat transfer analyses for grout disposal of radioactive double-shell slurry and customer wastes

    International Nuclear Information System (INIS)

    Robinson, S.M.; Gilliam, T.M.; McDaniel, E.W.

    1987-04-01

    Grout immobilization is being considered by Rockwell Hanford Operations (Rockwell Hanford) as a permanent disposal method for several radioactive waste streams. These include disposal of customer and double-shell slurry wastes in earthen trenches and in single-shell underground waste storage tanks. Heat transfer studies have previously been made to determine the maximum heat loading for grout disposal of various wastes under similar conditions, but a sensitivity analysis of temperature profiles to input parameters was needed. This document presents the results of heat transfer calculations for trenches containing grouted customer and double-shell slurry wastes and for in situ disposal of double-shell wastes in single-shell, domed concrete storage tanks. It discusses the conditions that lead to maximum grout temperatures of 250 0 F during the curing stage and 350 0 F thereafter and shows the dependence of these temperatures on input parameters such as soil and grout thermal conductivity, grout specific heat, waste loading, and disposal geometries. Transient heat transfer calculations were made using the HEATING6 computer code to predict temperature profiles in solidified low-level radioactive waste disposal scenarios at the Rockwell Hanford site. The calculations provide guidance for the development of safe, environmentally acceptable grout formulas for the Transportable Grout Facility. 11 refs

  11. 76 FR 16538 - Solid Waste Rail Transfer Facilities

    Science.gov (United States)

    2011-03-24

    ... leaving in place the rules issued in 2009, which were drafted without any input from industry and other... discarded by residential dwellings, hotels, motels, and other similar permanent or temporary housing... notice concerning the acquisition shall include a statement that a solid waste rail transfer facility...

  12. Low-level radioactive waste from nuclear power generating stations: Characterization, classification and assessment of activated metals and waste streams

    International Nuclear Information System (INIS)

    Thomas, V.W.; Robertson, D.E.; Thomas, C.W.

    1993-02-01

    Since the enactment of 10 CFR Part 61, additional difficult-to-measure long-lived radionuclides, not specified in Tables 1 2 of Part 61, have been identified (e.g., 108m Ag, 93 Mo, 36 Cl, 10 Be, 113m Cd, 121m Sn, 126 Sn, 93m Nb) that may be of concern in certain types of waste. These nuclides are primarily associated with activated metal and perhaps other nuclear power low-level waste (LLW) being sent to disposal facilities. The concentration of a radionuclide in waste materials is normally determined by direct measurement or by indirect calculational methods, such as using a scaling factor to relate inferred concentration of a difficult-to-measure radionuclide to another that is easily measured. The total disposal site inventory of certain difficult-to-measure radionuclides (e.g., 14 C, 129 I, and 99 Tc) often control the total quantities of radioactive waste permitted in LLW burial facilities. Overly conservative scaling factors based on lower limits of detection (LLD), often used in the nuclear power industry to estimate these controlling nuclides, could lead to premature closure of a disposal facility. Samples of LLW (Class B and C activated metals [AM] and other waste streams) are being collected from operating nuclear power stations and analyzed for radionuclides covered in 10 CFR Part 61 and the additional difficult-to-measure radionuclides. This analysis will enhance the NRC's understanding of the distribution and projected quantities of radionuclides within AM and LLW streams from commercial nuclear power stations. This research will also provide radiological characterization of AM specimens for others to use in leach-rate and lysimeter experiments to determine nuclide releases and subsequent movement in natural soil environments

  13. Greenhouse gas contribution of municipal solid waste collection: A case study in the city of Istanbul, Turkey.

    Science.gov (United States)

    Korkut, Nafiz E; Yaman, Cevat; Küçükağa, Yusuf; Jaunich, Megan K; Demir, İbrahim

    2018-02-01

    This article estimates greenhouse gas emissions and global warming factors resulting from collection of municipal solid waste to the transfer stations or landfills in Istanbul for the year of 2015. The aim of this study is to quantify and compare diesel fuel consumption and estimate the greenhouse gas emissions and global warming factors associated with municipal solid waste collection of the 39 districts of Istanbul. Each district's greenhouse gas emissions resulting from the provision and combustion of diesel fuel was estimated by considering the number of collection trips and distances to municipal solid waste facilities. The estimated greenhouse gases and global warming factors for the districts varied from 61.2 to 2759.1 t CO 2 -eq and from 4.60 to 15.20 kg CO 2 -eq t -1 , respectively. The total greenhouse gas emission was estimated as 46.4E3 t CO 2 -eq. Lastly, the collection data from the districts was used to parameterise a collection model that can be used to estimate fuel consumption associated with municipal solid waste collection. This mechanistic model can then be used to predict future fuel consumption and greenhouse gas emissions associated with municipal solid waste collection based on projected population, waste generation, and distance to transfer stations and landfills. The greenhouse gas emissions can be reduced by decreasing the trip numbers and trip distances, building more transfer stations around the city, and making sure that the collection trucks are full in each trip.

  14. A STRUCTURAL INTEGRITY EVALUATION OF THE TANK FARM WASTE TRANSFER SYSTEM

    Energy Technology Data Exchange (ETDEWEB)

    Wiersma, B.

    2006-03-09

    Radioactive supernate, salt, and/or sludge wastes (i.e., high level wastes) are confined in 49 underground storage tanks at the Savannah River Site (SRS). The waste is transported between tanks within and between the F and H area tank farms and other facilities on site via underground and a limited number of aboveground transfer lines. The Department of Energy - Savannah River Operations Office (DOE-SR) performed a comprehensive assessment of the structural integrity program for the Tank Farm waste transfer system at the SRS. This document addresses the following issues raised during the DOE assessment: (1) Inspections of failed or replaced transfer lines indicated that the wall thickness of some core and jacket piping is less than nominal; (2) No corrosion allowance is utilized in the transfer line structural qualification calculations. No basis for neglecting corrosion was provided in the calculations; (3) Wall loss due to erosion is not addressed in the transfer line structural qualification calculations; and (4) No basis is provided for neglecting intergranular stress corrosion cracking in the transfer line structural qualification calculations. The common theme in most of these issues is the need to assess the potential for occurrence of material degradation of the transfer line piping. The approach used to resolve these issues involved: (1) Review the design and specifications utilized to construct and fabricate the piping system; (2) Review degradation mechanisms for stainless steel and carbon steel and determine their relevance to the transfer line piping; (3) Review the transfer piping inspection data; (4) Life estimation calculations for the transfer lines; and (5) A Fitness-For-Service evaluation for one of the transfer line jackets. The evaluation concluded that the transfer line system piping has performed well for over fifty years. Although there have been instances of failures of the stainless steel core pipe during off-normal service, no significant

  15. Design of modified annulus air sampling system for the detection of leakage in waste transfer line

    International Nuclear Information System (INIS)

    Deokar, U.V; Khot, A.R.; Mathew, P.; Ganesh, G.; Tripathi, R.M.; Srivastava, Srishti

    2018-01-01

    Various liquid waste streams are generated during the operation of reprocessing plant. The High Level (HL), Intermediate Level (IL) and Low Level (LL) liquid wastes generated, are transferred from reprocessing plant to Waste Management Facility. These respective waste streams are transferred through pipe-in-pipe lines along the shielded concrete trench. For detection of radioactive leakage from primary waste transfer line into secondary line, sampling of the annulus air between the two pipes is carried out. The currently installed pressurized annulus air sampling system did not have online leakage detection provision. Hence, there are chances of personal exposure and airborne activity in the working area. To overcome these design flaws, free air flow modified online annulus air sampling system with more safety features is designed

  16. Potential for radioactive patient excreta in hospital trash and medical waste

    International Nuclear Information System (INIS)

    Evdokimoff, V.; Cash, C.; Buckley, K.

    1994-01-01

    Radioactive excreta from nuclear medicine patients can enter solid waste as common trash and medical biohazardous waste. Many landfills and transfer stations now survey these waste streams with scintillation detectors which may result in rejection of a hospital's waste. Our survey indicated that on the average either or both of Boston University Medical Center Hospital's waste streams can contain detectable radioactive excreta on a weekly basis. To avoid potential problems, radiation detectors were installed in areas where housekeepers carting trash and medical waste must pass through to ensure no radioactivity leaves the institution. 3 refs

  17. Determination of Erosion/Corrosion Rates in Hanford Tank Farms Radioactive Waste Transfer System Pipelines

    International Nuclear Information System (INIS)

    Washenfelder, D. J.; Girardot, C. L.; Wilson, E. R.; Page, J. A.; Engeman, J. K.; Gunter, J. R.; Johnson, J. M.; Baide, D. G.; Cooke, G. A.; Larson, J. D.; Castleberry, J. L.; Boomer, K. D.

    2015-01-01

    The twenty-eight double-shell underground radioactive waste storage tanks at the U. S. Department of Energy's Hanford Site near Richland, WA are interconnected by the Waste Transfer System network of buried steel encased pipelines and pipe jumpers in below-grade pits. The pipeline material is stainless steel or carbon steel in 51 mm to 152 mm (2 in. to 6 in.) sizes. The pipelines carry slurries ranging up to 20 volume percent solids and supernatants with less than one volume percent solids at velocities necessary to prevent settling. The pipelines, installed between 1976 and 2011, were originally intended to last until the 2028 completion of the double-shell tank storage mission. The mission has been subsequently extended. In 2010 the Tank Operating Contractor began a systematic evaluation of the Waste Transfer System pipeline conditions applying guidelines from API 579-1/ASME FFS-1 (2007), Fitness-For-Service. Between 2010 and 2014 Fitness-for-Service examinations of the Waste Transfer System pipeline materials, sizes, and components were completed. In parallel, waste throughput histories were prepared allowing side-by-side pipeline wall thinning rate comparisons between carbon and stainless steel, slurries and supernatants and throughput volumes. The work showed that for transfer volumes up to 6.1E+05 m"3 (161 million gallons), the highest throughput of any pipeline segment examined, there has been no detectable wall thinning in either stainless or carbon steel pipeline material regardless of waste fluid characteristics or throughput. The paper describes the field and laboratory evaluation methods used for the Fitness-for-Service examinations, the results of the examinations, and the data reduction methodologies used to support Hanford Waste Transfer System pipeline wall thinning conclusions.

  18. Determination of Erosion/Corrosion Rates in Hanford Tank Farms Radioactive Waste Transfer System Pipelines

    Energy Technology Data Exchange (ETDEWEB)

    Washenfelder, D. J.; Girardot, C. L.; Wilson, E. R.; Page, J. A.; Engeman, J. K.; Gunter, J. R.; Johnson, J. M.; Baide, D. G.; Cooke, G. A.; Larson, J. D.; Castleberry, J. L.; Boomer, K. D.

    2015-11-05

    The twenty-eight double-shell underground radioactive waste storage tanks at the U. S. Department of Energy’s Hanford Site near Richland, WA are interconnected by the Waste Transfer System network of buried steel encased pipelines and pipe jumpers in below-grade pits. The pipeline material is stainless steel or carbon steel in 51 mm to 152 mm (2 in. to 6 in.) sizes. The pipelines carry slurries ranging up to 20 volume percent solids and supernatants with less than one volume percent solids at velocities necessary to prevent settling. The pipelines, installed between 1976 and 2011, were originally intended to last until the 2028 completion of the double-shell tank storage mission. The mission has been subsequently extended. In 2010 the Tank Operating Contractor began a systematic evaluation of the Waste Transfer System pipeline conditions applying guidelines from API 579-1/ASME FFS-1 (2007), Fitness-For-Service. Between 2010 and 2014 Fitness-for-Service examinations of the Waste Transfer System pipeline materials, sizes, and components were completed. In parallel, waste throughput histories were prepared allowing side-by-side pipeline wall thinning rate comparisons between carbon and stainless steel, slurries and supernatants and throughput volumes. The work showed that for transfer volumes up to 6.1E+05 m3 (161 million gallons), the highest throughput of any pipeline segment examined, there has been no detectable wall thinning in either stainless or carbon steel pipeline material regardless of waste fluid characteristics or throughput. The paper describes the field and laboratory evaluation methods used for the Fitness-for-Service examinations, the results of the examinations, and the data reduction methodologies used to support Hanford Waste Transfer System pipeline wall thinning conclusions.

  19. Operating test report for project W-417, T-plant steam removal upgrade, waste transfer portion

    International Nuclear Information System (INIS)

    Myers, N.K.

    1997-01-01

    This Operating Test Report (OTR) documents the performance results of the Operating Test Procedure HNF-SD-W417-OTP-001 that provides steps to test the waste transfer system installed in the 221-T Canyon under project W-417. Recent modifications have been performed on the T Plant Rail Car Waste Transfer System. This Operating Test Procedure (OTP) will document the satisfactory operation of the 221-T Rail Car Waste Transfer System modified by project W-417. Project W-417 installed a pump in Tank 5-7 to replace the steam jets used for transferring liquid waste. This testing is required to verify that operational requirements of the modified transfer system have been met. Figure 2 and 3 shows the new and existing system to be tested. The scope of this testing includes the submersible air driven pump operation in Tank 5-7, liquid waste transfer operation from Tank 5-7 to rail car (HO-IOH-3663 or HO-IOH-3664), associated line flushing, and the operation of the flow meter. This testing is designed to demonstrate the satisfactory operation-of the transfer line at normal operating conditions and proper functioning of instruments. Favorable results will support continued use of this system for liquid waste transfer. The Functional Design Criteria for this system requires a transfer flow rate of 40 gallons per minute (GPM). To establish these conditions the pump will be supplied up to 90 psi air pressure from the existing air system routed in the canyon. An air regulator valve will regulate the air pressure. Tank capacity and operating ranges are the following: Tank No. Capacity (gal) Operating Range (gal) 5-7 10,046 0 8040 (80%) Rail car (HO-IOH-3663 HO-IOH-3664) 097219,157 Existing Tank level instrumentation, rail car level detection, and pressure indicators will be utilized for acceptance/rejection Criteria. The flow meter will be verified for accuracy against the Tank 5-7 level indicator. The level indicator is accurate to within 2.2 %. This will be for information only

  20. Results of Waste Transfer and Back-Dilution in Tanks 241-SY-101 and 241-SY-102

    International Nuclear Information System (INIS)

    Mahoney, L.A.; Antoniak, Z.I.; Barton, W.B.; Conner, J.M.; Kirch, N.W.; Stewart, C.W.; Wells, B.E.

    2000-01-01

    This report chronicles the process of remediation of the flammable gas hazard in Tank 241-SY-101 (SY-101) by waste transfer and back-dilution from December 18, 1999 through April 2, 2000. A brief history is given of the development of the flammable gas retention and release hazard in this tank, and the transfer and dilution systems are outlined. A detailed narrative of each of the three transfer and dilution campaigns is given to provide structure for the balance of the report. Details of the behavior of specific data are then described, including the effect of transfer and dilution on the waste levels in Tanks SY-101 and SY-102, data from strain gauges on equipment suspended from the tank dome, changes in waste configuration as inferred from neutron and gamma logs, headspace gas concentrations, waste temperatures, and the mixerpump operating performance. Operating data and performance of the transfer pump in SY-101 are also discussed

  1. Volume reduction/solidification of liquid radioactive waste using bitumen at Ontario hydro's Bruce nuclear generating station open-quotes Aclose quotes

    International Nuclear Information System (INIS)

    Day, J.E.; Baker, R.L.

    1994-01-01

    Ontario Hydro at the Bruce Nuclear Generating Station open-quotes Aclose quotes has undertaken a program to render the station's liquid radioactive waste suitable for discharge to Lake Huron by removing sufficient radiological and chemical contaminants from five different plant waste streams. The contaminants will be immobilized and stored at on-site radioactive waste storage facilities and the purified streams will be discharged. The discharge targets established by Ontario Hydro are set well below the limits established by the Ontario Ministry of Environment (MOE) and are based on the Best Available Technology Economically Achievable Approach (B.A.T.E.A.). ADTECHS Corporation has been selected by Ontario Hydro to provide volume reduction/solidification technology for one of the five waste streams. The system will dry and immobilize the contaminants from a liquid waste stream in emulsified asphalt using thin film evaporation technology

  2. Effects of stabilizers on the heat transfer characteristics of a nuclear waste canister

    International Nuclear Information System (INIS)

    Vafai, K.; Ettefagh, J.

    1986-07-01

    This report summarizes the feasibility and the effectiveness of using stabilizers (internal metal structural components) to augment the heat transfer characteristics of a nuclear waste canister. The problem was modeled as a transient two-dimensional heat transfer in two physical domains - the stabilizer and the wedge (a 30-degree-angle canister segment), which includes the heat-producing spent-fuel rods. This problem is solved by a simultaneous and interrelated numerical investigation of the two domains in cartesian and polar coordinate systems. The numerical investigations were performed for three cases. In the first case, conduction was assumed to be the dominant mechanism for heat transfer. The second case assumed that radiation was the dominant mechanism, and in the third case both radiation and conduction were considered as mechanisms of heat transfer. The results show that for typical conditions in a waste package design, the stabilizers are quite effective in reducing the overall temperature in a waste canister. Furthermore, the results show that increasing the stabilizer thickness over the thickness specified in the present design has a negligible effect on the temperature distribution in the canister. Finally, the presence of the stabilizers was found to shift the location of the peak temperature areas in the waste canister

  3. Waste conditioning for tank heel transfer. Preliminary data and results

    International Nuclear Information System (INIS)

    Ebadian, M.A.

    1999-01-01

    This report summarizes the research carried out at Florida International University's Hemispheric Center for Environmental Technology (FIU-HCET) for the fiscal year 1998 (FY98) under the Tank Focus Area (TFA) project ''Waste Conditioning for Tank Slurry Transfer.'' The objective of this project is to determine the effect of chemical and physical properties on the waste conditioning process and transfer. The focus of this research consisted in building a waste conditioning experimental facility to test different slurry simulants under different conditions, and analyzing their chemical and physical properties. This investigation would provide experimental data and analysis results that can make the tank waste conditioning process more efficient, improve the transfer system, and influence future modifications to the waste conditioning and transfer system. A waste conditioning experimental facility was built in order to test slurry simulants. The facility consists of a slurry vessel with several accessories for parameter control and sampling. The vessel also has a lid system with a shaft-mounted propeller connected to an air motor. In addition, a circulation system is connected to the slurry vessel for simulant cooling and heating. Experimental data collection and analysis of the chemical and physical properties of the tank slurry simulants has been emphasized. For this, one waste slurry simulant (Fernald) was developed, and another two simulants (SRS and Hanford) obtained from DOE sites were used. These simulants, composed of water, soluble metal salts, and insoluble solid particles, were used to represent the actual radioactive waste slurries from different DOE sites. The simulants' chemical and physical properties analyzed include density, viscosity, pH, settling rate, and volubility. These analyses were done to samples obtained from different experiments performed at room temperature but different mixing time and strength. The experimental results indicate that the

  4. Investigation on thermal environment improvement by waste heat recovery in the underground station in Qingdao metro

    Science.gov (United States)

    Liu, Jianwei; Liu, Jiaquan; Wang, Fengyin; Wang, Cuiping

    2018-03-01

    The thermal environment parameters, like the temperature and air velocity, are measured to investigate the heat comfort status of metro staff working area in winter in Qingdao. The temperature is affected obviously by the piston wind from the train and waiting hall in the lower Hall, and the temperature is not satisfied with the least heat comfort temperature of 16 °C. At the same time, the heat produced by the electrical and control equipments is brought by the cooling air to atmosphere for the equipment safety. Utilizing the water-circulating heat pump, it is feasible to transfer the emission heat to the staff working area to improve the thermal environment. Analyzed the feasibility from the technique and economy when using the heat pump, the water-circulating heat pump could be the best way to realize the waste heat recovery and to help the heat comfort of staff working area in winter in the underground metro station in north China.

  5. A multi-objective approach to solid waste management

    International Nuclear Information System (INIS)

    Galante, Giacomo; Aiello, Giuseppe; Enea, Mario; Panascia, Enrico

    2010-01-01

    The issue addressed in this paper consists in the localization and dimensioning of transfer stations, which constitute a necessary intermediate level in the logistic chain of the solid waste stream, from municipalities to the incinerator. Contextually, the determination of the number and type of vehicles involved is carried out in an integrated optimization approach. The model considers both initial investment and operative costs related to transportation and transfer stations. Two conflicting objectives are evaluated, the minimization of total cost and the minimization of environmental impact, measured by pollution. The design of the integrated waste management system is hence approached in a multi-objective optimization framework. To determine the best means of compromise, goal programming, weighted sum and fuzzy multi-objective techniques have been employed. The proposed analysis highlights how different attitudes of the decision maker towards the logic and structure of the problem result in the employment of different methodologies and the obtaining of different results. The novel aspect of the paper lies in the proposal of an effective decision support system for operative waste management, rather than a further contribution to the transportation problem. The model was applied to the waste management of optimal territorial ambit (OTA) of Palermo (Italy).

  6. A multi-objective approach to solid waste management.

    Science.gov (United States)

    Galante, Giacomo; Aiello, Giuseppe; Enea, Mario; Panascia, Enrico

    2010-01-01

    The issue addressed in this paper consists in the localization and dimensioning of transfer stations, which constitute a necessary intermediate level in the logistic chain of the solid waste stream, from municipalities to the incinerator. Contextually, the determination of the number and type of vehicles involved is carried out in an integrated optimization approach. The model considers both initial investment and operative costs related to transportation and transfer stations. Two conflicting objectives are evaluated, the minimization of total cost and the minimization of environmental impact, measured by pollution. The design of the integrated waste management system is hence approached in a multi-objective optimization framework. To determine the best means of compromise, goal programming, weighted sum and fuzzy multi-objective techniques have been employed. The proposed analysis highlights how different attitudes of the decision maker towards the logic and structure of the problem result in the employment of different methodologies and the obtaining of different results. The novel aspect of the paper lies in the proposal of an effective decision support system for operative waste management, rather than a further contribution to the transportation problem. The model was applied to the waste management of optimal territorial ambit (OTA) of Palermo (Italy). 2010 Elsevier Ltd. All rights reserved.

  7. High level waste (HLW) steam reducing station evaluation

    International Nuclear Information System (INIS)

    Gannon, R.E.

    1993-01-01

    Existing pressure equipment in High Level Waste does not have a documented technical baseline. Based on preliminary reviews, the existing equipment seems to be based on system required capacity instead of system capability. A planned approach to establish a technical baseline began September 1992 and used the Works Management System preventive maintenance schedule. Several issues with relief valves being undersized on steam reducing stations created a need to determine the risk of maintaining the steam in service. An Action Plan was developed to evaluate relief valves that did not have technical baselines and provided a path forward for continued operation. Based on Action Plan WER-HLE-931042, the steam systems will remain in service while the designs are being developed and implemented

  8. EVALUATION OF FROST HEAVE ON WASTE TRANSFER LINES WITH SHALLOW DEPTHS IN DST (DOUBLE SHELL TANK) FARMS

    Energy Technology Data Exchange (ETDEWEB)

    HAQ MA

    2009-05-12

    The purpose of this document is to evaluate the effect of frost heave on waste transfer lines with shallow depths in DST farms. Because of the insulation, well compacted sandy material around waste transfer lines, the type of sandy and gravel soil, and relatively low precipitation at Hanford site, it is concluded that waste transfer lines with one foot of soil covers (sandy cushion material and insulation) are not expected to undergo frost heave damaging effects.

  9. Waste heat of HTR power stations for district heating

    International Nuclear Information System (INIS)

    Bonnenberg, H.; Schlenker, H.V.

    1975-01-01

    The market situation, the applied techniques, and the transport, for district heating in combination with HTR plants are considered. Analysis of the heat market indicates a high demand for heat at temperatures between 100 and 150 0 C in household and industry. This market for district heating can be supplied by heat generated in HTR plants using two methods: (1) the combined heat and power generation in steam cycle plants by extracting steam from the turbine, and (2) the use of waste heat of a closed gas turbine cycle. The heat generation costs of (2) are negligible. The cost for transportation of heat over the average distance between existing plant sites and consumer regions (25 km) are between 10 and 20% of the total heat price, considering the high heat output of nuclear power stations. Comparing the price of heat gained by use of waste heat in HTR plants with that of conventional methods, considerable advantages are indicated for the combined heat and power generation in HTR plants. (author)

  10. Pollution profiles, health risk of VOCs and biohazards emitted from municipal solid waste transfer station and elimination by an integrated biological-photocatalytic flow system: a pilot-scale investigation.

    Science.gov (United States)

    Li, Guiying; Zhang, Zhengyong; Sun, Hongwei; Chen, Jiangyao; An, Taicheng; Li, Bing

    2013-04-15

    Volatile organic compounds (VOCs) and biohazards air pollution in municipal solid waste transfer station were investigated. As compressor working, the concentrations of almost all quantified 14 VOCs (0.32-306.03 μg m(-3)) were much higher than those as compressor off (0-13.31 μg m(-3)). Comparatively, only 3 VOCs with extremely low concentrations could be detected at control area. Total microorganism was 7567 CFU m(-3) as compressor working, which was 1.14 and 6.22 times higher than that of compressor off and control area, respectively. Bacteria were the most abundant microorganism at all three sampling places. At pilot-scale, during whole 60-day treatment, for VOCs, the average removal efficiencies were over 92% after biotrickling filter-photocatalytic (BTF-PC) treatment. Although non-cancer and cancer risks of some VOCs were over the concern level before treatment, almost all VOCs were removed substantially and both potential risks were below the concern after BTF-PC treatment. Additionally, biohazard concentrations decreased dramatically and air quality was purified from polluted to cleanness after PC treatment. All results demonstrated that the integrated technology possessed high removal capacity and long stability for the removal of VOCs and biohazards at a pilot scale. Copyright © 2013 Elsevier B.V. All rights reserved.

  11. Shippingport Station Decommissioning Project (SSDP). A progress report

    International Nuclear Information System (INIS)

    Mullee, G.R.; Usher, J.M.

    1986-01-01

    The Shippingport Atomic Power Station was shutdown in October, 1982 by the Plant Operator, Duquesne Light Company, for decommissioning by the US Department of Energy. The planning for decommissioning was completed in September, 1983. In September, 1984 operational responsibility for the station was transferred to the DOE's Decommissioning Operations Contractor - the General Electric Company (assisted by an integrated subcontractor, MK Ferguson Company). Significant accomplishments to date include the completion of all prerequisites for decommissioning, the removal of asbestos from plant systems, loading of irradiated reactor components into the reactor vessel for shipment, the commencement of electrical deactivations and the commencement of piping/component removal. Decontamination and waste processing are progressing in support of the project schedule. The reactor vessel will be shipped as one piece on a barge for burial at Hanford, Washington. The final release of the site is scheduled for April, 1990. A technology transfer program is being utilized to disseminate information about the project

  12. Definition of technology development missions for early space station, orbit transfer vehicle servicing. Volume 1: Executive summary

    Science.gov (United States)

    1983-01-01

    Orbital Transfer Vehicle (OTV) servicing study scope, propellant transfer, storage and reliquefaction technology development missions (TDM), docking and berthing TDM, maintenance TDM, OTV/payload integration TDM, combined TDMS design, summary space station accomodations, programmatic analysis, and TDM equipment operational usage are discussed.

  13. Low- and intermediate-level waste management practices in Canada

    International Nuclear Information System (INIS)

    Charlesworth, D.H.

    1982-05-01

    Low- and intermediate-level wastes arise in Canada from the operation of nuclear power stations, nuclear research establishments, nuclear fuel and radioisotope production facilities, as well as from many medical, research and industrial organizations. Essentially all of the solid radioactive wastas are stored in a retrievable fashion at five waste management areas from which a portion is expected to be transferred to future disposal facilities. Waste processing for volume reduction and stabilization is becoming an increasingly important part of low-level waste management because of the advantages it provides for both interim storage currently, and permanent disposal in the future

  14. Mass Transfer Model for a Breached Waste Package

    International Nuclear Information System (INIS)

    Hsu, C.; McClure, J.

    2004-01-01

    The degradation of waste packages, which are used for the disposal of spent nuclear fuel in the repository, can result in configurations that may increase the probability of criticality. A mass transfer model is developed for a breached waste package to account for the entrainment of insoluble particles. In combination with radionuclide decay, soluble advection, and colloidal transport, a complete mass balance of nuclides in the waste package becomes available. The entrainment equations are derived from dimensionless parameters such as drag coefficient and Reynolds number and based on the assumption that insoluble particles are subjected to buoyant force, gravitational force, and drag force only. Particle size distributions are utilized to calculate entrainment concentration along with geochemistry model abstraction to calculate soluble concentration, and colloid model abstraction to calculate colloid concentration and radionuclide sorption. Results are compared with base case geochemistry model, which only considers soluble advection loss

  15. Station Transfers

    Data.gov (United States)

    Department of Homeland Security — ixed rail transit external system transfers for systems within the Continental United States, Alaska, Hawaii, the District of Columbia, and Puerto Rico. The modes of...

  16. Implementation of the waste management transfer act. Requirements from a regulatory point of view

    International Nuclear Information System (INIS)

    Mueller-Dehn, Christian

    2017-01-01

    In future in Germany, the state will be responsible for financing and handling the interim and final storage of radioactive waste from nuclear power plants. With regard to interim storage, this objective is achieved with the provisions of the Waste Management Transfer Act. Regulatory implementation is based on these regulations. BGZ Gesellschaft fuer Zwischenlager mbH is responsible for interim storage on behalf of the Federal Government. Simultaneously with the transfer of interim storage facilities to BGZ a legal transfer of approval is carried out. Insofar as there is a technical, organisational or personnel conjunction with the nuclear power plant operation, which continues to exist beyond this deadline and is relevant for regulatory purposes, a regulation is made via a service contract with the BGZ. This ensures compliance with the licensing regulations. Irradiated fuel assemblies and the waste from reprocessing can be handed over to BGZ from 1 January 2019 onwards and waste with negligible heat generation can be disposed of as of the determination of their proper packaging.

  17. Waste processing of chemical cleaning solutions

    International Nuclear Information System (INIS)

    Peters, G.A.

    1991-01-01

    This paper reports on chemical cleaning solutions containing high concentrations of organic chelating wastes that are difficult to reduce in volume using existing technology. Current methods for evaporating low-level radiative waste solutions often use high maintenance evaporators that can be costly and inefficient. The heat transfer surfaces of these evaporators are easily fouled, and their maintenance requires a significant labor investment. To address the volume reduction of spent, low-level radioactive, chelating-based chemical cleaning solutions, ECOSAFE Liquid Volume Reduction System (LVRS) has been developed. The LVRS is based on submerged combustion evaporator technology that was modified for treatment of low-level radiative liquid wastes. This system was developed in 1988 and was used to process 180,000 gallons of waste at Oconee Nuclear Station

  18. Waste package transfer, emplacement and retrievability in the French deep geological repository

    Energy Technology Data Exchange (ETDEWEB)

    Roulet, Alain; Delort, Daniel; Herve, Jean Francois; Bosgiraud, Jean Michel; Guenin, Jean Jacques [Technical Department ANDRA (France)

    2009-06-15

    Safe, reliable and reversible handling of waste is a significant issue related to the design and safety assessment of deep geological repository in France. The first step taken was to study various waste handling solutions. ANDRA also decided to fabricate and demonstrate industrial scale handling equipment for HLW (since 2003) and for ILW-LL wastes (since 2008). We will review the main equipment developed for the transfer process in the repository, for both types of waste, and underline the benefits of developing industrial demonstrators within the framework of international cooperation agreements. Waste retrieval capability will be simultaneously examined. Two types of waste have to be handled underground in Andra's repository. The HLW disposal package for vitrified waste is a 2 ton carbon steel cylindrical canister with a diameter of 600 mm. The weight of ILW-LL concrete disposal packages range from a minimum of 6 tonnes to over 20 tonnes, and their volume from approximately 5 to 10 m3. The underground transfer to the disposal drift requires moving the disposal package within a shielded transfer cask placed on a trailer. Transfer cask design has evolved since 2005, due to optimisation studies and as a result of industrial feedback from SKB. For HLW handling equipment two design options have been studied. In the first solution (Andra's Dossier 2005), the waste package are emplaced, one at a time, in the disposal drift by a pushing robot. Successive steps in design and proto-typing have lead to improve the design of the equipment and to gain confidence. Recently a fully integrated process has been successfully demonstrated, at full scale, (in a 100 m long mock up drift) as part of the EC funded ESDRED Project. This demonstrator is now on display in Andra's Technology Centre at Saudron, near the Bure Underground Laboratory. The second disposal option which has been investigated is based on a concept of utilising an external apparatus to push a row of

  19. Technology, safety and costs of decommissioning a reference pressurized water reactor power station. Classification of decommissioning wastes. Addendum 3

    International Nuclear Information System (INIS)

    Murphy, E.S.

    1984-09-01

    The radioactive wastes expected to result from decommissioning of the reference pressurized water reactor power station are reviewed and classified in accordance with 10 CFR 61. The 17,885 cubic meters of waste from DECON are classified as follows: Class A, 98.0%; Class B, 1.2%; Class C, 0.1%. About 0.7% (133 cubic meters) of the waste would be generally unacceptable for disposal using near-surface disposal methods

  20. Definition of technology development missions for early space station, orbit transfer vehicle servicing, volume 2

    Science.gov (United States)

    1983-01-01

    Propellant transfer, storage, and reliquefaction TDM; docking and berthing technology development mission; maintenance technology development mission; OTV/payload integration, space station interface/accommodations; combined TDM conceptual design; programmatic analysis; and TDM equipment usage are discussed.

  1. A Cask Processing Enclosure for the TRU Waste Processing Center - 13408

    Energy Technology Data Exchange (ETDEWEB)

    Newman, John T.; Mendez, Nicholas [IP Systems, Inc., 2685 Industrial Lane, Broomfield, Colorado 80020 (United States)

    2013-07-01

    This paper will discuss the key elements considered in the design, construction, and use of an enclosure system built for the TRU Waste Processing Center (TWPC). The TWPC system is used for the repackaging and volume reduction of items contaminated with radioactive material, hazardous waste and mixed waste. The modular structural steel frame and stainless steel skin was designed for rapid field erection by the use of interchangeable self-framing panel sections to allow assembly of a sectioned containment building and for ease of field mobility. The structure was installed on a concrete floor inside of an outer containment building. The major sections included an Outer Cask Airlock, Inner Cask Airlock, Cask Process Area, and Personnel Airlocks. Casks in overpacks containing transuranic waste are brought in via an inter-site transporter. The overpack lid is removed and the cask/overpack is transferred into the Outer Cask Airlock. A contamination cover is installed on the overpack body and the Outer Cask Airlock is closed. The cask/overpack is transferred into the Inner Cask Airlock on a cask bogie and the Inner Cask Airlock is closed. The cask lid is removed and the cask is transferred into the Cask Process Area where it is placed on a cask tilting station. Once the Cask Processing Area is closed, the cask tilt station is activated and wastes are removed, size reduced, then sorted and re-packaged into drums and standard waste boxes through bag ports. The modular system was designed and built as a 'Fast Track' project at IP Systems in Broomfield Colorado and then installed and is currently in use at the DOE TWPC located near Oak Ridge, Tennessee. (authors)

  2. Handling, assessment, transport and disposal of tritiated waste materials at JET

    International Nuclear Information System (INIS)

    Newbert, G.; Haigh, A.; Atkins, G.

    1995-01-01

    All types of JET radioactive wastes are received for disposal at the Waste Handling Facility (WHF) which features a waste sorting and sampling station, a glove box, a compactor, and packaging and transfer systems. The WHF is operated as a contamination control area with monitored tritium discharges. Two main types of tritium monitors used are liquid scintillation counters and ionization chambers, and samples of various components and materials have now been assessed for tritium. The results so far indicate a widespread of tritium levels from 2Bq/g for cold gas transfer lines to 200kBq/g for in-vessel tiles. General soft housekeeping waste is assessed by a sniffing technique which has a limit of detection corresponding to 120Bq/g. Investigation of improved methods of tritium measurement and of component detritiation was made to facilitate future waste disposal. 8 refs., 6 figs., 2 tabs

  3. Solid waste disposed in the surrounding of Caetés Ecological Station - PE: opportunity of environmental education

    Directory of Open Access Journals (Sweden)

    Adriana Aparecida Megumi Nishiwaki

    2017-07-01

    Full Text Available Several human activities have affected the integrity and balance of conservation unit, compromising the efficiency of the preservation of biodiversity, natural resources and cultural. This work aims to study the solid waste irregular disposition in the surrounding of Caetés Ecological Station (PE and the impacts on site, as well as presenting a proposal of environmental education program involving the local community. The problem has been identified through visiting areas, resulting in primary data, which were crossed with secondary data about solid waste and its negative effects, as well as on environmental education in communities. The environmental education program developed consists in lectures, dynamics, workshops, partnerships with local schools and training. The community mobilization expected in the program will rescue of the history of the Caetés Ecological Station.

  4. PROSPECTS AND FEATURES OF BIOGASOLINE STATIONS

    OpenAIRE

    Grigorash O. V.; Kvitko A. V.; Koshko A. R.

    2015-01-01

    The article deals with one of the promising areas belonging to energy-saving technologies; it is the introduction of biogasoline stations into agricultural production. The analysis of the application in the world has been shown. To determine the cost-effectiveness of biogasoline stations we have shown the data for the calculation of the potential of biomass: organic waste settlements; animal waste; waste of poultry; crop residues; waste processing industry. We have obtained graphic dependence...

  5. Volatile trace compounds released from municipal solid waste at the transfer stage: Evaluation of environmental impacts and odour pollution.

    Science.gov (United States)

    Zhao, Yan; Lu, Wenjing; Wang, Hongtao

    2015-12-30

    Odour pollution caused by municipal solid waste is a public concern. This study quantitatively evaluated the concentration, environmental impacts, and olfaction of volatile trace compounds released from a waste transfer station. Seventy-six compounds were detected, and ethanol presented the highest releasing rate and ratio of 14.76 kg/d and 12.30 g/t of waste, respectively. Life cycle assessment showed that trichlorofluoromethane and dichlorodifluoromethane accounted for more than 99% of impact potentials to global warming and approximately 70% to human toxicity (non-carcinogenic). The major contributor for both photochemical ozone formation and ecotoxicity was ethanol. A detection threshold method was also used to evaluate odour pollution. Five compounds including methane thiol, hydrogen sulphide, ethanol, dimethyl disulphide, and dimethyl sulphide, with dilution multiples above one, were considered the critical compounds. Methane thiol showed the highest contribution to odour pollution of more than 90%, as indicated by its low threshold. Comparison of the contributions of the compounds to different environmental aspects indicated that typical pollutants varied based on specific evaluation targets and therefore should be comprehensively considered. This study provides important information and scientific methodology to elucidate the impacts of odourant compounds to the environment and odour pollution. Copyright © 2015 Elsevier B.V. All rights reserved.

  6. Application of Direct Assessment Approaches and Methodologies to Cathodically Protected Nuclear Waste Transfer Lines

    International Nuclear Information System (INIS)

    Dahl, Megan M.; Pikas, Joseph; Edgemon, Glenn L.; Philo, Sarah

    2013-01-01

    The U.S. Department of Energy's (DOE) Hanford Site is responsible for the safe storage, retrieval, treatment, and disposal of approximately 54 million gallons (204 million liters) of radioactive waste generated since the site's inception in 1943. Today, the major structures involved in waste management at Hanford include 149 carbon steel single-shell tanks, 28 carbon-steel double-shell tanks, plus a network of buried metallic transfer lines and ancillary systems (pits, vaults, catch tanks, etc.) required to store, retrieve, and transfer waste within the tank farm system. Many of the waste management systems at Hanford are still in use today. In response to uncertainties regarding the structural integrity of these systems,' an independent, comprehensive integrity assessment of the Hanford Site piping system was performed. It was found that regulators do not require the cathodically protected pipelines located within the Hanford Site to be assessed by External Corrosion Direct Assessment (ECDA) or any other method used to ensure integrity. However, a case study is presented discussing the application of the direct assessment process on pipelines in such a nuclear environment. Assessment methodology and assessment results are contained herein. An approach is described for the monitoring, integration of outside data, and analysis of this information in order to identify whether coating deterioration accompanied by external corrosion is a threat for these waste transfer lines

  7. Subsides for optimization of transfer of radioactive liquid waste from 99MO production plant to the waste treatment facility

    International Nuclear Information System (INIS)

    Rego, Maria Eugenia de Melo; Vicente, Roberto; Hiromoto, Goro

    2013-01-01

    The increasing need for radioisotopes lead Brazil to consider the domestic production of 99 Mo from fission of low enriched uranium targets. In order to meet the present demand of 99m Tc generators the planned 'end of irradiation' activity of 99 Mo is about 170 TBq per week. The radioactive waste from the production plant will be transferred to a waste treatment facility at the same site. The total activity of the actinides, fission and activation products present in the waste were predicted based on the fission yield and activation data for the irradiation conditions, such as composition and mass of uranium targets, irradiation time, neutron flux, production process and schedule, already established by the project management. The transfer of the waste from the production plant to the treatment facility will be done by means of special shielded packages. In the present study, the commercially available code Scale 6.0 was used to simulate the irradiation of the targets and the decay of radioactive products, assuming that an alkaline dissolution process would be performed on the targets before the removal and purification of 99 Mo. The assessment of the shielding required for the packages containing liquid waste was done using MicroShield 9 code. The results presented here are part of a project that aims at contributing to the design of the waste management system for the 99 Mo production facility. (author)

  8. High Level Waste Feed Delivery AZ-101 Batch Transfer to the Private Contractor Transfer and Mixing Process Improvements

    International Nuclear Information System (INIS)

    DUNCAN, G.P.

    2000-01-01

    The primary purpose of this business case is to provide Operations and Maintenance with a detailed transfer process review for the first High Level Waste (HLW) feed delivery to the Privatization Contractor (PC), AZ-101 batch transfer to PC. The Team was chartered to identify improvements that could be implemented in the field. A significant penalty can be invoked for not providing the quality, quantity, or timely delivery of HLW feed to the PC

  9. Design/Installation and Structural Integrity Assessment of the Bethel Valley Low-Level Waste Collection and Transfer System Upgrade for Building 3544 (Process Waste Treatment Plant) at Oak Ridge National Laboratory, Oak Ridge, Tennessee

    International Nuclear Information System (INIS)

    1996-12-01

    This document describes and assesses planned modifications to be made to the Building 3544 Process Waste Treatment Plant of the Oak Ridge National Laboratory, Oak Ridge, Tennessee. The modifications are made in response to the requirements of the Federal Facility Agreement (FFA) relating to environmental protection requirements for tank systems. The modifications include the provision of a new double contained LLW line replacing an existing buried line that does not provide double containment. This new above ground, double contained pipeline is provided to permit discharge of treated process waste fluid to an outside truck loading station. The new double contained discharge line is provided with leak detection and provisions to remove accumulated liquid. An existing LLW transfer pump, concentrated waste tank, piping and accessories are being utilized, with the addition of a secondary containment system comprised of a dike, a chemically resistant internal coating on the diked area surfaces and operator surveillance on a daily basis for the diked area leak detection. This assessment concludes that the planned modifications comply with applicable requirements of Federal Facility Agreement, Docket No. 89-04-FF, covering the Oak Ridge Reservation

  10. Order of 13 December 1985 on the transfer to ENRESA of the Radioactive Waste Management Facility at Sierra Albarrana

    International Nuclear Information System (INIS)

    1984-01-01

    This Order provides for the transfer of the Radioactive Waste Management Facility at Sierra Albarrana from the Junta de Energia Nuclear to ENRESA, the National Enterprise for Radioactive Waste; it also organises all stages of the transfer. (NEA) [fr

  11. Transfer Effect Ratio of Loosely Coupled Coils for Wireless Power through CB Wall under Station Blackout(SBO)

    International Nuclear Information System (INIS)

    Koo, Kil Mo; Hong, Seong Wan; Song, Jin Ho; Baek, Won Pil; Cheon, Sang Hoon

    2016-01-01

    Instrumentations have had the bad situation like a station blackout(SBO) as the severe accident in nuclear power plants. In recent years, there has been an increasing interest in wireless power transfer technology, In particular, significant processing has been charted for inductively coupled systems. In this paper, we introduce some new method as transfer effect ratio of loosely coupled coils for wireless power through the CB(Container Building) wall as an alternative method under a station blackout of severe accident conditions in nuclear power plants. As an equivalent circuit model that can describe wireless energy transfer systems via coupled magnetic resonances for the CB thickness wall. The solution shows that the transmission efficiency can be decreased simply by adjusting the spacing between the power and the sending coils or between the receiving and the load coils. The system design can be calculated the frequency characteristics, and then an equivalent circuit model was developed from the node equation and established in an electric design automation tool

  12. Transfer Effect Ratio of Loosely Coupled Coils for Wireless Power through CB Wall under Station Blackout(SBO)

    Energy Technology Data Exchange (ETDEWEB)

    Koo, Kil Mo; Hong, Seong Wan; Song, Jin Ho; Baek, Won Pil [KAERI, Daejeon (Korea, Republic of); Cheon, Sang Hoon [ETRI, Daejeon (Korea, Republic of)

    2016-05-15

    Instrumentations have had the bad situation like a station blackout(SBO) as the severe accident in nuclear power plants. In recent years, there has been an increasing interest in wireless power transfer technology, In particular, significant processing has been charted for inductively coupled systems. In this paper, we introduce some new method as transfer effect ratio of loosely coupled coils for wireless power through the CB(Container Building) wall as an alternative method under a station blackout of severe accident conditions in nuclear power plants. As an equivalent circuit model that can describe wireless energy transfer systems via coupled magnetic resonances for the CB thickness wall. The solution shows that the transmission efficiency can be decreased simply by adjusting the spacing between the power and the sending coils or between the receiving and the load coils. The system design can be calculated the frequency characteristics, and then an equivalent circuit model was developed from the node equation and established in an electric design automation tool.

  13. Improvement on control of waste disposal system at Genkai Nuclear Power Station No.1 and No.2 unit

    International Nuclear Information System (INIS)

    Morooka, Masatoshi; Tsutsumi, Akria

    1989-01-01

    At Genkai Nuclear Power Station, the operational and control systems of the boric acid evaporator, waste liquid evaporator and gaseous waste disposal system were converted from general purpose analong systems to computer instrumentation and control systems in order to improve their operability and controllability. The equipments were operated by batch processing system, so plant operators were required to operate them manually. By introducing the computer instrumentation and control systems, the automatic operation of the equipments has become possible. Furthermore, it has become possible to monitor the relevant parameters intensively with a CRT in the operating room, and it contributes to the improvement of reliability and labor saving. The operation of No.1 plant was begun in October, 1975, and No.2 plant in March, 1981. Both are the PWR plants of 625 MVA capacity. The outline of the power station facilities, the background of the reconstruction, the problems and the plan of reconstruction for the boric acid recovery facility, waste liquid evaporator and gas compressor, the peculiarity of the reconstruction works, and the effect of introducing the new systems are reported. (Kako, I.)

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

    Science.gov (United States)

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

    2017-10-01

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

  15. Heat transfer effects in vertically emplaced high level nuclear waste container

    International Nuclear Information System (INIS)

    Moujaes, S.F.; Lei, Y.M.

    1994-01-01

    Modeling free convection heat transfer in an cylindrical annular enclosure is still an active area of research and an important problem to be addressed in the high level nuclear waste repository. For the vertically emplaced waste container, the air gap which is between the container shell and the rock borehole, have an important role of dissipating heat to surrounding rack. These waste containers are vertically emplaced in the borehole 300 meters below ground, and in a horizontal grid of 30 x 8 meters apart. The borehole will be capped after the container emplacement. The expected initial heat generated is between 3--4.74 kW per container depending on the type of waste. The goal of this study is to use a computer simulation model to find the borehole wall, air-gap and the container outer wall temperature distributions

  16. Cross-Site Transfer System at Hanford: long-term strategy for waste acceptance

    International Nuclear Information System (INIS)

    Shekarriz, A.; Onishi, Y.; Smith, P.A.; Sterner, M.; Rector, D.R.; Virden, J.

    1997-02-01

    This report summarizes results of a technical panel review of the current methodology for accepting waste for transport through the Hanford Replacement Cross-Site Transfer System (RCSTS), which was constructed to replace the existing pipelines that hydraulically connect the 200 West and 200 East areas. This report is a complement to an existing document (Hudson 1996); the methodology proposed in that document was refined based on panel recommendations. The refinements were focused around predicting and preventing the 3 main modes suspected of plugging the existing CSTS: precipitation, gelation, particle dropout/settling. The proposed analysis will require integration of computer modeling and laboratory experiments to build a defensible case for transportability of a proposed slurry composition for a given tank. This will be validated by recirculating actual tank waste, in-tank and in-farm, prior to transport. The panel's recommendation was that the probability of success of waste transfer would be greatly improved by integrating the predictive analysis with real-time control during RCSTS operation. The methodology will be optimized

  17. Subsides for optimization of transfer of radioactive liquid waste from {sup 99}MO production plant to the waste treatment facility

    Energy Technology Data Exchange (ETDEWEB)

    Rego, Maria Eugenia de Melo; Vicente, Roberto; Hiromoto, Goro, E-mail: maria.eugenia@ipen.br, E-mail: rvicente@ipen.br, E-mail: hiromoto@ipen.br [Instituto de Pesquisas Energeticas e Nucleares (IPEN/CNEN-SP), Sao Paulo, SP (Brazil)

    2013-07-01

    The increasing need for radioisotopes lead Brazil to consider the domestic production of {sup 99}Mo from fission of low enriched uranium targets. In order to meet the present demand of {sup 99m}Tc generators the planned 'end of irradiation' activity of {sup 99}Mo is about 170 TBq per week. The radioactive waste from the production plant will be transferred to a waste treatment facility at the same site. The total activity of the actinides, fission and activation products present in the waste were predicted based on the fission yield and activation data for the irradiation conditions, such as composition and mass of uranium targets, irradiation time, neutron flux, production process and schedule, already established by the project management. The transfer of the waste from the production plant to the treatment facility will be done by means of special shielded packages. In the present study, the commercially available code Scale 6.0 was used to simulate the irradiation of the targets and the decay of radioactive products, assuming that an alkaline dissolution process would be performed on the targets before the removal and purification of {sup 99}Mo. The assessment of the shielding required for the packages containing liquid waste was done using MicroShield 9 code. The results presented here are part of a project that aims at contributing to the design of the waste management system for the {sup 99}Mo production facility. (author)

  18. Design/installation and structural integrity assessment under the Federal Facility Agreement for Bethel Valley Low-Level Waste Collection and Transfer System upgrade for Building 2026 (High Radiation Level Analytical Laboratory) and Building 2099 (Monitoring and Control Station) at Oak Ridge National Laboratory

    International Nuclear Information System (INIS)

    1994-10-01

    This document presents a Design/Installation and Structural Integrity Assessment for a replacement tank system for portions of the Bethel Valley Low Level Waste (LLW) System, located at the Oak Ridge Reservation, Oak Ridge, Tennessee. This issue of the assessment covers the design aspects of the replacement tank system, and certifies that the design has sufficient structural integrity and is acceptable for the storing or treating of hazardous and/or radioactive substances. The present issue identifies specific activities that must be completed during the fabrication, installation, and testing of the replacement tank system in order to provide assurance that the final installation complies with governing requirements. Portions of the LLW system are several decades old, or older, and do not comply with current environmental protection regulations. Several subsystems of the LLW system have been designated to receive a state-of-the-art replacement and refurbishment. One such subsystem serves Building 2026, the High Radiation Level Analytical Laboratory. This assessment focuses on the scope of work for the Building 2026 replacement LLW Collection and Transfer System, including the provision of a new Monitoring and Control Station (Building 2099) to receive, store, and treat (adjust pH) low level radioactive waste

  19. Heat transfer effects in vertically emplaced high level nuclear waste container

    International Nuclear Information System (INIS)

    Moujaes, S.F.; Lei, Y.M.

    1994-01-01

    Modeling free convection heat transfer in a cylindrical annular enclosure is still an active area of research and an important problem to be addressed in the high level nuclear waste repository. For the vertically emplaced waste container, the air gap which is between the container shell and the rock borehole, have an important role of dissipating heat to surrounding rock. These waste containers are vertically emplaced in the borehole 300 meters just below ground, and in a horizontal grid of 30 x 8 meters apart. The borehole will be capped after the container emplacement. The expected initial heat generated is between 3-4.74 kW per container depending on the type of waste. The goal of this study is to use a computer simulation model to find the borehole wall, air-gap and the container outer wall temperature distributions. The borehole wall temperature history has been found in the previous study, and was estimated to reach a maximum temperature of about 218 degrees C after 18 years from the emplacement. The temperature history of the rock surface is then used for the air-gap simulation. The problem includes convection and radiation heat transfer in a vertical enclosure. This paper will present the results of the convection in the air-gap over one thousand years after the containers' emplacement. During this long simulation period it was also observed that a multi-cellular air flow pattern can be generated in the air gap

  20. DOUBLE-SHELL TANK WASTE TRANSFER LINE ENCASEMENT INTEGRITY ASSESSMENT TECHNOLOGY STUDY

    International Nuclear Information System (INIS)

    BOWER, R.R.

    2006-01-01

    The report provides various alternative methods of performing integrity assessment inspections of buried Hanford Double Shell Tank waste transfer line encasements, and provides method recommendations as an alternative to costly encasement pneumatic leak testing. A schedule for future encasement integrity assessments is also included

  1. The main methods of solving the problem of radioactive waste management from nuclear power stations and spent fuel reprocessing plants in the USSR

    International Nuclear Information System (INIS)

    1978-09-01

    The main directions of solving the problem of radioactive waste management from nuclear power stations and radiochemical plants, the aspects of gaseous waste management, liquid HLW storage in vessels and the problems of heat removal during storage of vitrified HLW in surface storages are considered. The main problems arising during fine decontamination of gaseous discharges from nuclear power stations and reprocessing plants are discussed. The migration of fission products in the environment and technical aspects of their capture from gaseous discharges are also considered

  2. Development of on-site accident criteria for waste transfer casks

    International Nuclear Information System (INIS)

    Uldrich, E.D.

    1989-01-01

    Removal of radioactive waste must withstand the scrutiny of the public and various regulatory offices. Currently, there is no standard accident criteria or methodology for intra-site shipments at the Idaho National Engineering Laboratory (INEL). Since the radioactive waste transfer casks only carry material within the INEL site boundaries and are not used for normal over-the-road transport, the requirements of 10 CFR 71 Packaging and Transportation of Radioactive Material, do not provide suitable requirements for cask design or safety analyses. The objective is to develop realistically conservative accident scenarios consistent with the limited uses at the INEL for which the cask is approved

  3. Experience in industrial operation of the plant for immobilizing radioactive wastes in thermosetting resins at the Ardennes Nuclear Power Station

    International Nuclear Information System (INIS)

    Haller, P.; Romestain, P.; Bruant, J.P.

    1983-01-01

    The French Atomic Energy Commission (CEA) has developed, at the Grenoble Centre for Nuclear Studies, a procedure for immobilizing low- and intermediate-level wastes in thermosetting resins of the polyester or epoxy types. To demonstrate feasibility on an industrial scale, a pilot plant has been set up at the effluent treatment station of the Ardennes Franco-Belgium Nuclear Power Station (SENA), which is a 305 MW(e) PWR type. Assembly work began in January 1979. After a period devoted to final adjustments and operation with inactive products, conditioning of active products began in January 1981. In the paper, the methods of conditioning the three types of waste (evaporation concentrates, ion exchange resins and filter cartridges) are described, experience of the start-up and operation of the plant is reported and the principal results of coating characterization tests are given. The results of tests on active and inactive products show that the characteristics of the materials obtained on an industrial scale match those of laboratory products and confirm their high quality with regard to mechanical behaviour, fire resistance, homogeneity and low-leachability. Industrial experience and economic comparisons show that the process of immobilizing waste from nuclear power stations in thermosetting resins offers an extremely interesting alternative to classical methods of conditioning. (author)

  4. Continued Evaluation of the Pulse-Echo Ultrasonic Instrument for Critical Velocity Determination during Hanford Tank Waste Transfer Operations - 12518

    Energy Technology Data Exchange (ETDEWEB)

    Denslow, Kayte M.; Bontha, Jagannadha R.; Adkins, Harold E.; Jenks, Jeromy W.J.; Burns, Carolyn A.; Schonewill, Philip P.; Hopkins, Derek F. [Pacific Northwest National Laboratory, Richland, Washington 99354 (United States); Thien, Michael G.; Wooley, Theodore A. [Washington River Protection Solutions, Richland, Washington 99354 (United States)

    2012-07-01

    The delivery of Hanford double-shell tank waste to the Hanford Tank Waste Treatment and Immobilization Plant (WTP) will be governed by specific Waste Acceptance Criteria that are identified in ICD 19 - Interface Control Document for Waste Feed. Waste must be certified as acceptable before it can be delivered to the WTP. The fluid transfer velocity at which solid particulate deposition occurs in waste slurry transport piping (critical velocity) is a key waste parameter that must be accurately characterized to determine if the waste is acceptable for transfer to the WTP. In 2010 Washington River Protection Solutions and the Pacific Northwest National Laboratory began evaluating the ultrasonic PulseEcho instrument to accurately identify critical velocities in a horizontal slurry transport pipeline for slurries containing particles with a mean particle diameter of >50 micrometers. In 2011 the PulseEcho instrument was further evaluated to identify critical velocities for slurries containing fast-settling, high-density particles with a mean particle diameter of <15 micrometers. This two-year evaluation has demonstrated the ability of the ultrasonic PulseEcho instrument to detect the onset of critical velocity for a broad range of physical and rheological slurry properties that are likely encountered during the waste feed transfer operations between the Hanford tank farms and the WTP. (authors)

  5. Technology transfer on long-term radioactive waste management - a feasible option for small nuclear programmes?

    International Nuclear Information System (INIS)

    Mele, I.; Mathieson, J.

    2007-01-01

    The EU project CATT - Co-operation and technology transfer on long-term radioactive waste management for Member States with small nuclear programmes investigated the feasibility of countries with small nuclear programmes implementing long-term radioactive waste management solutions within their national borders, through collaboration on technology transfer with those countries with advanced disposal concepts. The main project objective was to analyse the existing capabilities of technology owning Member States and the corresponding requirements of potential technology acquiring Member States and, based on the findings, to develop a number of possible collaboration models and scenarios that could be used in a technology transfer scheme. The project CATT was performed as a specific support action under the EU sixth framework programme and it brought together waste management organisations from six EU Member States: UK, Bulgaria, Germany, Lithuania, Slovenia and Sweden. In addition, the EC Joint Research Centre from the Netherlands also participated as a full partner. The paper summarises the analyses performed and the results obtained within the project. (author)

  6. Waste Retrieval Sluicing System Campaign Number 3 Solids Volume Transferred Calculation

    International Nuclear Information System (INIS)

    CAROTHERS, K.G.

    1999-01-01

    Waste Retrieval Sluicing System (WRSS) operations at tank 241-C-106 began on Wednesday, November 18, 1998. The purpose of this system is to retrieve and transfer the high-heat sludge from the tank for storage in double-shell tank 241-AY-102, thereby resolving the high-heat safety issue for the tank, and to demonstrate modernized past-practice retrieval technology for single-shell tank waste. Performance Agreement (PA) TWR 1.2.2, C-106 Sluicing, was established by the Department of Energy, Office of River Protection (ORP) for achieving completion of sluicing retrieval of waste from tank 241-C-106 by September 30, 1999. This level of sludge removal is defined in the PA as either removal of approximately 72 inches of sludge or removal of 172,000 gallons of sludge (approximately 62 inches) and less than 6,000 gallons (approximately 2 inches) of sludge removal per 12 hour sluice batch for three consecutive batches. Preliminary calculations of the volume of tank 241-C-106 sludge removed as of September 29, 1999 were provided to ORP documenting completion of PA TWR 1.2.2 (Allen 1999a). The purpose of this calculation is to document the final sludge volume removed from tank 241-C-106 up through September 30, 1999. Additionally, the results of an extra batch completed October 6, 1999 is included to show the total volume of sludge removed through the end of WRSS operations. The calculation of the sludge volume transferred from the tank is guided by engineering procedure HNF-SD-WM-PROC-021, Section 15.0,Rev. 3, sub-section 4.4, ''Calculation of Sludge Transferred.''

  7. Waste Retrieval Sluicing System Campaign Number 3 Solids Volume Transferred Calculation

    International Nuclear Information System (INIS)

    CAROTHERS, K.G.

    1999-01-01

    Waste Retrieval Sluicing System (WRSS) operations at tank 241-C-106 began on Wednesday, November 18,1998. The purpose of this system is to retrieve and transfer the high-heat sludge from the tank for storage in double-shell tank 241-AY-102, thereby resolving the high-heat safety issue for the tank, and to demonstrate modernized past-practice retrieval technology for single-shell tank waste. Performance Agreement (PA) TWR 1.2.2, C-106 Sluicing, was established by the Department of Energy, Office of River Protection (ORP) for achieving completion of sluicing retrieval of waste from tank 241-C-106 by September 30,1999. This level of sludge removal is defined in the PA as either removal of approximately 72 inches of sludge or removal of 172,000 gallons of sludge (approximately 62 inches) and less than 6,000 gallons (approximately 2 inches) of sludge removal per 12 hour sluice batch for three consecutive batches. Preliminary calculations of the volume of tank 241-C-106 sludge removed as of September 29, 1999 were provided to ORP documenting completion of PA TWR 1.2.2 (Allen 1999a). The purpose of this calculation is to document the final sludge volume removed from tank 241-C-106 up through September 30, 1999. Additionally, the results of an extra batch completed October 6, 1999 is included to show the total volume of sludge removed through the end of WRSS operations. The calculation of the sludge volume transferred from the tank is guided by engineering procedure HNF-SD-WM-PROC-021, Section 15.0,Rev. 3, sub-section 4.4, ''Calculation of Sludge Transferred.''

  8. Definition of technology development missions for early space stations orbit transfer vehicle serving. Phase 2, task 1: Space station support of operational OTV servicing

    Science.gov (United States)

    1983-01-01

    Representative space based orbital transfer vehicles (OTV), ground based vehicle turnaround assessment, functional operational requirements and facilities, mission turnaround operations, a comparison of ground based versus space based tasks, activation of servicing facilities prior to IOC, fleet operations requirements, maintenance facilities, OTV servicing facilities, space station support requirements, and packaging for delivery are discussed.

  9. Influence of convective-energy transfer on calculated temperature distributions in proposed hard-rock nuclear waste repositories

    Energy Technology Data Exchange (ETDEWEB)

    Eaton, R R; Reda, D C [Sandia National Labs., Albuquerque, NM (USA)

    1982-06-01

    This study assesses the relative influence of convective-energy transfer on predicted temperature distributions for a nuclear-waste repository located in water-saturated rock. Using results for energy transfer by conduction only (no water motion) as a basis of comparison, it is shown that a considerable amount of energy can be removed from the repository by pumping out water that migrates into the drift from regions adjacent to the buried waste canisters. Furthermore, the results show that the influence of convective-energy transfer on mine drift cooling requirements can be significant for cases where the in-situ permeability of the rock is greater than one millidarcy (a regime potentially encountered in repository scenarios).

  10. Automated box/drum waste assay (252Cf shuffler) through the material access and accountability boundary

    International Nuclear Information System (INIS)

    Horley, E.C.; Bjork, C.W.; Bourret, S.C.; Polk, P.J.; Schneider, C.J.; Studley, R.V.

    1992-01-01

    For the first time, a shuffler waste-assay system has been made a part of material access and accountability boundary (MAAB). A 252 Cf Pass-Thru shuffler integrated with a conveyor handling system, will process box or drum waste across the MAAB. This automated system will significantly reduce personnel operating costs because security forces will not be required at the MAAB during waste transfer. Further, the system eliminates the chance of a mix-up between measured and nonmeasured waste. This Pass-Thru shuffler is to be installed in the Westinghouse Savannah River Company 321M facility to screen waste boxes and drums for 235 U. An automated conveyor will load waste containers into the shuffler, and upon verification, will transfer the containers across the MAAB. Verification will consist of a weight measurement followed by active neutron interrogation. Containers that pass low-level waste criteria will be conveyed to an accumulator section outside the MAAB. If a container fails to meet the waste criteria, it will be rejected and sent back to the load station for manual inspection and repackaging

  11. The potential for buoyant displacement gas release events in Tank 241-SY-102 after waste transfer from Tank 241-SY-101

    International Nuclear Information System (INIS)

    Wells, BE; Meyer, P.E.; Chen, G.

    2000-01-01

    Tank 241-SY-101 (SY-101) is a double-shell, radioactive waste storage tank with waste that, before the recent transfer and water back-dilution operations, was capable of retaining gas and producing buoyant displacement (BD) gas release events (GREs). Some BD GREs caused gas concentrations in the tank headspace to exceed the lower flammability limit (LFL). A BD GRE occurs when a portion of the nonconvective layer retains enough gas to become buoyant, rises to the waste surface, breaks up, and releases some of its stored gas. The installation of a mixer pump in 1993 successfully mitigated gas retention in the settled solids layer in SY-101 and has since prevented BD GREs. However, operation of the mixer pump over the years caused gas retention in the floating crust layer and a corresponding accelerated waste level growth. The accelerating crust growth trend observed in 1997--98 led to initiation of sequences of waste removal and water back-dilutions in December 1999. Waste is removed from the mixed slurry layer in Tank SY-101 and transferred into Tank 241-Sy-102 (SY-102). Water is then added back to dissolve soluble solids that retain gas. The initial transfer of 89,500 gallons of SY-101 waste, diluted in-line at 0.94:1 by volume with water, to SY-102 was conducted in December 1999. The second transfer of 230,000 gallons of original SY-101 waste, diluted approximately 0.9:1, was completed in January 2000, and the third transfer of 205,500 gallons of original SY-101 waste diluted at 0.9:1 was completed in March 2000

  12. Tianwan nuclear power station radioactive waste treatment and automatic conveying and temporary store system

    International Nuclear Information System (INIS)

    Long Chengyi; Tang Yifeng; Yang Zhida

    2012-01-01

    The treatment method of middle, low radioactive waste and the system of convey and temporal store in Tianwan nuclear power station were introduced. The primary system has some shortcoming, for example, the orientation precision isn't high, the work intensity is large, the operator is under superfluous nuclear radiation, and the capacity of storehouse isn't large, so the system need rebuild. In the premise of holding present house and facility, frequency conversion system was installed in the crane. In virtue of two laser telemeters and one revolving coder, three-dimensional coordinate parameter of crane can be measured. The application of IPC and PLC make the convey progress automatization, and the progress can be monitored by monitor system. After rebuild, the radioactivity to operator was reduced. Because of function of velocity regulating, the startup, running and braking of the crane is smooth, and the shake range of waste barrel was reduced. The crane orientation precision reach 1 mm, that reduce single waste barrel space, so the capacity of storehouse is evidently improved. (authors)

  13. Hazard evaluation for transfer of waste from tank 241-SY-101 to tank 241-SY-102

    International Nuclear Information System (INIS)

    Shultz, M.V.

    1999-01-01

    Tank 241-SY-101 waste level growth is an emergent, high priority issue. The purpose of this document is to record the hazards evaluation process and document potential hazardous conditions that could lead to the release of radiological and toxicological material from the proposed transfer of a limited quantity (approximately 100,000 gallons) of waste from Tank 241-SY-101 to Tank 241-SY-102. The results of the hazards evaluation were compared to the current Tank Waste Remediation System (TWRS) Basis for Interim Operation (HNF-SD-WM-BIO-001, 1998, Revision 1) to identify any hazardous conditions where Authorization Basis (AB) controls may not be sufficient or may not exist. Comparison to LA-UR-92-3196, A Safety Assessment for Proposed Pump Mixing Operations to Mitigate Episodic Gas Releases in Tank 241-SY-101, was also made in the case of transfer pump removal activities. Revision 1 of this document deletes hazardous conditions no longer applicable to the current waste transfer design and incorporates hazardous conditions related to the use of an above ground pump pit and overground transfer line. This document is not part of the AB and is not a vehicle for requesting authorization of the activity; it is only intended to provide information about the hazardous conditions associated with this activity. The AB Control Decision process will be used to determine the adequacy of controls and whether the proposed activity is within the AB. This hazard evaluation does not constitute an accident analysis

  14. Mass transfer resistance in ASFF reactors for waste water treatment.

    Science.gov (United States)

    Ettouney, H M; Al-Haddad, A A; Abu-Irhayem, T M

    1996-01-01

    Analysis of mass transfer resistances was performed for an aerated submerged fixed-film reactor (ASFF) for the treatment of waste water containing a mixture of sucrose and ammonia. Both external and internal mass transfer resistances were considered in the analysis, and characterized as a function of feed flow-rate and concentration. Results show that, over a certain operating regime, external mass transfer resistance in the system was greater for sucrose removal than ammonia. This is because the reaction rates for carbon removal were much larger than those of nitrogen. As a result, existence of any form of mass transfer resistance caused by inadequate mixing or diffusion limitations, strongly affects the overall removal rates of carbon more than nitrogen. Effects of the internal måss transfer resistance were virtually non-existent for ammonia removal. This behaviour was found over two orders of magnitude range for the effective diffusivity for ammonia, and one order of magnitude for the film specific surface area. However, over the same parameters' range, it is found that sucrose removal was strongly affected upon lowering its effective diffusivity and increasing the film specific surface area.

  15. Pollution profiles, health risk of VOCs and biohazards emitted from municipal solid waste transfer station and elimination by an integrated biological-photocatalytic flow system: A pilot-scale investigation

    International Nuclear Information System (INIS)

    Li, Guiying; Zhang, Zhengyong; Sun, Hongwei; Chen, Jiangyao; An, Taicheng; Li, Bing

    2013-01-01

    Highlights: ► VOCs and biohazards emitted during garbage compressing process were monitored. ► BTF–PC integrated reactor was employed for VOCs and biohazards removal. ► Health risk of target VOCs and biohazards were assessed before and after treatment. -- Abstract: Volatile organic compounds (VOCs) and biohazards air pollution in municipal solid waste transfer station were investigated. As compressor working, the concentrations of almost all quantified 14 VOCs (0.32–306.03 μg m −3 ) were much higher than those as compressor off (0–13.31 μg m −3 ). Comparatively, only 3 VOCs with extremely low concentrations could be detected at control area. Total microorganism was 7567 CFU m −3 as compressor working, which was 1.14 and 6.22 times higher than that of compressor off and control area, respectively. Bacteria were the most abundant microorganism at all three sampling places. At pilot-scale, during whole 60-day treatment, for VOCs, the average removal efficiencies were over 92% after biotrickling filter–photocatalytic (BTF–PC) treatment. Although non-cancer and cancer risks of some VOCs were over the concern level before treatment, almost all VOCs were removed substantially and both potential risks were below the concern after BTF–PC treatment. Additionally, biohazard concentrations decreased dramatically and air quality was purified from polluted to cleanness after PC treatment. All results demonstrated that the integrated technology possessed high removal capacity and long stability for the removal of VOCs and biohazards at a pilot scale

  16. MODELING OF THE HEAT PUMP STATION ADJUSTABLE LOOP OF AN INTERMEDIATE HEAT-TRANSFER AGENT (Part I

    Directory of Open Access Journals (Sweden)

    Sit B.

    2009-08-01

    Full Text Available There are examined equations of dynamics and statics of an adjustable intermediate loop of heat pump carbon dioxide station in this paper. Heat pump station is a part of the combined heat supply system. Control of transferred thermal capacity from the source of low potential heat source is realized by means of changing the speed of circulation of a liquid in the loop and changing the area of a heat-transmitting surface, both in the evaporator, and in the intermediate heat exchanger depending on the operating parameter, for example, external air temperature and wind speed.

  17. System Performance Testing of the Pulse-Echo Ultrasonic Instrument for Critical Velocity Determination during Hanford Tank Waste Transfer Operations - 13584

    Energy Technology Data Exchange (ETDEWEB)

    Denslow, Kayte M.; Bontha, Jagannadha R.; Adkins, Harold E.; Jenks, Jeromy W.J.; Hopkins, Derek F. [Pacific Northwest National Laboratory, Richland, Washington 99354 (United States); Thien, Michael G.; Kelly, Steven E.; Wooley, Theodore A. [Washington River Protection Solutions, Richland, Washington 99354 (United States)

    2013-07-01

    The delivery of Hanford double-shell tank waste to the Hanford Tank Waste Treatment and Immobilization Plant (WTP) is governed by specific Waste Acceptance Criteria that are identified in ICD 19 - Interface Control Document for Waste Feed. Waste must be certified as acceptable before it can be delivered to the WTP. The fluid transfer velocity at which solid particulate deposition occurs in waste slurry transport piping (critical velocity) is a key waste acceptance parameter that must be accurately characterized to determine if the waste is acceptable for transfer to the WTP. Washington River Protection Solutions and the Pacific Northwest National Laboratory have been evaluating the ultrasonic PulseEcho instrument since 2010 for its ability to detect particle settling and determine critical velocity in a horizontal slurry transport pipeline for slurries containing particles with a mean particle diameter of =14 micrometers (μm). In 2012 the PulseEcho instrument was further evaluated under WRPS' System Performance test campaign to identify critical velocities for slurries that are expected to be encountered during Hanford tank waste retrieval operations or bounding for tank waste feed. This three-year evaluation has demonstrated the ability of the ultrasonic PulseEcho instrument to detect the onset of critical velocity for a broad range of physical and rheological slurry properties that are likely encountered during the waste feed transfer operations between the Hanford tank farms and the WTP. (authors)

  18. Transferring knowledge about high-level waste repositories: An ethical consideration

    International Nuclear Information System (INIS)

    Berndes, S.; Kornwachs, K.

    1996-01-01

    The purpose of this paper is to present requirements to Information and Documentation Systems for high-level waste repositories from an ethical point of view. A structured synopsis of ethical arguments used by experts from Europe and America is presented. On the one hand the review suggests to reinforce the obligation to transfer knowledge about high level waste repositories. This obligation is reduced on the other hand by the objection that ethical obligations are dependent on the difference between our and future civilizations. This reflection results in proposing a list of well-balanced ethical arguments. Then a method is presented which shows how scenarios of possible future civilizations for different time horizons and related ethical arguments are used to justify requirements to the Information and Documentation System

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

    International Nuclear Information System (INIS)

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

    2007-01-01

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

  20. Knowledge and technology transfer to improve the municipal solid waste management system of Durango City, Mexico.

    Science.gov (United States)

    Valencia-Vázquez, Roberto; Pérez-López, Maria E; Vicencio-de-la-Rosa, María G; Martínez-Prado, María A; Rubio-Hernández, Rubén

    2014-09-01

    As society evolves its welfare level increases, and as a consequence the amount of municipal solid waste increases, imposing great challenges to municipal authorities. In developed countries, municipalities have established integrated management schemes to handle, treat, and dispose of municipal solid waste in an economical and environmentally sound manner. Municipalities of developing and transition countries are not exempted from the challenges involving municipal solid waste handling, but their task is not easy to accomplish since they face budget deficits, lack of knowledge, and deficiencies in infrastructure and equipment. In the northern territory of Mexico, the municipality of Durango is facing the challenge of increased volumes of waste with a lack of adequate facilities and infrastructure. This article analyses the evolution of the municipal solid waste management of Durango city, which includes actions such as proper facilities construction, equipment acquisition, and the implementation of social programmes. The World Bank, offering courses to municipal managers on landfill operation and waste management, promoted the process of knowledge and technology transfer. Thereafter, municipal authorities attended regional and some international workshops on waste management. In addition they followed suggestions of international contractors and equipment dealers with the intention to improve the situation of the waste management of the city. After a 15-year period, transfer of knowledge and technology resulted in a modern municipal solid waste management system in Durango municipality. The actual system did not reach the standard levels of an integrated waste management system, nevertheless, a functional evaluation shows clear indications that municipality actions have put them on the right pathway. © The Author(s) 2014.

  1. The development and implementation of a dry active waste (DAW) sorting program at Catawba Nuclear Station

    International Nuclear Information System (INIS)

    Schulte, J.H.; McNamara, P.N.

    1988-01-01

    Duke Power Company, like other nuclear utilities, bears a burdensome radwaste disposal cost that has rapidly escalated during recent years. Dry active waste (DAW) represents approximately 85% of the total radioactive waste volume shipped to low-level disposal facilities. Sorting waste with less than detectable radioactivity from waste with detectable radioactivity provides a volume reduction (VR) technique that can save significant radwaste disposal costs and conserve dwindling burial space. This paper presents the development and results of a project that was conducted at Catawba Nuclear Station to determine the volume reduction potential from sorting DAW. Guidelines are given so that other utilities can perform a VR potential study on a low cost basis. Based on the results of the DAW VR study, an overall DAW volume radiation program was initiated at Duke Power Company. This program includes personnel training, drumming techniques, bag tracking and equipment purchases for sorting. This program has been fully implemented at Duke Power Company since January 1, 1988 and preliminary results and savings are given

  2. 25 years of monitoring the Waste Management Center of the Almirante Alvaro Alberto Nuclear Power Station

    International Nuclear Information System (INIS)

    Ferreira, O.C; Barboza, E.; Cardoso, S.N.M.

    2013-01-01

    The goal of this paper is to present an assessment of 25 years of monitoring of the environment around the Waste Management Center (WMC) of the Almirante Alvaro Alberto Nuclear Power Station (AAANPS) since 1986 until 2011. The Environmental Monitoring Laboratory (EML) has, for purposes, to monitor the environment around the station to verify if there's a potential impact caused by the operation of the two units and to verify the dose rate levels around the waste deposits. The WMC is located in an area belonging to the AAANPS and receive solid waste of low and medium activities from Angra 1 NPP. The waste generated from Angra 2 NPP is stored inside the unit. The EML monitors the environment around the WMC to determine the environmental dose rate. The monitoring is made by direct measurement of the radiation using thermoluminescent dosimeters (TLD). Nowadays, the TLD are installed, at this time, in 6 points at the boundaries of WMC and are changed monthly. The locations of these points were already changed several times to allow the construction of new buildings. The constitution of the TLD are 4 crystals, being 3 crystals of Calcium Sulphate doped with Thulium (CaSO 4 :Tm) with 3 shields and 1 crystal of Lithium Borate doped with Copper (Li 2 B 4 O 7 :Cu) without shield. The results of the TLD measurements are normalized to a period of 30 days to compensate accidental statistical variations of the dose rates. The results, in these 25 years, show that the external area of the WMC is a supervised area, following the Norm CNEN-NN-3.01 - 'Diretrizes Basicas de Protecao Radiologica' - with access permitted only for authorized people. (author)

  3. 25 years of monitoring the Waste Management Center of the Almirante Alvaro Alberto Nuclear Power Station

    Energy Technology Data Exchange (ETDEWEB)

    Ferreira, O.C; Barboza, E.; Cardoso, S.N.M., E-mail: landocf@eletronuclear.gov.br, E-mail: barboza@eletronuclear.gov.br, E-mail: sergion@eletronuclear.gov.br [Eletrobras Eletronuclear S.A (ELETONUCLEAR), Paraty, RJ (Brazil). Lab. de Monitoracao Ambiental

    2013-07-01

    The goal of this paper is to present an assessment of 25 years of monitoring of the environment around the Waste Management Center (WMC) of the Almirante Alvaro Alberto Nuclear Power Station (AAANPS) since 1986 until 2011. The Environmental Monitoring Laboratory (EML) has, for purposes, to monitor the environment around the station to verify if there's a potential impact caused by the operation of the two units and to verify the dose rate levels around the waste deposits. The WMC is located in an area belonging to the AAANPS and receive solid waste of low and medium activities from Angra 1 NPP. The waste generated from Angra 2 NPP is stored inside the unit. The EML monitors the environment around the WMC to determine the environmental dose rate. The monitoring is made by direct measurement of the radiation using thermoluminescent dosimeters (TLD). Nowadays, the TLD are installed, at this time, in 6 points at the boundaries of WMC and are changed monthly. The locations of these points were already changed several times to allow the construction of new buildings. The constitution of the TLD are 4 crystals, being 3 crystals of Calcium Sulphate doped with Thulium (CaSO{sub 4}:Tm) with 3 shields and 1 crystal of Lithium Borate doped with Copper (Li{sub 2}B{sub 4}O{sub 7}:Cu) without shield. The results of the TLD measurements are normalized to a period of 30 days to compensate accidental statistical variations of the dose rates. The results, in these 25 years, show that the external area of the WMC is a supervised area, following the Norm CNEN-NN-3.01 - 'Diretrizes Basicas de Protecao Radiologica' - with access permitted only for authorized people. (author)

  4. Toxicity limitation on radioactive liquid waste discharge at OPG Nuclear Stations

    International Nuclear Information System (INIS)

    Dobson, T.; Lovasic, Z.; Nicolaides, G.

    2000-01-01

    This paper describes the Municipal and Industrial Strategy for Abatement (MISA) regulation, which came into effect in 1995 in Ontario (Ontario Regulation 215/95 under the Environmental Protection Act). This imposed additional limitations on liquid discharges from power generating stations. The MISA regulation has divided discharges into non-event and event streams, which have to be monitored for the prescribed parameters and for toxicity. Radioactive Waste Management Systems fall into the category of non-event streams. Standard toxicity testing involves monitoring lethality of Daphnia Magna and Rainbow trout in the effluent. The new legislation has imposed a need to address several issues: acute toxicity, complying with the specific limits prescribed by the regulation and, in the long run chronic toxicity

  5. A research on the environmental impact on nearby waters range at low-level radioactive waste water drain from the Dayawan nuclear power station

    International Nuclear Information System (INIS)

    Zhang Chunling; Xu Zitu; Xiao Zhang.

    1987-01-01

    The possible influence of the low-level radioactive waste water drain from the Dayawan nuclear power station upon nearby waters range is discussed. The contents of the article contains the numerical simulation on tidal currents and pollutant diffusion, the calculation of concentration distribution of radioactive contaminants in the water area and of polluted field, and the criterion on radioactive contaminant influence on nearby residents and aquatic biologicals. The result shows that when the Dayawan nuclear power station is on normal operation and after the low-level radioactive waste water has been drained off into the sea, the radioactive concentration is even lower than the natural background radiation just out-side the area of about 4 km 2 round the water outlet. As a result, it won't cause any danger to the water environment. Due to the fact that the concentration of the low-level radioactive waste water from the nuclear power station fully accords with the national standard GB4792-84 and the sea water quality sandard GBH2, 3-82. It is no harm to either residents and aquatic biologicals or ecological balance

  6. A proposed framework of food waste collection and recycling for renewable biogas fuel production in Hong Kong.

    Science.gov (United States)

    Woon, Kok Sin; Lo, Irene M C

    2016-01-01

    Hong Kong is experiencing a pressing need for food waste management. Currently, approximately 3600 tonnes of food waste are disposed of at landfills in Hong Kong daily. The landfills in Hong Kong are expected to be exhausted by 2020. In the long run, unavoidable food waste should be sorted out from the other municipal solid waste (MSW) and then valorized into valuable resources. A simple sorting process involving less behavioural change of residents is, therefore, of paramount importance in order to encourage residents to sort the food waste from other MSW. In this paper, a sustainable framework of food waste collection and recycling for renewable biogas fuel production is proposed. For an efficient separation and collection system, an optic bag (i.e. green bag) can be used to pack the food waste, while the residual MSW can be packed in a common plastic bag. All the wastes are then sent to the refuse transfer stations in the conventional way (i.e. refuse collection vehicles). At the refuse transfer stations, the food waste is separated from the residual MSW using optic sensors which recognize the colours of the bags. The food waste in the optic bags is then delivered to the proposed Organic Waste Treatment Facilities, in which biogas is generated following the anaerobic digestion technology. The biogas can be further upgraded via gas upgrading units to a quality suitable for use as a vehicle biogas fuel. The use of biogas fuel from food waste has been widely practiced by some countries such as Sweden, France, and Norway. Hopefully, the proposed framework can provide the epitome of the waste-to-wealth concept for the sustainable collection and recycling of food waste in Hong Kong. Copyright © 2015 Elsevier Ltd. All rights reserved.

  7. Tether applications for space station

    Science.gov (United States)

    Nobles, W.

    1986-01-01

    A wide variety of space station applications for tethers were reviewed. Many will affect the operation of the station itself while others are in the category of research or scientific platforms. One of the most expensive aspects of operating the space station will be the continuing shuttle traffic to transport logistic supplies and payloads to the space station. If a means can be found to use tethers to improve the efficiency of that transportation operation, it will increase the operating efficiency of the system and reduce the overall cost of the space station. The concept studied consists of using a tether to lower the shuttle from the space station. This results in a transfer of angular momentum and energy from the orbiter to the space station. The consequences of this transfer is studied and how beneficial use can be made of it.

  8. The technology of concrete in the disposal of radioactive waste

    International Nuclear Information System (INIS)

    Hironaga, Michihiko

    2000-01-01

    The fuel policy of Japan with poor energy resources requires for establishment of nuclear fuel cycle, where uranium fuel once used at a nuclear power station is effectively used at a form of cycling by its reprocessing and its reuse at a fast breeder reactor. At present, 51 units of nuclear power plants are under operation in Japan, of which power generation is 302.1 billion kWh corresponding to 34.6 % of annual power generation in Japan. Radioactive waste is a wasted material containing radioactive materials forming at operation of the nuclear power station and at reprocessing process and so forth carried out at the nuclear fuel cycle. It is required for isolation from human biosphere environment because of its characteristic. Concrete is expected for a play to control leakage of radioactive materials and transfer to biosphere environment as a structural and barrier material constructing a disposal facility of radioactive wastes. Here were described on play, present state, and future problem of concrete mainly used for civil engineering and structural materials and with a strong common recognition at a viewpoint of the 'disposal of radioactive wastes'. (G.K.)

  9. Heat-transfer aspects of Stirling power generation using incinerator waste energy

    Energy Technology Data Exchange (ETDEWEB)

    Hsu, S.T.; Lin, F.Y.; Chiou, J.S. [National Cheng Kung University, Tainan, Taiwan (China). Department of Mechanical Engineering

    2003-01-01

    The integration of a free-piston Stirling engine with linear alternator and an incinerator is able to effectively recover the waste energy and generate electrical power. In this study, a cycle-averaged heat transfer model is employed to investigate the performance of a free-piston Stirling engine installed on an incinerator. With the input of source and sink temperatures and other realistic heat transfer coefficients, the efficiency and the optimal power output are estimated, and the effect induced by internal and external irreversibilities is also evaluated. The proposed approach and modeling results presented in this study provide valuable information for engineers and designers to recover energy from small-scale incinerators. (author)

  10. [Investigation of microbial contamination of the air and equipment of a biological waste water purification station].

    Science.gov (United States)

    Alikbaeva, L A; Figurovskiĭ, A P; Vasil'ev, O D; Ermolaev-Makovskiĭ, M A; Merkur'eva, M A

    2010-01-01

    The paper describes the results of a study of ambient air microbiological pollution in the working premises and equipment surfaces in the main shops of the biological waste water purification station of a cardboard-polygraphic plant. The findings suggest that there is high microbial contamination of the working environment, which should be born in mind on developing measures to optimize working conditions and on studying morbidity rates among the workers.

  11. MODELING OF THE HEAT PUMP STATION CONTROLABLE LOOP OF AN INTERMEDIATE HEAT-TRANSFER AGENT (Part II

    Directory of Open Access Journals (Sweden)

    Sit M.L.

    2011-08-01

    Full Text Available It is studied the model of the heat pump station controllable loop of an intermediate heat-transfer agent for the use in wineries. There are demonstrated transients after the disturbing action of the temperature on the input of cooling jacket of the fermentation stirred tank. There are compared different control laws of the object.

  12. Thermal management of space stations

    Institute of Scientific and Technical Information of China (English)

    2001-01-01

    Thermal management aims at making full use of energy resources available in the space station to reduce energy consumption, waste heat rejection and the weight of the station. It is an extension of the thermal control. This discussion introduces the concept and development of thermal management, presents the aspects of thermal management and further extends its application to subsystems of the space station.

  13. Solidifying power station resins and sludges

    International Nuclear Information System (INIS)

    Willis, A.S.D.; Haigh, C.P.

    1984-01-01

    Radioactive ion exchange resins and sludges arise at nuclear power stations from various operations associated with effluent treatment and liquid waste management. As the result of an intensive development programme, the Central Electricity Generating Board (CEGB) has designed a process to convert power station resins and sludges into a shielded, packaged solid monolithic form suitable for final disposal. Research and development, the generic CEGB sludge/resin conditioning plant and the CEGB Active Waste Project are described. (U.K.)

  14. Fire hazards analysis for the replacement cross-site transfer system, project W-058

    International Nuclear Information System (INIS)

    Sepahpur, J.B.

    1996-01-01

    The fire hazards analysis assess the risk from fire and determines compliance with the applicable criteria of DOE 5480.7A, DOE 6430.1A, and RLID 5480.7. (Project W-058 will provide encased pipelines to connect the SY Tank Farms in 200 West Area with the tank farms in 200 East Area via an interface with the 244-A lift station. Function of the cross-site transfer system will be to transfer radioactive waste from the SY Tank Farm to treatment, storage, and disposal facilities in 200 East Area.)

  15. Co-ordination of federal and provincial environmental assessment processes for the Point Lepreau Generating Station Solid Radioactive Waste Management Facility modifications

    International Nuclear Information System (INIS)

    Hickman, C.; Thompson, P.D.; Barnes, J.

    2006-01-01

    Modification of the Solid Radioactive Waste Management Facility at Point Lepreau Generating Station is required to accommodate waste generated during and after an 18-month maintenance outage during which the station would be Refurbished. The modification of the facility triggered both federal and provincial environmental assessment requirements, and these assessments were conducted in a 'coordinated' and cooperative fashion. In this project, the coordinated approach worked well, and provided some significant advantages to the proponent, the public and the regulators. However, there are opportunities for further improvement in future projects, and this paper explores the advantages and disadvantages of this 'co-ordinated' approach. As part of this exploration, there is a discussion of administrative and regulatory changes that the province is considering for the environmental assessment process, and a discussion of the need for a formal 'harmonization' agreement. (author)

  16. Waste minimization and pollution prevention technology transfer : the Airlie House Projects

    International Nuclear Information System (INIS)

    Gatrone, R.; McHenry, J.; Myron, H.; Thout, J. R.

    1998-01-01

    The Airlie House Pollution Prevention Technology Transfer Projects were a series of pilot projects developed for the US Department of Energy with the intention of transferring pollution prevention technology to the private sector. The concept was to develop small technology transfer initiatives in partnership with the private sector. Argonne National Laboratory developed three projects: the microscale chemistry in education project, the microscale cost benefit study project, and the Bethel New Life recycling trainee project. The two microscale chemistry projects focused on introducing microscale chemistry technologies to secondary and college education. These programs were inexpensive to develop and received excellent evaluations from participants and regulators. The Bethel New Life recycling trainee project provided training for two participants who helped identify recycling and source reduction opportunities in Argonne National Laboratory's solid waste stream. The pilot projects demonstrated that technology transfer initiatives can be developed and implemented with a small budget and within a short period of time. The essential components of the pilot projects were identifying target technologies that were already available, identifying target audiences, and focusing on achieving a limited but defined objective

  17. Solid radioactive waste management in Daya Bay Nuclear Power Station

    International Nuclear Information System (INIS)

    Huang Laixi; He Wenxin; Chen Degan

    2004-01-01

    This paper introduces the solid radwaste management system, treatment methods and its continuous improvement during the past 9 years in Guangdong Daya Bay Nuclear Power Station (GNPS). GNPS has paid great attention and made a lot of efforts to implement the principle of waste minimization with source control, improvement of treatment process and strict management, so the output of solid radwastes has annually decreased since 1994. In 2002, the output of solid radwastes in GNPS was 63.5 m 3 , only 50% of 1995 (127 m 3 ), reached the advanced level as the same type NPPs in France. During the period 1994-2002, the accumulated production of solid radwaste Packages in GNPS is 1563.51 m 3 only 18% of the design value; all the packages meet the standard and requirement for safe disposal. Besides, this paper analyzes some new technical processes and presents some proposals for further decreasing the solid radwaste production

  18. DOE Low-Level Waste Management Program perspective on technology transfer: opportunities and challenges

    International Nuclear Information System (INIS)

    Large, D.E.

    1982-01-01

    The Department of Energy's Low-Level Waste Management Program (DOE LLWMP) perspective in regard to transfer of LLWMP technology to current and potential users in both the commercial and defense sectors is discussed. Past, present, and future opportunities and challenges for the whole nuclear waste management are indicated. Elements considered include: historical and evolutionary events and activities; the purpose of the Program and its inherent opportunities and challenges; achievements and expected accomplishments; supporters and interactors; packaging and delivering technology; implementing and serving potential users; determining and meeting users' needs; and identifying and responding to opportunities and challenges. The low-level waste management effort to improve shallow land burial technology began in FY 1977 and has expanded to include waste treatment and alternative disposal methods. Milestones have been established and are used as principal management control items. This technology, the Program Product, is described and is made available. This year, the Program has drafted criteria for inclusion in a DOE order for radioactive waste management operations at DOE sites

  19. Autonomous rendezvous and docking operations of unmanned expendable cargo transfer vehicles (e.g. Centaur) with Space Station Freedom

    Science.gov (United States)

    Emmet, Brian R.

    1991-01-01

    This paper describes the results of the feasibility study using Centaur or other CTV's to deliver payloads to the Space Station Freedom (SSF). During this study was examined the requirements upon unmanned cargo transfer stages (including Centaur) for phasing, rendezvous, proximity operations and docking/berthing (capture).

  20. Effect of waste mica on transfer factors of 134Cs to spinach and lettuce

    International Nuclear Information System (INIS)

    Sreenivasa Chari, M.; Manjaiah, K.M.; Sachdev, P.; Sachdev, M.S.

    2011-01-01

    A greenhouse pot culture experiment was conducted to study the effect of graded levels of waste mica (0, 10, 20 and 40 g kg -1 ) on reducing the radiocesium uptake by spinach (Spinacia olerecea L) and lettuce (Lactuca sativa L.) grown in 134 Cs-contaminated (at 37 k Bq kg -1 soil) Inceptisols, Vertisols and Ultisols. The biomass yield, and potassium content and its uptake by crops have been significantly improved by waste mica application. The crops grown in Vertisols recorded higher biomass yield, and K content and its uptake as compared with Inceptisols and Ultisols. The average 134 Cs transfer factor values recorded were: 0.21, 0.17 and 0.26 at the first cutting, 0.15, 0.12 and 0.28 at the second cutting and 0.07, 0.05 and 0.23 at the third cutting from Inceptisols, Vertisols and Ultisols, respectively. Waste mica significantly suppressed radiocesium uptake, the effect being more pronounced at 40 g mica kg -1 soil. There exists an inverse relationship between the 134 Cs transfer factors with plant potassium content and also the K uptake by the crops. (authors)

  1. Heat transfer analysis of the geologic disposal of spent fuel and high-level waste storage canisters

    International Nuclear Information System (INIS)

    Allen, G.K.

    1980-08-01

    Near-field temperatures resulting from the storage of high-level waste canisters and spent unreprocessed fuel assembly canisters in geologic formations were determined. Preliminary design of the repository was modeled for a heat transfer computer code, HEATING5, which used the Crank-Nicolson finite difference method to evaluate transient heat transfer. The heat transfer system was evaluated with several two- and three-dimensional models which transfer heat by a combination of conduction, natural convention, and radiation. Physical properties of the materials in the model were based upon experimental values for the various geologic formations. The effects of canister spacing, fuel age, and use of an overpack were studied for the analysis of the spent fuel canisters; salt, granite, and basalt were considered as the storage media for spent fuel canisters. The effects of canister diameter and use of an overpack were studied for the analysis of the high-level waste canisters; salt was considered as the only storage media for high-level waste canisters. Results of the studies on spent fuel assembly canisters showed that the canisters could be stored in salt formations with a maximum heat loading of 134 kw/acre without exceeding the temperature limits set for salt stability. The use of an overpack had little effect on the peak canister temperatures. When the total heat load per acre decreased, the peak temperatures reached in the geologic formations decreased; however, the time to reach the peak temperatures increased. Results of the studies on high-level waste canisters showed that an increased canister diameter will increase the canister interior temperatures considerably; at a constant areal heat loading, a 381 mm diameter canister reached almost a 50 0 C higher temperature than a 305 mm diameter canister. An overpacked canister caused almost a 30 0 C temperature rise in either case

  2. Pump Jet Mixing and Pipeline Transfer Assessment for High-Activity Radioactive Wastes in Hanford Tank 241-AZ-102

    Energy Technology Data Exchange (ETDEWEB)

    Y Onishi; KP Recknagle; BE Wells

    2000-08-09

    The authors evaluated how well two 300-hp mixer pumps would mix solid and liquid radioactive wastes stored in Hanford double-shell Tank 241-AZ-102 (AZ-102) and confirmed the adequacy of a three-inch (7.6-cm) pipeline system to transfer the resulting mixed waste slurry to the AP Tank Farm and a planned waste treatment (vitrification) plant on the Hanford Site. Tank AZ-102 contains 854,000 gallons (3,230 m{sup 3}) of supernatant liquid and 95,000 gallons (360 m{sup 3}) of sludge made up of aging waste (or neutralized current acid waste). The study comprises three assessments: waste chemistry, pump jet mixing, and pipeline transfer. The waste chemical modeling assessment indicates that the sludge, consisting of the solids and interstitial solution, and the supernatant liquid are basically in an equilibrium condition. Thus, pump jet mixing would not cause much solids precipitation and dissolution, only 1.5% or less of the total AZ-102 sludge. The pump jet mixing modeling indicates that two 300-hp mixer pumps would mobilize up to about 23 ft (7.0 m) of the sludge nearest the pump but would not erode the waste within seven inches (0.18 m) of the tank bottom. This results in about half of the sludge being uniformly mixed in the tank and the other half being unmixed (not eroded) at the tank bottom.

  3. Pump Jet Mixing and Pipeline Transfer Assessment for High-Activity Radioactive Wastes in Hanford Tank 241-AZ-102

    International Nuclear Information System (INIS)

    Onishi, Y.; Recknagle, K.P.; Wells, B.E.

    2000-01-01

    The authors evaluated how well two 300-hp mixer pumps would mix solid and liquid radioactive wastes stored in Hanford double-shell Tank 241-AZ-102 (AZ-102) and confirmed the adequacy of a three-inch (7.6-cm) pipeline system to transfer the resulting mixed waste slurry to the AP Tank Farm and a planned waste treatment (vitrification) plant on the Hanford Site. Tank AZ-102 contains 854,000 gallons (3,230 m 3 ) of supernatant liquid and 95,000 gallons (360 m 3 ) of sludge made up of aging waste (or neutralized current acid waste). The study comprises three assessments: waste chemistry, pump jet mixing, and pipeline transfer. The waste chemical modeling assessment indicates that the sludge, consisting of the solids and interstitial solution, and the supernatant liquid are basically in an equilibrium condition. Thus, pump jet mixing would not cause much solids precipitation and dissolution, only 1.5% or less of the total AZ-102 sludge. The pump jet mixing modeling indicates that two 300-hp mixer pumps would mobilize up to about 23 ft (7.0 m) of the sludge nearest the pump but would not erode the waste within seven inches (0.18 m) of the tank bottom. This results in about half of the sludge being uniformly mixed in the tank and the other half being unmixed (not eroded) at the tank bottom

  4. Plasma arc melting treatment of low level radioactive waste with centrifugal hearth

    International Nuclear Information System (INIS)

    Tsuji, Yukito

    1997-01-01

    Plasma Arc Melting technology may possible be able to treat various kinds of waste streams through volume reduction and stabilization into a disposal waste form. The ability of other melting technologies to convert inorganic material in a single step, however, varies according to the characteristics of the materials. Plasma technology also can treat organic waste by selecting the oxidation atmosphere. The Japan Atomic Power Company (JAPC) has decided to construct a low level radioactive waste treatment facility using the Plasma Arc Centrifugal Treatment (PACT) process with an 8 ft rotating hearth and 1.2 MW transferred torch developed by Retech (Ukiah, CA. USA) in the Tsuruga power station. In Japan, the plasma technology has been developed for incineration ash treatment, but the JAPC plant will be the first treatment system using plasma technology for solid waste with various characteristics and shapes. (author)

  5. 42 CFR 35.21 - Authorization of transfer.

    Science.gov (United States)

    2010-10-01

    ... EXAMINATIONS HOSPITAL AND STATION MANAGEMENT Transfer of Patients § 35.21 Authorization of transfer. Except as... of a station or hospital of the Service may provide, without any cost to the patient, for the transfer of the patient either from such station or hospital to another station or hospital of the Service...

  6. Collection, transfer and transport of waste: accounting of greenhouse gases and global warming contribution

    DEFF Research Database (Denmark)

    Eisted, Rasmus; Larsen, Anna Warberg; Christensen, Thomas Højlund

    2009-01-01

    ) emissions were quantified. The emission factors were assigned a global warming potential (GWP) and aggregated into global warming factors (GWFs), which express the potential contribution to global warming from collection, transport and transfer of 1 tonne of wet waste. Six examples involving collection...

  7. UMTS Network Stations

    Science.gov (United States)

    Hernandez, C.

    2010-09-01

    The weakness of small island electrical grids implies a handicap for the electrical generation with renewable energy sources. With the intention of maximizing the installation of photovoltaic generators in the Canary Islands, arises the need to develop a solar forecasting system that allows knowing in advance the amount of PV generated electricity that will be going into the grid, from the installed PV power plants installed in the island. The forecasting tools need to get feedback from real weather data in "real time" from remote weather stations. Nevertheless, the transference of this data to the calculation computer servers is very complicated with the old point to point telecommunication systems that, neither allow the transfer of data from several remote weather stations simultaneously nor high frequency of sampling of weather parameters due to slowness of the connection. This one project has developed a telecommunications infrastructure that allows sensorizadas remote stations, to send data of its sensors, once every minute and simultaneously, to the calculation server running the solar forecasting numerical models. For it, the Canary Islands Institute of Technology has added a sophisticated communications network to its 30 weather stations measuring irradiation at strategic sites, areas with high penetration of photovoltaic generation or that have potential to host in the future photovoltaic power plants connected to the grid. In each one of the stations, irradiance and temperature measurement instruments have been installed, over inclined silicon cell, global radiation on horizontal surface and room temperature. Mobile telephone devices have been installed and programmed in each one of the weather stations, which allow the transfer of their data taking advantage of the UMTS service offered by the local telephone operator. Every minute the computer server running the numerical weather forecasting models receives data inputs from 120 instruments distributed

  8. Close-out of open pit and waste rock piles of a uranium mine in Guangxi province of China

    International Nuclear Information System (INIS)

    Xu Lechang; Zhang Zhao; Zhang Guopu; Liu Min

    2012-01-01

    Close-out of projects of a mine in Guangxi province of China includes open pit,east and west waste rock piles, ore transfer station, industrial fields, buildings, ore transporting road, and equipment and conduits. The following remediation limits are introduced: environment penetrating radiation dose rate and 222 Rn flux of open pit and waste rock piles, 226 Ra specific activity of soil and individual dose. Remediation objective and programme are discussed in details. Remediation effects are evaluated. (authors)

  9. Co-ordination of federal and provincial environmental assessment processes for the Point Lepreau Generating Station Solid Radioactive Waste Management Facility modifications

    Energy Technology Data Exchange (ETDEWEB)

    Hickman, C.; Thompson, P.D. [Point Lepreau Generating Station, Point Lepreau Refurbishment Project, Lepreau, New Brunswick (Canada); Barnes, J. [Jacques Whitford Environment Ltd., Fredericton, New Brunswick (Canada)

    2006-07-01

    Modification of the Solid Radioactive Waste Management Facility at Point Lepreau Generating Station is required to accommodate waste generated during and after an 18-month maintenance outage during which the station would be Refurbished. The modification of the facility triggered both federal and provincial environmental assessment requirements, and these assessments were conducted in a 'coordinated' and cooperative fashion. In this project, the coordinated approach worked well, and provided some significant advantages to the proponent, the public and the regulators. However, there are opportunities for further improvement in future projects, and this paper explores the advantages and disadvantages of this 'co-ordinated' approach. As part of this exploration, there is a discussion of administrative and regulatory changes that the province is considering for the environmental assessment process, and a discussion of the need for a formal 'harmonization' agreement. (author)

  10. Polybrominated diphenyl ethers in e-waste: Level and transfer in a typical e-waste recycling site in Shanghai, Eastern China

    Energy Technology Data Exchange (ETDEWEB)

    Li, Yue; Duan, Yan-Ping, E-mail: duanyanping@tongji.edu.cn; Huang, Fan; Yang, Jing; Xiang, Nan; Meng, Xiang-Zhou; Chen, Ling

    2014-06-01

    Highlights: • PBDEs were detected in the majority of e-waste. • PBDEs were found in TVs made in China after 1990. • The levels of ΣPBDEs in e-waste made in Japan far exceed the threshold limit of RoHS. • The inappropriate recycling and disposal of e-waste is an important source of PBDEs. - Abstract: Very few data for polybrominated diphenyl ethers (PBDEs) were available in the electronic waste (e-waste) as one of the most PBDEs emission source. This study reported concentrations of PBDEs in e-waste including printer, rice cooker, computer monitor, TV, electric iron and water dispenser, as well as dust from e-waste, e-waste dismantling workshop and surface soil from inside and outside of an e-waste recycling plant in Shanghai, Eastern China. The results showed that PBDEs were detected in the majority of e-waste, and the concentrations of ΣPBDEs ranged from not detected to 175 g/kg, with a mean value of 10.8 g/kg. PBDEs were found in TVs made in China after 1990. The mean concentrations of ΣPBDEs in e-waste made in Korea, Japan, Singapore and China were 1.84 g/kg, 20.5 g/kg, 0.91 g/kg, 4.48 g/kg, respectively. The levels of ΣPBDEs in e-waste made in Japan far exceed the threshold limit of RoHS (1.00 g/kg). BDE-209 dominated in e-waste, accounting for over 93%. The compositional patterns of PBDEs congeners resembled the profile of Saytex 102E, indicating the source of deca-BDE. Among the samples of dust and surface soil from a typical e-waste recycling site, the highest concentrations of Σ{sub 18}PBDEs and BDE-209 were found in dust in e-waste, ranging from 1960 to 340,710 ng/g and from 910 to 320,400 ng/g, which were 1–2 orders of magnitude higher than other samples. It suggested that PBDEs released from e-waste via dust, and then transferred to surrounding environment.

  11. An automated rendezvous and capture system design concept for the cargo transfer vehicle and Space Station Freedom

    Science.gov (United States)

    Fuchs, Ron; Marsh, Steven

    1991-01-01

    A rendezvous sensor system concept was developed for the cargo transfer vehicle (CTV) to autonomously rendezvous with and be captured by Space Station Freedom (SSF). The development of requirements, the design of a unique Lockheed developed sensor concept to meet these requirements, and the system design to place this sensor on the CTV and rendezvous with the SSF are described .

  12. Low-level waste (LLW) reclamation program for the Point Lepreau Solid Radioactive Waste Management Facility (SRWMF)

    International Nuclear Information System (INIS)

    Mersereau, M.; McIntyre, K.

    2006-01-01

    Low level radioactive waste retrieved from intermediate storage vaults at Point Lepreau Generating Station has been sorted to remove the non-radioactive portion. The program began with trials to validate procedures and equipment, followed by a production run that is on-going. Waste boxes are opened and sorted at a ventilated sorting table. The sorted waste is directed to the station's free-release ('Likely Clean') waste stream or to the radioactive waste stream, depending on activity measurements. The radioactive waste content of the sorted materials has been reduced by 96% (by mass) using this process. (author)

  13. Low-level waste (LLW) reclamation program for the Point Lepreau Solid Radioactive Waste Management Facility (SRWMF)

    Energy Technology Data Exchange (ETDEWEB)

    Mersereau, M.; McIntyre, K. [Point Lepreau Generating Station, Lepreau, New Brunswick (Canada)]. E-mail: MMersereau@nbpower.com; KMcIntyre@nbpower.com

    2006-07-01

    Low level radioactive waste retrieved from intermediate storage vaults at Point Lepreau Generating Station has been sorted to remove the non-radioactive portion. The program began with trials to validate procedures and equipment, followed by a production run that is on-going. Waste boxes are opened and sorted at a ventilated sorting table. The sorted waste is directed to the station's free-release ('Likely Clean') waste stream or to the radioactive waste stream, depending on activity measurements. The radioactive waste content of the sorted materials has been reduced by 96% (by mass) using this process. (author)

  14. Heat Transfer Model of a Small-Scale Waste Glass Melter with Cold Cap Layer

    Energy Technology Data Exchange (ETDEWEB)

    Abboud, Alexander; Guillen, Donna Post; Pokorny, Richard

    2016-09-01

    At the Hanford site in the state of Washington, more than 56 million gallons of radioactive waste is stored in underground tanks. The cleanup plan for this waste is vitrification at the Waste Treatment Plant (WTP), currently under construction. At the WTP, the waste will be blended with glass-forming materials and heated to 1423K, then poured into stainless steel canisters to cool and solidify. A fundamental understanding of the glass batch melting process is needed to optimize the process to reduce cost and decrease the life cycle of the cleanup effort. The cold cap layer that floats on the surface of the glass melt is the primary reaction zone for the feed-to-glass conversion. The conversion reactions include water release, melting of salts, evolution of batch gases, dissolution of quartz and the formation of molten glass. Obtaining efficient heat transfer to this region is crucial to achieving high rates of glass conversion. Computational fluid dynamics (CFD) modeling is being used to understand the heat transfer dynamics of the system and provide insight to optimize the process. A CFD model was developed to simulate the DM1200, a pilot-scale melter that has been extensively tested by the Vitreous State Laboratory (VSL). Electrodes are built into the melter to provide Joule heating to the molten glass. To promote heat transfer from the molten glass into the reactive cold cap layer, bubbling of the molten glass is used to stimulate forced convection within the melt pool. A three-phase volume of fluid approach is utilized to model the system, wherein the molten glass and cold cap regions are modeled as separate liquid phases, and the bubbling gas and plenum regions are modeled as one lumped gas phase. The modeling of the entire system with a volume of fluid model allows for the prescription of physical properties on a per-phase basis. The molten glass phase and the gas phase physical properties are obtained from previous experimental work. Finding representative

  15. Sorting and recycling of domestic waste. Review of occupational health problems and their possible causes

    DEFF Research Database (Denmark)

    Poulsen, O M; Breum, N O; Ebbehøj, N

    1995-01-01

    In order to reduce the strain on the environment from the deposition of waste in landfills and combustion at incineration plants, several governments throughout the industrialized world have planned greatly increased recycling of domestic waste by the turn of the millennium. To implement the plans......, new waste recycling facilities are to be built and the number of workers involved in waste sorting and recycling will increase steadily during the next decade. Several studies have reinforced the hypothesis that exposure to airborne microorganisms and the toxic products thereof are important factors...... causing a multitude of health problems among workers at waste sorting and recycling plants. Workers at transfer stations, landfills and incineration plants may experience an increased risk of pulmonary disorders and gastrointestinal problems. High concentrations of total airborne dust, bacteria, faecal...

  16. Product quality follow-up for the start of an industrial plant, e.g.: The waste station No 3 at La Hague

    International Nuclear Information System (INIS)

    Saas, A.; Vidal, H.; Alvy, J.C.; Boudry, J.C.; Bouin, R.

    1990-01-01

    During the start-up of the plant for waste treatment and mud coating in bitumen (waste station No 3 La Hague), the Characterization and Estimate of Containments and Analyses Service performed several different controls and tests to verify: whether the industrial plant was operating according to the defined procedure, whether the coated products obtained were in line with provisional specifications, whether the operational sector of the plant ensured the final quality of the coated product. The main results of these measurements and tests are presented in this paper. (orig./DG)

  17. A cell-based study on pedestrian acceleration and overtaking in a transfer station corridor

    Science.gov (United States)

    Ji, Xiangfeng; Zhou, Xuemei; Ran, Bin

    2013-04-01

    Pedestrian speed in a transfer station corridor is faster than usual and sometimes running can be found among some of them. In this paper, pedestrians are divided into two categories. The first one is aggressive, and the other is conservative. Aggressive pedestrians weaving their way through crowd in the corridor are the study object of this paper. During recent decades, much attention has been paid to the pedestrians' behavior, such as overtaking (also deceleration) and collision avoidance, and that continues in this paper. After sufficiently analyzing the characteristics of pedestrian flow in transfer station corridor, a cell-based model is presented in this paper, including the acceleration (also deceleration) and overtaking analysis. Acceleration (also deceleration) in a corridor is fixed according to Newton's Law and then speed calculated with a kinematic formula is discretized into cells based on the fuzzy logic. After the speed is updated, overtaking is analyzed based on updated speed and force explicitly, compared to rule-based models, which herein we call implicit ones. During the analysis of overtaking, a threshold value to determine the overtaking direction is introduced. Actually, model in this paper is a two-step one. The first step is to update speed, which is the cells the pedestrian can move in one time interval and the other is to analyze the overtaking. Finally, a comparison between the rule-based cellular automata, the model in this paper and data in HCM 2000 is made to demonstrate our model can be used to achieve reasonable simulation of acceleration (also deceleration) and overtaking among pedestrians.

  18. Ariane Transfer Vehicle in service of man in orbit

    Science.gov (United States)

    Deutscher, N.; Schefold, K.; Cougnet, C.

    1988-10-01

    The Ariane Transfer Vehicle (ATV), an unmanned propulsion system that is designed to be carried by the Ariane 5 launch vehicle, will undertake the logistical support required by the International Space Station and the Man-Tended Free Flyer, carrying both pressurized and unpressurized cargo to these spacecraft and carrying away wastes. The ATV is an expendable vehicle, disposed of by burn-up during reentry, and will be available for initial operations in 1996. In order to minimize development costs and recurrent costs, the ATV design will incorporate existing hardware and software.

  19. Model Predictive Control of Offshore Power Stations With Waste Heat Recovery

    DEFF Research Database (Denmark)

    Pierobon, Leonardo; Chan, Richard; Li, Xiangan

    2016-01-01

    The implementation of waste heat recovery units on oil and gas offshore platforms demands advances in both design methods and control systems. Model-based control algorithms can play an important role in the operation of offshore power stations. A novel regulator based on a linear model predictive...... control (MPC) coupled with a steady-state performance optimizer has been developed in the SIMULINK language and is documented in the paper. The test case is the regulation of a power system serving an oil and gas platform in the Norwegian Sea. One of the three gas turbines is combined with an organic...... Rankine cycle (ORC) turbogenerator to increase the energy conversion efficiency. Results show a potential reduction of frequency drop up to 40%for a step in the load set-point of 4 MW, compared to proportional–integral control systems. Fuel savings in the range of 2–3% are also expected by optimizing on...

  20. Civil nuclear and responsibilities related to radioactive wastes. The 'cumbersome' wastes of the civil nuclear; The Parliament and the management of wastes from the civil nuclear; The Swiss legal framework related to the shutting down of nuclear power stations and to the management of radioactive wastes; Economic theory and management of radioactive wastes: to dare the conflict

    International Nuclear Information System (INIS)

    Rambour, Muriel; Pauvert, Bertrand; Zuber-Roy, Celine; Thireau, Veronique

    2015-01-01

    This publication presents the contributions to a research seminar organised by the European Centre of research on Risk, Collective Accident and Disasters Law (CERDACC) on the following theme: civil nuclear and responsibilities related to radioactive wastes. Three main thematic issues have been addressed: the French legal framework for waste processing, the comparison with the Swiss case, and the controversy about the exposure of societies to waste-induced risks. The first contribution addressed the cumbersome wastes of the civil nuclear industry: characterization and management solutions, the hypothesis of reversibility of the storage of radioactive wastes. The second one comments the commitment of the French Parliament in the management of wastes of the civil nuclear industry: role of Parliamentary Office of assessment of scientific and technological choices (OPECST) to guide law elaboration, assessment by the Parliament of the management of nuclear wastes (history and evolution of legal arrangements). The next contribution describes the Swiss legal framework for the shutting down of nuclear power stations (decision and decommissioning) and for the management of radioactive wastes (removal, financing). The last contribution discusses the risk related to nuclear waste management for citizen and comments how economists address this issue

  1. Space Station fluid management logistics

    Science.gov (United States)

    Dominick, Sam M.

    1990-01-01

    Viewgraphs and discussion on space station fluid management logistics are presented. Topics covered include: fluid management logistics - issues for Space Station Freedom evolution; current fluid logistics approach; evolution of Space Station Freedom fluid resupply; launch vehicle evolution; ELV logistics system approach; logistics carrier configuration; expendable fluid/propellant carrier description; fluid carrier design concept; logistics carrier orbital operations; carrier operations at space station; summary/status of orbital fluid transfer techniques; Soviet progress tanker system; and Soviet propellant resupply system observations.

  2. Vehicle Radiation Monitoring Systems for Medical Waste Disposal - 12102

    Energy Technology Data Exchange (ETDEWEB)

    Kondrashov, Vladislav S.; Steranka, Steve A. [RadComm Systems Corp., 2931 Portland Dr., Oakville, ON L6H 5S4 (Canada)

    2012-07-01

    Hospitals often declare their waste as being 'non-radioactive'; however this material often has excessive levels of radiation caused either by an accident or lack of control. To ensure the best possible protection against the accidental receipt of radioactive materials and as a safety precaution for their employees, waste-handling companies have installed large-scale radiation portal monitors at their weigh scales or entry gates of the incinerator plant, waste transfer station, and/or landfill. Large-volume plastic scintillator-based systems can be used to monitor radiation levels at entry points to companies handling medical waste. The recent and intensive field tests together with the thousands of accumulated hours of actual real-life vehicle scanning have proven that the plastic scintillation based system is an appropriate radiation control instrument for waste management companies. The Real-Time background compensation algorithm is flexible with automatic adjustable coefficients that will response to rapidly changing environmental and weather conditions maintaining the preset alarm threshold levels. The Dose Rate correction algorithms further enhance the system's ability to meet the stringent requirements of the waste industries need for Dose Rate measurements. (authors)

  3. Integrated water management system - Description and test results. [for Space Station waste water processing

    Science.gov (United States)

    Elden, N. C.; Winkler, H. E.; Price, D. F.; Reysa, R. P.

    1983-01-01

    Water recovery subsystems are being tested at the NASA Lyndon B. Johnson Space Center for Space Station use to process waste water generated from urine and wash water collection facilities. These subsystems are being integrated into a water management system that will incorporate wash water and urine processing through the use of hyperfiltration and vapor compression distillation subsystems. Other hardware in the water management system includes a whole body shower, a clothes washing facility, a urine collection and pretreatment unit, a recovered water post-treatment system, and a water quality monitor. This paper describes the integrated test configuration, pertinent performance data, and feasibility and design compatibility conclusions of the integrated water management system.

  4. Implementation of the waste management transfer act. Requirements from a regulatory point of view; Zur Umsetzung des Entsorgungsuebergangsgesetzes. Anforderungen aus regulatorischer Sicht

    Energy Technology Data Exchange (ETDEWEB)

    Mueller-Dehn, Christian [PreussenElektra GmbH, Hannover (Germany). Regulierung, Grundsatzfragen

    2017-11-15

    In future in Germany, the state will be responsible for financing and handling the interim and final storage of radioactive waste from nuclear power plants. With regard to interim storage, this objective is achieved with the provisions of the Waste Management Transfer Act. Regulatory implementation is based on these regulations. BGZ Gesellschaft fuer Zwischenlager mbH is responsible for interim storage on behalf of the Federal Government. Simultaneously with the transfer of interim storage facilities to BGZ a legal transfer of approval is carried out. Insofar as there is a technical, organisational or personnel conjunction with the nuclear power plant operation, which continues to exist beyond this deadline and is relevant for regulatory purposes, a regulation is made via a service contract with the BGZ. This ensures compliance with the licensing regulations. Irradiated fuel assemblies and the waste from reprocessing can be handed over to BGZ from 1 January 2019 onwards and waste with negligible heat generation can be disposed of as of the determination of their proper packaging.

  5. The waste management implications of decommissioning

    International Nuclear Information System (INIS)

    Passant, F.H.

    1988-01-01

    Decommissioning policy can only be framed in the light of radioactive waste management policy. What can be done with the waste materials, how and when, will determine the overall decommissioning plans and costs. In this paper the waste management options and their costs are reviewed for the decommissioning of the Central Electricity Generating Boards civil nuclear power stations. The paper concentrates on the decommissioning of Magnox stations, although comparative information on waste volumes and costs are given for the AGR programme and a typical PWR. (author)

  6. Biotechnology opportunities on Space Station

    Science.gov (United States)

    Deming, Jess; Henderson, Keith; Phillips, Robert W.; Dickey, Bernistine; Grounds, Phyllis

    1987-01-01

    Biotechnology applications which could be implemented on the Space Station are examined. The advances possible in biotechnology due to the favorable microgravity environment are discussed. The objectives of the Space Station Life Sciences Program are: (1) the study of human diseases, (2) biopolymer processing, and (3) the development of cryoprocessing and cryopreservation methods. The use of the microgravity environment for crystal growth, cell culturing, and the separation of biological materials is considered. The proposed Space Station research could provide benefits to the fields of medicine, pharmaceuticals, genetics, agriculture, and industrial waste management.

  7. Reconnaissance survey of the intermediate-level liquid waste transfer line between X-10 and the hydrofracture site

    International Nuclear Information System (INIS)

    Duguid, J.O.; Sealand, O.M.

    1975-08-01

    Two leakage points on an intermediate-level liquid waste line were located. The waste line is used periodically to transfer waste between X-10 and the hydrofracture site. The first leak occurred prior to this survey and had been repaired, but no contaminated soil had been removed. The second leak resulted in soil contamination that was more intense than at the first leak. Analyses of soil samples taken from both locations are given in this report. Groundwater data indicate the effectiveness of the removal of the contaminated material from leak two. 1 ref., 5 figs., 3 tabs

  8. Reconnaissance survey of the intermediate level liquid waste transfer line between X-10 and the hydrofracture site

    International Nuclear Information System (INIS)

    Duguid, J.O.; Sealand, O.M.

    1975-08-01

    Two leakage points on an intermediate-level liquid waste line were located. The waste line is used periodically to transfer waste between X-10 and the hydrofracture site. The first leak had occurred prior to this survey and had been repaired. However, no contaminated soil had been removed. The second leak had not been discovered previously and soil contamination in this area was more intense than at the first leak. Analyses of soil samples taken from both locations are given in this report. Groundwater data that indicate the effectiveness of the removal of the contaminated material from leak two are presented. (U.S.)

  9. BY tank farm waste inventory and transfer data for ITS-2 operation during January To December 1971

    Energy Technology Data Exchange (ETDEWEB)

    Reich, F.R., Westinghouse Hanford

    1996-08-02

    Data record inventory of pumping activities and liquid level changes including occasional operations comments for the BY Tank Farm. Waste inventory and transfer data for ITS-2 operation during January to December 1971.

  10. Municipal solid waste composition determination supporting the integrated solid waste management system in the island of Crete

    International Nuclear Information System (INIS)

    Gidarakos, E.; Havas, G.; Ntzamilis, P.

    2006-01-01

    A one-year survey was conducted in the greater region of Crete (located at the lower region of the Aegean Sea) for the purpose of identifying waste composition (including chemical and physical characterization), as well as any seasonal variation. The investigation was carried out repeatedly at seven landfills and one transfer station in Crete, in four phases. Each sampling phase corresponded to a season (autumn, winter, spring, summer). ASTM D5231-92(2003) standard method and RCRA Waste Sampling Draft Technical Guidance were used. Hand sorting was used for classifying the collected wastes into the following categories: plastics, paper, metals, aluminium, leather-wood-textiles-rubbers, organic wastes, non-combustibles and miscellaneous. Further analysis included proximate and ultimate analysis of combustible materials. Metals such as lead, cadmium and mercury were also investigated. The results show that there has been a significant decrease of organic wastes during the last decade due to the increase of packaging materials, as a result of a change in consumption patterns. Three main waste categories were determined: organic wastes, paper and plastics, which combined represent 76% of the total waste in Crete. Furthermore, a high fraction of glass and a seasonal variation of aluminium indicate a strong correlation of waste composition with certain human activities, such as tourism. There is also a variation between the municipal solid waste (MSW) composition in the region of Crete (2003-2004) and MSW composition suggested in the National Solid Waste Planning (2000) [National Solid Waste Planning, 2000. Completion and particularization of Common Ministerial Act 113944//1944/1997: National Solid Waste Planning, June 2000]. The results of this survey are to be utilized by the regional solid waste authorities in order to establish an integrated waste treatment site, capable of fulfilling the regional waste management demands

  11. Municipal solid waste composition determination supporting the integrated solid waste management system in the island of Crete.

    Science.gov (United States)

    Gidarakos, E; Havas, G; Ntzamilis, P

    2006-01-01

    A one-year survey was conducted in the greater region of Crete (located at the lower region of the Aegean Sea) for the purpose of identifying waste composition (including chemical and physical characterization), as well as any seasonal variation. The investigation was carried out repeatedly at seven landfills and one transfer station in Crete, in four phases. Each sampling phase corresponded to a season (autumn, winter, spring, summer). ASTM D5231-92(2003) standard method and RCRA Waste Sampling Draft Technical Guidance were used. Hand sorting was used for classifying the collected wastes into the following categories: plastics, paper, metals, aluminium, leather-wood-textiles-rubbers, organic wastes, non-combustibles and miscellaneous. Further analysis included proximate and ultimate analysis of combustible materials. Metals such as lead, cadmium and mercury were also investigated. The results show that there has been a significant decrease of organic wastes during the last decade due to the increase of packaging materials, as a result of a change in consumption patterns. Three main waste categories were determined: organic wastes, paper and plastics, which combined represent 76% of the total waste in Crete. Furthermore, a high fraction of glass and a seasonal variation of aluminium indicate a strong correlation of waste composition with certain human activities, such as tourism. There is also a variation between the municipal solid waste (MSW) composition in the region of Crete (2003-2004) and MSW composition suggested in the National Solid Waste Planning (2000) [National Solid Waste Planning, 2000. Completion and particularization of Common Ministerial Act 113944//1944/1997: National Solid Waste Planning, June 2000]. The results of this survey are to be utilized by the regional solid waste authorities in order to establish an integrated waste treatment site, capable of fulfilling the regional waste management demands.

  12. Characteristics of volatile compound emission and odor pollution from municipal solid waste treating/disposal facilities of a city in Eastern China

    DEFF Research Database (Denmark)

    Guo, Hanwen; Duan, Zhenhan; Zhao, Yan

    2017-01-01

    Transfer station, incineration plant, and landfill site made up the major parts of municipal solid waste disposal system of S city in Eastern China. Characteristics of volatile compounds (VCs) and odor pollution of each facility were investigated from a systematic perspective. Also major index...... in the waste tipping port of the incineration plant. A positive correlation between the olfactory and chemical odor concentrations was found with R2 = 0.918 (n = 15, P technology to deal...... with the non-source-separated waste. Strong attention thus needs to be paid on the enclosed systems in incineration plant to avoid any accidental odor emission....

  13. International remote monitoring project Argentina Nuclear Power Station Spent Fuel Transfer Remote Monitoring System

    International Nuclear Information System (INIS)

    Schneider, S.; Lucero, R.; Glidewell, D.

    1997-01-01

    The Autoridad Regulataria Nuclear (ARN) and the United States Department of Energy (DOE) are cooperating on the development of a Remote Monitoring System for nuclear nonproliferation efforts. A Remote Monitoring System for spent fuel transfer will be installed at the Argentina Nuclear Power Station in Embalse, Argentina. The system has been designed by Sandia National Laboratories (SNL), with Los Alamos National Laboratory (LANL) and Oak Ridge National Laboratory (ORNL) providing gamma and neutron sensors. This project will test and evaluate the fundamental design and implementation of the Remote Monitoring System in its application to regional and international safeguards efficiency. This paper provides a description of the monitoring system and its functions. The Remote Monitoring System consists of gamma and neutron radiation sensors, RF systems, and video systems integrated into a coherent functioning whole. All sensor data communicate over an Echelon LonWorks Network to a single data logger. The Neumann DCM 14 video module is integrated into the Remote Monitoring System. All sensor and image data are stored on a Data Acquisition System (DAS) and archived and reviewed on a Data and Image Review Station (DIRS). Conventional phone lines are used as the telecommunications link to transmit on-site collected data and images to remote locations. The data and images are authenticated before transmission. Data review stations will be installed at ARN in Buenos Aires, Argentina, ABACC in Rio De Janeiro, IAEA Headquarters in Vienna, and Sandia National Laboratories in Albuquerque, New Mexico. 2 refs., 2 figs

  14. MHD power station with coal gasification

    International Nuclear Information System (INIS)

    Brzozowski, W.S.; Dul, J.; Pudlik, W.

    1976-01-01

    A description is given of the proposed operating method of a MHD-power station including a complete coal gasification into lean gas with a simultaneous partial gas production for the use of outside consumers. A comparison with coal gasification methods actually being used and full capabilities of power stations heated with coal-derived gas shows distinct advantages resulting from applying the method of coal gasification with waste heat from MHD generators working within the boundaries of the thermal-electric power station. (author)

  15. Periodical inspection in nuclear power stations

    International Nuclear Information System (INIS)

    1986-01-01

    Periodical inspection is presently being made of eight nuclear power plants in nuclear power stations. Up to the present time, in three of them, failures as follows have been observed. (1) Unit 3 (PWR) of the Mihama Power Station in The Kansai Electric Power Co., Inc. Nineteen heat-transfer tubes of the steam generators were plugged up due to failure. A fuel assembly with a failed spring fixture and in another the control-rod cluster with a failed control rod fixture were replaced. (2) Unit 2 (PWR) of the Oi Power Station in The Kansai Electric Power Co., Inc. Eight heat-transfer tubes of the heat exchangers were plugged up due to failure. (3) Unit 6 (BWR) of the Fukushima Nuclear Power Station I in The Tokyo Electric Power Co., Inc. A fuel assembly with leakage was replaced. (Mori, K.)

  16. Technology transfer and radioactive waste management at TMI-2 [Three Mile Island Unit 2

    International Nuclear Information System (INIS)

    Saunders, J.R.

    1988-01-01

    The accident that occurred on March 28, 1979, at the Three Mile Island Unit 2 (TMI-2) nuclear generating station caused extensive damage to the reactor core and created high radiation contamination levels throughout the facility. The electric power industry, regulators, and government agencies were faced with one of the most technically challenging recovery situations ever encountered in this country. But it was also realized that this adversity presented opportunities for the advancement of state-of-the-art technologies as well as the potential to produce information that could enhance nuclear power plant safety and reliability. Perhaps one of the more significant aspects of the TMI-2 recovery has been the advancement of radioactive waste management technology. The high levels and unusual nature of the TMI-2 radioactive waste necessitated the development of innovative techniques for processing, packaging, shipping, and disposal. The investment in research was rewarded with large volume reductions and associated cost savings. It is anticipated that the TMI-2 radioactive waste management technology will make major contributions to the design of new systems to meet this growing need. The following areas appear particularly suited for this purpose: volume reduction, high-integrity containers, and selective isotope removal

  17. Waste sludge resuspension and transfer: development program

    International Nuclear Information System (INIS)

    Weeren, H.O.; Mackey, T.S.

    1980-02-01

    The six Gunite waste tanks at Oak Ridge National Laboratory (ORNL) contain about 400,000 gal of sludge that has precipitated from solution and settled during the 35 years these tanks have been in service. Eventual decommissioning of the tanks has been proposed. The first part of this program is to resuspend the accumulated sludge, to transfer it to new storage tanks in Melton Valley, and to dispose of it by the shale-fracturing process. On the basis of preliminary information, a tentative operational concept was adopted. The sludge in each tank would be resuspended by hydraulic sluicing and pumped from the tank. This resuspended sludge would be treated as necessary to keep the particles in suspension and would be pumped to the new waste-storage tanks. Subsequently the sludge would be pumped from the tanks, combined with a cement-base mix, and disposed of by the shale-fracturing facility. Verification of the feasibility of this concept required development effort on characterization of the sludge and development of techniques for resuspending the sludge and for keeping it in suspension. These development efforts are described in this report. Sections of the report describe both the known properties of the sludge and the tests of grinding methods investigated, discuss tests of various suspenders, describe tests with cement-base mixes, summarize hot-cell tests on actual sludge samples, and describe tests that were made at a mockup of a Gunite tank installation. On the basis of the tests made, it was concluded that reslurrying and resuspension of the sludge is quite feasible and that the suspensions can be made compatible with cement mixes

  18. Preoperational test report, cross-site transfer system integrated test (POTR-007)

    Energy Technology Data Exchange (ETDEWEB)

    Pacquet, E.A.

    1998-04-02

    This report documents the results obtained during the performance of Preoperational Test POTP-007, from December 12, 1997 to March 27, 1998. The main objectives were to demonstrate the operation of the following Cross-Site Transfer System components: Booster pumps P-3125A and P-3125B interlocks and controls, both local and remote; Booster pump P-3125A and P-3125B and associated variable speed drives VSD-1 and VSD-2 performance in both manual and automatic modes; and Water filling, circulation, venting and draining of the transfer headers (supernate and slurry line). As described in reference 1, the following components of the Cross-Site Transfer System that would normally be used during an actual waste transfer, are not used in this specific test: Water Flush System; Valving and instrumentation associated with the 241-SY-A valve pit jumpers; and Valving and instrumentation associated with the 244-A lift station.

  19. Preoperational test report, cross-site transfer system integrated test (POTR-007)

    International Nuclear Information System (INIS)

    Pacquet, E.A.

    1998-01-01

    This report documents the results obtained during the performance of Preoperational Test POTP-007, from December 12, 1997 to March 27, 1998. The main objectives were to demonstrate the operation of the following Cross-Site Transfer System components: Booster pumps P-3125A and P-3125B interlocks and controls, both local and remote; Booster pump P-3125A and P-3125B and associated variable speed drives VSD-1 and VSD-2 performance in both manual and automatic modes; and Water filling, circulation, venting and draining of the transfer headers (supernate and slurry line). As described in reference 1, the following components of the Cross-Site Transfer System that would normally be used during an actual waste transfer, are not used in this specific test: Water Flush System; Valving and instrumentation associated with the 241-SY-A valve pit jumpers; and Valving and instrumentation associated with the 244-A lift station

  20. Waste management procedures for fusion-based central power stations

    International Nuclear Information System (INIS)

    Botts, T.E.; Powell, J.R.

    1977-08-01

    Several early conceptual designs of fusion demonstration and commercial reactors are used in a discussion of radioactive waste streams, methods of handling these wastes, and their possible environmental effects. Comparisons are made between these waste streams and the fuel cycles of the light water reactor and the liquid metal fast breeder reactor. Most radioactive waste in fusion reactors is generated through replacement of the inner blanket region. Because there is a high degree of uncertainty with regard to blanket lifetimes, there is some uncertainty concerning the activity levels that must be handled. However, in general, fusion reactors are expected to create larger physical amounts of radioactive waste with lower and shorter-lived activity than do fission plants. Material recycling of fusion blanket waste, for nuclear applications, seems feasible after a 100-yr holding time

  1. Mobile environmental radiation monitoring station

    International Nuclear Information System (INIS)

    Assido, H.; Shemesh, Y.; Mazor, T.; Tal, N.; Barak, D.

    1997-01-01

    A mobile environmental radiation monitoring station has been developed and established for the Israeli Ministry of Environment. The radiation monitoring station is ready for immediate placing in any required location, or can be operated from a vehicle. The station collects data Tom the detector and transfers it via cellular communication network to a Computerized Control Center for data storage, processing, and display . The mobile station is fully controlled from the. Routinely, the mobile station responses to the data request accumulated since the last communication session. In case of fault or alarm condition in the mobile station, a local claim is activated and immediately initiates communication with the via cellular communication network. (authors)

  2. Shippingport Atomic Power Station. Quarterly operating report, third quarter 1978

    Energy Technology Data Exchange (ETDEWEB)

    Jones, T. D.

    1978-01-01

    A loss of ac power to the station occurred on July 28, 1978 caused by an interaction between Beaver Valley Power Station and Shippingport Atomic Power Station when the main transformer of Unit No. 1 of the Beaver Valley Power Station developed an internal failure and tripped the BVPS. Two environmental studies were continued this quarter. The first involves reduction of main unit condenser chlorination and the second, river intake screen fish impingement sampling. There were no radioactive liquid discharges from the Radioactive Waste Processing System to the river this quarter. During the third quarter of 1978, 874 cubic feet of radioactive solid waste was shipped out of state for burial. At the end of the quarter, the Fall shutdown continued with the plant heated up, the main turbine on turning gear and plant testing in progress prior to Station startup.

  3. Environmental impact assessment of solid waste management in Beijing City, China

    International Nuclear Information System (INIS)

    Zhao Yan; Christensen, Thomas H.; Lu Wenjing; Wu Huayong; Wang Hongtao

    2011-01-01

    The environmental impacts of municipal solid waste management in Beijing City were evaluated using a life-cycle-based model, EASEWASTE, to take into account waste generation, collection, transportation, treatment/disposal technologies, and savings obtained by energy and material recovery. The current system, mainly involving the use of landfills, has manifested significant adverse environmental impacts caused by methane emissions from landfills and many other emissions from transfer stations. A short-term future scenario, where some of the landfills (which soon will reach their capacity because of rising amount of waste in Beijing City) are substituted by incinerators with energy recovery, would not result in significant environmental improvement. This is primarily because of the low calorific value of mixed waste, and it is likely that the incinerators would require significant amounts of auxiliary fuels to support combustion of wet waste. As for the long-term future scenario, efficient source separation of food waste could result in significant environmental improvements, primarily because of increase in calorific value of remaining waste incinerated with energy recovery. Sensitivity analysis emphasized the importance of efficient source separation of food waste, as well as the electricity recovery in incinerators, in order to obtain an environmentally friendly waste management system in Beijing City.

  4. Governmental Decree No. 224/1997 of 13 August 1997 on fees levied on nuclear waste producers and on the transfer of such fees to the Nuclear Account

    International Nuclear Information System (INIS)

    1997-01-01

    Nuclear power plants are obliged to pay a fee of CZK 50 per MWe produced. This amount is transferred to the Nuclear Account. The fee return is filed with the Czech Radioactive Repositories Administration. Minor radioactive waste producers only pay the radioactive waste storage cost; this sum is also transferred to the Nuclear Account. Each entity applying with the State Office for Nuclear Safety for a licence regarding activities which are associated with the production of radioactive wastes shall register with the Radioactive Repositories Administration as a prospective radioactive waste producer. (P.A.)

  5. Geochemistry of coals, coal ashes and combustion wastes from coal-fired power stations

    International Nuclear Information System (INIS)

    Vassilev, S.V.; Vassileva, C.G.

    1997-01-01

    Contents, concentration trends, and modes of occurrence of 67 elements in coals, coal ashes, and combustion wastes at eleven Bulgarian thermoelectric power stations (TPS) were studied. A number of trace elements in coal and coal ash have concentrations greater than their respective worldwide average contents (Clarke values). Trace elements are concentrated mainly in the heavy accessory minerals and organic matter in coal. In decreasing order of significance, the trace elements in coal may occur as: element-organic compounds; impurities in the mineral matter; major components in the mineral matter; major and impurity components in the inorganic amorphous matter; and elements in the fluid constituent. A number of trace elements in the waste products, similar to coal ashes, exceed known Clarke contents. Trace elements are mainly enriched in non-magnetic, heavy and fine-grained fractions of fly ash. They are commonly present as impurities in the glass phases, and are included in the crystalline components. Their accessory crystalline phases, element-organic compounds, liquid and gas forms, are of subordinate importance. Some elements from the chalcophile, lithophile and siderophile groups may release into the atmosphere during coal burning. For others, the combustion process appears to be a powerful factor causing their relative enrichment in the fly ash and rarely in the bottom ash and slag. 65 refs., 1 fig., 11 tabs

  6. Shippingport Station decommissioning project overview

    International Nuclear Information System (INIS)

    Schreiber, J.J.

    1985-01-01

    The U.S. Department of Energy is in the process of decommissioning the Shippingport Atomic Power Station located on the Ohio River, 30 miles northwest of Pittsburgh, Pennsylvania. The Shippingport Station is the first commercial size nuclear power plant to undergo decommissioning in the United Staes. The plant is located on approximately 7 acres of land owned by the Duquesne Light Company (DLC) and leased to the U.S. Government. DLC operates two nuclear power plants, Beaver Valley 1 and 2, located immediately adjacent to the site and the Bruce Mansfield coal-fired power plant is also within the immediate area. The Station was shutdown in October, 1982. Defueling operations began in 1983 and were completed by September, 1984. The Shippingport Station consists of a 275' x 60' fuel handling building containing the reactor containment chamber, the service building, the turbine building, the radioactive waste processing building, the administration building and other smaller support buildings. The Station has four coolant loops and most of the containment structures are located below grade. Structures owned by the U.S. Government including the fuel handling building, service building, contaminated equipment room, the boiler chambers, the radioactive waste processing building and the decontamination and laydown buildings will be dismantled and removed to 3 feet below grade. The area will then be filled with clean soil and graded. The turbine building, testing and training building and the administration building are owned by DLC and will remain

  7. Defense-in-depth evaluation for the New Waste Transfer Facility

    International Nuclear Information System (INIS)

    Hayes, T.G.; Kelly, J.L.

    1995-01-01

    This report fulfills part of the requirements of References 2 and 3 by documenting a Defense-In-Depth evaluation for the New Waste Transfer Facility (NWTF). This evaluation was performed using methodology similar to that used in an evaluation for the Defense Waste Processing Facility (DWPF). It differs because the DWPF evaluation was based on an existing Process Hazards Analysis (PHA) while NWTF's is based on a Preoperational Process Hazards Review (PHR) (Ref. 1). The accidents in the Process Hazards Review (PHR) were reviewed to determine those that might have significant consequences. Significance was based on the findings of the PHR, The facility design was reviewed to determine the Structures, Systems, and Components (SSCs) and administrative controls available before and after each accident. From this was developed a list of the Lines of Defense (LODs) available to contain the hazard associated with the accident. A summary of these LODs is given in Appendix C. Items are tabulated that are suggested for consideration in the functional classification as worker protection items. The specific criteria used in the evaluation is given in the methodology section of this report. The results are documented in Appendices A, B, C, and D

  8. Hazard evaluation for transfer of waste from tank 241-SY-101 to tank 241-SY-102

    International Nuclear Information System (INIS)

    SHULTZ, M.V.

    1999-01-01

    Tank 241-SY-101 (SY-101) waste level growth is an emergent, high priority issue. The purpose of this document is to record the hazards evaluation process and document potential hazardous conditions that could lead to the release of radiological and toxicological material from the proposed transfer of a limited quantity (approximately 100,000 gallons) of waste from SY-101 to 241-SY-102 (SY-102). The results of the hazards evaluation will be compared to the current Tank Waste Remediation System (TWRS) Basis for Interim Operation (HNF-SD-WM-BIO-001, 1998, Revision 1) to identify any hazardous conditions where Authorization Basis (AB) controls may not be sufficient or may not exist. Comparison to LA-UR-92-3196, A Safety Assessment for Proposed Pump Mixing Operations to Mitigate Episodic Gas Releases in Tank 241-SY-101, was also made in the case of transfer pump removal activities. This document is not intended to authorize the activity or determine the adequacy of controls; it is only intended to provide information about the hazardous conditions associated with this activity. The Unreviewed Safety Question (USQ) process will be used to determine the adequacy of controls and whether the proposed activity is within the AB. This hazard evaluation does not constitute an accident analysis

  9. Electrostatic pickup station

    CERN Multimedia

    CERN PhotoLab

    1982-01-01

    Electrostatic pickup station, with 4 interleaved electrodes, to measure beam position in the horizontal and vertical plane. This type is used in the transfer lines leaving the PS (TT2, TT70, TTL2). See also 7904075.

  10. Heat transfer in vitrified radioactive waste

    International Nuclear Information System (INIS)

    Palancar, M.C.; Luis, M.A.; Luis, P.; Aragon, J.M.; Montero, M.A.

    1987-01-01

    An experimental method for measuring the thermal conductivity and convection coefficient of borosilicate glass cylinders, containing a simulated high level radioactive waste, is described. A simulation of the thermal behaviour of matrices of solidified waste during the cooling in air, water and a geological repository has been done. The experimental values of the thermal conductivity are ranging from 0.267 to 0.591 w/m K, for matrices with simulated waste contents of 10 to 40% (the waste is simulated by no radioactive isotopes). The convection coefficient for air/cylinders under the operating conditions used is 116 w/m 2 K. The simulated operation of cooling in air shows that about 1-2 days are enough to cool a solidified waste cylinder 0.6m diameter from 900 to 400 0 C. The cooling under water from 400 to near 80 0 C is faster than in air, but sharp temperature gradients within the matrices could be expected. The simulation of geological repositories lead to some criteria of arranging the matrices for avoiding undesirable high temperature points. (author) 1 fig

  11. Wastes

    International Nuclear Information System (INIS)

    Bovard, Pierre

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

  12. Technology, safety and costs of decommissioning nuclear reactors at multiple-reactor stations

    International Nuclear Information System (INIS)

    Wittenbrock, N.G.

    1982-01-01

    Safety and cost information is developed for the conceptual decommissioning of large (1175-MWe) pressurized water reactors (PWR) and large (1155-MWe) boiling water reactors (BWR) at multiple-reactor stations. Three decommissioning alternatives are studied: DECON (immediate decontamination), SAFSTOR (safe storage followed by deferred decontamination), and ENTOMB (entombment). Safety and costs of decommissioning are estimated by determining the impact of probable features of multiple-reactor-station operation that are considered to be unavailable at a single-reactor station, and applying these estimated impacts to the decommissioning costs and radiation doses estimated in previous PWR and BWR decommissioning studies. The multiple-reactor-station features analyzed are: the use of interim onsite nuclear waste storage with later removal to an offsite waste disposal facility, the use of permanent onsite nuclear waste disposal, the dedication of the site to nuclear power generation, and the provision of centralized services

  13. Mobile incineration services at Commonwealth Edison's nuclear stations

    International Nuclear Information System (INIS)

    Smith, K.R.

    1985-01-01

    As the costs for low-level waste disposal escalate, and as the January 1, 1986 date draws nearer, utilities throughout the United States are formulating and implementing plans to reduce the volumes of the low-level radioactive waste being generated at their nuclear power stations. Techniques being used to accomplish this goal range from sorting of dry active waste to complete volume reduction systems, like the Aerojet VR Systems being installed at Commonwealth Edison's Byron and Braidwood Stations. In between these extremes are partial solutions to the problem, including compaction, shredding and compaction, super-compaction, resin dewatering, liquid drying, and now, mobile incineration. In June, 1983, Commonwealth Edison Company (CECO) of Chicago, Illinois, contracted Aerojet Energy Conversion Company (AECC) of Sacramento, California, to supply mobile VR services to the Dresden, La Salle, Quad Cities, and Zion Nuclear Stations. Per the contract, AECC is responsible for the design, fabrication, delivery, operation, and maintenance of a Mobile Volume Reduction System (MVRS) capable of processing combustible dry active waste and contaminated oil generated at these Com-Ed facilities. Initial commercial operation of the MVRS is planned for the Dresden Nuclear Power Station in May, 1985. This paper is intended to summarize some of the key elements resulting from the design, fabrication, and testing of the MVRS. In addition, it is intended to identify the tasks a potential user of the MVRS service must complete in order to receive permission from the Nuclear Regulatory Commission to operate the MVRS at their site

  14. (Shippingport Atomic Power Station). Quarterly operating report, third quarter 1980

    Energy Technology Data Exchange (ETDEWEB)

    Zagorski, J. F.

    1980-01-01

    At the beginning of the third quarter of 1980, the Shippingport Atomic Power Station was operating with the 1A, 1B, 1C, and 1D reactor coolant loops and the 1AC and 1BD purification loops in service. During the quarter, the Station was operated for Duquesne Light Company System grid including base load and swing load operation. Twelve (12) planned swing load operations were performed on the LWBR Core this quarter to complete the LWBR operating plan of fifty (50) during this operating phase. The Station was shutdown on September 12 for the Fall 1980 Shutdown and remained in this mode through the end of the quarter. The LWBR Core has generated 18,297.98 EFPH from start-up through the end of the quarter. There were no radioactive liquid discharges from the Radioactive Waste Processing System to the river this quarter. The radioactive liquid waste effluent line to the river remained blanked off to prevent inadvertent radioactive liquid waste discharges. During the quarter, approximately 0.001 curies of Xe 133 activity were released from the station. The radioactivity released from Shippingport Station is far too small to have any measurable effect on the general background environmental radioactivity outside the plant.

  15. W-320 waste retrieval sluicing system transfer line flushing volume and frequency calculation

    International Nuclear Information System (INIS)

    Bailey, J.W.

    1997-01-01

    The calculations contained in this analysis document establish the technical basis for the volume, frequency, and flushing fluid to be utilized for routine Waste Retrieval Sluicing System (WRSS) process line flushes. The WRSS was installed by Project W-320, Tank 241-C-106 Sluicing. The double contained pipelines being flushed have 4 inch stainless steel primary pipes. The flushes are intended to prevent hydrogen buildup in the transfer lines and to provide ALARA conditions for maintenance personnel

  16. Torness: proposed nuclear power station

    International Nuclear Information System (INIS)

    Anon.

    1979-01-01

    The need for and desirability of nuclear power, and in particular the proposed nuclear power station at Torness in Scotland, are questioned. Questions are asked, and answered, on the following topics: position, appearance and cost of the proposed Torness plant, and whether necessary; present availability of electricity, and forecast of future needs, in Scotland; energy conservation and alternative energy sources; radiation hazards from nuclear power stations (outside, inside, and in case of an accident); transport of spent fuel from Torness to Windscale; radioactive waste management; possibility of terrorists making a bomb with radioactive fuel from a nuclear power station; cost of electricity from nuclear power; how to stop Torness. (U.K.)

  17. Defining waste acceptance criteria for the Hanford Replacement Cross-Site Transfer System

    International Nuclear Information System (INIS)

    Hudson, J.D.

    1996-04-01

    This document provides a methodology for defining waste acceptance criteria for the Hanford Replacement Cross-Site Transfer System (RCSTS). This methodology includes characterization, transport analysis, and control. A framework is described for each of these functions. A tool was developed for performing the calculations associated with the transport analysis. This tool, a worksheet that is available in formats acceptable for a variety of PC spreadsheet programs, enables a comparison of the pressure required to transport a given slurry at a rate that particulate suspension is maintained to the pressure drop available from the RCSTS

  18. The nuclear techniques in function of improving the efficiency of the flocculators and floats in the industrial waste treatment station of PETROBRAS

    International Nuclear Information System (INIS)

    Damera Martinez, Arnaldo; Ramos Espinosa, Kenia A.; Pinto, Amenonia Ferreira; Barbalho, Andrea de Magalhaes; Derivet Zarzabal, Milagros

    2001-01-01

    This work was carried out in the Station of Treatment of Industrial Waste (STIW) in PETROBRAS (Brazil). The STIW has the function of receiving, to treat and storage liquid wastes coming from diverse points of the refinery, avoiding the environment contamination. This study consists on the determination of the time of residence inside the flocculators and floats, by means of nuclear technique of radioactive tracer, using Tc-99m. This technique has a great economic and environmental importance because the time of residence obtained experimentally in the flocculators and the floats, can be compared with those obtained theoretically, which allow to influence on the system, optimizing its operation

  19. Radionuclide mass transfer rates from a pinhole in a waste container for an inventory-limited and a constant concentration source

    International Nuclear Information System (INIS)

    LeNeveu, D.M.

    1996-03-01

    Analytical solutions for transient and steady state diffusive mass transfer rates from a pinhole in a waste container are developed for constant concentration and inventory-limited source conditions. Mass transport in three media are considered, inside the pinhole (medium 2), outside the container (medium 3) and inside the container (medium 1). Simple equations are developed for radionuclide mass transfer rates from a pinhole. It is shown that the medium with the largest mass transfer resistance need only be considered to provide a conservative estimate of mass transfer rates. (author) 11 refs., 3 figs

  20. Comparison of Waste Feed Delivery Small Scale Mixing Demonstration Simulant to Hanford Waste

    Energy Technology Data Exchange (ETDEWEB)

    Wells, Beric E.; Gauglitz, Phillip A.; Rector, David R.

    2012-07-10

    The Hanford double-shell tank (DST) system provides the staging location for waste that will be transferred to the Hanford Tank Waste Treatment and Immobilization Plant (WTP). Specific WTP acceptance criteria for waste feed delivery describe the physical and chemical characteristics of the waste that must be met before the waste is transferred from the DSTs to the WTP. One of the more challenging requirements relates to the sampling and characterization of the undissolved solids (UDS) in a waste feed DST because the waste contains solid particles that settle and their concentration and relative proportion can change during the transfer of the waste in individual batches. A key uncertainty in the waste feed delivery system is the potential variation in UDS transferred in individual batches in comparison to an initial sample used for evaluating the acceptance criteria. To address this uncertainty, a number of small-scale mixing tests have been conducted as part of Washington River Protection Solutions' Small Scale Mixing Demonstration (SSMD) project to determine the performance of the DST mixing and sampling systems. A series of these tests have used a five-part simulant composed of particles of different size and density and designed to be equal or more challenging than AY-102 waste. This five-part simulant, however, has not been compared with the broad range of Hanford waste, and thus there is an additional uncertainty that this simulant may not be as challenging as the most difficult Hanford waste. The purpose of this study is to quantify how the current five-part simulant compares to all of the Hanford sludge waste, and to suggest alternate simulants that could be tested to reduce the uncertainty in applying the current testing results to potentially more challenging wastes.

  1. Municipal solid waste management in Beijing City

    International Nuclear Information System (INIS)

    Li Zhenshan; Yang Lei; Qu XiaoYan; Sui Yumei

    2009-01-01

    This paper presents an overview of municipal solid waste (MSW) management in Beijing City. Beijing, the capital of China, has a land area of approximately 1368.32 km 2 with an urban population of about 13.33 million in 2006. Over the past three decades, MSW generation in Beijing City has increased tremendously from 1.04 million tons in 1978 to 4.134 million tons in 2006. The average generation rate of MSW in 2006 was 0.85 kg/capita/day. Food waste comprised 63.39%, followed by paper (11.07%), plastics (12.7%) and dust (5.78%). While all other wastes including tiles, textiles, glass, metals and wood accounted for less than 3%. Currently, 90% of MSW generated in Beijing is landfilled, 8% is incinerated and 2% is composted. Source separation collection, as a waste reduction method, has been carried out in a total of 2255 demonstration residential and commercial areas (covering about 4.7 million people) up to the end of 2007. Demonstration districts should be promoted over a wider range instead of demonstration communities. The capacity of transfer stations and treatment plants is an urgent problem as these sites are seriously overloaded. These problems should first be solved by constructing more sites and converting to new treatment technologies. Improvements in legislation, public education and the management of waste pickers are problematic issues which need to be addressed.

  2. Waste retrieval sluicing system campaign number 1 solids volume transferred calculation

    International Nuclear Information System (INIS)

    BAILEY, J.W.

    1999-01-01

    This calculation has been prepared to document the volume of sludge removed from tank 241-C-106 during Waste Retrieval Sluicing System (WRSS) Sluicing Campaign No.1. This calculation will be updated, if necessary, to incorporate new data. This calculation supports the declaration of completion of WRSS Campaign No.1 and, as such, is also the documentation for completion of Performance Agreement TWR 1.2.1 , C-106 Sluicing Performance Expectations. It documents the performance of all the appropriate tank 241-C-106 mass transfer verifications, evaluations, and appropriate adjustments discussed in HNF-SD-WM-PROC-021, Chapter 23, ''Process Engineering Calculations for Tank 241-C-106 Sluicing and Retrieval''

  3. Waste retrieval sluicing system campaign number 1 solids volume transferred calculation

    International Nuclear Information System (INIS)

    BAILEY, J.W.

    1999-01-01

    This calculation has been prepared to document the volume of sludge removed from tank 241-C-106 during Waste Retrieval Sluicing System (WRSS) Sluicing Campaign No.1. This calculation will be updated, if necessary, to incorporate new data. This calculation supports the declaration of completion of WRSS Campaign No.1 and, as such, is also the documentation for completion of Performance Agreement TWR 1.2.1 C-106 Sluicing Performance Expectations. It documents the performance of all the appropriate tank 241-C-106 mass transfer verifications, evaluations, and appropriate adjustments discussed in HNF-SD-WM-PROC-021, Chapter 23, ''Process Engineering Calculations for Tank 241-C-106 Sluicing and Retrieval''

  4. Mission analysis for cross-site transfer

    International Nuclear Information System (INIS)

    Riesenweber, S.D.; Fritz, R.L.; Shipley, L.E.

    1995-11-01

    The Mission Analysis Report describes the requirements and constraints associated with the Transfer Waste Function as necessary to support the Manage Tank Waste, Retrieve Waste, and Process Tank Waste Functions described in WHC-SD-WM-FRD-020, Tank Waste Remediation System (TWRS) Functions and Requirements Document and DOE/RL-92-60, Revision 1, TWRS Functions and Requirements Document, March 1994. It further assesses the ability of the ''initial state'' (or current cross-site transfer system) to meet the requirements and constraints

  5. Electrostatic pickup station

    CERN Multimedia

    CERN PhotoLab

    1979-01-01

    Electrostatic pickup station, with 4 electrodes, to measure beam position in the horizontal and vertical plane. This type is used in the transfer lines leaving the PS (TT2, TTL2, TT70). See also 8206063, where the electrode shapes are clearly visible.

  6. The International Stripa Project: Technology transfer from cooperation in scientific and technological research on nuclear waste disposal

    International Nuclear Information System (INIS)

    Levich, R.A.; Ferrigan, P.M.; Wilkey, P.L.

    1990-01-01

    The Nuclear Energy Agency of the organization for Economic Cooperation and Development (OECD/NEA) sponsors the International Stripa Project. The objectives of the Stripa Project are to develop techniques for characterizing sites located deep in rock formations that are potentially suitable for the geologic disposal of high-level radioactive wastes and to evaluate particular engineering design considerations that could enhance the long-term safety of a high-level radioactive waste repository in a geologic medium. The purpose of this paper is to briefly summarize the research conducted at Stripa and discuss the ways in which the technology developed for the Stripa Project has been and will be transfered to the United States Civilian Radioactive Waste Management Program's Yucca Mountain Project. 3 refs., 2 figs

  7. Shielded cells transfer automation

    International Nuclear Information System (INIS)

    Fisher, J.J.

    1984-01-01

    Nuclear waste from shielded cells is removed, packaged, and transferred manually in many nuclear facilities. Radiation exposure is absorbed by operators during these operations and limited only through procedural controls. Technological advances in automation using robotics have allowed a production waste removal operation to be automated to reduce radiation exposure. The robotic system bags waste containers out of glove box and transfers them to a shielded container. Operators control the system outside the system work area via television cameras. 9 figures

  8. Radioactive waste from nuclear power stations and other nuclear facilities

    International Nuclear Information System (INIS)

    Jelinek-Fink, P.

    1976-01-01

    After estimating the amounts of liquid and solid radioactive wastes that will be produced in nuclear power plants, reprocessing plants, by the fuel cycle industry, and in the nuclear research centers in the FRG until 1990, it is reported on the state of technology and on the tendencies in the development of processing radioactive waste. The paper also describes, how waste disposal is managed by those producing radioactive waste (see above), and discusses the future development of the complex of waste disposal from the industry's point of view. (HR/LN) [de

  9. Elaboration d'une structure de collecte des matieres residuelles selon la Theorie Constructale

    Science.gov (United States)

    Al-Maalouf, George

    Currently, more than 80% of the waste management costs are attributed to the waste collection phase. In order to reduce these costs, one current solution resides in the implementation of waste transfer stations. In these stations, at least 3 collection vehicles transfer their load into a larger hauling truck. This cost reduction is based on the principle of economy of scale applied to the transportation sector. This solution improves the efficiency of the system; nevertheless, it does not optimize it. Recent studies show that the compactor trucks used in the collection phase generate significant economic losses mainly due to the frequent stops and the transportation to transfer stations often far from the collection area. This study suggests the restructuring of the waste collection process by dividing it into two phases: the collection phase, and the transportation to the transfer station phase. To achieve this, a deterministic theory called: "the Constructal Theory" (CT) is used. The results show that starting a certain density threshold, the application of the CT minimizes energy losses in the system. In fact, the collection is optimal if it is done using a combination of low capacity vehicle to collect door to door and transfer their charge into high-capacity trucks. These trucks will then transport their load to the transfer station. To minimize the costs of labor, this study proposes the use of Cybernetic Transport System (CTS) as an automated collection vehicle to collect small amounts of waste. Finally, the optimization method proposed is part of a decentralized approach to the collection and treatment of waste. This allows the implementation of multi-process waste treatment facilities on a territory scale. Keywords: Waste collection, Constructal Theory, Cybernetic Transportation Systems.

  10. Emerging catalytic technologies related to the denoxing of waste gases from thermal power stations

    International Nuclear Information System (INIS)

    Busca, G.

    2002-01-01

    The emerging catalytic technologies related to the DeNOxing of waste gases from thermal power stations are briefly discussed. In the case of the Selective Catalytic Reduction of NO x with hydrocarbons new zeolite-based or metal oxide catalytic systems are under development, whose stability and performances approach more and more those needed for a commercial process. The processes for the low temperature Selective Catalytic Reduction of NO x with ammonia are apparently promising allowing a possible application in a tail-end process configuration, at least after a total abatement of SO x . The processes of combined abatement of NO x and dioxins are already applied industrially. Also the Selective Oxidation of ammonia slip to nitrogen is already proposed as commercial process. In both last cases, however, few information is available in the open literature [it

  11. Resolving legal issues in the transfer of technologies in environmental restoration and waste management

    International Nuclear Information System (INIS)

    Katz, J.; Richards, F. III; Underwood, J.P.

    1994-01-01

    In reforming its contracting and procurement processes, the Department of Energy (DOE) should also make reforms to facilitate the transfer and commercialization of environmental restoration and waste management technologies between DOE laboratories and the private sector. These reforms would address the three related legal issues of patents, conflict of interest, and liability. This paper discusses each issue and considers possible solutions to them. These solutions include contractual clauses to specifically address the needs of all involved parties, improved definition of development and implementation rights, and increased protections for contractors. If DOE, or the Federal Government more generally, successfully resolves these issues and makes the appropriate changes to the DOE procurement system, transfer and commercialization will more efficiently, effectively, and easily occur

  12. 结合重心法和层次分析法研究垃圾转运站选址%Location Selection of Waste Transfer Station Based on Combining Gravity Method and AHP Model

    Institute of Scientific and Technical Information of China (English)

    曹勇锋; 荣宏伟; 张可方; 张朝升

    2012-01-01

    Gravity method was combined with AHP model to study the location selection of rural waste transfer station. Based on analysis of rural household yield and distribution, gravity method was used for initial selection of primary locations, then using AHP model to screen out standby locations to obtain the optimal location. Compared with traditional methods of location selection, the method not only takes costs into account, but also the impact location of environmental benefits, basic conditions as well as laws and regulations. The result is closer to reality. The method is used and verified in a southern rural area, with satisfactory location selection plan.%将重心法和层次分析法结合起来研究农村生活垃圾转运站选址问题,首先分析农村生活垃圾产生量及分布,采用重心法对转运站进行初始选址,得出备选地址,然后运用层次分析法对备选地址进行筛选,得到最佳选址方案.与传统选址方法相比,该方法不仅考虑了费用,还综合考虑了影响选址的环境效益、基础条件、法律法规等因素,因此得到的结果更贴近实际.将该方法应用于南方某农村,得到了满意的选址方案.

  13. Replacement of the cross-site transfer system liquid waste transport alternatives evaluation, Project W-058

    International Nuclear Information System (INIS)

    Vo, D.V.; Epperson, E.M.

    1995-05-01

    This document examines high-/low-level radioactive liquid waste transport alternatives. Radioactive liquid waste will be transported from the 200 West Area to the 200 East Area and within the 200 East Areas for safe storage and disposal. The radioactive waste transport alternatives are the Aboveground Transport System (French LR-56 Cask System [3,800 L (1,000 gal)]), 19,000-L (5,000-gal) trailer tanker system, 75,700-L (20,000-gal) rail tanker system and Underground Transport System (buried pipe [unlimited transfer volume capability]). The evaluation focused on the following areas: initial project cost, operational cost, secondary waste generation, radiation exposure, and final decommissioning. The evaluation was based on the near term (1995 to 2005) estimated volume of 49.509 million L (13.063 million gal) and long term (1995 to 2028) estimated volume of 757.1 million L (200 million gal). The conclusion showed that the buried pipe (Underground Transport System) resulted in the lowest overall total cost for near and long term, the trailer container resulted in the highest total cost for near and long term, and the French truck was operationally impractical and cost prohibitive

  14. Joint Coordinating Committee on environmental restoration and waste management (JCCEM) support, technology transfer, and special projects

    International Nuclear Information System (INIS)

    Edgar, D.E.

    1993-01-01

    Argonne National Laboratory (ANL) assisted in identifying and evaluating foreign technologies to meet EM needs; supported the evaluation, removal, and/or revision of barriers to international technology and information transfer/exchange; facilitated the integration and coordination of U.S. government international environmental restoration and waste management activities; and enhanced U.S. industry's competitiveness in the international environmental technology market

  15. Characteristics of soil-to-plant transfer of elements relevant to radioactive waste in boreal forest

    Energy Technology Data Exchange (ETDEWEB)

    Roivainen, P.

    2011-07-01

    The use of nuclear energy generates large amounts of different types of radioactive wastes that can be accidentally released into the environment. Soil-to-plant transfer is a key process for the dispersion of radionuclides in the biosphere and is usually described by a concentration ratio (CR) between plant and soil concentrations in radioecological models. Our knowledge of the soil-to-plant transfer of many radionuclides is currently limited and concerns mainly agricultural species and temperate environments. The validity of radioecological modelling is affected by the accuracy of the assumptions and parameters used to describe soil-to-plant transfer. This study investigated the soil-to-plant transfer of six elements (cobalt (Co), molybdenum (Mo), nickel (Ni), lead (Pb), uranium (U) and zinc (Zn)) relevant to radioactive waste at two boreal forest sites and assessed the factors affecting the CR values. May lily (Maianthemum bifolium), narrow buckler fern (Dryopteris carthusiana) and blueberry (Vaccinium myrtillus) were selected as representatives of understory species, while rowan (Sorbus aucuparia) and Norway spruce (Picea abies) represented trees in this study. All the elements studied were found to accumulate in plant roots, indicating that separate CR values for root and aboveground plant parts are needed. The between-species variation in CR values was not clearly higher than the within-species variation, suggesting that the use of generic CR values for understory species and trees is justified. No linear relationship was found between soil and plant concentrations for the elements studied and a non-linear equation was found to be the best for describing the dependence of CR values on soil concentration. Thus, the commonly used assumption of a linear relationship between plant and soil concentrations may lead to underestimation of plant root uptake at low soil concentrations. Plant nutrients potassium, magnesium, manganese, phosphorus and sulphur were found to

  16. Characteristics of soil-to-plant transfer of elements relevant to radioactive waste in boreal forest

    International Nuclear Information System (INIS)

    Roivainen, P.

    2011-01-01

    The use of nuclear energy generates large amounts of different types of radioactive wastes that can be accidentally released into the environment. Soil-to-plant transfer is a key process for the dispersion of radionuclides in the biosphere and is usually described by a concentration ratio (CR) between plant and soil concentrations in radioecological models. Our knowledge of the soil-to-plant transfer of many radionuclides is currently limited and concerns mainly agricultural species and temperate environments. The validity of radioecological modelling is affected by the accuracy of the assumptions and parameters used to describe soil-to-plant transfer. This study investigated the soil-to-plant transfer of six elements (cobalt (Co), molybdenum (Mo), nickel (Ni), lead (Pb), uranium (U) and zinc (Zn)) relevant to radioactive waste at two boreal forest sites and assessed the factors affecting the CR values. May lily (Maianthemum bifolium), narrow buckler fern (Dryopteris carthusiana) and blueberry (Vaccinium myrtillus) were selected as representatives of understory species, while rowan (Sorbus aucuparia) and Norway spruce (Picea abies) represented trees in this study. All the elements studied were found to accumulate in plant roots, indicating that separate CR values for root and aboveground plant parts are needed. The between-species variation in CR values was not clearly higher than the within-species variation, suggesting that the use of generic CR values for understory species and trees is justified. No linear relationship was found between soil and plant concentrations for the elements studied and a non-linear equation was found to be the best for describing the dependence of CR values on soil concentration. Thus, the commonly used assumption of a linear relationship between plant and soil concentrations may lead to underestimation of plant root uptake at low soil concentrations. Plant nutrients potassium, magnesium, manganese, phosphorus and sulphur were found to

  17. W-026, transuranic waste restricted waste management (TRU RWM) glovebox operational test report

    Energy Technology Data Exchange (ETDEWEB)

    Leist, K.J.

    1998-02-18

    The TRU Waste/Restricted Waste Management (LLW/PWNP) Glovebox 401 is designed to accept and process waste from the Transuranic Process Glovebox 302. Waste is transferred to the glovebox via the Drath and Schraeder Bagless Transfer Port (DO-07401) on a transfer stand. The stand is removed with a hoist and the operator inspects the waste (with the aid of the Sampling and Treatment Director) to determine a course of action for each item. The waste is separated into compliant and non compliant. One Trip Port DO-07402A is designated as ``Compliant``and One Trip Port DO-07402B is designated as ``Non Compliant``. As the processing (inspection, bar coding, sampling and treatment) of the transferred items takes place, residue is placed in the appropriate One Trip port. The status of the waste items is tracked by the Data Management System (DMS) via the Plant Control System (PCS) barcode interface. As an item is moved for sampling or storage or it`s state altered by treatment, the Operator will track an items location using a portable barcode reader and entry any required data on the DMS console. The Operational Test Procedure (OTP) will perform evolutions (described here) using the Plant Operating Procedures (POP) in order to verify that they are sufficient and accurate for controlled glovebox operation.

  18. W-026, transuranic waste restricted waste management (TRU RWM) glovebox operational test report

    International Nuclear Information System (INIS)

    Leist, K.J.

    1998-01-01

    The TRU Waste/Restricted Waste Management (LLW/PWNP) Glovebox 401 is designed to accept and process waste from the Transuranic Process Glovebox 302. Waste is transferred to the glovebox via the Drath and Schraeder Bagless Transfer Port (DO-07401) on a transfer stand. The stand is removed with a hoist and the operator inspects the waste (with the aid of the Sampling and Treatment Director) to determine a course of action for each item. The waste is separated into compliant and non compliant. One Trip Port DO-07402A is designated as ''Compliant''and One Trip Port DO-07402B is designated as ''Non Compliant''. As the processing (inspection, bar coding, sampling and treatment) of the transferred items takes place, residue is placed in the appropriate One Trip port. The status of the waste items is tracked by the Data Management System (DMS) via the Plant Control System (PCS) barcode interface. As an item is moved for sampling or storage or it's state altered by treatment, the Operator will track an items location using a portable barcode reader and entry any required data on the DMS console. The Operational Test Procedure (OTP) will perform evolutions (described here) using the Plant Operating Procedures (POP) in order to verify that they are sufficient and accurate for controlled glovebox operation

  19. Liquid radwaste process optimization at Catawba Nuclear Station

    International Nuclear Information System (INIS)

    Cauthen, B.E.; Taylor, J.C.

    1990-01-01

    Since commercial operation in 1985, Catawba Nuclear Station has experienced significant filtration problems with the radioactive liquid waste system. The performance of the filtration and ion exchange equipment has been significantly worse than other Duke Power stations. Full scale tests have been performed to investigate the causes and potential solutions to the waste processing difficulties. The initial waste stream characterization study revealed a large percentage of sub-micron particles. This information immediately suggested that the existing filtration equipment was not adequately sized to effectively process the waste stream. New technologies which would effectively enhance the performance of the processing system and reduce both operating and maintenance costs were researched. This included bag filters, depth filtration, custom designed ion exchange vessels and radionuclide specific ion exchange media. The subsequent full scale testing resulted in a processing scheme which resulted in extended filter life, over 100 percent increase in ion exchange bed life, 90 percent reduction in filter media costs and improved radionuclide removal. 4 refs., 4 figs., 1 tab

  20. Characterization of solid radwaste generated at Virginia Power's Surry and North Anna stations

    International Nuclear Information System (INIS)

    Lippard, D.W.; Elguindy, H.; Nelson, R.A.

    1987-01-01

    This paper describes the results of a study on characterization of the major constituents of the solid radwaste generated at Virginia Power's North Anna and Surry Power Stations. The characterization consisted of identifying the individual constituents of the dry active waste (DAW) and estimating the fraction of the total DAW (both weight and volume) made up by each constituent. The analysis of the characterization of solid waste streams generated at both North Anna and Surry stations has lead to recommending techniques for both source minimization and waste volume reduction

  1. Tank Farm Waste Transfer Compatibility Program

    International Nuclear Information System (INIS)

    FOWLER, K.D.

    2001-01-01

    The compatibility program described in this document formalizes the process for determining waste compatibility. The primary goal of the program is to ensure that sufficient controls are in place to prevent the formation of incompatible mixtures during future operations. The process described involves characterizing waste, comparing characteristics with criteria, resolving potential incompatibilities and documenting the process

  2. Tank Farm Waste Transfer Compatibility Program

    International Nuclear Information System (INIS)

    FOWLER, K.D.

    2000-01-01

    The compatibility program described in this document formalizes the process for determining waste compatibility. The primary goal of the program is to ensure that sufficient controls are in place to prevent the formation of incompatible mixtures during future operations. The process described involves characterizing waste, comparing characteristics with criteria, resolving potential incompatibilities and documenting the process

  3. Experimental study on heat transfer performance of fin-tube exchanger and PSHE for waste heat recovery

    Science.gov (United States)

    Chen, Ting; Bae, Kyung Jin; Kwon, Oh Kyung

    2018-02-01

    In this paper, heat transfer characteristics of fin-tube heat exchanger and primary surface heat exchanger (PSHE) used in waste heat recovery were investigated experimentally. The flow in the fin-tube heat exchanger is cross flow and in PSHE counter flow. The variations of friction factor and Colburn j factor with air mass flow rate, and Nu number with Re number are presented. Various comparison methods are used to evaluate heat transfer performance, and the results show that the heat transfer rate of the PSHE is on average 17.3% larger than that of fin-tube heat exchanger when air mass flow rate is ranging from 1.24 to 3.45 kg/min. However, the PSHE causes higher pressure drop, and the fin-tube heat exchanger has a wider application range which leads to a 31.7% higher value of maximum heat transfer rate compared to that of the PSHE. Besides, under the same fan power per unit frontal surface, a higher heat transfer rate value is given in the fin-tube heat exchanger.

  4. Space station propulsion requirements study

    Science.gov (United States)

    Wilkinson, C. L.; Brennan, S. M.

    1985-01-01

    Propulsion system requirements to support Low Earth Orbit (LEO) manned space station development and evolution over a wide range of potential capabilities and for a variety of STS servicing and space station operating strategies are described. The term space station and the overall space station configuration refers, for the purpose of this report, to a group of potential LEO spacecraft that support the overall space station mission. The group consisted of the central space station at 28.5 deg or 90 deg inclinations, unmanned free-flying spacecraft that are both tethered and untethered, a short-range servicing vehicle, and a longer range servicing vehicle capable of GEO payload transfer. The time phasing for preferred propulsion technology approaches is also investigated, as well as the high-leverage, state-of-the-art advancements needed, and the qualitative and quantitative benefits of these advancements on STS/space station operations. The time frame of propulsion technologies applicable to this study is the early 1990's to approximately the year 2000.

  5. Optimization of waste heat utilization in cold end system of thermal power station based on neural network algorithm

    Science.gov (United States)

    Du, Zenghui

    2018-04-01

    At present, the flue gas waste heat utilization projects of coal-fired boilers are often limited by low temperature corrosion problems and conventional PID control. The flue gas temperature cannot be reduced to the best efficiency temperature of wet desulphurization, resulting in the failure of heat recovery to be the maximum. Therefore, this paper analyzes, researches and solves the remaining problems of the cold end system of thermal power station, so as to provide solutions and theoretical support for energy saving and emission reduction and upgrading and the improvement of the comprehensive efficiency of the units.

  6. Bioremediation for coal-fired power stations using macroalgae.

    Science.gov (United States)

    Roberts, David A; Paul, Nicholas A; Bird, Michael I; de Nys, Rocky

    2015-04-15

    Macroalgae are a productive resource that can be cultured in metal-contaminated waste water for bioremediation but there have been no demonstrations of this biotechnology integrated with industry. Coal-fired power production is a water-limited industry that requires novel approaches to waste water treatment and recycling. In this study, a freshwater macroalga (genus Oedogonium) was cultivated in contaminated ash water amended with flue gas (containing 20% CO₂) at an Australian coal-fired power station. The continuous process of macroalgal growth and intracellular metal sequestration reduced the concentrations of all metals in the treated ash water. Predictive modelling shows that the power station could feasibly achieve zero discharge of most regulated metals (Al, As, Cd, Cr, Cu, Ni, and Zn) in waste water by using the ash water dam for bioremediation with algal cultivation ponds rather than storage of ash water. Slow pyrolysis of the cultivated algae immobilised the accumulated metals in a recalcitrant C-rich biochar. While the algal biochar had higher total metal concentrations than the algae feedstock, the biochar had very low concentrations of leachable metals and therefore has potential for use as an ameliorant for low-fertility soils. This study demonstrates a bioremediation technology at a large scale for a water-limited industry that could be implemented at new or existing power stations, or during the decommissioning of older power stations. Copyright © 2015 Elsevier Ltd. All rights reserved.

  7. Disposal of solid waste in Istanbul and along the Black Sea coast of Turkey

    International Nuclear Information System (INIS)

    Berkun, Mehmet; Aras, Egemen; Nemlioglu, Semih

    2005-01-01

    The increasing amount of solid waste arising from municipalities and other sources and its consequent disposal has been one of the major environmental problems in Turkey. Istanbul is a metropolitan city with a current population of around 14 million, and produces about 9000 ton of solid waste every day. The waste composition for Istanbul has changed markedly from 1981 to 1996 with large decreases in waste density, much of which is related to decreased amounts of ash collected in winter. In recent years, the Istanbul region has implemented a new solid waste management system with transfer stations, sanitary landfills, and methane recovery, which has led to major improvements. In the Black Sea region of Turkey, most of the municipal and industrial solid wastes, mixed with hospital and hazardous wastes, are dumped on the nearest lowlands and river valleys or into the sea. The impact of riverside and seashore dumping of solid wastes adds significantly to problems arising from sewage and industry on the Black Sea coast. Appropriate integrated solid waste management systems are needed here as well; however, they have been more difficult to implement than in Istanbul because of more difficult topography, weaker administrative structures, and the lower incomes of the inhabitants

  8. ASSESSMENT OF MEDICAL WASTE MANAGEMENT IN EDUCATIONAL HOSPITALS OF TEHRAN UNIVERSITY MEDICAL SCIENCES

    Directory of Open Access Journals (Sweden)

    M. H. Dehghani, K. Azam, F. Changani, E. Dehghani Fard

    2008-04-01

    Full Text Available The management of medical waste is of great importance due to its potential environmental hazards and public health risks. In the past, medical waste was often mixed with municipal solid waste and disposed in residential waste landfills or improper treatment facilities in Iran. In recent years, many efforts have been made by environmental regulatory agencies and waste generators to better managing the wastes from healthcare facilities. This study was carried in 12 educational hospitals of Tehran University of Medical Sciences. The goals of this study were to characterize solid wastes generated in healthcare hospitals, to report the current status of medical waste management and to provide a framework for the safe management of these wastes at the considered hospitals. The methodology was descriptive, cross-sectional and consisted of the use of surveys and interviews with the authorities of the healthcare facilities and with personnel involved in the management of the wastes. The results showed that medical wastes generated in hospitals were extremely heterogeneous in composition. 42% of wastes were collected in containers and plastic bags. In 75% of hospitals, the stay-time in storage sites was about 12-24h. 92% of medical wastes of hospitals were collected by covered-trucks. In 46% of hospitals, transferring of medical wastes to temporary stations was done manually. The average of waste generation rates in the hospitals was estimated to be 4.42kg/bed/day.

  9. Consolidation of existing solid waste management plans in the Greater Toronto Area

    Energy Technology Data Exchange (ETDEWEB)

    1989-08-01

    The municipalities of the Greater Toronto Area (GTA) will be implementing initiatives in solid waste management, in view of the fact that current landfill capacity is nearly exhausted. A consolidation of information is provided on the solid waste management plans, programs, and facilities within the GTA. In response to environmental concerns coupled with difficulties encountered in developing new solid waste disposal facilities, waste reduction, reuse, and recycling efforts are developing rapidly. Some of the measures currently implemented and under investigation include: curbside recycling programs for newspapers, glass, metal, and plastic containers; expanding recycling efforts to apartment buildings; expanding the kinds of materials collected through the curbside programs; improving recycling services in rural areas; public education and promotional programs; promotion of home composting; household hazardous waste programs; recovery of cardboard from commercial and industrial sources, coupled with bans on cardboard at landfills; recovery of selected waste building materials such as wood and drywall, coupled with bans on these materials at landfills; recovery of paper from office buildings; and programs to assist industries in waste reduction, reuse, and recycling. The solid wastes generated in the GTA are managed in a number of facilities including recycling centers, transfer stations, and landfill sites. A 410 tonne/day energy-from-waste facility has recently been approved for Peel Region and is planned to be constructed in the coming year. 21 refs., 1 fig., 14 tabs.

  10. Characterizing the transformation and transfer of nitrogen during the aerobic treatment of organic wastes and digestates

    Energy Technology Data Exchange (ETDEWEB)

    Zeng Yang, E-mail: yang.zeng@irstea.fr [Irstea, UR GERE, 17 avenue de Cucille, CS 64427, F-35044 Rennes Cedex (France); Universite Europeenne de Bretagne, F-35000 Rennes (France); Guardia, Amaury de; Daumoin, Mylene; Benoist, Jean-Claude [Irstea, UR GERE, 17 avenue de Cucille, CS 64427, F-35044 Rennes Cedex (France)

    2012-12-15

    Highlights: Black-Right-Pointing-Pointer Ammonia emissions varied depending on the nature of wastes and the treatment conditions. Black-Right-Pointing-Pointer Nitrogen losses resulted from ammonia emissions and nitrification-denitrification. Black-Right-Pointing-Pointer Ammonification can be estimated from biodegradable carbon and carbon/nitrogen ratio. Black-Right-Pointing-Pointer Ammonification was the main process contributing to N losses. Black-Right-Pointing-Pointer Nitrification rate was negatively correlated to stripping rate of ammonia nitrogen. - Abstract: The transformation and transfer of nitrogen during the aerobic treatment of seven wastes were studied in ventilated air-tight 10-L reactors at 35 Degree-Sign C. Studied wastes included distinct types of organic wastes and their digestates. Ammonia emissions varied depending on the kind of waste and treatment conditions. These emissions accounted for 2-43% of the initial nitrogen. Total nitrogen losses, which resulted mainly from ammonia emissions and nitrification-denitrification, accounted for 1-76% of the initial nitrogen. Ammonification was the main process responsible for nitrogen losses. An equation which allows estimating the ammonification flow of each type of waste according to its biodegradable carbon and carbon/nitrogen ratio was proposed. As a consequence of the lower contribution of storage and leachate rates, stripping and nitrification rates of ammonia nitrogen were negatively correlated. This observation suggests the possibility of promotingnitrification in order to reduce ammonia emissions.

  11. Submersible canned motor transfer pump

    International Nuclear Information System (INIS)

    Guardiani, R.F.; Pollick, R.D.; Nyilas, C.P.; Denmeade, T.J.

    1997-01-01

    A transfer pump is described which is used in a waste tank for transferring high-level radioactive liquid waste from a waste tank and having a column assembly, a canned electric motor means, and an impeller assembly with an upper impeller and a lower impeller connected to a shaft of a rotor assembly. The column assembly locates a motor housing with the electric motor means adjacent to the impeller assembly which creates an hydraulic head, and which forces the liquid waste, into the motor housing to cool the electric motor means and to cool and/or lubricate the radial and thrust bearing assemblies. Hard-on-hard bearing surfaces of the bearing assemblies and a ring assembly between the upper impeller and electric motor means grind large particles in the liquid waste flow. Slots in the static bearing member of the radial bearing assemblies further grind down the solid waste particles so that only particles smaller than the clearances in the system can pass there through, thereby resisting damage to and the interruption of the operation of the transfer pump. The column assembly is modular so that sections can be easily assembled, disassembled and/or removed. A second embodiment employs a stator jacket which provides an alternate means for cooling the electric motor means and lubricating and/or cooling the bearing assemblies, and a third embodiment employs a variable level suction device which allows liquid waste to be drawn into the transfer pump from varying and discrete levels in the waste tank. 17 figs

  12. Reducing nitrogen oxides from power stations

    International Nuclear Information System (INIS)

    Scheller, W.

    1986-12-01

    The report contains 17 individual lectures of the seminar included in databanks. The lectures concern combustion and waste gas measures for reducing the sulfur dioxide and nitrogen oxide emission from coal-fired and gas-fired power stations. (PW) [de

  13. 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

  14. Recouping the thermal-to-electric conversion loss by the use of waste heat

    International Nuclear Information System (INIS)

    Bradley, W.J.

    1976-01-01

    This paper looks at ways to recoup the thermal-to-electric conversion loss of our thermal power generating stations. These stations now produce twice as much low-grade waste heat as they do electricity. We can improve the situation in two ways: by improving the station efficiency, and by utilizing the low-grade heat beneficially. The following options are examined: N 2 O 4 turbines condensing at 10 deg C; power from moderator waste heat; 50 MW heat pump for district heating; industrial parks with integrated waste heat upgrading station. (author)

  15. Household hazardous waste

    DEFF Research Database (Denmark)

    Fjelsted, Lotte; Christensen, Thomas Højlund

    2007-01-01

    .) comprised 15-25% and foreign items comprised 10-20%. Water-based paint was the dominant part of the paint waste. The chemical composition of the paint waste and the paint-like waste was characterized by an analysis of 27 substances in seven waste fractions. The content of critical substances was tow......'Paint waste', a part of the 'household hazardous waste', amounting to approximately 5 tonnes was collected from recycling stations in two Danish cities. Sorting and analyses of the waste showed paint waste comprised approximately 65% of the mass, paint-like waste (cleaners, fillers, etc...... and the paint waste was less contaminated with heavy metals than was the ordinary household waste. This may suggest that households no longer need to source-segregate their paint if the household waste is incinerated, since the presence of a small quantity of solvent-based paint will not be harmful when...

  16. Impact of cementitious materials decalcification on transfer properties: application to radioactive waste deep repository

    International Nuclear Information System (INIS)

    Perlot, C.

    2005-09-01

    Cementitious materials have been selected to compose the engineering barrier system (EBS) of the French radioactive waste deep repository, because of concrete physico-chemical properties: the hydrates of the cementitious matrix and the pH of the pore solution contribute to radionuclides retention; furthermore the compactness of these materials limits elements transport. The confinement capacity of the system has to be assessed while a period at least equivalent to waste activity (up to 100.000 years). His durability was sustained by the evolution of transfer properties in accordance with cementitious materials decalcification, alteration that expresses structure long-term behavior. Then, two degradation modes were carried out, taking into account the different physical and chemical solicitations imposed by the host formation. The first mode, a static one, was an accelerated decalcification test using nitrate ammonium solution. It replicates the EBS alteration dues to underground water. Degradation kinetic was estimated by the amount of calcium leached and the measurement of the calcium hydroxide dissolution front. To evaluate the decalcification impact, samples were characterized before and after degradation in term of microstructure (porosity, pores size distribution) and of transfer properties (diffusivity, gas and water permeability). The influence of cement nature (ordinary Portland cement, blended cement) and aggregates type (lime or siliceous) was observed: experiments were repeated on different mortars mixes. On this occasion, an essential reflection on this test metrology was led. The second mode, a dynamical degradation, was performed with an environmental permeameter. It recreates the EBS solicitations ensured during the re-saturation period, distinguished by the hydraulic pressure imposed by the geologic layer and the waste exothermicity. This apparatus, based on triaxial cell functioning, allows applying on samples pressure drop between 2 and 10 MPa and

  17. Hanford facility dangerous waste permit application, 325 hazardous waste treatment units. Revision 1

    International Nuclear Information System (INIS)

    1997-07-01

    This report contains the Hanford Facility Dangerous Waste Permit Application for the 325 Hazardous Waste Treatment Units (325 HWTUs) which consist of the Shielded Analytical Laboratory, the 325 Building, and the 325 Collection/Loadout Station Tank. The 325 HWTUs receive, store, and treat dangerous waste generated by Hanford Facility programs. Routine dangerous and/or mixed waste treatment that will be conducted in the 325 HWTUs will include pH adjustment, ion exchange, carbon absorption, oxidation, reduction, waste concentration by evaporation, precipitation, filtration, solvent extraction, solids washing, phase separation, catalytic destruction, and solidification/stabilization

  18. Hanford facility dangerous waste permit application, 325 hazardous waste treatment units. Revision 1

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1997-07-01

    This report contains the Hanford Facility Dangerous Waste Permit Application for the 325 Hazardous Waste Treatment Units (325 HWTUs) which consist of the Shielded Analytical Laboratory, the 325 Building, and the 325 Collection/Loadout Station Tank. The 325 HWTUs receive, store, and treat dangerous waste generated by Hanford Facility programs. Routine dangerous and/or mixed waste treatment that will be conducted in the 325 HWTUs will include pH adjustment, ion exchange, carbon absorption, oxidation, reduction, waste concentration by evaporation, precipitation, filtration, solvent extraction, solids washing, phase separation, catalytic destruction, and solidification/stabilization.

  19. Liquid waste processing at Comanche Peak

    International Nuclear Information System (INIS)

    Hughes-Edwards, L.M.; Edwards, J.M.

    1996-01-01

    This article describes the radioactive waste processing at Comanche Peak Steam Electric Station. Topics covered are the following: Reduction of liquid radioactive discharges (system leakage, outage planning); reduction of waste resin generation (waste stream segregation, processing methodology); reduction of activity released and off-site dose. 8 figs., 2 tabs

  20. Management of reactor waste

    International Nuclear Information System (INIS)

    Baatz, H.

    1976-01-01

    The author discusses the type, production and amount of radioactive waste produced in a nuclear power station (LWR) as well as its conditioning and disposal. The mobile system developed by STEAG for the solidification of medium-activity waste and sludge is referred to in this connection. (HR) [de

  1. Heat transfer: Pittsburgh 1987

    International Nuclear Information System (INIS)

    Lyczkowski, R.W.

    1987-01-01

    This book contains papers divided among the following sections: Process Heat Transfer; Thermal Hydraulics and Phase Change Phenomena; Analysis of Multicomponent Multiphase Flow and Heat Transfer; Heat Transfer in Advanced Reactors; General Heat Transfer in Solar Energy; Numerical Simulation of Multiphase Flow and Heat Transfer; High Temperature Heat Transfer; Heat Transfer Aspects of Severe Reactor Accidents; Hazardous Waste On-Site Disposal; and General Papers

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

    Energy Technology Data Exchange (ETDEWEB)

    1994-09-01

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

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

    International Nuclear Information System (INIS)

    1994-09-01

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

  4. Regulatory experience in nuclear power station decommissioning

    International Nuclear Information System (INIS)

    Ross, W.M.; Waters, R.E.; Taylor, F.E.; Burrows, P.I.

    1995-01-01

    In the UK, decommissioning on a licensed nuclear site is regulated and controlled by HM Nuclear Installations Inspectorate on behalf of the Health and Safety Executive. The same legislative framework used for operating nuclear power stations is also applied to decommissioning activities and provides a continuous but flexible safety regime until there is no danger from ionising radiations. The regulatory strategy is discussed, taking into account Government policy and international guidance for decommissioning and the implications of the recent white paper reviewing radioactive waste management policy. Although each site is treated on a case by case basis as regulatory experience is gained from decommissioning commercial nuclear power stations in the UK, generic issues have been identified and current regulatory thinking on them is indicated. Overall it is concluded that decommissioning is an evolving process where dismantling and waste disposal should be carried out as soon as reasonably practicable. Waste stored on site should, where it is practical and cost effective, be in a state of passive safety. (Author)

  5. Modeling transient heat transfer in nuclear waste repositories.

    Science.gov (United States)

    Yang, Shaw-Yang; Yeh, Hund-Der

    2009-09-30

    The heat of high-level nuclear waste may be generated and released from a canister at final disposal sites. The waste heat may affect the engineering properties of waste canisters, buffers, and backfill material in the emplacement tunnel and the host rock. This study addresses the problem of the heat generated from the waste canister and analyzes the heat distribution between the buffer and the host rock, which is considered as a radial two-layer heat flux problem. A conceptual model is first constructed for the heat conduction in a nuclear waste repository and then mathematical equations are formulated for modeling heat flow distribution at repository sites. The Laplace transforms are employed to develop a solution for the temperature distributions in the buffer and the host rock in the Laplace domain, which is numerically inverted to the time-domain solution using the modified Crump method. The transient temperature distributions for both the single- and multi-borehole cases are simulated in the hypothetical geological repositories of nuclear waste. The results show that the temperature distributions in the thermal field are significantly affected by the decay heat of the waste canister, the thermal properties of the buffer and the host rock, the disposal spacing, and the thickness of the host rock at a nuclear waste repository.

  6. Mass transfer in a salt repository

    International Nuclear Information System (INIS)

    Pigford, T.H.; Chambre, P.L.

    1985-05-01

    To meet regulatory requirements for radioactive waste in a salt repository it is necessary to predict the rates of corrosion of the waste container, the release rates of radionuclides from the waste package, and the cumulative release of radionuclides into the accessible environment. The mechanisms that may control these rates and an approach to predicting these rates from mass-transfer theory are described. This new mechanistic approach is suggested by three premises: (a) a brine inclusion originally in a salt crystal moves along grain boundaries after thermal-induced migration out of the crystal, (b) brine moves along a grain boundary under the influence of a pressure gradient, and (c) salt surrounding a heat-generating waste package will soon creep and consolidate as a monolithic medium surrounding and in contact with the waste package. After consolidation there may be very little migration of intergranular and intragranular brine to the waste package. The corrosion rate of the waste container may then be limited by the rate at which brine reaches the container and may be calculable from mass-transfer theory, and the rate at which dissolved radionuclides leave the waste package may be limited by molecular diffusion in intragranular brine and may be calculable from mass-transfer theory. If porous nonsalt interbeds intersect the waste-package borehole, the release rate of dissolved radionuclides to interbed brine may also be calculable from mass-transfer theory. The logic of these conclusions is described, as an aid in formulating the calculations that are to be made

  7. Design of the fill/transfer station cryostat for the OMEGA cryogenic target system

    International Nuclear Information System (INIS)

    Gibson, C.R.; Charmin, C.M.; Del Bene, J.V.; Hoffmann, E.H.; Besenbruch, G.E.; Anteby, I.

    1997-09-01

    General Atomics is designing, testing and fabricating a system for supplying cryogenic targets for the University of Rochester's OMEGA laser system. A prototype system has demonstrated the filling of 1 mm diameter, 3 microm wall plastic spheres to 111 MPa (1,100 atm) with deuterium and then cooling to 18 K to condense the fuel. The production design must be capable of routinely filling and cooling targets with a 50/50 mix of deuterium and tritium and transferring them to a device which places the targets into the focus of 60 laser beams. This paper discusses the design and analysis of the production Fill/Transfer Station cryostat. The cryostat has two major components, a fixed base and a removable dome. The joint between the base and the dome is similar to a bayonet fitting and is sealed by a room temperature elastomeric o-ring. Since the cryostat must be housed in a glovebox, its design is driven strongly by maintenance requirements. To reach the equipment inside the cryostat, the dome is simply unbolted and lifted. The inside of the cryostat is maintained at 16 K by a closed loop helium flow system. Gaseous helium at about 1.4 MPa (200 psi) flows through tubes which are brazed to the inner walls. Cooling is provided by several cryocoolers which are located external to the cryostat. Liquid nitrogen is used as a heat intercept and to precool the helium gas

  8. Waste Analysis Plan for 241-Z

    International Nuclear Information System (INIS)

    HIRZEL, D.R.

    2000-01-01

    The 241-2 waste tanks are used to store, treat, and transfer waste to Tank Farms. The sampling requirements are established to identify the composition of the tank waste. The primary goal is to meet the Tank Farms acceptance criteria. Tank Farms will not accept waste without extensive characterization sample data. Process and lab wastes are sampled for suitability prior to routing to Tk-D8. The samples are helpful in tracking the amount of chemical constituents to determine treatment and are required to maintain Pu inventory and criticality prevention limitations. Likewise, the waste is sampled prior to inter-tank transfers. The revised Waste Analysis Plan for 241-2 (WAP) contains current facility, process and waste descriptions. The WAP lists the Double Shell Tank (DST) system acceptance criteria, sampling parameters and required analyses. The characterization data on historical process wastes was deleted. A section on the Tank Farms waste approval procedural process was added to describe the steps necessary and documentation required to transfer waste to the DST system. Failure to collect proper samples will result in Tank Farms' refusal to accept PFP waste until proper sampling conditions are met. This will use up unnecessary time and resources but not place the plant in a hazardous position

  9. ESP's Tank 42 washwater transfer to the 241-F/H tank farms

    International Nuclear Information System (INIS)

    Aponte, C.I.; Lee, E.D.

    1997-12-01

    As a result of the separation of the High-Level Liquid Waste Department into three separate organizations (formerly there were two) (Concentration, Storage, and Transfer (CST), Waste Pre-Treatment (WPT) and Waste Disposition (WD)) process interface controls were required. One of these controls is implementing the Waste the waste between CST and WPT. At present, CST's Waste Acceptance Criteria is undergoing revision and WPT has not prepared the required Waste Compliance Plan (WCP). The Waste Pre-Treatment organization is making preparations for transferring spent washwater in Tank 42 to Tank 43 and/or Tank 22. The washwater transfer is expected to complete the washing steps for preparing ESP batch 1B sludge. This report is intended to perform the function of a Waste Compliance Plan for the proposed transfer. Previously, transfers between the Tank Farm and ITP/ESP were controlled by requirements outlined in the Tank Farm's Technical Standards and ITP/ESP's Process Requirements. Additionally, these controls are implemented primarily in operating procedure 241-FH-7TSQ and ITP Operations Manual SW16.1-SOP-WTS-1 which will be completed prior to performing the waste transfers

  10. Two-way laser ranging and time transfer experiments between LOLA and an Earth-based satellite laser ranging station

    Science.gov (United States)

    Mao, D.; Sun, X.; Neumann, G. A.; Barker, M. K.; Mazarico, E. M.; Hoffman, E.; Zagwodzki, T. W.; Torrence, M. H.; Mcgarry, J.; Smith, D. E.; Zuber, M. T.

    2017-12-01

    Satellite Laser Ranging (SLR) has established time-of-flight measurements with mm precision to targets orbiting the Earth and the Moon using single-ended round-trip laser ranging to passive optical retro-reflectors. These high-precision measurements enable advances in fundamental physics, solar system dynamics. However, the received signal strength suffers from a 1/R4 decay, which makes it impractical for measuring distances beyond the Moon's orbit. On the other hand, for a two-way laser transponder pair, where laser pulses are both transmitted to and received from each end of the laser links, the signal strength at both terminals only decreases by 1/R2, thus allowing a greater range of distances to be covered. The asynchronous transponder concept has been previously demonstrated by a test in 2005 between the Mercury Laser Altimeter (MLA) aboard the MESSENGER (MErcury Surface, Space ENvironment, Geochemistry, and Ranging) spacecraft and NASA's Goddard Geophysical and Astronomical Observatory (GGAO) at a distance of ˜0.16 AU. In October 2013, regular two-way transponder-type range measurements were obtained over 15 days between the Lunar Laser Communication Demonstration (LLCD) aboard the Lunar Atmosphere and Dust Environment Explorer (LADEE) spacecraft and NASA's ground station at White Sands, NM. The Lunar Orbiter Laser Altimeter (LOLA) aboard the Lunar Reconnaissance Orbiter (LRO) provides us a unique capability to test time-transfer beyond near Earth orbit. Here we present results from two-way transponder-type experiments between LOLA and GGAO conducted in March 2014 and 2017. As in the time-transfer by laser link (T2L2) experiments between a ground station and an earth-orbiting satellite, LOLA and GGAO ranged to each other simultaneously in these two-way tests at lunar distance. We measured the time-of-flight while cross-referencing the spacecraft clock to the ground station time. On May 4th, 2017, about 20 minutes of two-way measurements were collected. The

  11. Radioactive wastes handling facility

    International Nuclear Information System (INIS)

    Hirose, Emiko; Inaguma, Masahiko; Ozaki, Shigeru; Matsumoto, Kaname.

    1997-01-01

    There are disposed an area where a conveyor is disposed for separating miscellaneous radioactive solid wastes such as metals, on area for operators which is disposed in the direction vertical to the transferring direction of the conveyor, an area for receiving the radioactive wastes and placing them on the conveyor and an area for collecting the radioactive wastes transferred by the conveyor. Since an operator can conduct handling while wearing a working cloth attached to a partition wall as he wears his ordinary cloth, the operation condition can be improved and the efficiency for the separating work can be improved. When the area for settling conveyors and the area for the operators is depressurized, cruds on the surface of the wastes are not released to the outside and the working clothes can be prevented from being involved. Since the wastes are transferred by the conveyor, the operator's moving range is reduced, poisonous materials are fallen and moved through a sliding way to an area for collecting materials to be separated. Accordingly, the materials to be removed can be accumulated easily. (N.H.)

  12. Space Station - Opportunity for international cooperation and utilization

    Science.gov (United States)

    Pedersen, K. S.

    1984-01-01

    In connection with his announcement regarding the development of a permanently manned Space Station, President Reagan invited the United States' friends and allies to join in the Space Station program. The President's invitation was preceded by more than two years of interaction between NASA and some of its potential partners in Space Station planning activities. Attention is given to international participation in Space Station planning, international cooperation on the Space Station, the guidelines for international cooperation, and the key challenges. Questions regarding quid pro quos are considered along with aspects of technology transfer, commercial use, problems of management, and the next steps concerning the Space Station program.

  13. CEGB's radioactive waste management strategy

    International Nuclear Information System (INIS)

    Passant, F.H.; Maul, P.R.

    1989-01-01

    The Central Electricity Generating Board (CEGB) produces low-level and intermediate-level radioactive wastes in the process of operating its eight Magnox and five Advanced Gas Cooled Reactor (AGR) nuclear power stations. Future wastes will also arise from a programme of Pressurised Water Reactors (PWRs) and the decommissioning of existing reactors. The paper gives details of how the UK waste management strategy is put into practice by the CEGB, and how general waste management principles are developed into strategies for particular waste streams. (author)

  14. Radiation protection in transference of radioactive wastes among buildings of an intermediary deposit

    International Nuclear Information System (INIS)

    Mitake, Malvina Boni; Suzuki, Fabio Fumio

    2011-01-01

    This paper describes the planning of radioprotection realized for transfer operation of radioactive wastes from two old buildings for a one of the new buildings. For planning purposes the operation was divided into nine stages and, for evaluation of collective dose, it was considered various relevant factors. The result of radioprotection optimization it was expected a total collective dose of 58.6 mSv per person. The measured dose per dosemeter of direct reading was of 3.9 mSv per person. These difference among the values is due to conservative factors used in the calculation

  15. Identification of Heat Transfer Resistance of Scale Deposit on theEvaporator of Radioactive Waste Management Installation

    International Nuclear Information System (INIS)

    Zainus-Salimin

    2000-01-01

    Identification of heat transfer resistance of scale deposit from fixedhardness of liquid waste in the form of CaSO 4 and MgSO 4 ratio 2:1 has beendone on the evaporation system of Serpong Nuclear Facilities fordetermination of the quality of heat transfer obstruction from heating sourceto solution. Evaporation simulation of solution containing hardness withconcentration 0.5; 1; 2; and 2.5% mass were done on the stainless steelcontainer of 1 / volume with electrical heater in which a stainless-steeltube is put down on the base container. After 24, 168, 336, 504 and 672 hoursevaporation process it is obtained the thickness of scale deposit on thesurface of tube for determining the fouling factor. Heat transfer resistanceof scale deposit from 672 hours evaporation of solution 2.5% concentrationhampered heat transfer, the value of fouling factor be superior to limitsvalue of 0.000515 hours.m 2 . o C/kcal.The fouling factor from the evaporationof solution of 0.5; 1; and 2% concentration during 672 hours be inferior tolimits value. (author)

  16. Real-time transfer and display of radiography image

    International Nuclear Information System (INIS)

    Liu Ximing; Wu Zhifang; Miao Jicheng

    2000-01-01

    The information process network of cobalt-60 container inspection system is a local area network based on PC. The system requires reliable transfer of radiography image between collection station and process station and the real-time display of radiography image on process station. Due to the very high data acquisition rate, in order to realize the real-time transfer and display of radiography image, 100 M Ethernet technology and network process communication technology are adopted in the system. Windows Sockets is the most common process communication technology up to now. Several kinds of process communication way under Windows Sockets technology are compared and tested. Finally the author realized 1 Mbyte/s' inerrant image transfer and real-time display with blocked datagram transfer technology

  17. Waste management in the regional level: Example of municipalities Pljevlja and Žabljak

    Directory of Open Access Journals (Sweden)

    Šljivančanin Dušan

    2011-01-01

    Full Text Available The problem of proper disposal of all types of solid waste and its inadequate treatment is one of the most dominant spatial-ecological problems of modern society, and as such seriously threatens the quality of basic environmental media and public health. The aim is to point out opportunities for sustainable development of Pljevlja and Zabljak Municipalities through the development of waste management system that will control waste generation, educe the impact of waste on the environment, improve resource efficiency, ensure the proper disposal, stimulate investment in public-private sector and maximize the economic opportunities arising from waste. The subject of this paper is to find an effective model of sustainable waste management in the municipalities of Zabljak and Pljevlja, with the main objective of rational use of space, as a limited resource, and reduce overall costs of waste treatment. The studied area that includes the administrative boundaries of these municipalities in the north of Montenegro, among to traffic geographical and functional correlation, present an area that is in the official republic documents (Spatial Rlan of Montenegro until 2020, 2008 recognized as a region in which envisages the construction of regional sanitary landfills and transfer stations network. In this sense, the work will represent the implementation of policies on waste management in Montenegro, in accordance with the recommendations, directives and EU guidelines.

  18. Components for containment enclosures - Part 3: Transfer systems such as plain doors, airlock chambers, double door transfer systems, leaktight connections for waste drums. 1. ed.

    International Nuclear Information System (INIS)

    1998-01-01

    This part of ISO 11933 specifies requirements for the selection, construction and use of the following leak tight components: doors, airlock chambers, double door transfer systems, leaktight connections for waste drums. Some of the elements, double doors or airlock chambers are described in ISO 11933-1 and ISO 11933-2 as well. Doors having bigger dimensions used for personnel od larger objects are not covered by this document

  19. Treatment and conditioning of historical radioactive waste

    International Nuclear Information System (INIS)

    Dogaru, Ghe.; Dragolici, F.; Ionascu, L.; Rotarescu, Ghe.

    2009-01-01

    The paper describes the management of historical radioactive waste from the storage facility of Radioactive Waste Treatment Plant. The historical waste stored into storage facility of IFIN-HH consists of spent sealed radioactive sources, empty contaminated containers, wooden radioactive waste, low specific activity radioactive waste, contaminated waste as well as radioactive waste from operation of WWR-S research reactor. After decommissioning of temporary storage facility about 5000 packages with radioactive waste were produced and transferred to the disposal facility. A large amount of packages have been transferred and disposed of to repository but at the end of 2000 there were still about 800 packages containing cement conditioned radioactive waste in an advanced state of degradation declared by authorities as 'historical waste'. During the management of historical waste campaign there were identified: radium spent radioactive sources, containers containing other spent sealed radioactive sources, packages containing low specific activity waste consist of thorium scrap allow, 30 larger packages (316 L), packages with activity lower than activity limit for disposal, packages with activity higher than activity limit for disposal. At the end of 2008, the whole amount of historical waste which met the waste acceptance criteria has been conditioned and transferred to disposal facility. (authors)

  20. Solid radwaste characterization at surry and North Anna Power Stations

    International Nuclear Information System (INIS)

    Lippard, D.W.

    1987-01-01

    This paper describes a characterization of the solid radwaste generated at Virginia Power's North Anna and Surry power stations. The primary focus of this characterization was dry active waste (DAW). The characterization, covering the 21-month period from January 1985 through September 1986, was based on information in the station's health physics procurement records, radwaste shipping records, and from interviews with station personnel. The procurement records were the principal source of information for DAW. They were reviewed to determine the quantities of various materials, purchased during the study period, that were expected to become DAW. This provides an upper limit on the quantity in the waste for several major DAW components and a basis for the total amount of other components in the waste. The approach to characterizing DAW discussed in this paper could be implemented and regularly updated by utilizing a computerized procurement records system. If a use code (i.e., contaminated or noncontaminated) is associated with each stock requisition, a characterization could be performed by a computer run. This approach would help track minimization effort effectiveness and would refine the characterization of DAW considerably

  1. Contaminated concrete scabbling at the Shippingport station decommissioning project

    International Nuclear Information System (INIS)

    Bauer, R.G.

    1989-01-01

    The Shippingport atomic power station was the first commercial nuclear power plant in the United States, joining the Duquesne Light Company (DLC) grid in December 1957. The Shippingport station was shut down in October 1982 and defueled in preparation for dismantling. On September 6, 1984, the Shippingport Station Decommissioning Project (SSDP) office of the US Department of Energy (DOE) assumed responsibility for the site. At turnover, there were several areas in the plant where radioactive contamination was entrained in concrete surfaces. The removal of contaminated concrete at SSDP was an important part of the decontamination to meet site release criteria, which is a major consideration in the decommissioning of nuclear power reactors. The highlights of this activity include: (1) development and application of remote scabbling tools, which effectively removed the contaminated concrete surfaces, and (2) use of scabblers minimized the removal of noncontaminated concrete by removing shallow layers of the surface and contributed to waste control, since the waste form enabled good packaging efficiency

  2. Double Shell Tank (DST) Transfer Pump Subsystem Specification

    International Nuclear Information System (INIS)

    GRAVES, C.E.

    2001-01-01

    This specification establishes the performance requirements and provides the references to the requisite codes and standards to be applied during the design of the Double-Shell Tank (DST) Transfer Pump Subsystem that supports the first phase of waste feed delivery (WFD). The DST Transfer Pump Subsystem consists of a pump for supernatant and/or slurry transfer for the DSTs that will be retrieved during the Phase 1 WFD operations. This system is used to transfer low-activity waste (LAW) and high-level waste (HLW) to designated DST staging tanks. It also will deliver blended LAW and HLW feed from these staging tanks to the River Protection Project (RPP) Waste Treatment Plant where it will be processed into an immobilized waste form. This specification is intended to be the basis for new projects/installations (W-521, etc.). This specification is not intended to retroactively affect previously established project design criteria without specific direction by the program

  3. Preventing Buoyant Displacement Gas Release Events in Hanford Double-Shell Waste Tanks

    Energy Technology Data Exchange (ETDEWEB)

    Meyer, Perry A.; Stewart, Charles W.

    2001-01-01

    This report summarizes the predictive methods used to ensure that waste transfer operations in Hanford waste tanks do not create waste configurations that lead to unsafe gas release events. The gas release behavior of the waste in existing double-shell tanks has been well characterized, and the flammable gas safety issues associated with safe storage of waste in the current configuration are being formally resolved. However, waste is also being transferred between double-shell tanks and from single-shell tanks into double-shell tanks by saltwell pumping and sluicing that create new wastes and waste configurations that have not been studied as well. Additionally, planning is underway for various waste transfer scenarios to support waste feed delivery to the proposed vitrification plant. It is critical that such waste transfers do not create waste conditions with the potential for dangerous gas release events.

  4. Shippingport Station Decommissioning Project

    International Nuclear Information System (INIS)

    McKernan, M.L.

    1989-01-01

    The Shippingport Atomic Power Station was located on the Ohio River in Shippingport Borough (Beaver County), Pennsylvania, USA. The US Atomic Energy Commission (AEC) constructed the plant in the mid-1950s on a seven and half acre parcel of land leased from Duquesne Light Company (DLC). The purposes were to demonstrate and to develop Pressurized Water Recovery technology and to generate electricity. DLC operated the Shippingport plant under supervision of (the successor to AEC) the Department of Energy (DOE)-Naval Reactors (NR) until operations were terminated on October 1, 1982. NR concluded end-of-life testing and defueling in 1984 and transferred the Station's responsibility to DOE Richland Operations Office (RL), Surplus Facility Management Program Office (SFMPO5) on September 5, 1984. SFMPO subsequently established the Shippingport Station Decommissioning Project and selected General Electric (GE) as the Decommissioning Operations Contractor. This report is intended to provide an overview of the Shippingport Station Decommissioning Project

  5. Liquid radwaste processing history at Fort Calhoun Nuclear Station

    International Nuclear Information System (INIS)

    Bilau, A.; Rutar, F.

    1989-01-01

    This report presents a historical perspective of liquid radwaste processing at the Fort Calhoun Unit 1 Nuclear Power Station, located in east central Nebraska. Of particular interest is the textual and graphical comparison of the operational implications of the various waste processing methods employed in the last ten years at the Fort Calhoun Station. Fort Calhoun's waste collection and processing systems are described in detail. These process systems include evaporation and solidification employing an in-plant drum solidification system. This solidification system was later replaced with vendor solidification services which solidified wastes in large liners. Ultimately, the plant converted its processing operation to ion exchange cleanup using ion selective media. The operational and economic impact of each of these process systems is discussed including overall costs, personnel exposure, capital expenditure requirements, burial volumes generated, maintenance and reliability assessments. Operational goals and performance criteria employed in the decision-making process for selection of the optimal technology are discussed, including the impact of various influent and effluent requirements

  6. Preliminary evaluation of the impact and inter-generation risk transfers related to the release and disposal of radioactive waste from the nuclear fuel cycle

    International Nuclear Information System (INIS)

    Tort, V.; Lochard, J.; Schneider, T.; Sugier, A.

    1997-12-01

    This report is an attempt to contribute to the complex issue of the decision-making in the field of radioactive waste management. Because of the complex and multidimensional nature of the distant future consequences of waste management options, their analysis implies the taking into considerations of various aggregated indicators which depend on the elapse of time during which the radionuclides remain in the environment and their local, regional or world-wide dispersion. This report is a preliminary work sponsored by IPSN mainly focused on the risk transfer dimension, inherent to waste disposal management. Its objective is to illustrate, using the French nuclear fuel cycle context, the relative impact of some simple waste management options, outlining particularly the issue of inter-generation risk transfer. Even though the selected six radionuclides are the most important, a complete assessment should include all the radionuclides contained in the waste, what is particularly important in case of underground waste disposal were both normal evolution scenarios and intrusion must be considered. The extreme alternatives, i.e. the total disposal or total release of the radionuclides are analyzed but realistic are the intermediate options, which should be thoroughly examined from the technical point of view. The analysis of intermediate management options could give an estimation of the most appropriate solution in an ALARA perspective

  7. State Waste Discharge Permit application, 100-N Sewage Lagoon

    International Nuclear Information System (INIS)

    1994-06-01

    As part of the Hanford Federal Facility Agreement and Consent Order negotiations (Ecology et al. 1994), the US Department of Energy, Richland Operations Office, the US Environmental Protection Agency, and the Washington State Department of Ecology agreed that liquid effluent discharges to the ground on the Hanford Site which affect groundwater or have the potential to affect groundwater would be subject to permitting under the structure of Chapter 173--216 (or 173--218 where applicable) of the Washington Administrative Code, the State Waste Discharge Permit Program. As a result of this decision, the Washington State Department of Ecology and the US Department of Energy, Richland Operations Office entered into Consent Order No. DE 91NM-177, (Ecology and DOE-RL 1991). This document constitutes the State Waste Discharge Permit application for the 100-N Sewage Lagoon. Since the influent to the sewer lagoon is domestic waste water, the State Waste Discharge Permit application for Public Owned Treatment Works Discharges to Land was used. Although the 100-N Sewage Lagoon is not a Public Owned Treatment Works, the Public Owned Treatment Works application is more applicable than the application for industrial waste water. The 100-N Sewage Lagoon serves the 100-N Area and other Hanford Site areas by receiving domestic waste from two sources. A network of sanitary sewer piping and lift stations transfers domestic waste water from the 100-N Area buildings directly to the 100-N Sewage Lagoon. Waste is also received by trucks that transport domestic waste pumped from on site septic tanks and holding tanks. Three ponds comprise the 100-N Sewage Lagoon treatment system. These include a lined aeration pond and stabilization pond, as well as an unlined infiltration pond. Both piped-in and trucked-in domestic waste is discharged directly into the aeration pond

  8. West Valley waste removal system study

    International Nuclear Information System (INIS)

    Janicek, G.P.

    1981-04-01

    This study addresses the specific task of removing high-level wastes from underground tanks at Western New York Nuclear Center and delivering them to an onsite waste solidification plant. It begins with a review of the design and construction features of the waste storage tanks pertinent to the waste removal task with particular emphasis on the unique and complex tank internals which severely complicate the task of removal. It follows with a review of tank cleaning techniques used and under study at both Hanford and Savannah River and previous studies proposing the use of these techniques at West Valley. It concludes from these reviews that existing techniques are not directly transferable to West Valley and that a new approach is required utilizing selected feature and attributes from existing methodology. The study also concludes, from an investigation of the constraints imposed by the processing facility, that waste removal will be intermittent, requiring batch transfer over the anticipated 3 years of processing operations. Based on these reviews and conclusions, the study proposes that the acid waste be processed first and that one of the 15,000-gallon acid tanks then be used for batch feeding the neutralized waste. The proposed system would employ commercially available pumping equipment to transfer the wastes from the batch tank to processing via existing process piping. A commercially available mixed-flow pump and eight turbine pumps would homogenize the neutralized waste in conjunction with eight custom-fabricated sluicers for periodic transfer to the batch tank

  9. Double Shell Tank (DST) Transfer Piping Subsystem Specification

    International Nuclear Information System (INIS)

    GRAVES, C.E.

    2000-01-01

    This specification establishes the performance requirements and provides references to the requisite codes and standards to be applied during design of the Double-Shell Tank (DST) Transfer Piping Subsystem that supports the first phase of Waste Feed Delivery. This specification establishes the performance requirements and provides references to the requisite codes and standards to be applied during design of the Double-Shell Tank (DST) Transfer Piping Subsystem that supports the first phase of waste feed delivery. This subsystem transfers waste between transfer-associated structures (pits) and to the River Protection Project (RPP) Privatization Contractor Facility where it will be processed into an immobilized waste form. This specification is intended to be the basis for new projects/installations (W-521, etc.). This specification is not intended to retroactively affect previously established project design criteria without specific direction by the program

  10. A conveyor system for feeding work stations

    International Nuclear Information System (INIS)

    Sheader, J.; Davies, K.J.

    1986-01-01

    A conveyor system comprises carriages drive, e.g. by a linear motor, a pre-arranged sequence of steps to move workpieces in forward and reverse directions between work stations. Each work station has a part position and a work position and each carriage has a number of compartments for workpieces spaced apart at a pitch equal to the spacing between the part and work positions at each station. Transfer means at the work stations move workpieces between the carriage compartments and the part and work positions. The workpieces can be nuclear fuel pins mounted in carriers and the carriages shuttle to and fro between adjacent stations to move fuel pins and carriers in a forward direction and the return empty carriers in a reverse direction. (author)

  11. The Princess Elisabeth Station

    Science.gov (United States)

    Berte, Johan

    2012-01-01

    Aware of the increasing impact of human activities on the Earth system, Belgian Science Policy Office (Belspo) launched in 1997 a research programme in support of a sustainable development policy. This umbrella programme included the Belgian Scientific Programme on Antarctic Research. The International Polar Foundation, an organization led by the civil engineer and explorer Alain Hubert, was commissioned by the Belgian Federal government in 2004 to design, construct and operate a new Belgian Antarctic Research Station as an element under this umbrella programme. The station was to be designed as a central location for investigating the characteristic sequence of Antarctic geographical regions (polynia, coast, ice shelf, ice sheet, marginal mountain area and dry valleys, inland plateau) within a radius of 200 kilometers (approx.124 miles) of a selected site. The station was also to be designed as "state of the art" with respect to sustainable development, energy consumption, and waste disposal, with a minimum lifetime of 25 years. The goal of the project was to build a station and enable science. So first we needed some basic requirements, which I have listed here; plus we had to finance the station ourselves. Our most important requirement was that we decided to make it a zero emissions station. This was both a philosophical choice as we thought it more consistent with Antarctic Treaty obligations and it was also a logistical advantage. If you are using renewable energy sources, you do not have to bring in all the fuel.

  12. Physical decommissioning of the Shippingport Atomic Power Station

    International Nuclear Information System (INIS)

    Crimi, F.P.

    1988-01-01

    The Shippingport Atomic Power Station consists of the nuclear steam supply system and associated radioactive waste processing systems, which are owned by the United States Department of Energy (USDOE), and the turbine-generator and balance of plant which is owned by the Duquesne Light Company. The station is located at Shippingport, Pennsylvania on seven acres of land leased by USDOE from the Duquesne Light Company. The Shippingport Station Decommissioning Project (SSDP) is being managed for the USDOE by the General Electric Company and its integated subcontractor, Morrison Knudsen-Ferguson (MK-F) Company. The objectives of the Shippingport Station Decommissioning Project (SSDP) are to: Demonstrate the safe and cost effective dismantlement of a large scale nuclear power plant; Provide useful data for future decommissioning projects

  13. Heat transfer analysis of the waste-container sleeve/salt configuration

    International Nuclear Information System (INIS)

    Callahan, G.D.; Ratigan, J.L.; Russell, J.E.; Fossum, A.F.

    1975-01-01

    Prior to this investigation, the heat transport considered was only that of straight conduction. The waste container, air gap, and sleeve arrangement was considered to be a single, consistent, time-dependent, heat-generating unit in intimate contact with the salt. The conduction model does not accurately model the heat transfer mechanisms available. Thus radiation and combined radiation and convection must also be considered in the determination of the temperature field. As would be expected, the canister temperatures are higher for the case of radiation across the airgap than those that result from conduction when the canister is in intimate contact with the salt. For the radiation case, the canister temperatures rise rapidly to a temperature of approximately 1,140 0 F and maintain an almost steady state condition for one year whereafter the temperatures slowly decrease. The far field temperatures, near the pillar centerline, are essentially equivalent for all cases. As time proceeds, the far field temperatures of the conduction models are about 15% different

  14. Treatment and disposal of radioactive waste from nuclear power stations

    International Nuclear Information System (INIS)

    Baehr, W.

    1981-01-01

    The Federal Republic of Germany and many other European countries, having very high population densities, must make the most efficient use of their soil, their ground and surface waters. In Germany, no method of waste disposal could be used which included direct storage or seepage into the upper strata of the soil or a discharge into rivers or lakes. It has been shown after more than 20 years experience of treatment of low and intermediate level liquid and solid wastes and disposal of solidified residues in a salt mine, that a number of techniques and procedures are available for manageing this kind of waste with a high degree of safety. A complete system of waste collection, treatment methods and controlled disposal of low and intermediate radioactive residues in accordance with legally established rules and regulations offers the best guarantee for environmental protection. (orig./RW)

  15. Certification Plan, Radioactive Mixed Waste Hazardous Waste Handling Facility

    International Nuclear Information System (INIS)

    Albert, R.

    1992-01-01

    The purpose of this plan is to describe the organization and methodology for the certification of radioactive mixed waste (RMW) handled in the Hazardous Waste Handling Facility at Lawrence Berkeley Laboratory (LBL). RMW is low-level radioactive waste (LLW) or transuranic (TRU) waste that is co-contaminated with dangerous waste as defined in the Westinghouse Hanford Company (WHC) Solid Waste Acceptance Criteria (WAC) and the Washington State Dangerous Waste Regulations, 173-303-040 (18). This waste is to be transferred to the Hanford Site Central Waste Complex and Burial Grounds in Hanford, Washington. This plan incorporates the applicable elements of waste reduction, which include both up-front minimization and end-product treatment to reduce the volume and toxicity of the waste; segregation of the waste as it applies to certification; an executive summary of the Waste Management Quality Assurance Implementing Management Plan (QAIMP) for the HWHF (Section 4); and a list of the current and planned implementing procedures used in waste certification

  16. Radioactive waste storage facility and underground disposal method for radioactive wastes using the facility

    International Nuclear Information System (INIS)

    Endo, Yoshihiro.

    1997-01-01

    A sealed container storage chamber is formed in underground rocks. A container storage pool is formed on the inner bottom of the sealed vessel storage chamber. A heat exchanger for cooling water and a recycling pump are disposed on an operation floor of the sealed vessel storage chamber. Radioactive wastes sealed vessels in which radioactive wastes are sealed are transferred from the ground to the sealed vessel storage chamber through a sealed vessel transferring shaft, and immersed in cooling water stored in the vessel storage pool. When after heat of the radioactive wastes is removed by the cooling water, the cooling water in the vessel storage pool is sucked up to the ground surface. After dismantling equipments, bentonite-type fillers are filled in the inside of the sealed vessel storage chamber, sealed vessel transferring shaft, air supplying shaft and air exhaustion shaft, and the radioactive waste-sealed vessels can be subjected stably to into underground disposal. (I.N.)

  17. Parametric optimization and heat transfer analysis of a dual loop ORC (organic Rankine cycle) system for CNG engine waste heat recovery

    International Nuclear Information System (INIS)

    Yang, Fubin; Zhang, Hongguang; Yu, Zhibin; Wang, Enhua; Meng, Fanxiao; Liu, Hongda; Wang, Jingfu

    2017-01-01

    In this study, a dual loop ORC (organic Rankine cycle) system is adopted to recover exhaust energy, waste heat from the coolant system, and intercooler heat rejection of a six-cylinder CNG (compressed natural gas) engine. The thermodynamic, heat transfer, and optimization models for the dual loop ORC system are established. On the basis of the waste heat characteristics of the CNG engine over the whole operating range, a GA (genetic algorithm) is used to solve the Pareto solution for the thermodynamic and heat transfer performances to maximize net power output and minimize heat transfer area. Combined with optimization results, the optimal parameter regions of the dual loop ORC system are determined under various operating conditions. Then, the variation in the heat transfer area with the operating conditions of the CNG engine is analyzed. The results show that the optimal evaporation pressure and superheat degree of the HT (high temperature) cycle are mainly influenced by the operating conditions of the CNG engine. The optimal evaporation pressure and superheat degree of the HT cycle over the whole operating range are within 2.5–2.9 MPa and 0.43–12.35 K, respectively. The optimal condensation temperature of the HT cycle, evaporation and condensation temperatures of the LT (low temperature) cycle, and exhaust temperature at the outlet of evaporator 1 are kept nearly constant under various operating conditions of the CNG engine. The thermal efficiency of the dual loop ORC system is within the range of 8.79%–10.17%. The dual loop ORC system achieves the maximum net power output of 23.62 kW under the engine rated condition. In addition, the operating conditions of the CNG engine and the operating parameters of the dual loop ORC system significantly influence the heat transfer areas for each heat exchanger. - Highlights: • A dual loop ORC system is adopted to recover the waste heat of a CNG engine. • Parametric optimization and heat transfer analysis are

  18. Selection of combined water electrolysis and resistojet propulsion for Space Station Freedom

    Science.gov (United States)

    Schmidt, George R.

    1988-01-01

    An analytical rationale is presented for the configuration of the NASA Space Station's two-element propulsion system, and attention is given to the cost benefits accruing to this system over the Space Station's service life. The principal system element uses gaseous oxygen and hydrogen obtained through water electrolysis to furnish attitude control, backup attitude control, and contingency maneuvering. The secondary element uses resistojets to augment Space Station reboost through the acceleration of waste gases in the direction opposite the Station's flight path.

  19. Arc plasma incineration of surrogate radioactive wastes

    International Nuclear Information System (INIS)

    Girold, C.; Cartier, R.; Taupiac, J.P.; Vandensteendam, C.; Baronnet, J.M.

    1995-01-01

    The aim of this presentation is to demonstrate the feasibility to substitute a single plasma reactor, where the arc is transferred on a melt glass bath, for several steps in an existing nuclear technological wastes incinerator. The incineration of wastes, the produced gas treatment and the vitrification of ashes issued from waste incineration are the three simultaneous functions of this new kind of reactor. The three steps of the work are described: first, post-combustion in an oxygen plasma of gases generated from the waste pyrolysis, then, vitrification of ashes from the calcination of wastes in the transferred plasma furnace and finally, incineration/vitrification of wastes in the same furnace

  20. Transit Station Congestion Index Research Based on Pedestrian Simulation and Gray Clustering Evaluation

    Directory of Open Access Journals (Sweden)

    Shu-wei Wang

    2013-01-01

    Full Text Available A congestion phenomenon in a transit station could lead to low transfer efficiency as well as a hidden danger. Effective management of congestion phenomenon shall help to reduce the efficiency decline and danger risk. However, due to the difficulty in acquiring microcosmic pedestrian density, existing researches lack quantitative indicators to reflect congestion degree. This paper aims to solve this problem. Firstly, platform, stair, transfer tunnel, auto fare collection (AFC machine, and security check machine were chosen as key traffic facilities through large amounts of field investigation. Key facilities could be used to reflect the passenger density of a whole station. Secondly, the pedestrian density change law of each key traffic facility was analyzed using pedestrian simulation, and the load degree calculating method of each facility was defined, respectively, afterwards. Taking pedestrian density as basic data and gray clustering evaluation as algorithm, an index called Transit Station Congestion Index (TSCI was constructed to reflect the congestion degree of transit stations. Finally, an evaluation demonstration was carried out with five typical transit transfer stations in Beijing, and the evaluation results show that TSCI can objectively reflect the congestion degree of transit stations.

  1. Aspects of nuclear waste management

    International Nuclear Information System (INIS)

    Moberg, L.

    1990-10-01

    Six areas of concern in nuclear waste management have been dealt with in a four-year Nordic research programme. They include work in two international projects, Hydrocoin dealing with modelling of groundwater flow in crystalline rock, and Biomovs, concerned with biosphere models. Geologic questions of importance to the prediction of future behaviour are examined. Waste quantities from the decommissioning of nuclear power stations are estimated, and total amounts of waste to be transported in the Nordic countries are evaluated. Waste amounts from a hypothetical reactor accident are also calculated. (au)

  2. "Artificial intelligence" at streamgaging stations

    Science.gov (United States)

    R. B. Thomas

    1985-01-01

    Two types of problems are related to collecting hydrologic data at stream gaging stations. One includes the technical/logistical questions associated with measuring and transferring data for processing. Effort spent on these problems ranges from improving devices for sensing data to using electronic data loggers.

  3. Comparison of Nintendo Wii and PlayStation2 for enhancing laparoscopic skills.

    Science.gov (United States)

    Ju, Rujin; Chang, Peter L; Buckley, Adam P; Wang, Karen C

    2012-01-01

    The increase in laparoscopic surgery has led to a growing need to train residents in this skill. Virtual reality simulators and box trainers have been used as educational tools outside of the operating room, but both approaches have advantages and disadvantages. Video games have been an area of interest in the search for other modalities to train residents. Experience with the traditional single controller unit video games have been correlated with better surgical skill acquisition. In 2006, Nintendo introduced the Wii, a novel gaming modality that mimics movements in laparoscopy better than traditional games do. Our objective was to compare the Nintendo Wii and PlayStation2 for enhancing laparoscopy skills. The study included stratified randomization of 23 less experienced ( 12 laparoscopy cases per year) and 19 more experienced ( 12 per year) physicians, residents, and medical students to 30 min of Wii versus PlayStation2 in a university-affiliated hospital Department of Obstetrics and Gynecology. Pre- and posttest bead transfer and suturing scores were obtained. Baseline characteristics were similar for both video game groups. Participants assigned to Wii and PlayStation2 both demonstrated significant improvement in bead transfer. Neither Wii nor PlayStation2 participants improved in suturing scores. The Wii group improved more in bead transfer scores when compared to the PlayStation2 group (60 points vs. 40 points, respectively), but this difference was not statistically significant. Both Wii and PlayStation2 significantly improved laparoscopic skills in bead transfer. These video games may be inexpensive alternatives to laparoscopy training simulators.

  4. Life cycle assessment of municipal solid waste management methods: Ankara case study.

    Science.gov (United States)

    Ozeler, D; Yetiş, U; Demirer, G N

    2006-04-01

    Different solid waste management system scenarios were developed and compared for the Municipal Solid Waste Management System of Ankara by using the life cycle assessment (LCA) methodology. The solid waste management methods considered in the scenarios were collection and transportation of wastes, source reduction, Material Recovery Facility (MRF)/Transfer Stations (TS), incineration, anaerobic digestion and landfilling. The goal of the study was to determine the most environmentally friendly option of MSWM system for Ankara. The functional unit of the study was the amount of solid waste generated in the system area of concern, which are the districts of Ankara. The life cycle inventory analysis was carried out by IWM Model-1. The inputs and outputs of each management stage were defined and the inventory emissions calculated by the model were classified in to impact categories; non-renewable energy sources exhausting potential, final solid waste as hazardous and non-hazardous, global warming, acidification, eutrophication and human toxicity. The impacts were quantified with the weighing factors of each category to develop the environmental profiles of each scenario. In most of the categories, Source Reduction Scenario was found to be the most feasible management method, except the global warming category. The lowest contribution to GWP was calculated for the anaerobic digestion process. In the interpretation and improvement assessment stage, the results were further evaluated and recommendations were made to improve the current solid waste management system of Ankara.

  5. Processing of sump sludges at the Commonwealth Edison Byron Nuclear Generating Station

    International Nuclear Information System (INIS)

    Herrmann, D.; Gardner, D.A.; Taylor, E.R. Jr.

    1990-01-01

    A basic criterion for the disposal of radioactive waste by shallow land burial is that the material must not contain free liquids. In addition burial sites' requirements regarding radioactive waste containing oils, even though solidified, are restrictive. At Commonwealth Edison Byron Nuclear Generating Station a methodology for processing treated waste sludges, originating form the turbine building's floor drains was developed and implemented. As a result of this effort, 322 drums of oil and water sludge were processed. A dry cake, i.e., no free liquids, was produced, packaged, and readied for disposal. The dry cake contained less than 2% oil. The liquid phases resulting from the processing of the treated waste sludge were oil (that was to be processed for disposal as non-radioactive) and filtrate containing less than 5 ppm total suspended solids (TSS) and oil/grease. The filtrate TSS was below the Station's National Pollution Discharge Elimination System (NPDES) permit release limits. 4 figs

  6. A reliable technique for transfer of radioactivity filled vial from transport container to the processing station

    International Nuclear Information System (INIS)

    Kothalkar, Chetan; Dey, A.C.

    2005-01-01

    In Technetium Column Generator Production Facility (TCGPF project) of BRIT, a facility for unloading vial containing radioactive liquid sodium molybdate- 99 Mo solution from the transport cask into the processing station and unsealing the vial to transfer the liquid to a storage bottle has been developed. This is specifically conceptualized for safe handling of radioactivity and minimizing the radiation dose exposure to the personnel working at the time of transferring the radioactivity from the transport cask to a place for further processing. The facility, designed to handle around 1850 GBq activity, has two cells enclosed in 102mm thick lead wall and connected by a gravity actuated trolley conveyor. The first cell handles the transport cask carrying the vial-containing radioactivity, which houses two types of vial lifting gadgets assisted by manually operatable tongs. Gadgets use compressed air. In an experiment, it is found that the HDPE vial lifting gadget using suction cup continue to function up to 30-40 minutes after power failure. The experience shows that gadget using 3-point radial gripper to lift the glass vial will remain in grab position, even if the compressed air supply stops. In this facility the dose receivable, while handling radioactivity by the operator, is likely to be negligibly small (approx. 3.15 x 10 -4 mSv per year at the rate four glass vials/week and 2.25 x 10 -4 mSv per year considering at the rate 1 vial/week for HOPE vial transfer). (author)

  7. State of nuclear waste management of German nuclear power stations

    International Nuclear Information System (INIS)

    1983-01-01

    The waste management of nuclear power plants in the Federal Republic of Germany is today prevailing in the public discussion. Objections raised in this connection, e.g. that the nuclear waste management has been omitted from the development of peaceful utilization of nuclear energy or remained insolved, are frequently accepted without examination, and partly spread as facts. This is, however, not the truth: From the outset in 1955 the development of nuclear technology in the Federal Republic of Germany has included investigations of the problems of reprocessing and non-detrimental disposal of radioactive products, and the results have been compiled in a national nuclear waste management concept. (orig.) [de

  8. Retrofitting and operation solid radwaste system Dresden Station, Units 2 and 3

    International Nuclear Information System (INIS)

    Testa, J.; Homer, J.C.

    1982-01-01

    Units 2 and 3 at Dresden Station are twin 794 MW (net) BWR units that became operational in 1970 and 1971. The waste streams are typical of BWR stations, namely, bead resin and filter sludge (powdered resins and diatomaceous earth), evaporator concentrate containing approximately 25% dissolved solids and dry active waste. The original solid radwaste system utilized cement for solidification in open top 55 gallon drums. Remote handling was provided by means of a monorail with moving platforms supporting the drums. A relatively light-weight compactor was used to compact DAW into 55 gallon drums. Difficulties were experienced with this system

  9. Transfer of radioactive waste management expertise from Switzerland to other countries with small nuclear power programmes

    International Nuclear Information System (INIS)

    McKinley, I.; Birkhaeuser, Ph.; Kickmaier, W.; Vomvoris, S.; Zuidema, P.

    2000-01-01

    A legal requirement which coupled demonstration of the feasibility of nuclear waste disposal to the extension of reactor operational licenses beyond 1985 acted to force rapid development of the Swiss radioactive waste management programme. Over a period of almost 30 years and at a cost of approximately 800 M CHF Nagra has become established as a centre of excellence in this field. Resources include highly experienced manpower, literature and databases supporting development of national repositories for L/ILW and HLW/TRU and state-of-the-art R and D infrastructure (including 2 underground laboratories, hot-laboratory facilities at PSI (Paul Scherrer Institute), modelling groups at universities etc.). This paper reviews Nagra's experience and considers various ways in which expertise can be transferred to other small countries to minimise duplication of effort and optimise development of their own national programmes. (author)

  10. Pellet transfer apparatus and method

    International Nuclear Information System (INIS)

    DiGrande, J.T.; Huggins, T.B. Sr.; Lambert, D.V.; Roberts, E.

    1991-01-01

    This patent describes a pellet inspection system having a station for inspecting a predetermined parameter of a pellet. It comprises means for aligning and guiding pellets in a first row to be advanced along a linear path past the pellet inspecting station and in a second row previously advanced along the linear path past the pellet inspecting station; and a transfer mechanism operable for engaging at least one of the pellets in each of the first and second rows and moving from an initial position through a forward stroke to advance the first and second rows of pellets along the liner path such that the inspecting station can inspect the preselected parameter of the pellets in the first row as they are advanced successively , the transfer mechanism being operable for disengaging the pellets and moving through a return stroke relative to the stationary advanced first and second rows of pellets back to the initial position

  11. Wastes in space

    International Nuclear Information System (INIS)

    2011-01-01

    As human space activities have created more wastes on low and high Earth orbits over the past 50 years than the solar system injected meteorites over billions of years, this report gives an overview of this problem. It identifies the origins of these space debris and wastes (launchers, combustion residues, exploitation wastes, out-of-use satellites, accidental explosions, accidental collisions, voluntary destructions, space erosion), and proposes a stock list of space wastes. Then, it distinguishes the situation for the different orbits: low Earth orbit or LEO (traffic, presence of the International Space Station), medium Earth orbits or MEO (traffic, operating satellites, wastes), geostationary Earth orbit or GEO (traffic, operating satellites, wastes). It also discusses wastes and bacteria present on the moon (due to Apollo missions or to crash tests). It evokes how space and nuclear industry is concerned, and discusses the re-entry issue (radioactive boomerang, metallic boomerang). It also indicates elements of international law

  12. 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.

  13. Application of the minicomputer at Genkai Nuclear Power Station

    Energy Technology Data Exchange (ETDEWEB)

    Kitamura, H [Kyushu Electric Power Co., Inc., Fukuoka (Japan)

    1977-03-01

    Genkai Nuclear Power Station introduced a minicomputer system for the data control purpose in addition to a process control computer introduced in the same manner as other PWR nuclear power stations. This system employs two computers; the one for on-line data aquisition, and another for data processing. The control system introduced includes four systems amoung various data control businesses in the nuclear power station. The language used is mainly an assembler language. The first is the meteorological control system which collects, edits and transmits the weather data sent from the observation instruments around the power station. The second is the personal radiation exposure control system which is designed to realize the labor-saving in book-keeping, the speed-up and the improvement of accuracy in the preparation of the reports to the authorities and the head office and the data for exposure control, and the unification of data processing. The third is the waste control system composed of three subsystems of gas, liquid and solid waste control. The fourth is the maintenance and repair control system which gives inputs to the computer according to the classification written in the slips for maintenance and repair, and prepares a number of statistical tables for maintenance control.

  14. Hazardous Waste Research Center

    Data.gov (United States)

    Federal Laboratory Consortium — The U.S. Army Engineer Waterways Experiment Station (WES) is playing a major role in development of technologies for cleanup of toxic and hazardous waste in military...

  15. Aspects of the storage of radioactive waste

    International Nuclear Information System (INIS)

    Nienhuys, K.

    1978-01-01

    The expansion in the number of nuclear power stations in the netherlands is amongst other things, dependent on an acceptable policy for the storage of the waste from the stations. Consequently the idea has developed for storage in a salt-dome. The sub-committee on radioactive waste substances of the Interdepartmental Committee for Nuclear Energy has therefore given a mandate to initiate further research. For the risk analysis over the definitive storage of nuclear waste the sub-comittee produced a report in 1975, entitled 'Safety analysis for the underground storage of nuclear waste in salt-dome outcrops'. The analysis reveals a number of defective features. This makes especially clear that statements about the definitive storage of nuclear waste in salt domes can only be made with a great deal of uncertainty. There is no guarantee that the nuclear waste generated may be stowed away so that it will never return to the ionosphere. The speed whereby the nuclear waste may return would be dependent on a combination of events which cannot generally be calculated or assessed. The long term consequences of an irreversible radioactive contamination of the biosphere is not acceptable. There is insufficient proof that the storage of radioactive waste in salt domes is feasible. (G.C.)

  16. Path Transmissibility Analysis Considering Two Types of Correlations in Hydropower Stations

    Directory of Open Access Journals (Sweden)

    Baoping Zhi

    2013-01-01

    Full Text Available A new vibration model is built by introducing the head-cover vibration transfer path based on a previous analysis of the vertical vibration model for hydropower station units and powerhouses. This research focuses on disturbance- and parameter-related transfer paths in a practical situation. In a complex situation, the application of the stochastic perturbation method is expanded using an algebra synthesis method the Hadamard product, and theoretical analyses, and numerical simulations of transfer paths in the new vibration model are carried out through the expanded perturbation method. The path transfer force, the path transmissibility, and the path disturbance ranges in the frequency domain are provided. The results indicate that the methods proposed in this study can efficiently reduce the disturbance range and can accurately analyze the transfer paths of hydraulic-source vertical vibration in hydropower stations.

  17. Results of special security inspection on improvement of security management setup in Head Office and Tsuruga Nuclear Power Station of the Japan Atomic Power Company and improvement of facilities in Tsuruga Nuclear Power Station

    International Nuclear Information System (INIS)

    1982-01-01

    In connection with the series of accidents in the Tsuruga Nuclear Power Station, the Agency of Natural Resources and Energy had instructed JAPC to make comprehensive inspection on the security management setup and to take improvement measures in the nuclear power station. The results of the subsequent inspection by ANRE confirmed that the improvements made by JAPC are adequate, and the following items are described: improvement of security management setup - communication and reporting in emergency, the management of inspection and maintenance records, work control and supervision in repair, improvement, etc., functional authority and responsibility in maintenance management, operation management, radiation control, personnel education; improvement of facilities - feed water heaters, laundry waste-water filter room, radioactive waste treatment facility, general drainage, concentrated waste liquid storage tanks in newly-built waste treatment building, etc. (J.P.N.)

  18. Decommissioning of multiple-reactor stations: facilitation by sequential decommissioning

    International Nuclear Information System (INIS)

    Moore, E.B.; Smith, R.I.; Wittenbrock, N.G.

    1982-01-01

    Reductions in cost and radiation dose can be achieved for decommissionings at multiple reactor stations because of factors not necessarily present at a single reactor station: reactors of similar design, the opportunity for sequential decommissioning, a site dedicated to nuclear power generation, and the option of either interim or permanent low-level radioactive waste storage facilities onsite. The cost and radiation dose reductions occur because comprehensive decommissioning planning need only be done once, because the labor force is stable and need only be trained once, because there is less handling of radioactive wastes, and because central stores, equipment, and facilities may be used. The cost and radiation dose reductions are sensitive to the number and types of reactors on the site, and to the alternatives selected for decommissioning. 3 tables

  19. The Optimization Based Dynamic and Cyclic Working Strategies for Rechargeable Wireless Sensor Networks with Multiple Base Stations and Wireless Energy Transfer Devices

    Science.gov (United States)

    Ding, Xu; Han, Jianghong; Shi, Lei

    2015-01-01

    In this paper, the optimal working schemes for wireless sensor networks with multiple base stations and wireless energy transfer devices are proposed. The wireless energy transfer devices also work as data gatherers while charging sensor nodes. The wireless sensor network is firstly divided into sub networks according to the concept of Voronoi diagram. Then, the entire energy replenishing procedure is split into the pre-normal and normal energy replenishing stages. With the objective of maximizing the sojourn time ratio of the wireless energy transfer device, a continuous time optimization problem for the normal energy replenishing cycle is formed according to constraints with which sensor nodes and wireless energy transfer devices should comply. Later on, the continuous time optimization problem is reshaped into a discrete multi-phased optimization problem, which yields the identical optimality. After linearizing it, we obtain a linear programming problem that can be solved efficiently. The working strategies of both sensor nodes and wireless energy transfer devices in the pre-normal replenishing stage are also discussed in this paper. The intensive simulations exhibit the dynamic and cyclic working schemes for the entire energy replenishing procedure. Additionally, a way of eliminating “bottleneck” sensor nodes is also developed in this paper. PMID:25785305

  20. The optimization based dynamic and cyclic working strategies for rechargeable wireless sensor networks with multiple base stations and wireless energy transfer devices.

    Science.gov (United States)

    Ding, Xu; Han, Jianghong; Shi, Lei

    2015-03-16

    In this paper, the optimal working schemes for wireless sensor networks with multiple base stations and wireless energy transfer devices are proposed. The wireless energy transfer devices also work as data gatherers while charging sensor nodes. The wireless sensor network is firstly divided into sub networks according to the concept of Voronoi diagram. Then, the entire energy replenishing procedure is split into the pre-normal and normal energy replenishing stages. With the objective of maximizing the sojourn time ratio of the wireless energy transfer device, a continuous time optimization problem for the normal energy replenishing cycle is formed according to constraints with which sensor nodes and wireless energy transfer devices should comply. Later on, the continuous time optimization problem is reshaped into a discrete multi-phased optimization problem, which yields the identical optimality. After linearizing it, we obtain a linear programming problem that can be solved efficiently. The working strategies of both sensor nodes and wireless energy transfer devices in the pre-normal replenishing stage are also discussed in this paper. The intensive simulations exhibit the dynamic and cyclic working schemes for the entire energy replenishing procedure. Additionally, a way of eliminating "bottleneck" sensor nodes is also developed in this paper.

  1. Setting of cesium residual ratio of molten solidified waste produced in Japan Atomic Power Company Tokai and Tokai No.2 Power Stations

    International Nuclear Information System (INIS)

    2013-02-01

    JNES investigated the appropriateness of a view of the Japan Nuclear Fuel Co. on cesium residual content and the radioactivity measurement precision regarding the molten solidified (with lowered inorganic salt used) radioactive wastes which were produced from Japan Atomic Power Company Tokai and Tokai No. 2 Power Stations. Based on the written performance report from the request and past disposal confirmation experience, a view of the JNFC is confirmed as appropriate that setting of 15% cesium residual ratio for molten solidified with volume ratio larger than 4% and less than 10% cases. (S. Ohno)

  2. DETERMINING THE STUDENTS’ VIEWS TOWARDS THE LEARNING STATIONS DEVELOPED FOR THE ENVIRONMENTAL EDUCATION

    Directory of Open Access Journals (Sweden)

    Cem Gerçek

    2016-02-01

    Full Text Available This study aims to increase awareness in students in relation to environmental consciousness. Therefore, the prepared presentations and the adapted learning stations were used to create awareness of students in the out-of-the-school learning environment supported by the municipality of a county in Ankara the capital city of Turkey. Learning stations serve to people’s individual study. The basic goal here is to develop higher order skills and to make sure that students work in stations according to their abilities in a pre-determined order. The study group was composed of volunteering 15 fifth graders of a private school in Ankara. Firstly, the content to be applied in the study was developed. Prior to the application, a readiness presentation was made so as to raise students’ interest and awareness in terms of the importance of waste and recycling the waste. As a conclusion of the current study, it may be said that students’ interest in and awareness of the environment and collecting the waste developed. Enlarging this pilot project and applying it to bigger groups is important in terms of the success of the educational activities for separating the waste and in terms of the durability of the relevant behavior.

  3. Aerospace vehicle water-waste management

    Science.gov (United States)

    Pecoraro, J. N.

    1973-01-01

    The collection and disposal of human wastes, such as urine and feces, in a spacecraft environment are performed in an aesthetic and reliable manner to prevent degradation of crew performance. The waste management system controls, transfers, and processes materials such as feces, emesis, food residues, used expendables, and other wastes. The requirements, collection, transport, and waste processing are described.

  4. Solid Waste Management Practices in the Eastern Province of Saudi Arabia

    Science.gov (United States)

    Khan, Hasin U.; Husain, Tahir; Khan, Suhail M.

    1987-11-01

    Solid waste management practices in the Eastern Province of Saudi Arabia are reviewed. The officials of various municipalities and agencies responsible for collecting and disposing of municipal waste were interviewed. The refuse generation rate found is in the range of 1.61 2.72 kg per capita per day. The refuse composition data indicate a high percentage of glass, metals, and wood. For storage purposes, 0.2-m3 barrels are used in residential areas and 0.75 to 1.50 m3-capacity containers are used in commerical areas. The present solid-waste collection system is labor-intensive, and a significant part of the budget is spent on collection and haul operations. The unit collection and haul cost is much higher than the unit disposal cost of refuse. The direct haul of refuse is the common practice, and the use of transfer stations has not yet been considered. It is also observed that the disposal methods used at these sites are not in line with modern techniques for refuse disposal. Landfilling and combined burning and landfilling are the common disposal methods at all the sites.

  5. Inauguration of the ANDRA atmospheric station in Houdelaincourt; Inauguration de la station atmospherique de l'Andra a Houdelaincourt

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2011-07-01

    This document briefly presents the atmospheric monitoring station inaugurated in Houdelaincourt (Meuse) and installed by the ANDRA within the frame of the ICOS (Integrated Carbon Observing System) European infrastructure project which aims at developing air and greenhouse gas monitoring over Europe. It also recalls that this station is part of a set of means of monitoring, experimentation and protection of the environment within the frame of high and medium level nuclear waste storage project in Meuse and Haute-Marne. The document also proposes brief presentations of the different actors involved in the creation of this station: the LSCE (laboratory of sciences of climate and environment), Meteo-France, Air Lorraine, the IRSN, and the LGGE (laboratory of glaciology and geophysics of the environment)

  6. Remaining Sites Verification Package for 132-D-3, 1608-D Effluent Pumping Station. Attchment to Waste Site Reclassification Form 2005-033

    International Nuclear Information System (INIS)

    Carlson, R.A.

    2006-01-01

    Decommissioning and demolition of the 132-D-3 site, 1608-D Effluent Pumping Station was performed in 1986. Decommissioning included removal of equipment, water, and sludge for disposal as radioactive waste. The at- and below-grade structure was demolished to at least 1 m below grade and the resulting rubble buried in situ. The area was backfilled to grade with at least 1 m of clean fill and contoured to the surrounding terrain. Residual concentrations support future land uses that can be represented by a rural-residential scenario and pose no threat to groundwater or the Columbia River based on RESRAD modeling

  7. Radioactive waste material melter apparatus

    Science.gov (United States)

    Newman, D.F.; Ross, W.A.

    1990-04-24

    An apparatus for preparing metallic radioactive waste material for storage is disclosed. The radioactive waste material is placed in a radiation shielded enclosure. The waste material is then melted with a plasma torch and cast into a plurality of successive horizontal layers in a mold to form a radioactive ingot in the shape of a spent nuclear fuel rod storage canister. The apparatus comprises a radiation shielded enclosure having an opening adapted for receiving a conventional transfer cask within which radioactive waste material is transferred to the apparatus. A plasma torch is mounted within the enclosure. A mold is also received within the enclosure for receiving the melted waste material and cooling it to form an ingot. The enclosure is preferably constructed in at least two parts to enable easy transport of the apparatus from one nuclear site to another. 8 figs.

  8. Radioactive waste material melter apparatus

    International Nuclear Information System (INIS)

    Newman, D.F.; Ross, W.A.

    1990-01-01

    An apparatus for preparing metallic radioactive waste material for storage is disclosed. The radioactive waste material is placed in a radiation shielded enclosure. The waste material is then melted with a plasma torch and cast into a plurality of successive horizontal layers in a mold to form a radioactive ingot in the shape of a spent nuclear fuel rod storage canister. The apparatus comprises a radiation shielded enclosure having an opening adapted for receiving a conventional transfer cask within which radioactive waste material is transferred to the apparatus. A plasma torch is mounted within the enclosure. A mold is also received within the enclosure for receiving the melted waste material and cooling it to form an ingot. The enclosure is preferably constructed in at least two parts to enable easy transport of the apparatus from one nuclear site to another. 8 figs

  9. Effect of heterogeneity and anisotropy related to the construction method on transfer processes in waste rock piles.

    Science.gov (United States)

    Lahmira, Belkacem; Lefebvre, René; Aubertin, Michel; Bussière, Bruno

    2016-01-01

    Waste rock piles producing acid mine drainage (AMD) are partially saturated systems involving multiphase (gas and liquid) flow and coupled transfer processes. Their internal structure and heterogeneous properties are inherited from their wide-ranging material grain sizes, their modes of deposition, and the underlying topography. This paper aims at assessing the effect of physical heterogeneity and anisotropy of waste rock piles on the physical processes involved in the generation of AMD. Generic waste rock pile conditions were represented with the numerical simulator TOUGH AMD based on those found at the Doyon mine waste rock pile (Canada). Models included four randomly distributed material types (coarse, intermediate, fine and very fine-grained). The term "randomly" as used in this study means that the vertical profile and spatial distribution of materials in waste rock piles (internal structure) defy stratigraphy principles applicable to natural sediments (superposition and continuity). The materials have different permeability and capillary properties, covering the typical range of materials found in waste rock piles. Anisotropy with a larger horizontal than vertical permeability was used to represent the effect of pile construction by benches, while the construction by end-dumping was presumed to induce a higher vertical than horizontal permeability. Results show that infiltrated precipitation preferentially flows in fine-grained materials, which remain almost saturated, whereas gas flows preferentially through the most permeable coarse materials, which have higher volumetric gas saturation. Anisotropy, which depends on pile construction methods, often controls global gas flow paths. Construction by benches favours lateral air entry close to the pile slope, whereas end-dumping leads to air entry from the surface to the interior of the pile by secondary gas convection cells. These results can be useful to construct and rehabilitate waste rock piles to minimize

  10. Study on disaster waste around Fukushima Daiichi NPS

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2012-08-15

    Extreme difficulties exists in Fukushima Prefecture in disposing of waste generated from the tsunami disaster (hereinafter referred to as disaster waste) and contaminated with radioactive material released from the crippled Fukushima Daiichi Nuclear Power Station. Although the waste should be treated according to the level of radioactivity, there were only air dose rates and radionuclide analyses of soil due to monitoring around the Fukushima Daiichi Nuclear Power Station and there had been no information on the radioactivity concentration of the disaster waste. The radioactivity concentration of the disaster waste was investigated by sampling measurement and in-situ Ge measurement at 20 temporary disaster waste storages in Fukushima Prefecture excluding the evacuation zone and 'deliberate evacuation zone.' JNES carried out tins investigation upon a request from die Nuclear and Industrial Safety Agency. The investigation revealed that the measured radioactivity concentrations of the disaster waste lumps were enveloped within the soil monitoring readings in Fukushima Prefecture and also within a correlated curve between the air dose rates obtained from air dose rate readings around the disaster waste and the radioactivity concentrations of it. Based on the results of this study, JNES compiled a manual on measurement technique for contaminated disaster waste. (author)

  11. Study on disaster waste around Fukushima Daiichi NPS

    International Nuclear Information System (INIS)

    2012-01-01

    Extreme difficulties exists in Fukushima Prefecture in disposing of waste generated from the tsunami disaster (hereinafter referred to as disaster waste) and contaminated with radioactive material released from the crippled Fukushima Daiichi Nuclear Power Station. Although the waste should be treated according to the level of radioactivity, there were only air dose rates and radionuclide analyses of soil due to monitoring around the Fukushima Daiichi Nuclear Power Station and there had been no information on the radioactivity concentration of the disaster waste. The radioactivity concentration of the disaster waste was investigated by sampling measurement and in-situ Ge measurement at 20 temporary disaster waste storages in Fukushima Prefecture excluding the evacuation zone and 'deliberate evacuation zone.' JNES carried out tins investigation upon a request from die Nuclear and Industrial Safety Agency. The investigation revealed that the measured radioactivity concentrations of the disaster waste lumps were enveloped within the soil monitoring readings in Fukushima Prefecture and also within a correlated curve between the air dose rates obtained from air dose rate readings around the disaster waste and the radioactivity concentrations of it. Based on the results of this study, JNES compiled a manual on measurement technique for contaminated disaster waste. (author)

  12. Food waste collection and recycling for value-added products: potential applications and challenges in Hong Kong.

    Science.gov (United States)

    Lo, Irene M C; Woon, Kok Sin

    2016-04-01

    About 3600 tonnes food waste are discarded in the landfills in Hong Kong daily. It is expected that the three strategic landfills in Hong Kong will be exhausted by 2020. In consideration of the food waste management environment and community needs in Hong Kong, as well as with reference to the food waste management systems in cities such as Linköping in Sweden and Oslo in Norway, a framework of food waste separation, collection, and recycling for food waste valorization is proposed in this paper. Food waste can be packed in an optic bag (i.e., a bag in green color), while the residual municipal solid waste (MSW) can be packed in a common plastic bag. All the wastes are then sent to the refuse transfer stations, in which food waste is separated from the residual MSW using an optic sensor. On the one hand, the sorted food waste can be converted into valuable materials (e.g., compost, swine feed, fish feed). On the other hand, the sorted food waste can be sent to the proposed Organic Waste Treatment Facilities and sewage treatment works for producing biogas. The biogas can be recovered to produce electricity and city gas (i.e., heating fuel for cooking purpose). Due to the challenges faced by the value-added products in Hong Kong, the biogas is recommended to be upgraded as a biogas fuel for vehicle use. Hopefully, the proposed framework will provide a simple and effective approach to food waste separation at source and promote sustainable use of waste to resource in Hong Kong.

  13. Mass transfer from penetrations in waste containers

    International Nuclear Information System (INIS)

    Pescatore, C.; Sastre, C.

    1987-01-01

    Recent studies have indicated that localized corrosion of a relatively small area of a waste container may impair the containment function to such an extent that larger releases may be possible than from the bare waste form. This would take place when a large number of holes coexist on the container while their concentration fields do not interact significantly with each other. After performing a steady state analysis of the release from a hole, it is shown that much fewer independent holes can coexist on a container surface than previously estimated. The calculated radionuclide release from multiple independent holes must be changed accordingly. Previous analyses did not proceed to a correct application of the linear superposition principle. This resulted in unacceptable physical conclusions and undue strain on the performance assessment necessary for a container licensing procedure. The paper also analyzes the steady state release from penetrations of finite length and whose concentration fields interact with one another. The predicted release from these penetrations is lower than the previously calculated release from holes of zero thickness. It is concluded here that the steady-state release from multiple holes on a waste container can not exceed the release from the bare waste form and that multiple perforations need not be a serious liability to container performance. 8 refs., 3 figs., 1 tab

  14. Preliminary ECLSS waste water model

    Science.gov (United States)

    Carter, Donald L.; Holder, Donald W., Jr.; Alexander, Kevin; Shaw, R. G.; Hayase, John K.

    1991-01-01

    A preliminary waste water model for input to the Space Station Freedom (SSF) Environmental Control and Life Support System (ECLSS) Water Processor (WP) has been generated for design purposes. Data have been compiled from various ECLSS tests and flight sample analyses. A discussion of the characterization of the waste streams comprising the model is presented, along with a discussion of the waste water model and the rationale for the inclusion of contaminants in their respective concentrations. The major objective is to establish a methodology for the development of a waste water model and to present the current state of that model.

  15. Double Shell Tank (DST) Transfer Pump Subsystem Specification

    International Nuclear Information System (INIS)

    LESHIKAR, G.A.

    2000-01-01

    This specification establishes the performance requirements and provides references to the requisite codes and standards to be applied to the Double-Shell Tank (DST) Transfer Pump Subsystem which supports the first phase of Waste Feed Delivery (WFD). This specification establishes the performance requirements and provides the references to the requisite codes and standards to be applied during the design of the DST Transfer Pump Subsystem that supports the first phase of (WFD). The DST Transfer Pump Subsystem consists of a pump for supernatant and or slurry transfer for the DSTs that will be retrieved during the Phase 1 WFD operations. This system is used to transfer low-activity waste (LAW) and high-level waste (HLW) to designated DST staging tanks. It also will deliver blended LAW and HLW feed from these staging tanks to the River Protection Project (RPP) Privatization Contractor facility where it will be processed into an immobilized waste form. This specification is intended to be the basis for new projects/installations (W-521, etc.). This specification is not intended to retroactively affect previously established project design criteria without specific direction by the program

  16. Application to transfer radioactive waste to the Nevada Test Site

    International Nuclear Information System (INIS)

    1992-01-01

    All waste described in this application has been, and will be, generated by LANL in support of the nuclear weapons test program at the NTS. All waste originates on the NTS. DOE Order 5820.2A states that low-level radioactive waste shall be disposed of at the site where it is generated, when practical. Since the waste is produced at the NTS, it is cost effective for LANL to dispose of the waste at the NTS

  17. Thermophysical and heat transfer properties of phase change material candidate for waste heat transportation system

    Science.gov (United States)

    Kaizawa, Akihide; Maruoka, Nobuhiro; Kawai, Atsushi; Kamano, Hiroomi; Jozuka, Tetsuji; Senda, Takeshi; Akiyama, Tomohiro

    2008-05-01

    A waste heat transportation system trans-heat (TH) system is quite attractive that uses the latent heat of a phase change material (PCM). The purpose of this paper is to study the thermophysical properties of various sugars and sodium acetate trihydrate (SAT) as PCMs for a practical TH system and the heat transfer property between PCM selected and heat transfer oil, by using differential scanning calorimetry (DSC), thermogravimetry-differential thermal analysis (TG-DTA) and a heat storage tube. As a result, erythritol, with a large latent heat of 344 kJ/kg at melting point of 117°C, high decomposition point of 160°C and excellent chemical stability under repeated phase change cycles was found to be the best PCM among them for the practical TH system. In the heat release experiments between liquid erythritol and flowing cold oil, we observed foaming phenomena of encapsulated oil, in which oil droplet was coated by solidification of PCM.

  18. Transfer of test samples and wastes between post-irradiation test facilities (FMF, AGF, MMF)

    International Nuclear Information System (INIS)

    Ishida, Yasukazu; Suzuki, Kazuhisa; Ebihara, Hikoe; Matsushima, Yasuyoshi; Kashiwabara, Hidechiyo

    1975-02-01

    Wide review is given on the problems associated with the transfer of test samples and wastes between post-irradiation test facilities, FMF (Fuel Monitoring Facility), AGF (Alpha Gamma Facility), and MMF (Material Monitoring Facility) at the Oarai Engineering Center, PNC. The test facilities are connected with the JOYO plant, an experimental fast reactor being constructed at Oarai. As introductory remarks, some special features of transferring irradiated materials are described. In the second part, problems on the management of nuclear materials and radio isotopes are described item by item. In the third part, the specific materials that are envisaged to be transported between JOYO and the test facilities are listed together with their geometrical shapes, dimensions, etc. In the fourth part, various routes and methods of transportation are explained with many block charts and figures. Brief explanation with lists and drawings is also given to transportation casks and vessels. Finally, some future problems are discussed, such as the prevention of diffusive contamination, ease of decontamination, and the identification of test samples. (Aoki, K.)

  19. A hazard and probabilistic safety analysis of a high-level waste transfer process

    International Nuclear Information System (INIS)

    Bott, T.F.; Sasser, M.K.

    1996-01-01

    This paper describes a safety analysis of a transfer process for high-level radioactive and toxic waste. The analysis began with a hazard assessment that used elements of What If, Checklist, Failure Modes and Effects Analysis, and Hazards and Operability Study (HAZOP) techniques to identify and rough-in accident sequences. Based on this preliminary analysis, the most significant accident sequences were developed further using event trees. Quantitative frequency estimates for the accident sequences were based on operational data taken from the historical record of the site where the process is performed. Several modeling challenges were encountered in the course of the study. These included linked initiating and accident progression events, fire propagation modeling, accounting for administrative control violations, and handling mission-phase effects

  20. Waste Preparation and Transport Chemistry: Results of the FY 2002 Studies

    Energy Technology Data Exchange (ETDEWEB)

    Hunt, R.D.

    2003-07-10

    The initial step in the remediation of nuclear waste stored at Hanford and the Savannah River Site (SRS) involves the retrieval and transfer of the waste to another tank or to a treatment facility. The retrieved waste can range from a filtered supernatant to a slurry. Nearly all of the recent solid formation problems encountered during waste transfers and subsequent treatment steps have involved decanted or filtered supernatants. Problems with slurry transfers have not yet surfaced, because tank farm operations at Hanford and the SRS have focused primarily on supernatant transfers and treatment. For example, the interim stabilization program at Hanford continues to reduce the level of supernatants and interstitial liquids in its single-shell tanks through saltwell pumping of filtered liquid. In addition, at present, the cross-site transfer lines at Hanford can be used only to transfer liquids. Another reason for fewer problems with slurry transfers involves the additions of large quantities of dilution water prior to the transfer. When the waste is transferred, a drop in temperature is expected because most transfer lines are not heated. However, the dilution water reduces or eliminates solid formation caused by this temperature drop. In sharp contrast, decanted or filtered supernatants are near or at saturation for certain compounds. In such cases, tank farm operators must continue to evaporate their liquid waste since available tank space is quite limited. Solid formation can occur when the temperature of saturated solutions drops even slightly. The evaporation step can also lead to the formation of problematic solids. At the SRS, the evaporation of a relatively dilute waste stream was suspended due to the formation of deposits in the evaporator system. Therefore, small drops in temperature or evaporation can lead to problematic solid formations.

  1. Waste Preparation and Transport Chemistry: Results of the FY 2002 Studies

    International Nuclear Information System (INIS)

    Hunt, R.D.

    2003-01-01

    The initial step in the remediation of nuclear waste stored at Hanford and the Savannah River Site (SRS) involves the retrieval and transfer of the waste to another tank or to a treatment facility. The retrieved waste can range from a filtered supernatant to a slurry. Nearly all of the recent solid formation problems encountered during waste transfers and subsequent treatment steps have involved decanted or filtered supernatants. Problems with slurry transfers have not yet surfaced, because tank farm operations at Hanford and the SRS have focused primarily on supernatant transfers and treatment. For example, the interim stabilization program at Hanford continues to reduce the level of supernatants and interstitial liquids in its single-shell tanks through saltwell pumping of filtered liquid. In addition, at present, the cross-site transfer lines at Hanford can be used only to transfer liquids. Another reason for fewer problems with slurry transfers involves the additions of large quantities of dilution water prior to the transfer. When the waste is transferred, a drop in temperature is expected because most transfer lines are not heated. However, the dilution water reduces or eliminates solid formation caused by this temperature drop. In sharp contrast, decanted or filtered supernatants are near or at saturation for certain compounds. In such cases, tank farm operators must continue to evaporate their liquid waste since available tank space is quite limited. Solid formation can occur when the temperature of saturated solutions drops even slightly. The evaporation step can also lead to the formation of problematic solids. At the SRS, the evaporation of a relatively dilute waste stream was suspended due to the formation of deposits in the evaporator system. Therefore, small drops in temperature or evaporation can lead to problematic solid formations

  2. VLBI and GPS-based Time-Transfer Using CONT08 Data

    Science.gov (United States)

    Rieck, Carsten; Haas, Ruediger; Jaldehag, Kenneth; Jahansson, Jan

    2010-01-01

    One important prerequisite for geodetic Very Long Baseline Interferometry (VLBI) is the use of frequency standards with excellent short term stability. This makes VLBI stations, which are often co-located with Global Navigation Satellite System (GNSS) receiving stations, interesting for studies of time- and frequency-transfer techniques. We present an assessment of VLBI time-transfer based on the data of the two week long consecutive IVS CONT08 VLBI campaign by using GPS Carrier Phase (GPSCP). CONT08 was a 15 day long campaign in August 2008 that involved eleven VLBI stations on five continents. For CONT08 we estimated the worst case VLBI frequency link stability between the stations of Onsala and Wettzell to 1e-15 at one day. Comparisons with GPSCP confirm the VLBI results. We also identify time-transfer related challenges of the VLBI technique as used today.

  3. Exergo-economic analysis of finned tube for waste heat recovery including phase change heat transfer

    International Nuclear Information System (INIS)

    Wu, Shuang Ying; Jiu, Jing Rui; Xiao, Lan; Li, You Rong; Liu, Chao; Xu, Jin Liang

    2013-01-01

    In this paper, an exergo-economic criterion, i.e. the net profit per unit transferred heat load, is established from the perspective of exergy recovery to evaluate the performance of finned tube used in waste heat recovery. Also, the dimensionless exergy change number is introduced to investigate the effect of the flow (mechanical) exergy loss rate on the recovered thermal exergy. Selecting R245fa as a working fluid and exhaust flue gas as a heat source, the effects of the internal Reynolds number Re_i, the external Reynolds number Re_o , the unit cost of thermal exergy ε_q , the geometric parameter of finned tube η_oβ and the phase change temperature T_v etc. on the performance of finned tube are discussed in detail. The results show that the higher T_v and η_oβ, and lower Re_i may lead to the negligible flow(mechanical) exergy loss rate. There exists an optimal value of Re_i where the net profit per unit transferred heat load peaks, while the variations of Re_o, ε_q and T_v cause monotonic change of the net profit per unit transferred heat load. The phase change temperature exerts relatively greater influence on the exergo-economic performance of finned tube in comparison with other parameters. And there exists a critical phase change temperature, where the net profit per unit transferred heat load is equal to zero.

  4. Nuclear waste storage container with metal matrix

    Science.gov (United States)

    Sump, Kenneth R.

    1978-01-01

    The invention relates to a storage container for high-level waste having a metal matrix for the high-level waste, thereby providing greater impact strength for the waste container and increasing heat transfer properties.

  5. Nuclear waste storage container with metal matrix

    International Nuclear Information System (INIS)

    Sump, K.R.

    1978-01-01

    The invention relates to a storage container for high-level waste having a metal matrix for the high-level waste, thereby providing greater impact strength for the waste container and increasing heat transfer properties

  6. Component Data Base for Space Station Resistojet Auxiliary Propulsion

    Science.gov (United States)

    Bader, Clayton H.

    1988-01-01

    The resistojet was baselined for Space Station auxiliary propulsion because of its operational versatility, efficiency, and durability. This report was conceived as a guide to designers and planners of the Space Station auxiliary propulsion system. It is directed to the low thrust resistojet concept, though it should have application to other station concepts or systems such as the Environmental Control and Life Support System (ECLSS), Manufacturing and Technology Laboratory (MTL), and the Waste Fluid Management System (WFMS). The information will likely be quite useful in the same capacity for other non-Space Station systems including satellite, freeflyers, explorers, and maneuvering vehicles. The report is a catalog of the most useful information for the most significant feed system components and is organized for the greatest convenience of the user.

  7. Sizewell 'B' power station public inquiry: CEGB proof of evidence

    International Nuclear Information System (INIS)

    Gregory, A.R.

    1982-11-01

    The procedure for decommissioning a CEGB nuclear power station is described. Regulatory and licensing procedures in the UK are first listed. The principal sources of radioactivity in the station after final shutdown are classified. The three stages of the decommissioning procedure are then described. Finally the following topics are dealt with briefly: the management of decommissioning wastes, radiological protection during the operation, possible faults arising having radiological significance, design for decommissioning and costs. (U.K.)

  8. The Improvement on the Xinjiekou Subway Transfer Channel of Nanjing

    Science.gov (United States)

    Xu, X. D.; Zheng, C. J.

    The subway, which is an effective way to alleviate the traffic congestion, has gradually been constructed in many cities. With the completion of the construction, the transfer station will become the factor that affects the efficiency of the whole transport network. Based on investigation and analysis of the present situation of the passenger flow, the essay will make a prediction with the multiple linear regression and put forward two kinds of transfer channel improvement schemes for xinjiekou transfer station.

  9. A new MV bus transfer scheme for nuclear power plants

    International Nuclear Information System (INIS)

    Chang, C.K.

    2015-01-01

    The auxiliary power system of many generating stations consists of offsite power supply system and onsite power supply system, including emergency diesel generators (EDG) to provide secure power to auxiliary loads. If a normal power supply fails to supply power, then the power source is transferred to a standby power supply. In the case of nuclear power plants (NPP), the unit auxiliary transformer (UAT) and standby auxiliary transformer (SAT) - or station service transformer - are installed and powered from 2 offsite power circuits to meet regulatory requirements. The transfer methods of a motor bus from a normal source to a standby source used in power generating stations are fast bus transfer, in-phase transfer, or residual transfer. Fast bus transfer method is the most popular and residual voltage transfer method that is used as a backup in medium voltage buses in general. The use of the advanced technology like open circuit voltage prediction and digital signal processing algorithms can improve the reliability of fast transfer scheme. However, according to the survey results of the recent operation records in nuclear power plants, there were many instances where the fast transfer scheme has failed. To assure bus transfer in any conditions and circumstances, un-interruptible bus transfer scheme utilizing the state of the art medium voltage UPS (Un-interruptible Power Supply) is discussed and elaborated

  10. Radioactive Waste Repositories Administration - SURAO

    International Nuclear Information System (INIS)

    Kucerka, M.

    1998-01-01

    The Atomic Act specifies, among other things, responsibilities of the government in the field of safe disposal of radioactive wastes. To satisfy this responsibility, the Ministry of Industry and Trade has established the Radioactive Waste Repositories Administration (SURAO). SURAO's major responsibilities include: (a) the preparation, construction, commissioning, operation, and decommissioning of radioactive waste repositories and the monitoring of their environmental impacts; (b) radioactive waste management; (c) spent or irradiated nuclear fuel processing into a form suitable for storage/disposal or reuse; (d) record-keeping of received radioactive wastes and their producers; (e) administration of fund transfers as stipulated by the Atomic Act, Article 27; (f) development of proposals for specification of fees to be paid to the Nuclear Account; (g) responsibility for and coordination of research and development in the field of radioactive waste handling and management; (h) supervision of licensees' margin earmarked for the decommissioning of their facilities; (i) providing services in radioactive waste handling and management; (j) handling and management of radioactive wastes that have been transferred to the Czech Republic from abroad and cannot be sent back; (k) interim administration of radioactive wastes that have become state property. The Statute of the Administration is reproduced in full. (P.A.)

  11. Taiwan industrial cooperation program technology transfer for low-level radioactive waste final disposal - phase I.

    Energy Technology Data Exchange (ETDEWEB)

    Knowlton, Robert G.; Cochran, John Russell; Arnold, Bill Walter; Jow, Hong-Nian; Mattie, Patrick D.; Schelling, Frank Joseph Jr. (; .)

    2007-01-01

    Sandia National Laboratories and the Institute of Nuclear Energy Research, Taiwan have collaborated in a technology transfer program related to low-level radioactive waste (LLW) disposal in Taiwan. Phase I of this program included regulatory analysis of LLW final disposal, development of LLW disposal performance assessment capabilities, and preliminary performance assessments of two potential disposal sites. Performance objectives were based on regulations in Taiwan and comparisons to those in the United States. Probabilistic performance assessment models were constructed based on limited site data using software including GoldSim, BLT-MS, FEHM, and HELP. These software codes provided the probabilistic framework, container degradation, waste-form leaching, groundwater flow, radionuclide transport, and cover infiltration simulation capabilities in the performance assessment. Preliminary performance assessment analyses were conducted for a near-surface disposal system and a mined cavern disposal system at two representative sites in Taiwan. Results of example calculations indicate peak simulated concentrations to a receptor within a few hundred years of LLW disposal, primarily from highly soluble, non-sorbing radionuclides.

  12. Tank waste remediation system dangerous waste training plan

    International Nuclear Information System (INIS)

    POHTO, R.E.

    1999-01-01

    This document outlines the dangerous waste training program developed and implemented for all Treatment, Storage, and Disposal (TSD) Units operated by Lockheed Martin Hanford Corporation (LMHC) Tank Waste Remediation System (TWRS) in the Hanford 200 East, 200 West and 600 Areas and the <90 Day Accumulation Area at 209E. Operating TSD Units operated by TWRS are: the Double-Shell Tank (DST) System (including 204-AR Waste Transfer Building), the 600 Area Purgewater Storage and the Effluent Treatment Facility. TSD Units undergoing closure are: the Single-Shell Tank (SST) System, 207-A South Retention Basin, and the 216-B-63 Trench

  13. Environmental radiological studies downstream from Rancho Seco Nuclear Power Generating Station

    International Nuclear Information System (INIS)

    Noshkin, V.E.; Wong, K.M.; Eagle, R.J.; Dawson, J.W.; Brunk, J.L.; Jokela, T.A.

    1985-01-01

    This report summarizes the information compiled in 1984 while assessing the environmental impact of radionuclides in aquatic releases from the Rancho Seco Nuclear Power Generating Station. Gamma-emitting radionuclides discharged since 1981 are found in many of the dietary components derived from the creeks receiving the effluent wastewater. Some soils and crops are found to contain radionuclides that originate from the contaminated water that was transferred to land during the irrigation season. 134 Cs and 137 Cs are the primary gamma-emitting radionuclides detected in the edible flesh of fish from the creeks. Concentrations in the flesh of fish decreased exponentially with distance from the plant. No significant differences in the 137 Cs activity were found between male and female fish of equal size, but concentrations may vary in fish of different size, with the season and diet. 21% of the total 137 Cs and 134 Cs discharged between 1981 and 1984 is associated with the creek sediments to a distance of 27 km from the plant. Fractions of the missing inventory have been transferred to land during the irrigation season or to downstream regions more distant than 27 km from the plant. The radiocesium content of the sediments in 1984 decreased significantly in a downstream direction, much in the same manner as concentrations decreased in fish. Radioactivity originating from the plant was not above detection limits in any terrestrial food item sampled beyond 6.5 km from the plant. Based on the usage factors provided by individuals interviewed in a 1984 survey, the fish and aquatic-organism ingestion pathway contributed the largest radiological dose to humans utilizing products contaminated with the radionuclides in the liquid wastes discharged from the Rancho Seco Nuclear Power Generating Station in 1984

  14. Waste Receiving and Processing Module 2A waste certification strategy

    International Nuclear Information System (INIS)

    LeClair, M.D.; Pottmeyer, J.A.; Hyre, R.A.

    1994-01-01

    This document addresses the certification of Mixed Low Level Waste (MLLW) that will be treated in the Waste Receiving and Processing Facility Module 2A (WRAP 2A) and is destined for disposal in the MLLW trench of the Low Level Burial Grounds (LLBG). The MLLW that will be treated in WRAP 2A contains land disposal restricted and radioactive constituents. Certification of the treated waste is dependent on numerous waste management activities conducted throughout the WRAP 2A operation. These activities range from waste treatability testing conducted prior to WRAP 2A waste acceptance to overchecking final waste form quality prior to transferring waste to disposal. This document addresses the high level strategies and methodologies for certifying the final waste form. Integration among all design and verification activities that support final waste form quality assurance is also discussed. The information generated from this effort may directly support other ongoing activities including the WRAP 2A Waste Characterization Study, WRAP 2A Waste Analysis Plan development, Sample Plan development, and the WRAP 2A Data Management System functional requirements definition

  15. Mixing Modeling Analysis For SRS Salt Waste Disposition

    International Nuclear Information System (INIS)

    Lee, S.

    2011-01-01

    Nuclear waste at Savannah River Site (SRS) waste tanks consists of three different types of waste forms. They are the lighter salt solutions referred to as supernate, the precipitated salts as salt cake, and heavier fine solids as sludge. The sludge is settled on the tank floor. About half of the residual waste radioactivity is contained in the sludge, which is only about 8 percentage of the total waste volume. Mixing study to be evaluated here for the Salt Disposition Integration (SDI) project focuses on supernate preparations in waste tanks prior to transfer to the Salt Waste Processing Facility (SWPF) feed tank. The methods to mix and blend the contents of the SRS blend tanks were evalutaed to ensure that the contents are properly blended before they are transferred from the blend tank such as Tank 50H to the SWPF feed tank. The work consists of two principal objectives to investigate two different pumps. One objective is to identify a suitable pumping arrangement that will adequately blend/mix two miscible liquids to obtain a uniform composition in the tank with a minimum level of sludge solid particulate in suspension. The other is to estimate the elevation in the tank at which the transfer pump inlet should be located where the solid concentration of the entrained fluid remains below the acceptance criterion (0.09 wt% or 1200 mg/liter) during transfer operation to the SWPF. Tank 50H is a Waste Tank that will be used to prepare batches of salt feed for SWPF. The salt feed must be a homogeneous solution satisfying the acceptance criterion of the solids entrainment during transfer operation. The work described here consists of two modeling areas. They are the mixing modeling analysis during miscible liquid blending operation, and the flow pattern analysis during transfer operation of the blended liquid. The modeling results will provide quantitative design and operation information during the mixing/blending process and the transfer operation of the blended

  16. Solid waste integrated cost analysis model: 1991 project year report. Part 2

    Energy Technology Data Exchange (ETDEWEB)

    1991-12-31

    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.

  17. WASTES: a waste management logistics/economics model

    International Nuclear Information System (INIS)

    McNair, G.W.; Shay, M.R.; Fletcher, J.F.; Cashwell, J.W.

    1985-02-01

    The WASTES model simulates a user defined system for nuclear waste transportation and storage at both temporary and long-term storage facilities. The model is written in FORTRAN 77 as an extension to the SLAM commercial simulation package (Pritsker and Pegden 1979). SLAM (Simulation Language for Alternative Modeling) is utilized in a discrete event mode to model the passage of spent fuel through the system. The system is initiated with individual reactor discharges of spent fuel as described in the reactor discharge data file or as supplied by the user. The reactor discharge file contains deterministic information on the date (year/month) and quantity of spent fuel discharges. From this point, the model is controlled by a combination of source originated and destination originated transfers. Source driven transfers occur when a reactor pool violates the full core reserve (FCR) storage margin or when the reactor is decommissioned. At these times, the source reactor checks destination facilities to see if they can accept material. A dry storage facility is assumed to exist for each reactor and is allowed to grow as necessary to contain spent fuel which cannot be shipped to any other facility. In this way the FCR margin is always maintained. Destination driven transfers occur when the annual capacity of a facility will not be met by full core reserve or decommissioning shipments. An attempt is made at the end of each calendar year to schedule enough shipments of spent fuel from facilities with non-critical storage capacity to fill the annual capacity of each destination facility. Allowable facility types are reprocessing plants, federal interim storage (FIS), monitored retrievable storage (MRS), and repositories. The number, capacities, location and priority for receipt of spent fuel is user specified. This report describes in detail the waste generating model, the waste facilities model, the transportation model and the basic transportation scheme

  18. Enhanced Waste Tank Level Model

    Energy Technology Data Exchange (ETDEWEB)

    Duignan, M.R.

    1999-06-24

    'With the increased sensitivity of waste-level measurements in the H-Area Tanks and with periods of isolation, when no mass transfer occurred for certain tanks, waste-level changes have been recorded with are unexplained.'

  19. Treatability study of absorbent polymer waste form for mixed waste treatment

    International Nuclear Information System (INIS)

    Herrmann, S. D.; Lehto, M. A.; Stewart, N. A.; Croft, A. D.; Kern, P. W.

    2000-01-01

    A treatability study was performed to develop and characterize an absorbent polymer waste form for application to low level (LLW) and mixed low level (MLLW) aqueous wastes at Argonne National Laboratory-West (ANL-W). In this study absorbent polymers proved effective at immobilizing aqueous liquid wastes in order to meet Land Disposal Restrictions for subsurface waste disposal. Treatment of aqueous waste with absorbent polymers provides an alternative to liquid waste solidification via high-shear mixing with clays and cements. Significant advantages of absorbent polymer use over clays and cements include ease of operations and waste volume minimization. Absorbent polymers do not require high-shear mixing as do clays and cements. Granulated absorbent polymer is poured into aqueous solutions and forms a gel which passes the paint filter test as a non-liquid. Pouring versus mixing of a solidification agent not only eliminates the need for a mixing station, but also lessens exposure to personnel and the potential for spread of contamination from treatment of radioactive wastes. Waste minimization is achieved as significantly less mass addition and volume increase is required of and results from absorbent polymer use than that of clays and cements. Operational ease and waste minimization translate into overall cost savings for LLW and MLLW treatment

  20. Neutralized current acid waste consolidation management plan

    International Nuclear Information System (INIS)

    Powell, W.J.; Brown, R.G.; Galbraith, J.; Jensen, C.; Place, D.E.; Reddick, G.W.; Zuroff, W.; Brothers, A.J.

    1996-01-01

    The scope of this evaluation is to recommend a management plan for the high-heat tank waste, including neutralized current acid waste (NCAW) in AY and AZ Tank Farms, and tank C-106 waste. The movement of solids, liquids and salt cake in the designated tank farms is included. Decision analysis techniques were used to determine a recommended alternative. The recommended course of action was replacement of a 75-hp mixer pump in tank AY-102 and in-tank concentration of tank AZ-102 supernate. The alternative includes transfer fo tank C-106 sludge to tank AY-102, then transfer to tank AY-102 and tank C-106 sludge to tank AZ-101 using the new 75-hp mixer pump installed in tank AY-102. Tank AZ-101 becomes a storage tank for high-level waste (HLW) sludge, with the capacity to mix and transfer sludge as desired

  1. Refurbishment of Point Lepreau Generating Station

    International Nuclear Information System (INIS)

    Thompson, P.D.; Jaitly, R.; Ichiyen, N.; Petrilli, M.A.

    2004-01-01

    achieving clarity of the regulatory position and thus to minimize the financial risk associated with regulatory uncertainty. The Refurbishment outage is preceded by a detailed Engineering Project Phase that includes: Finalizing details of the Retube process including modeling, tooling development, site facilities and training of personnel; Perform Engineering activities related to design modifications, safety analysis and level II PSA; Construction of new waste storage structures to house Retube Waste and other additional waste storage structures for the extended life of the station; Setup necessary temporary construction facilities (offices, storage areas, change rooms, decontamination and maintenance areas); Perform detailed outage planning; Initiate development of detailed layup, commissioning and return to service procedures; Procure equipment and components. Although final project approval is still pending, NB Power has been carrying on a limited scope of activities that are important in reducing overall project financial risk. A number of these up-front activities relate to safety analysis and licensing issues related to life extension. In particular, a level II PSA along with additional safety analyses are being performed to complement that which currently support the existing Operating License for the station. This paper discusses the Safety and Licensing activities that were involved in defining the project scope and outlines the safety analysis related activities that will be performed in support of the Refurbishment project and extended operation. (author)

  2. Integrated assessment of a new Waste-to-Energy facility in Central Greece in the context of regional perspectives

    International Nuclear Information System (INIS)

    Perkoulidis, G.; Papageorgiou, A.; Karagiannidis, A.; Kalogirou, S.

    2010-01-01

    The main aim of this study is the integrated assessment of a proposed Waste-to-Energy facility that could contribute in the Municipal Solid Waste Management system of the Region of Central Greece. In the context of this paper alternative transfer schemes for supplying the candidate facility were assessed considering local conditions and economical criteria. A mixed-integer linear programming model was applied for the determination of optimum locations of Transfer Stations for an efficient supplying chain between the waste producers and the Waste-to-Energy facility. Moreover different Regional Waste Management Scenarios were assessed against multiple criteria, via the Multi Criteria Decision Making method ELECTRE III. The chosen criteria were total cost, Biodegradable Municipal Waste diversion from landfill, energy recovery and Greenhouse Gas emissions and the analysis demonstrated that a Waste Management Scenario based on a Waste-to-Energy plant with an adjacent landfill for disposal of the residues would be the best performing option for the Region, depending however on the priorities of the decision makers. In addition the study demonstrated that efficient planning is necessary and the case of three sanitary landfills operating in parallel with the WtE plant in the study area should be avoided. Moreover alternative cases of energy recovery of the candidate Waste-to-Energy facility were evaluated against the requirements of the new European Commission Directive on waste in order for the facility to be recognized as recovery operation. The latter issue is of high significance and the decision makers in European Union countries should take it into account from now on, in order to plan and implement facilities that recover energy efficiently. Finally a sensitivity check was performed in order to evaluate the effects of increased recycling rate, on the calorific value of treated Municipal Solid Waste and the gate fee of the candidate plant and found that increased

  3. The Museum of Solid Waste and Energy.

    Science.gov (United States)

    National Energy Education Development Project, Reston, VA.

    This activity geared for grades 5-9 involves students in creating museum stations on eight solid waste and energy topics. While working in groups, students present their station topic to other students who are conducting a "museum tour." In doing so participants are encouraged to enhance their reading, writing, public speaking, and artistic skills…

  4. Improved liquid waste processing system of PWR plant

    International Nuclear Information System (INIS)

    Suehiro, Kazuyasu

    1977-01-01

    Mitsubishi Heavy Industries, Ltd. has engaged in the improvement and enhancement of waste-processing facilities for PWR power stations, and recently established the improved processing system. With this system, it becomes possible to contain radioactive waste gas semi-permanently within plants and to recycle waste liquid after the treatment, thus to make the release of radioactive wastes practically zero. The improved system has the following features, namely the recycling system is adopted, drain is separated and each separated drain is treated by specialized process, the reboiler type evaporator and the reverse osmosis equipment are used, and the leakless construction is adopted for the equipments. The radioactive liquid wastes in PWR power stations are classified into coolant drain, drain from general equipments, chemical drain and cleaning water. The outline of the improved processing system and the newly developed equipments such as the reboiler type evaporator and the reverse osmosis equipment are explained. With the evaporator, the concentration rate of waste liquid can be raised to about three times, and foaming waste can be treated efficiently. The decontamination performance is excellent. The reverse osmosis treatment is stable and reliable method, and is useful for the treatment of cleaning water. It is also effective for concentrating treatment. The unmanned automatic operation is possible. (Kako, I.)

  5. Management of radioactive waste nuclear power plants

    International Nuclear Information System (INIS)

    Dlouhy, Z.; Marek, J.

    1976-01-01

    The authors give a survey of the sources, types and amounts of radioactive waste in LWR nuclear power stations (1,300 MWe). The amount of solid waste produced by a Novovorenezh-type PWR reactor (2 x 400 resp. 1 x 1,000 MWe) is given in a table. Treatment, solidification and final storage of radioactive waste are shortly discussed with special reference to the problems of final storage in the CSR. (HR) [de

  6. A dynamic simulation model of the Savannah River Site high level waste complex

    International Nuclear Information System (INIS)

    Gregory, M.V.; Aull, J.E.; Dimenna, R.A.

    1994-01-01

    A detailed, dynamic simulation entire high level radioactive waste complex at the Savannah River Site has been developed using SPEEDUP(tm) software. The model represents mass transfer, evaporation, precipitation, sludge washing, effluent treatment, and vitrification unit operation processes through the solution of 7800 coupled differential and algebraic equations. Twenty-seven discrete chemical constituents are tracked through the unit operations. The simultaneous simultaneous simulation of concurrent batch and continuous processes is achieved by several novel, customized SPEEDUP(tm) algorithms. Due to the model's computational burden, a high-end work station is required: simulation of a years operation of the complex requires approximately three CPU hours on an IBM RS/6000 Model 590 processor. The model will be used to develop optimal high level waste (HLW) processing strategies over a thirty year time horizon. It will be employed to better understand the dynamic inter-relationships between different HLW unit operations, and to suggest strategies that will maximize available working tank space during the early years of operation and minimize overall waste processing cost over the long-term history of the complex. Model validation runs are currently underway with comparisons against actual plant operating data providing an excellent match

  7. Waste treatment plant

    International Nuclear Information System (INIS)

    Adesanmi, C.A

    2009-01-01

    Waste Treatment Plant (WTP) is designed to provide appropriate systems for processing, immobilization and storage of low and medium radioactive waste arising from the operation of the research facilities of the Nuclear Technology Centre (NTC). It will serve as central collection station processing active waste generated through application of radionuclide in science, medicine and industry in the country. WTP building and structures will house the main waste processing systems and supporting facilities. All facilities will be interconnected. The interim storage building for processed waste drums will be located separately nearby. The separate interim storage building is located near the waste treatment building. Considering the low radiation level of the waste, storage building is large with no solid partitioning walls and with no services or extra facilities other than lighting and smoke alarm sensors. The building will be designed such that drums(200-1)are stacked 3 units high using handling by fork lift truck. To prevent radiation exposure to on-site personnel, the interim storage building will be erected apart from waste treatment plant or other buildings. The interim storage building will also be ready for buffer storage of unconditioned waste waiting for processing or decay and for storage material from the WTP

  8. The GNC Measurement System for the Automated Transfer Vehicle

    Science.gov (United States)

    Roux, Y.; da Cunha, P.

    The Automated Transfer Vehicle (ATV) is a European Space Agency (ESA) funded spacecraft developed by EADS Space Transportation as prime contractor for the space segment together with major European industrial partners, in the frame of the International Space Station (ISS). Its mission objective is threefold : to supply the station with fret and propellant, to reboost ISS to a higher orbit and to dispose of waste from the station. The ATV first flight, called Jules Verne and planned on 2005, will be the first European Vehicle to perform an orbital rendezvous. The GNC Measurement System (GMS) is the ATV on board function in charge of the measurement data collection and preconditioning for the navigation, guidance and control (GNC) algorithms. The GMS is made up of hardware which are the navigation sensors (with a certain level of hardware redundancy for each of them), and of an on-board software that manages, monitors and performs consistency checks to detect and isolate potential sensor failures. The GMS relies on six kinds of navigation sensors, used during various phases of the mission : the gyrometers assembly (GYRA), the accelerometers assembly (ACCA), the star trackers (STR), the GPS receivers, the telegoniometers (TGM) and the videometers (VDM), the last two being used for the final rendezvous phase. The GMS function is developed by EADS Space Transportation together with other industrial partners: EADS Astrium, EADS Sodern, Laben and Dasa Jena Optronik.

  9. Generation, storage, collection and transportation of municipal solid waste - A case study in the city of Kathmandu, capital of Nepal

    International Nuclear Information System (INIS)

    Alam, R.; Chowdhury, M.A.I.; Hasan, G.M.J.; Karanjit, B.; Shrestha, L.R.

    2008-01-01

    Solid waste management (SWM) services have consistently failed to keep up with the vast amount of solid waste produced in urban areas. There is not currently an efficient system in place for the management, storage, collection, and transportation of solid waste. Kathmandu City, an important urban center of South Asia, is no exception. In Kathmandu Metropolitan City, solid waste generation is predicted to be 1091 m 3 /d (245 tons/day) and 1155 m 3 /d (260 tons/day) for the years 2005 and 2006, respectively. The majority (89%) of households in Kathmandu Metropolitan City are willing to segregate the organic and non-organic portions of their waste. Overall collection efficiency was 94% in 2003. An increase in waste collection occurred due to private sector involvement, the shutdown of the second transfer station near the airport due to local protest, a lack of funding to maintain trucks/equipment, a huge increase in plastic waste, and the willingness of people to separate their waste into separate bins. Despite a substantial increase in total expenditure, no additional investments were made to the existing development plan to introduce a modern disposal system due to insufficient funding. Due to the lack of a proper lining, raw solid waste from the existing dumping site comes in contact with river water directly, causing severe river contamination and deteriorating the quality of the water

  10. Release of low-contaminated reactor wastes for unrestricted use

    International Nuclear Information System (INIS)

    Carleson, G.

    1982-01-01

    A generic methodology has been used to evaluate the dose contributions to an individual and to the population of five categories of low-contaminated reactor wastes produced according to the Swedish program and released for unrestricted handling and use. A reference quantity with a surface dose rate below a predetermined level is followed along the whole commercial pathway from the reactor station to the final product consumer and/or a municipal waste station. Dose contributions are calculated for each step in a normal pathway under maximally unfavourable conditions. (Auth.)

  11. Mass transfer and transport in salt repositories

    International Nuclear Information System (INIS)

    Pigford, T.H.; Chambre, P.L.; Lee, W.W.L.

    1989-02-01

    Salt is a unique rock isolation of nuclear waste because it is ''dry'' and nearly impermeable. In this paper we summarize some mass-transfer and transport analyses of salt repositories. First we analyses brine migration. Heating by high-level waste can cause brine in grain boundaries to move due to pressure-gradients. We analyze brine migration treating salt as a thermoelastic solid and found that brine migration is transient and localized. We use previously developed techniques to estimate release rates from waste packages by diffusion. Interbeds exist in salt and may be conduits for radionuclide migration. We analyze steady-state migration due to brine flow in the interbed, as a function of the Peclet number. Then we analyze transient mass transfer, both into the interbed and directly to salt, due only to diffusion. Finally we compare mass transfer rates of a waste cylinder in granite facing a fracture and in salt facing an interbed. In all cases, numerical illustrations of the analytic solution are given. 10 refs., 4 figs., 3 tabs

  12. Assessment of Available Particle Size Data to Support an Analysis of the Waste Feed Delivery System Transfer System

    International Nuclear Information System (INIS)

    JEWETT, J.R.

    2000-01-01

    Available data pertaining to size distribution of the particulates in Hanford underground tank waste have been reviewed. Although considerable differences exist between measurement methods, it may be stated with 95% confidence that the median particle size does not exceed 275 (micro)m in at least 95% of the ten tanks selected as sources of HLW feed for Phase 1 vitrification in the RPP. This particle size is recommended as a design basis for the WFD transfer system

  13. Hanford Waste Vitrification Plant capacity increase options

    International Nuclear Information System (INIS)

    Larson, D.E.

    1996-04-01

    Studies are being conducted by the Hanford Waste Vitrification Plant (HWVP) Project on ways to increase the waste processing capacity within the current Vitrification Building structural design. The Phase 1 study on remote systems concepts identification and extent of capacity increase was completed. The study concluded that the HWVP capacity could be increased to four times the current capacity with minor design adjustments to the fixed facility design, and the required design changes would not impact the current footprint of the vitrification building. A further increase in production capacity may be achievable but would require some technology development, verification testing, and a more systematic and extensive engineering evaluation. The primary changes included a single advance melter with a higher capacity, new evaporative feed tank, offgas quench collection tank, ejector venturi scrubbers, and additional inner canister closure station,a smear test station, a new close- coupled analytical facility, waste hold capacity of 400,000 gallon, the ability to concentrate out-of-plant HWVP feed to 90 g/L waste oxide concentration, and limited changes to the current base slab construction package

  14. 7 CFR 29.75c - Display of tobacco at receiving stations.

    Science.gov (United States)

    2010-01-01

    ... receiving stations. Each lot of tobacco delivered for sale at receiving stations and transferred to a conveyor system for unloading shall maintain a distance between adjacent lots of not less than 18 inches during the inspection process. The platform area used for examination with a conveyor system shall be a...

  15. Electricity Generation Through the Koeberg Nuclear Power Station of Eskom in South Africa

    International Nuclear Information System (INIS)

    Dladla, G.; Joubert, J.

    2015-01-01

    The poster provides information on the process of nuclear energy generation in a nuclear power plant in order to produce electricity. Nuclear energy currently provides approximately 11% of the world’s electricity needs, with Koeberg Nuclear Power Station situated in the Western Cape providing 4.4% of South Africa’s electricity needs. As Africa’s first nuclear power station, Koeberg has an installed capacity of 1910 MW of power. Koeberg’ s total net output is 1860 MW. While there are significant differences, there are many similarities between nuclear power plants and other electrical generating facilities. Uranium is used for fuel in nuclear power plants to make electricity. With the exception of solar, wind, and hydroelectric plants, all others including nuclear plants convert water to steam that spins the propeller-like blades of a turbine that spins the shaft of a generator. Inside the generator coils of wire and magnetic fields interact to create electricity. The energy needed to boil water into steam is produced in one of two ways: by burning coal, oil, or gas (fossil fuels) in a furnace or by splitting certain atoms of uranium in a nuclear energy plant. The uranium fuel generates heat through a controlled fission process fission, which is described in this poster presentation. The Koeberg Nuclear Power Station is a Pressurised water reactor (PWR). The operating method and the components of the Koeberg Power Station are also described. The nuclear waste generated at a nuclear power station is described under three headings— low-level waste, intermediate-level waste and used or spent fuel, which can be solid, liquid or gaseous. (author)

  16. Plasma vitrification program for radioactive waste treatment

    International Nuclear Information System (INIS)

    Hung, Tsungmin; Tzeng, Chinchin; Kuo, Pingchun

    1998-01-01

    In order to treat radioactive wastes effectively and solve storage problems, INER has developed the plasma arc technology and plasma process for various waste forms for several years. The plasma vitrification program is commenced via different developing stages through nine years. It includes (a) development of non-transferred DC plasma torch, (b) establishment of a lab-scale plasma system with home-made 100kW non-transferred DC plasma torch, (c) testing of plasma vitrification of simulated radioactive wastes, (d) establishment of a transferred DC plasma torch delivering output power more than 800 kW, (e) study of NOx reduction process for the plasma furnace, (f) development of a pilot-scale plasma melting furnace to verify the vitrification process, and (g) constructing a plasma furnace facility in INER. The final goal of the program is to establish a plasma processing plant with capacity of 250 kg/hr to treat the low-level radioactive wastes generated from INER itself and domestic institutes due to isotope applications. (author)

  17. Instructive for radioactive solid waste management

    International Nuclear Information System (INIS)

    Mora Rodriguez, Patricia

    2014-01-01

    An instructive is established for the management system of radioactive solid residues waste of the Universidad de Costa Rica, ensuring the collection, segregation, storage and disposal of waste. The radioactive solid waste have been segregated and transferred according to features and provisions of the Universidad de Costa Rica and CICANUM [es

  18. Development of the Arctic radionuclide monitoring station

    International Nuclear Information System (INIS)

    King, S.E.; Phillips, G.W.; Aakenes, U.R.

    1996-01-01

    In recent years, the world has learned about the dumping of nuclear reactors and other waste into the Arctic seas by the former Soviet Union. Most of the information on the present levels of radioactivity in the region has been obtained by oceanographic expeditions conducted during the brief Arctic summers. Year-round monitoring of the movement of radio-activity during dynamic seasonal and episodic chances is hampered by the difficulties caused by sea ice, logistics and communication constraints associated with deployment and maintenance of monitoring equipment in this remote region. We have designed an autonomous station to measure the benthic gamma-ray emitting radioactivity for periods of at least one year. The station is capable of detecting a 30 Bq/m 3 increase in the 137 Cs activity in a 24 hour period. After a year-long deployment, the station releases its anchor and rises to the surface to transmit the accumulated spectra and oceanographic data via an Argos satellite link. The design and performance characteristics of the prototype station will be discussed

  19. Development of the Arctic radionuclide monitoring station

    Science.gov (United States)

    King, S. E.; Aakenes, U. R.; McCoy, K.; Phillips, G. W.

    1997-06-01

    The world has learned about the dumping of nuclear reactors and other waste into the Arctic seas by the former Soviet Union. Most of the information on the present levels of radioactivity in the region has been obtained by oceanographic expeditions conducted during the brief Arctic summers. Year-round monitoring of the movement of radioactivity during dynamic seasonal and episodic changes is hampered by the difficulties caused by sea ice, logistics and communication constraints associated with deployment and maintenance of monitoring equipment in this remote region. The authors have designed an autonomous station to measure the benthic gamma-ray emitting radioactivity for periods of at least one year. The station is capable of detecting a 30 Bq/m/sup 3/ increase in the /sup 137/Cs activity in a 24 hour period. After a year-long deployment, the station releases its anchor and rises to the surface to transmit the accumulated spectra and oceanographic data via an Argos satellite link. The design and performance characteristics of the prototype station are discussed.

  20. Preconceptual design for a Monitored Retrievable Storage (MRS) transfer facility

    International Nuclear Information System (INIS)

    Woods, W.D.; Jowdy, A.K.; Smith, R.I.

    1990-09-01

    The contract between the DOE and the utilities specifies that the DOE will receive spent fuel from the nuclear utilities in 1998. This study investigates the feasibility of employing a simple Transfer Facility which can be constructed quickly, and operate while the full-scale MRS facilities are being constructed. The Transfer Facility is a hot cell designed only for the purpose of transferring spent fuel assemblies from the Office of Civilian Radioactive Waste Management (OCRWM) transport casks (shipped from the utility sites) into onsite concrete storage casks. No operational functions other than spent fuel assembly transfers and the associated cask handling, opening, and closing would be performed in this facility. Radioactive waste collected in the Transfer Facility during operations would be stored until the treatment facilities in the full-scale MRS facility became operational, approximately 2 years after the Transfer Facility started operation. An alternate wherein the Transfer Facility was the only waste handling building on the MRS site was also examined and evaluated. 6 figs., 26 tabs

  1. Parameters of passenger facilities according to railway station characteristics

    Directory of Open Access Journals (Sweden)

    Ondřej HAVLENA

    2014-12-01

    Full Text Available The article presents ways and goals of categorization of railway stations and stops in the Czech railway network. The aim of this categorization is to classify railway stations (or stops in the railway network according to a suite of entrance parameters (e.g. municipality population, transfer links, job opportunities, tourist attractiveness. On the basis of these parameters, railway stations and stops will be classified into several categories, which will be used to specify the conclusions for station equipment concerning ticket offices, commercial services, waiting rooms and other accessories. Research results can be used as a support for infrastructure managers and railway operators to optimise the scale of their services.

  2. The Handling of Liquid Waste at the Research Station of Studsvik, Sweden

    International Nuclear Information System (INIS)

    Lindhe, Soeren; Linder, Per

    1965-03-01

    The following quantities of radioactive waste are allowed to be released into a strait between the islands of Stora Bergoe and Studsviksholme: Total α-activity 0,2 curie/month. Total β-activity 36 curie/month of which cerium, yttrium, rare earth 15 curie/month, strontium 2,4 curie/month. Before the release the radioactive waste has to be collected and controlled. Quantities approaching or exceeding the disposal limits have to be removed and concentrated by evaporation. The liquid waste is classified in several categories depending upon the level of activity: high active and medium active waste, low active waste, process water, sanitary water, surface water and reactor cooling water. The technical dimensioning of each category was based upon expected specific production figures (volume/man - month and activity/ man - month). These figures are based upon information obtained from Harwell. Actual production figures obtained during 1963 and the first half of 1964 are shown and compared with the expected ones. As a conclusion is stated that the actual production follows the predictions fairly well

  3. The Handling of Liquid Waste at the Research Station of Studsvik, Sweden

    Energy Technology Data Exchange (ETDEWEB)

    Lindhe, Soeren; Linder, Per

    1965-03-15

    The following quantities of radioactive waste are allowed to be released into a strait between the islands of Stora Bergoe and Studsviksholme: Total {alpha}-activity 0,2 curie/month. Total {beta}-activity 36 curie/month of which cerium, yttrium, rare earth 15 curie/month, strontium 2,4 curie/month. Before the release the radioactive waste has to be collected and controlled. Quantities approaching or exceeding the disposal limits have to be removed and concentrated by evaporation. The liquid waste is classified in several categories depending upon the level of activity: high active and medium active waste, low active waste, process water, sanitary water, surface water and reactor cooling water. The technical dimensioning of each category was based upon expected specific production figures (volume/man - month and activity/ man - month). These figures are based upon information obtained from Harwell. Actual production figures obtained during 1963 and the first half of 1964 are shown and compared with the expected ones. As a conclusion is stated that the actual production follows the predictions fairly well.

  4. Investigations of the gas-side heat transfer and flow characteristics of steam generators in AGR stations

    Energy Technology Data Exchange (ETDEWEB)

    Lis, J [Central Electricity Research Laboratories, Leatherhead, Surrey (United Kingdom)

    1984-07-01

    This paper describes the experimental and analytical investigations of the gas-side heat transfer and flow characteristics of steam generators in the AGR stations carried out by CERL. The majority of the experimental work on heat transfer and flow characteristics of close-packed tube arrangements in cross-flow of gases is carried out in a pressurised heat exchanger rig. The rig is operated on-line by a dedicated PDP 11/40 computer over the range of Reynolds number 10{sup 4} to 3x10{sup 5}. Atmospheric wind tunnels employing either small or large scale models of the specific sections of steam generators are used for a variety of supplementary and development studies. Various measurements techniques and, in particular, LDA and hot wire anemometry employed in these studies are described. The more important aspects of various investigations are illustrated by typical results. In order to ensure the efficient operation and integrity of steam generators under asymmetric boundary conditions a MIX suite of 2-dimensional codes has been developed. The codes calculate the gas and water/steam flow and temperature distributions in each channel of the steam generator taking into account thermal mixing in the gas as it passes through the generator. Application of the MIX codes to the solution of various operational problems is illustrated by typical examples and the continuing exercise of validating the codes against plant operational data is discussed. (author)

  5. Investigations of the gas-side heat transfer and flow characteristics of steam generators in AGR stations

    International Nuclear Information System (INIS)

    Lis, J.

    1984-01-01

    This paper describes the experimental and analytical investigations of the gas-side heat transfer and flow characteristics of steam generators in the AGR stations carried out by CERL. The majority of the experimental work on heat transfer and flow characteristics of close-packed tube arrangements in cross-flow of gases is carried out in a pressurised heat exchanger rig. The rig is operated on-line by a dedicated PDP 11/40 computer over the range of Reynolds number 10 4 to 3x10 5 . Atmospheric wind tunnels employing either small or large scale models of the specific sections of steam generators are used for a variety of supplementary and development studies. Various measurements techniques and, in particular, LDA and hot wire anemometry employed in these studies are described. The more important aspects of various investigations are illustrated by typical results. In order to ensure the efficient operation and integrity of steam generators under asymmetric boundary conditions a MIX suite of 2-dimensional codes has been developed. The codes calculate the gas and water/steam flow and temperature distributions in each channel of the steam generator taking into account thermal mixing in the gas as it passes through the generator. Application of the MIX codes to the solution of various operational problems is illustrated by typical examples and the continuing exercise of validating the codes against plant operational data is discussed. (author)

  6. Konrad transport study: Safety analysis of the transportation of radioactive waste to the Konrad waste disposal site

    International Nuclear Information System (INIS)

    Lange, F.; Gruendler, D.; Schwarz, G.

    1992-05-01

    For the purpose of the study the anticipated waste transport volume and the waste properties were analysed in detail. This included information on the transport containers, waste product properties, activity inventories and local dose rates of the waste packages being transported. The envisaged practical implementation, i.e. the transport arrangements including shunting operations at the Braunschweig marshalling yard and the Beddingen interchange station, were also included. The two shipping scenarios 100% transportation by rail and 80% transportation by rail, 20% by road, which could be considered to bound the real conditions, were analysed. The relevant transport regulations contain the requirements to be met by the transport of shipping units carrying radioactive waste. In addition, the ''Konrad preliminary waste acceptance criteria'' contain activity limits for waste packages being disposed of in conjunction with further requirements relating to the properties of waste products and waste containers. (orig./DG)

  7. Waste management at the Ardennes power plant

    International Nuclear Information System (INIS)

    Abraham, J.P.

    1979-01-01

    In 1976, the SENA (with the participation of EDF, CEA and CEC in the framework of a research program on the management and storage of radioactive wastes) has developed an industrial pilot plant for the encapsulation of wastes in thermosetting polyester resins. The industrial putting in operation of the plant will enable most of the wastes from the nuclear station to be processed. The quality of products will be improved and the volume and processing cost reduced

  8. Distribution of 137Cs Radionuclide in Industrial Wastes Effluents of Gresik, East Java, Indonesia

    Directory of Open Access Journals (Sweden)

    Muslim

    2015-04-01

    Full Text Available The distribution of anthropogenic radionuclides 137Cs was measured from industrial waste effluent of Gresik to Gresik Sea in east Java, Indonesia. The activity of 37Cs detected at all stations was much lower than in northeast Japan both before and after NPP Fukushima accident. This indicated that in Gresik industrials waste did not consist of 137Cs. The lowest activity 137Cs occurred at the station nearest to the industrial waste effluent that contained some particle ions that were able to scavenge 137Cs and then precipate this radionuclide. Furthermore, the greatest 137Cs occured at the station that has high current speeds that stirred up sediment to release 137Cs in seawater as a secondary source. The lowest salinity did not effect on the activity of 137Cs even though the lowest salinity and activity 137Cs occured at the same station

  9. Environmental implications of fossil-fuelled power stations

    International Nuclear Information System (INIS)

    Robson, A.

    1979-01-01

    The public health and environmental implications of electricity generation by fossil-fuelled power stations are discussed with respect to pollutant emission and the disposal of waste products. The following conclusions were deduced. The policy of using tall chimney stacks has ensured that acceptable concentrations of potential pollutants are observed in the vicinity of power stations. Large scale carbon dioxide emission may represent a problem in the future due to its effect on the climate. The effects of sulphur dioxide and the oxides of nitrogen need to be kept under review but it is likely that sources other than power stations will be of greater importance in this context. Pulverised fuel ash is a safe and useful by product of power production. Finally the radiation dose to man caused by the release of naturally occurring radioisotopes is negligible compared to the natural background levels. (UK)

  10. Analysis of the behavior of tubular-type equipment for nuclear waste treatment: sensitivities of the parameters affecting mass transfer yield

    International Nuclear Information System (INIS)

    Yoo, Jae Hyung; Lee, Byung Jik; Shim, Joon Bo; Kim, Eung Ho

    2007-01-01

    It was intended in this study to investigate the effects of various parameters on the chemical reaction or mass transfer yield in a tubular-type nuclear waste treatment equipment. Since such equipment. as a tubular reactor, multistage solvent extractor, and adsorption column, accompany chemical reaction or mass transfer along the fluid-flowing direction, mathematical modeling for each equipment was carried out first. Then their behaviors of the chemical reaction or mass transfer were predicted through computer simulations. The inherent major parameters for each equipment were chosen and their sensitivities affecting the reaction or mass transfer yield were analyzed. For the tubular reactor, the effects of axial diffusion coefficient and reaction rate constant on the reaction yield were investigated. As for the multistage solvent extractor, the back mixing of continuous phase and the distribution coefficient between fluid and solvent were considered as the major parameters affecting the extraction yield as well as concentration profiles throughout the axial direction of the extractor. For the adsorption column, the equilibrium constant between fluid and adsorbent surface. and the overall mass transfer coefficient between the two phases were taken as the major factors that affect the adsorption rate

  11. Decommissioning of nuclear power stations

    International Nuclear Information System (INIS)

    Gregory, A.R.

    1988-01-01

    In the United Kingdom the Electricity Boards, the United Kingdom Atomic Energy Authority (UKAEA) and BNFL cooperate on all matters relating to the decommissioning of nuclear plant. The Central Electricity Generating Board's (CEGB) policy endorses the continuing need for nuclear power, the principle of reusing existing sites where possible and the building up of sufficient funds during the operating life of a nuclear power station to meet the cost of its complete clearance in the future. The safety of the plant is the responsibility of the licensee even in the decommissioning phase. The CEGB has carried out decommissioning studies on Magnox stations in general and Bradwell and Berkeley in particular. It has also been involved in the UKAEA Windscale AGR decommissioning programme. The options as to which stage to decommission to are considered. Methods, costs and waste management are also considered. (U.K.)

  12. ENGINEERING SPECIALTY ASSESSMENT OF TANK WASTE COMPATIBILITY REPORTING

    International Nuclear Information System (INIS)

    KNIGHT, M.A.

    2003-01-01

    This Engineering Specialty Assessment was conducted to review the Tank Farm Waste Transfer Compatibility Program to assess whether the program meets the needs of accelerated retrieval and closure and waste feed delivery and to identify areas and methods for streamlining the program. The assessment was conducted in June 2003 and resulted in two findings and thirteen observations. The assessment results indicate that significant opportunities exist for streamlining the program by reducing the number of criteria requiring evaluation from 21 to 11, with only six of the criteria requiring evaluation for the majority of transfers. The assessment identified areas where existing criteria require strengthening to ensure that the risks of undesirable solids precipitation, from either waste mixing or waste transfer, are minimized. The assessment further identified opportunities for using existing engineering tools to simplify the calculations involved with preparation of waste compatibility assessments. The need to ensure that a revision to the waste compatibility program is prepared to align the program criteria with those that will be implemented with the DSA approval was also identified. Finally, the assessment identified that corrective actions are required to implement a tank-by-tank PCB inventory within the Best Basis Inventory and to ensure that sample data from external waste generators is entered into the TWINS database

  13. Integrated waste and water management system

    Science.gov (United States)

    Murray, R. W.; Sauer, R. L.

    1986-01-01

    The performance requirements of the NASA Space Station have prompted a reexamination of a previously developed integrated waste and water management system that used distillation and catalytic oxydation to purify waste water, and microbial digestion and incineration for waste solids disposal. This system successfully operated continuously for 206 days, for a 4-man equivalent load of urine, feces, wash water, condensate, and trash. Attention is given to synergisms that could be established with other life support systems, in the cases of thermal integration, design commonality, and novel technologies.

  14. The state of radioactive waste management and of personnel radiation exposure in nuclear power generating facilities in fiscal 1983

    International Nuclear Information System (INIS)

    1985-01-01

    (1) The state of radioactive waste management in nuclear power generating facilities: In the nuclear power stations, the released quantities of radioactive gaseous and liquid wastes are all below the control objective levels. For the respective nuclear power stations, the released quantities of radioactive gaseous and liquid wastes in fiscal 1983 and the objective levels are given in table. And, the quantities of solid wastes taken into storage and the cumulative amounts are given. For reference, the results each year since fiscal 1974 are shown. (2) The state of personnel radiation exposure in nuclear power generating facilities: In the nuclear power stations, the personnel radiation exposures are all below the permissible levels. The dose distribution etc. in the respective nuclear power stations are given in table. For reference, the results each year since fiscal 1974 are shown. (Mori, K.)

  15. Polymer solidification: Technology transfer to DOE and industry

    International Nuclear Information System (INIS)

    Kalb, P.D.; Strand, G.

    1994-01-01

    In keeping with the congressional mandate for technology transfer between federal research and development institutions and U.S. industry, the Brookhaven National Laboratory (BNL) Environmental and Waste Technology Center is pursuing industrial partnership with industry. These efforts, supported by the Department of Energy's Office of Environmental Restoration and Waste Management involve both the transfer of BNL developed technology to industry and the use of commercially developed technologies as part of an integrated waste treatment system. A Cooperative Research and Development Agreement has been established with VECTRA Technologies, Inc. (formerly Pacific Nuclear), a U.S. company that provides waste treatment and other services to the commercial nuclear power industry. The agreement involves investigation of polyethylene encapsulation for treatment of ion exchange resin wastes. In addition, other avenues of cooperation are being investigated including use of a VECTRA Technologies volume reduction pre-treatment process for use with the polyethylene technology in treating aqueous radioactive, hazardous, and mixed wastes

  16. Mixed waste certification plan for the Lawrence Berkeley Laboratory Hazardous Waste Handling Facility. Revision 1

    International Nuclear Information System (INIS)

    1995-01-01

    The purpose of this plan is to describe the organization and methodology for the certification of mixed waste handled in the Hazardous Waste Handling Facility (HWHF) at Lawrence Berkeley Laboratory (LBL). This plan is composed to meet the requirements found in the Westinghouse Hanford Company (WHC) Solid Waste Acceptance Criteria (WAC) and follows the suggested outline provided by WHC in the letter of April 26, 1990, to Dr. R.H. Thomas, Occupational Health Division, LBL. Mixed waste is to be transferred to the WHC Hanford Site Central Waste Complex and Burial Grounds in Hanford, Washington

  17. The buried waste integrated demonstration

    International Nuclear Information System (INIS)

    Kostelnik, K.M.

    1991-01-01

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

  18. Requirements Verification Report AN Farm to 200E Waste Transfer System for Project W-314, Tank Farm Restoration and Safe Operations

    International Nuclear Information System (INIS)

    MCGREW, D.L.

    1999-01-01

    This Requirements Verification Report (RVR) for Project W-314 ''AN Farm to 200E Waste Transfer System'' package provides documented verification of design compliance to all the applicable Project Development Specification (PDS) requirements. Additional PDS requirements verification will be performed during the project's procurement, construction, and testing phases, and the RVR will be updated to reflect this information as appropriate

  19. Guidelines for generators of hazardous chemical waste at LBL and Guidelines for generators of radioactive and mixed waste at LBL

    International Nuclear Information System (INIS)

    1991-07-01

    The purpose of this document is to provide the acceptance criteria for the transfer of hazardous chemical, radioactive, and mixed waste to Lawrence Berkeley Laboratory's (LBL) Hazardous Waste Handling Facility (HWHF). These guidelines describe how a generator of wastes can meet LBL's acceptance criteria for hazardous chemical, radioactive, and mixed waste. 9 figs

  20. 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

  1. 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.

  2. 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

  3. From waste to technology. An environmental acceptable technology

    International Nuclear Information System (INIS)

    Tabasaran, O.

    2001-01-01

    Modern thermal waste treatment has the task to produce deposit capable inert products and is able to reduce contaminants emitted to the environment. In addition waste to energy plants enable the recovery of energy by a maximum amount of environmental protection even in the comparison with modern power stations or other industrial plants. Over that, regarding modern technical solutions, today's waste to energy plants can no more be turned on financial reasons [it

  4. Mixed and chelated waste test programs with bitumen solidification

    International Nuclear Information System (INIS)

    Simpson, S.I.; Morris, M.; Vidal, H.

    1988-01-01

    This paper presents the results of bitumen solidification tests on mixed wastes and chelated wastes. The French Atomic Energy Commission (CEA) performed demonstration tests on radioactive wastes contaminated with chelating agents for Associated Technologies, Inc. (ATI). The chelated wastes were produced and concentrated by Commonwealth Edison Co. as a result of reactor decontamination at Dresden Nuclear Station, Unit 1. Law Engineering in Charlotte, N. C. produced samples and performed tests on simulated heavy metal laden radioactive waste (mixed) to demonstrate the quality of the bituminous product. The simulation is intended to represent waste produced at Oak Ridge National Labs operated by Martin-Marietta

  5. Functional check of telescoping transfer pumps

    International Nuclear Information System (INIS)

    Sharpe, C.L.

    1994-01-01

    Activities are defined which constitute a functional check of a telescoping transfer pump (TTP). This report is written to the Procedures group of HLW and particularly applies to those TTP's which are the sole means of emergency transfer from a HLW waste tank

  6. Impact of Biogas Stations on CO2 Emission from Agriculture

    Directory of Open Access Journals (Sweden)

    Josef Slaboch

    2017-01-01

    Full Text Available This paper deals with the effects of biogas stations on CO2 emissions produced within agricultural sector. In last years, owing to a positive policy of renewable energy resources a number of biogas stations in the CR has rapidly increased – actually over 350 agricultural biogas stations with the total installed power 365 MW are in operation. Concerning CO2 emissions from the agricultural sector, there is a presumption of decrease in produced emissions owing to decrease of influence of animal wastes which are processed just in the biogas stations. From the results it is obvious that CO2 emissions produced by agriculture in the CR decrease by 93.7 thousand tonnes annually. A presumption P1 that building of biogas stations will further support this trend is documented with results of a simple dynamic linear regression model. Further, elasticities of particular variables influencing the total emission from agriculture are investigated in the paper.

  7. Nevada Test Site Waste Acceptance Criteria

    International Nuclear Information System (INIS)

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

    2005-01-01

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

  8. Development of radioactive waste treatment system for nuclear power stations by Toshiba (III)

    International Nuclear Information System (INIS)

    Irie, H.; Takahara, T.; Matsuda, T.; Matsuura, H.; Yasumura, K.; Nakayama, Y.

    1989-01-01

    This paper describes a solidification process with thermosetting resin to satisfy both requirements of volume reduction and quality of solidified products. Volumes of solidified products in drums generated from spent resins and concentrated wastes were reduced respectively to 1/4 and less than 1/6 of those in the conventional cement solidification process. In plants using a simple demineralizing system for condensate polishing, a large amount of waste water with regenerant chemicals is generated from the condensate demineralizer. In general, radioactivity concentration of wastes from this type of nuclear power plant is comparatively high, so the dose rate at the surface of drums containing solidified wastes exceeds 200mR/h. A pelletizing system for radioactive wastes was developed to reduce their volumes and allow their interim storage until the radioactivity decays down to a level at which they can be handled easily

  9. NEVADA TEST SITE WASTE ACCEPTANCE CRITERIA

    International Nuclear Information System (INIS)

    U.S. DEPARTMENT OF ENERGY, NATIONAL NUCLEAR SECURITY ADMINISTRATION, NEVADA SITE OFFICE

    2005-01-01

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

  10. MECHANISMS GOVERNING TRANSIENTS FROM THE BATCH INCINERATION OF LIQUID WASTES IN ROTARY KILNS

    Science.gov (United States)

    When "containerized" liquid wastes, bound on sorbents. are introduced into a rotary kiln in a batch mode, transient phenomena in-volving heat transfer into, and waste mass transfer out of, the sorbent can oromote the raoid release of waste vaoor into the kiln environment. This ra...

  11. Solidification of low-level wastes by inorganic binder

    International Nuclear Information System (INIS)

    Sasaki, M.T.; Shimojo, M.; Suzuki, K.; Kajikawa, A.; Karasawa, Y.

    1995-01-01

    The use of an alkali activated slag binder has been studied for solidification and stabilization of low-level wastes in nuclear power stations and spent fuel processing facilities. The activated slag effectively formed waste products having good physical properties with high waste loading for sodium sulfate, sodium nitrate, calcium pyrophosphate/phosphate and spent ion-exchange resins. Moreover, the results of the study suggest the slag has the ability to become a common inorganic binder for the solidification of various radioactive wastes. This paper also describes the fixation of radionuclides by the activated slag binder

  12. Waste law. November 2013 - September 2014

    International Nuclear Information System (INIS)

    Lanoy, Laurence

    2014-01-01

    The author comments the main evolution noticed regarding legal aspects (laws, decrees, jurisprudence, and so on) about wastes between November 2013 and September 2014. The main events have been the adoption of the bill on social and solidarity economy which contained some measures related to waste prevention, and the transposition of a European directive related to waste electric and electronic equipment. The author addresses the different concerned domains: the modalities of waste management (prescriptions applied to installations receiving wastes, the waste status, the case of radioactive wastes, the case of waste electronic and electric equipment, waste cross-border transfers, general orientations of the French and European waste laws), and the responsibility for wastes (administrative responsibility, waste related taxation, producer responsibility)

  13. Hinkley Point 'C' power station public inquiry: statement of case

    International Nuclear Information System (INIS)

    1988-08-01

    This Statement of Case contains full particulars of the case which the Central Electricity Generating Board (CEGB) proposes to put forward at the Hinkley Point ''C'' Inquiry. It relates to the planning application made by the CEGB for the construction of a 1200 MW Pressurized Water Reactor (PWR) power station at Hinkley Point in the United Kingdom, adjacent to an existing nuclear power station. The inquiry will consider economic, safety, environmental and planning matters relevant to the application and the implications for agriculture and local amenities of re-aligning two power transmission lines. The Statement contains submissions on the following matters: Topic 1 The Requirement for the Station; Topic 2 Safety and Design, including Radioactive Discharges; Topic 3 The On-Site Management of Radioactive Waste and Decommissioning of the Station; Topic 4 Emergency Arrangements; Topic 5 Local and Environmental Issues. (author)

  14. Operation of low-level radioactive waste incinerator

    International Nuclear Information System (INIS)

    Choi, E.C.; Drolet, T.S.; Stewart, W.B.; Campbell, A.V.

    1979-01-01

    Ontaro Hydro's radioactive waste incinerator designed to reduce the volume of low-level combustible wastes from nuclear generating station's was declared in-service in September 1977. Hiterto about 1500 m 3 of combustible waste have been processed in over 90 separate batches. The process has resulted in 40:1 reduction in the volume and 12.5:1 reduction in the weight of the Type 1 wastes. The ultimate volume reduction factor after storage is 23:1. Airborne emissions has been maintained at the order of 10 -3 to 10 -5 % of the Derived Emission Limits. Incineration of radioactive combustible wastes has been proven feasible, and will remain as one of the most important processes in Ontario Hydro's Radioactive Waste Management Program

  15. MRS transfer facility feasibility study

    International Nuclear Information System (INIS)

    Jowdy, A.K.; Smith, R.I.

    1990-12-01

    Under contract to the US Department of Energy, Parsons was requested to evaluate the feasibility of building a simple hot cell (waste handling) transfer facility at the Monitored Retrievable Storage (MRS) site to facilitate acceptance of spent fuel into the Federal Waste Management System starting in early 1998. The Transfer Facility was intended to provide a receiving and transfer to storage capability at a relatively low throughput rate (approximately 500 MTU/yr) and to provide the recovery capability needed on the site in the event of a transport or storage cask seal failure during a period of about two years while the larger Spent Fuel Handling Building (SFHB) was being completed. Although the original study basis postulated an incremental addition to the larger, previously considered MRS configurations, study results show that the Transfer Facility may be capable of receiving and storing spent fuel at annual rates of 3000 MTU/yr or more, making a larger fuel handling structure unnecessary. In addition, the study analyses showed that the Transfer Facility could be constructed and put into service in 15--17 months and would cost less than the previous configurations. 2 figs., 2 tabs

  16. Radioactive waste processing

    International Nuclear Information System (INIS)

    Curtiss, D.H.; Heacock, H.W.

    1976-01-01

    The description is given of a process for treating radioactive waste whereby a mud of radioactive waste and cementing material is formed in a mixer. This mud is then transferred from the mixer to a storage and transport container where it is allowed to harden. To improve transport efficiency an alkali silicate or an alkaline-earth metal silicate is added to the mud. For one hundred parts by weight of radioactive waste in the mud, twenty to one hundred parts by weight of cementing material are added and five to fifty parts by weight of silicate, the amount of waste in the mud exceeding the combined amount of cementing and silicate material [fr

  17. W-314, waste transfer alternative piping system description

    International Nuclear Information System (INIS)

    Papp, I.G.

    1998-01-01

    It is proposed that the reliability, operability, and flexibility of the Retrieval Transfer System be substantially upgraded by replacing the planned single in-farm pipeline from the AN-AY-AZ-(SY) Tank Farm Complex to the AP Farm with three parallel pipelines outside the tank farms. The proposed system provides simplified and redundant routes for the various transfer missions, and prevents the risk of transfer gridlock when the privatization effort swings into full operation

  18. W-314, waste transfer alternative piping system description

    Energy Technology Data Exchange (ETDEWEB)

    Papp, I.G.

    1998-04-30

    It is proposed that the reliability, operability, and flexibility of the Retrieval Transfer System be substantially upgraded by replacing the planned single in-farm pipeline from the AN-AY-AZ-(SY) Tank Farm Complex to the AP Farm with three parallel pipelines outside the tank farms. The proposed system provides simplified and redundant routes for the various transfer missions, and prevents the risk of transfer gridlock when the privatization effort swings into full operation.

  19. TMI abnormal wastes disposal options

    International Nuclear Information System (INIS)

    Ayers, A.L. Jr.

    1984-03-01

    A substantial quantity of high beta-gamma/high-TRU contaminated wastes are expected from cleanup activities of Unit 2 of the Three Mile Island Nuclear Power Station. Those wastes are not disposable because of present regulatory constraints. Therefore, they must be stored temporarily. This paper discusses three options for storage of those wastes at the Idaho National Engineering Laboratory: (1) storage in temporary storage casks; (2) underground storage in vaults; and (3) storage in silos at a hot shop. Each option is analyzed and evaluated. Also included is a discussion of future disposal strategies, which might be pursued when a suitable federal or commercial repository is built

  20. Infrastructure needs for waste management

    International Nuclear Information System (INIS)

    Takahashi, M.

    2001-01-01

    National infrastructures are needed to safely and economically manage radioactive wastes. Considerable experience has been accumulated in industrialized countries for predisposal management of radioactive wastes, and legal, regulatory and technical infrastructures are in place. Drawing on this experience, international organizations can assist in transferring this knowledge to developing countries to build their waste management infrastructures. Infrastructure needs for disposal of long lived radioactive waste are more complex, due to the long time scale that must be considered. Challenges and infrastructure needs, particularly for countries developing geologic repositories for disposal of high level wastes, are discussed in this paper. (author)

  1. Manned space stations - A perspective

    Science.gov (United States)

    Disher, J. H.

    1981-09-01

    The findings from the Skylab missions are discussed as they relate to the operations planning of future space stations such as Spacelab and the proposed Space Operations Center. Following a brief description of the Skylab spacecraft, the significance of the mission as a demonstration of the possibility of effecting emergency repairs in space is pointed out. Specific recommendations made by Skylab personnel concerning capabilities for future in-flight maintenance are presented relating to the areas of spacecraft design criteria, tool selection and spares carried. Attention is then given to relevant physiological findings, and to habitability considerations in the areas of sleep arrangements, hygiene, waste management, clothing, and food. The issue of contamination control is examined in detail as a potential major system to be integrated into future design criteria. The importance of the Skylab results to the designers of future space stations is emphasized.

  2. Man/machine interface for a nuclear cask remote handling control station: system design requirements

    International Nuclear Information System (INIS)

    Clarke, M.M.; Kreifeldt, J.G.; Draper, J.V.

    1984-01-01

    Design requirements are presented for a control station of a proposed semi-automated facility for remote handling of nuclear waste casks. Functional and operational man/machine interface: controls, displays, software format, station architecture, and work environment. In addition, some input is given to the design of remote sensing systems in the cask handling areas. 18 references, 9 figures, 12 tables

  3. Management of Radioactive Wastes

    International Nuclear Information System (INIS)

    Tchokosa, P.

    2010-01-01

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

  4. Incinerator for power reactor low-level radioactive waste

    International Nuclear Information System (INIS)

    Drolet, T.S.; Sovka, J.A.

    1976-01-01

    The technique chosen for volume reduction of combustible waste is incineration by a propane-fired unit. Noncombustible material will be compacted into 200 liter drums. A program of segregation of wastes at the producing nuclear stations was instituted. The design and operation of the incinerator, dose limits to the public, and derived release limits for airborne effluents are discussed

  5. Technical baseline description of high-level waste and low-activity waste feed mobilization and delivery

    International Nuclear Information System (INIS)

    Papp, I.G.

    1997-01-01

    This document is a compilation of information related to the high-level waste (HLW) and low-activity waste (LAW) feed staging, mobilization, and transfer/delivery issues. Information relevant to current Tank Waste Remediation System (TWRS) inventories and activities designed to feed the Phase I Privatization effort at the Hanford Site is included. Discussions on the higher level Phase II activities are offered for a perspective on the interfaces

  6. Nevada Test Site Waste Acceptance Criteria, December 2000

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2000-12-01

    This document establishes the US Department of Energy, Nevada Operations Office waste acceptance criteria. The waste acceptance criteria provides the requirements, terms, and conditions under which the Nevada Test Site will accept low-level radioactive waste and mixed waste for disposal. It includes requirements for the generator waste certification program, characterization, traceability, waste form, packaging, and transfer. The criteria apply to radioactive waste received at the Nevada Test Site Area 3 and Area 5 Radioactive Waste Management Sites for storage or disposal.

  7. Nevada Test Site Waste Acceptance Criteria, December 2000

    International Nuclear Information System (INIS)

    2000-01-01

    This document establishes the US Department of Energy, Nevada Operations Office waste acceptance criteria. The waste acceptance criteria provides the requirements, terms, and conditions under which the Nevada Test Site will accept low-level radioactive waste and mixed waste for disposal. It includes requirements for the generator waste certification program, characterization, traceability, waste form, packaging, and transfer. The criteria apply to radioactive waste received at the Nevada Test Site Area 3 and Area 5 Radioactive Waste Management Sites for storage or disposal

  8. Optimal waste-to-energy strategy assisted by GIS For sustainable solid waste management

    International Nuclear Information System (INIS)

    Tan, S T; Hashim, H; Lee, C T; Lim, J S; Kanniah, K D

    2014-01-01

    Municipal solid waste (MSW) management has become more complex and costly with the rapid socio-economic development and increased volume of waste. Planning a sustainable regional waste management strategy is a critical step for the decision maker. There is a great potential for MSW to be used for the generation of renewable energy through waste incineration or landfilling with gas capture system. However, due to high processing cost and cost of resource transportation and distribution throughout the waste collection station and power plant, MSW is mostly disposed in the landfill. This paper presents an optimization model incorporated with GIS data inputs for MSW management. The model can design the multi-period waste-to-energy (WTE) strategy to illustrate the economic potential and tradeoffs for MSW management under different scenarios. The model is capable of predicting the optimal generation, capacity, type of WTE conversion technology and location for the operation and construction of new WTE power plants to satisfy the increased energy demand by 2025 in the most profitable way. Iskandar Malaysia region was chosen as the model city for this study

  9. Optimal waste-to-energy strategy assisted by GIS For sustainable solid waste management

    Science.gov (United States)

    Tan, S. T.; Hashim, H.

    2014-02-01

    Municipal solid waste (MSW) management has become more complex and costly with the rapid socio-economic development and increased volume of waste. Planning a sustainable regional waste management strategy is a critical step for the decision maker. There is a great potential for MSW to be used for the generation of renewable energy through waste incineration or landfilling with gas capture system. However, due to high processing cost and cost of resource transportation and distribution throughout the waste collection station and power plant, MSW is mostly disposed in the landfill. This paper presents an optimization model incorporated with GIS data inputs for MSW management. The model can design the multi-period waste-to-energy (WTE) strategy to illustrate the economic potential and tradeoffs for MSW management under different scenarios. The model is capable of predicting the optimal generation, capacity, type of WTE conversion technology and location for the operation and construction of new WTE power plants to satisfy the increased energy demand by 2025 in the most profitable way. Iskandar Malaysia region was chosen as the model city for this study.

  10. Plasma vitrification of waste materials

    Science.gov (United States)

    McLaughlin, David F.; Dighe, Shyam V.; Gass, William R.

    1997-01-01

    This invention provides a process wherein hazardous or radioactive wastes in the form of liquids, slurries, or finely divided solids are mixed with finely divided glassformers (silica, alumina, soda, etc.) and injected directly into the plume of a non-transferred arc plasma torch. The extremely high temperatures and heat transfer rates makes it possible to convert the waste-glassformer mixture into a fully vitrified molten glass product in a matter of milliseconds. The molten product may then be collected in a crucible for casting into final wasteform geometry, quenching in water, or further holding time to improve homogeneity and eliminate bubbles.

  11. Plasma vitrification of waste materials

    International Nuclear Information System (INIS)

    McLaughlin, D.F.; Dighe, S.V.; Gass, W.R.

    1997-01-01

    This invention provides a process wherein hazardous or radioactive wastes in the form of liquids, slurries, or finely divided solids are mixed with finely divided glassformers (silica, alumina, soda, etc.) and injected directly into the plume of a non-transferred arc plasma torch. The extremely high temperatures and heat transfer rates makes it possible to convert the waste-glassformer mixture into a fully vitrified molten glass product in a matter of milliseconds. The molten product may then be collected in a crucible for casting into final wasteform geometry, quenching in water, or further holding time to improve homogeneity and eliminate bubbles. 4 figs

  12. The law on wastes. November 2016 - october 2017

    International Nuclear Information System (INIS)

    Lanoy, Laurence

    2017-01-01

    In France, the law on wastes has been subject to important reforms following the passing, in 2015, of the law on the 'energy transition for a green growth'. In the continuity of this law, various evolutions concerning regulations and jurisprudence have been applied. These evolutions mainly concern waste management modalities (technical prescriptions applicable to facilities receiving wastes, status of wastes, domestic wastes, radioactive wastes, special wastes and cross-border waste transfers, general orientations of French and European laws on wastes) and liabilities related to wastes (administrative liability, taxation related to wastes, waste producer liabilities)

  13. Defense High Level Waste Disposal Container System Description Document

    International Nuclear Information System (INIS)

    2000-01-01

    The Defense High Level Waste Disposal Container System supports the confinement and isolation of waste within the Engineered Barrier System of the Monitored Geologic Repository (MGR). Disposal containers are loaded and sealed in the surface waste handling facilities, transferred to the underground through the accesses using a rail mounted transporter, and emplaced in emplacement drifts. The defense high level waste (HLW) disposal container provides long-term confinement of the commercial HLW and defense HLW (including immobilized plutonium waste forms (IPWF)) placed within disposable canisters, and withstands the loading, transfer, emplacement, and retrieval loads and environments. U.S. Department of Energy (DOE)-owned spent nuclear fuel (SNF) in disposable canisters may also be placed in a defense HLW disposal container along with commercial HLW waste forms, which is known as 'co-disposal'. The Defense High Level Waste Disposal Container System provides containment of waste for a designated period of time, and limits radionuclide release. The disposal container/waste package maintains the waste in a designated configuration, withstands maximum handling and rockfall loads, limits the individual canister temperatures after emplacement, resists corrosion in the expected handling and repository environments, and provides containment of waste in the event of an accident. Defense HLW disposal containers for HLW disposal will hold up to five HLW canisters. Defense HLW disposal containers for co-disposal will hold up to five HLW canisters arranged in a ring and one DOE SNF canister in the ring. Defense HLW disposal containers also will hold two Multi-Canister Overpacks (MCOs) and two HLW canisters in one disposal container. The disposal container will include outer and inner cylinders, outer and inner cylinder lids, and may include a canister guide. An exterior label will provide a means by which to identify the disposal container and its contents. Different materials

  14. The CANDU 9 fuel transfer system

    International Nuclear Information System (INIS)

    Keszthelyi, Z.G.; Morikawa, D.T.

    1996-01-01

    The CANDU 9 fuel transfer system is based on the CANDU 6 and the Ontario Hydro Darlington NGD designs, modified to suit the CANDU 9 requirements. The CANDU 9 new fuel transfer system is very similar to the CANDU 6, with modifications to allow new fuel loading from outside containment, similar to Darlington. The CANDU 9 irradiated fuel transfer system is based on the Darlington irradiated fuel transfer system, with modifications to meet the more stringent containment requirements, improve performance, and match station layout. (author). 2 refs., 6 figs

  15. The CANDU 9 fuel transfer system

    Energy Technology Data Exchange (ETDEWEB)

    Keszthelyi, Z G [Canadian General Electric Co. Ltd., Peterborough, ON (Canada); Morikawa, D T [Atomic Energy of Canada Ltd., Mississauga, ON (Canada)

    1997-12-31

    The CANDU 9 fuel transfer system is based on the CANDU 6 and the Ontario Hydro Darlington NGD designs, modified to suit the CANDU 9 requirements. The CANDU 9 new fuel transfer system is very similar to the CANDU 6, with modifications to allow new fuel loading from outside containment, similar to Darlington. The CANDU 9 irradiated fuel transfer system is based on the Darlington irradiated fuel transfer system, with modifications to meet the more stringent containment requirements, improve performance, and match station layout. (author). 2 refs., 6 figs.

  16. Monitoring gas retention and slurry transport during the transfer of waste from Tank 241-C-106 to Tank 241-AY-102

    International Nuclear Information System (INIS)

    Stewart, C.W.; Erian, F.F.; Meyer, P.A.

    1997-07-01

    The retained gas volume can be estimated by several methods. All of these methods have significant uncertainties, but together they form a preponderance of evidence that describes the gas retention behavior of the tank. The methods are (1) an increase in nonconvective layer thickness; (2) a waste surface level rise (surface level effect [SLE] model); (3) the barometric pressure effect (BPE model); (4) direct void measurement; and (5) the consequences of the transfer process. The nonconvective layer thickness can be determined with sufficient accuracy to describe the overall waste configuration by means of temperature profiles or densitometer indications. However, the presence of a nonconvective layer does not necessarily indicate significant gas retention, and small changes in layer thickness that could quantify gas retention cannot be detected reliably with the methods available. The primary value of this measurement is in establishing the actual open-quotes fluffing factorclose quotes for thermal calculations. Surface level rise is not a useful measure of gas retention in Tank 241-C-106 (C-106) since the waste level fluctuates with regular makeup water additions. In Tank 241-AY-102 (AY-102) with the existing ventilation system it should be possible to determine the gas retention rate within 30-60% uncertainty from the surface level rise, should a significant rise be observed. The planned ventilation system upgrades in AY- 102 will greatly reduce the exhaust flow and the headspace humidity, and the evaporation rate should be significantly lower when transfers begin. This could reduce the uncertainty in gas retention rate estimates to around ± 10%

  17. Data Quality Objectives for Tank Farms Waste Compatibility Program

    International Nuclear Information System (INIS)

    BANNING, D.L.

    1999-01-01

    There are 177 waste storage tanks containing over 210,000 m 3 (55 million gal) of mixed waste at the Hanford Site. The River Protection Project (RPP) has adopted the data quality objective (DQO) process used by the U.S. Environmental Protection Agency (EPA) (EPA 1994a) and implemented by RPP internal procedure (Banning 1999a) to identify the information and data needed to address safety issues. This DQO document is based on several documents that provide the technical basis for inputs and decision/action levels used to develop the decision rules that evaluate the transfer of wastes. A number of these documents are presently in the process of being revised. This document will need to be revised if there are changes to the technical criteria in these supporting documents. This DQO process supports various documents, such as sampling and analysis plans and double-shell tank (DST) waste analysis plans. This document identifies the type, quality, and quantity of data needed to determine whether transfer of supernatant can be performed safely. The requirements in this document are designed to prevent the mixing of incompatible waste as defined in Washington Administrative Code (WAC) 173-303-040. Waste transfers which meet the requirements contained in this document and the Double-Shell Tank Waste Analysis Plan (Mulkey 1998) are considered to be compatible, and prevent the mixing of incompatible waste

  18. Transfer factor for 137Cs in fresh water aquatic environment

    International Nuclear Information System (INIS)

    Varughese, K.G.; Ramkumar, S.; John, Jaison T.; Rajan, M.P.; Gurg, R.P.

    2002-01-01

    137 Cs is one of the most abundant radionuclides produced in nuclear fission and due to its long radiological half-life and chemical similarity to potassium it has greater biological significance. Radioactive waste materials generated at nuclear facilities are generally disposed within the plant premises under its administrative control for effective radiation protection practices. However trace quantities of radionuclides are released into the environment through liquid and gaseous releases under the guidelines of regulatory agencies. The concentration of these radioactive elements in the environment is not detectable under normal circumstances due to the large dispersion and dilutions available in the environment. But these radionuclides can get accumulated in environmental matrices like silt, weed etc. and indicate the presence of radioactivity in the environment. This paper presents the results of a face-controlled studies conducted at Environmental Survey Laboratories at the Rajasthan Atomic Power Station (RAPS) and Kakrapar Atomic Power Station (KAPS) to estimate distribution of low-level radioactivity in the fresh water system. An attempt has been made to derive the Transfer Factor for 137 Cs in fish, weed, and silt and to evaluate the concentration of 137 Cs in water samples, which is otherwise not detectable under normal procedure of measurement. (author)

  19. Hazardous and Industrial Wastes Management: a Case Study of Khazra Industrial Park, Kerman

    Directory of Open Access Journals (Sweden)

    Hossein Jafari Mansoorian

    2013-08-01

    Full Text Available Background & Aims of the Study: Increasing hazardous industrial wastes and lack of necessary regulations for management of them have led to serious problems in some parts of Iran. The aim of this study was to evaluate the situation of collection, transportation, recycling, and disposal of hazardous industrial wastes in the Khazra Industrial Park of Kerman, Iran. Materials & Methods: This study was a descriptive cross-sectional study that was done using questionnaires and local visits during year 2009. In this questionnaire, some information about the industrial wastes, production, storage on site , collection, transformation, sorting, recycling, and disposal were recorded. Results:   In the Khazra Industrial Park, 71,600 kg/day of different industrial waste is produced. The biggest proportion of waste includes metals, and construction and demolition waste which are about 16,500 tons a year. The smallest proportion is non-iron metal waste, which is produced at a rate of 8 tons per year. 88.7 percent of the active industries at the Khazra Industrial Park produce solid industrial waste. Most of the industrial units do not use a united and coordinated system for storing waste and have no specific place for temporary storage inside the industrial park. The majority of industrial waste collection, which is about 59.8%, is done by private contractors. The industrial units transfer their waste separately, and just 9 industrial units recycle their waste. Disposal of these wastes is mainly done by selling to trading agencies. Each day, 3 tons of hazardous industrial waste is produced in this park. The highest production belongs to the oil factory (Keyhan Motor. Conclusions: According to the results, the Khazra Industrial Park needs a unified system for storing, transporting and collecting the sorted waste, and it also needs to have a transportation station with basic facilities. The wastes of most industrial units at the Khazra Industrial Park have the

  20. CFD modeling and experience of waste-to-energy plant burning waste wood

    DEFF Research Database (Denmark)

    Rajh, B.; Yin, Chungen; Samec, N.

    2013-01-01

    Computational Fluid Dynamics (CFD) is being increasingly used in industry for in-depth understanding of the fundamental mixing, combustion, heat transfer and pollutant formation in combustion processes and for design and optimization of Waste-to-Energy (WtE) plants. In this paper, CFD modeling...... the conversion of the waste wood in the fuel bed on the grate, which provides the appropriate inlet boundary condition for the freeboard 3D CFD simulation. The CFD analysis reveals the detailed mixing and combustion characteristics in the waste wood-fired furnace, pinpointing how to improve the design...

  1. Generation of domestic waste electrical and electronic equipment on Fernando de Noronha Island: qualitative and quantitative aspects.

    Science.gov (United States)

    Araujo, Dhiego Raphael Rodrigues; de Oliveira, José Diego; Selva, Vanice Fragoso; Silva, Maisa Mendonça; Santos, Simone Machado

    2017-08-01

    The accelerated growth trajectory of waste electrical and electronic equipment (WEEE) is a matter of concern for governments worldwide. In developing countries, the problem is more complex because municipal waste management is still a challenge for municipalities. Fernando de Noronha Island, an environmentally protected area, has a transfer station for solid waste before it is sent to the final destination abroad, which is different waste management model to most urban areas. In order to check the specifics of management of WEEE, this study aimed to qualitatively and quantitatively evaluate the generation of this type of waste on the main island of Fernando de Noronha, taking into consideration aspects related to consumption habits and handling of waste. During the in situ research, a questionnaire was applied to a sample of 83 households. The results provide a picture of the generation of WEEE for a period of 1 year, when a production of 1.3 tons of WEEE was estimated. Relationships between education level and monthly income and between education level and number of plasma/LCD TVs and washing machines were confirmed. Another important result is that only two socioeconomic variables (monthly income and education level) are related to two recycling behavior variables. In addition, the population and government treat WEEE as ordinary waste, ignoring its contaminant potential. Despite the existence of relevant legislation concerning the treatment and disposal of WEEE, additional efforts will be required by the government in order to properly manage this type of waste on the island.

  2. Virtual model of an automated system for the storage of collected waste

    Directory of Open Access Journals (Sweden)

    Enciu George

    2017-01-01

    Full Text Available One of the problems identified in waste collection integrated systems is the storage space. The design process of an automated system for the storage of collected waste includes finding solutions for the optimal exploitation of the limited storage space, seen that the equipment for the loading, identification, transport and transfer of the waste covers most of the available space inside the integrated collection system. In the present paper a three-dimensional model of an automated storage system designed by the authors for a business partner is presented. The storage system can be used for the following types of waste: plastic and glass recipients, aluminium cans, paper, cardboard and WEEE (waste electrical and electronic equipment. Special attention has been given to the transfer subsystem, specific for the storage system, which should be able to transfer different types and shapes of waste. The described virtual model of the automated system for the storage of collected waste will be part of the virtual model of the entire integrated waste collection system as requested by the beneficiary.

  3. Waste acceptance and logistics

    International Nuclear Information System (INIS)

    Carlson, James H.

    1992-01-01

    There are three major components which are normally highlighted when the Civilian Radioactive Waste Management Program is discussed - the repository, the monitored retrievable storage facility, and the transportation system. These are clearly the major physical system elements and they receive the greatest external attention. However, there will not be a successful, operative waste management system without fully operational waste acceptance plans and logistics arrangements. This paper will discuss the importance of developing, on a parallel basis to the normally considered waste management system elements, the waste acceptance and logistics arrangements to enable the timely transfer of spent nuclear fuel from more than one hundred and twenty waste generators to the Federal government. The paper will also describe the specific activities the Program has underway to make the necessary arrangements. (author)

  4. Sizewell 'B' power station public inquiry: CEGB proof of evidence

    International Nuclear Information System (INIS)

    Mawer, W.T.

    1982-11-01

    The cooling water system which would be needed for the proposed Sizewell B power station is described. The possible effects upon public safety, local fishing interests and the existing seabed are examined. Studies of the heat dispersion from outfalls, the location of offshore structures and the control of marine growth in the system are reported. Finally the essential service water system, the reserve ultimate heat sink, the discharge of liquid radioactive waste into the sea and the possible use of waste heat for agricultural and fish farming purposes are discussed. (U.K.)

  5. Technology transfer

    International Nuclear Information System (INIS)

    Boury, C.

    1986-01-01

    This paper emphasizes in the specific areas of design, engineering and component production. This paper presents what Framatome has to offer in these areas and its export oriented philosophy. Then, a typical example of this technology transfer philosophy is the collaboration with the South Korean firm, Korea Heavy Industries Corporation (KHIC) for the supply of KNU 9 and KNU 10 power stations

  6. Nuclear waste

    International Nuclear Information System (INIS)

    Anon.

    1983-01-01

    The Koeberg nuclear power station, planned to come on stream in 1984, is expected to save South Africa some six million t/annum of coal, and to contribute some 10 per cent of the country's electricity requirements. The use of nuclear energy will provide for growing national energy needs, and reduce high coal transport costs for power generation at the coast. In the long term, however, it gives rise to the controversial question of nuclear waste storage. The Atomic Energy Corporation of South Africa Ltd (AEC) recently announced the purchase of a site in Namaqualand (NW Cape) for the storage of low-level radioactive waste. The Nuclear Development Corporation of South Africa (Pty) Ltd, (NUCOR) will develop and operate the site. The South African Mining and Engineering Journal interviewed Dr P.D. Toens, manager of the Geology Department and Mr P.E. Moore, project engineer, on the subject of nuclear waste, the reasons behind Nucor's choice of site and the storage method

  7. The assay of encapsulated alpha-bearing waste: feasibility study

    International Nuclear Information System (INIS)

    Curry, R.G.

    1983-09-01

    This report contains a review of potentially applicable techniques for the determination of actinide isotopes in radioactive waste and a summary of results obtained with various prototype instruments. A schematic design of a complete assay station is derived with consideration given to practical aspects like remote handling, maintenance etc. and recommendations for further work are made. The place of waste assay in the overall quality assurance of packaged waste is also considered. (author)

  8. A University forum on low-level waste

    International Nuclear Information System (INIS)

    Ring, J.; Lorenzen, W.; Osborne, F.; Shapiro, J.

    1995-01-01

    This article describes the Biomedical Radioactive Waste Management Program at Harvard University. Included is an overview of the program and specific discussions of education of laboratory technicians; specific waste processing methods; laboratory decay-in-storage; packaging by researcher; processing in the local waste room; transfer from local disposal to on-site management facility; program results

  9. The Trencin water power station

    International Nuclear Information System (INIS)

    2005-01-01

    This leaflet describes the Trencin water power station. The Trencin water power station was built seven years after the Dubnica nad Vahom water power station started its operation and was the last stage of the first and the oldest derived cascade of water power stations on the Vah River. After completing water power stations at Ladce (1936), Ilava (1946) and Dubnica nad Vahom (1949) and before constructing the Trencin water power station, the whole second derived cascade of water power stations including water power stations at Kostolna, Nove Mesto nad Vahom and Horna Streda was built as soon as possible mainly because the need to get compensation for discontinued electricity supplies as well as energetic coal from the Czech Republic. Hereby, experiences from the construction of previous grades were used, mainly as far as the dimensioning was concerned, as the fi rst installed power stations had, in comparison with the growing requirements on the electricity supplies, very low absorption capacity - only 150 m 3 .s -1 . Thus the Trencin power station (original name was the Skalka power station) was already dimensioned for the same absorption capacity as the cascade located downstream the river, that is 180 m 3 .s -1 . That was related also to growing demands on electricity supplies during the peaks in the daily electric system load diagram, and thus to the transfer from continuous operation of the water power station to semi-peak or even peak performance. According to the standards of power station classification, the Trencin water power station is a medium size, low pressure, channel power station with two units equipped by Kaplan turbines and synchronous hydro-alternators. The water power station installed capacity is 16.1 MW in total and its designed annual production of electrical energy for medium water year is 85,000 MWh, while the average annual production during the last 30 years is 86,252 MWh. Installed unit has a four-blade Kaplan turbine with the diameter

  10. Molten metal technologies advance waste processing systems for liquid radioactive waste treatment for PWRs and BWRs

    International Nuclear Information System (INIS)

    Strand, Gary; Vance, Jene N.

    1997-01-01

    Molten Metal Technologies (MMT) has recently acquired a proprietary filtration process for specific use in radioactive liquid waste processing systems. The filtration system has been incorporated in to a PWR liquid radwaste system which is currently being designed for the ComEd Byron Nuclear Station. It has also been adopted as the prefiltration step up from of the two RO systems which were part of the VECTRA acquisition and which are currently installed in the ComEd Dresden and Lacily Nuclear Stations. The filtration process has been successfully pilot-tested at both Byron and Dresden and is currently being tested at LaSalle. The important features of the filtration process are the high removal efficiencies for particulates, including colloidal particles, and the low solid waste volume generation per gallon filtered which translates into very small annual solid waste volumes. This filtration process system has been coupled with the use of selective ion exchange media in the PWR processing system to reduce the solid waste volumes generated compared to the current processing methods and to reduce the curie quantities discharged to the environs. In the BWR processing system, this filtration method allows the coupling of an RO system to provide for recycling greater than 95% of the liquid radwaste back to the plant for reuse while significantly reducing the solid waste volumes and operating costs. This paper discusses the process system configurations for the MMT Advanced Waste Processing Systems for both PWRs and BWRs. In addition, the pilot test data and full-scale performance projections for the filtration system are discussed which demonstrate the important features of the filtration process

  11. The history of radwaste at Zion Station - its problems and solutions

    International Nuclear Information System (INIS)

    Bennett, K.J.

    1982-01-01

    Zion Station is located adjacent to Lake Michigan about 40 miles north of Chicago. The twin Zion units are four loop PWR's each rated at 1080 MWE with units 1 and 2 beginning commercial operation in 1973 and 1974 respectively. The radwaste system at Zion Station was designed in 1967 when radwaste operations of a nuclear power plant received little consideration. At Zion, the system was to be automated with occasional operator interface to pump down a tank when full or to solidify waste. The solidification equipment purchased was designed for the 40 year life of the station; due to the under estimation of the input to radwaste, this was not the case

  12. Performance assessment of Point Lepreau Generating Station

    International Nuclear Information System (INIS)

    Alikhan, S.

    1991-01-01

    The Point Lepreau Generating Station, a 680 MWe CANDU unit, is located about 40 km southwest of the city of Saint John, New Brunswick, Canada. It was declared in-service on 1 February, 1983 and, since then, has demonstrated an average cross capacity factor of over 93% up to the end of 1990. This paper compared the performance of the station with other sister CANDU units and the Light Water Reactors world-wide using the following ten performance indicators, as applicable: - gross capacity factor; - fuel burn-up; - heavy water upkeep; - unplanned reactor trips while critical; - forced outage rate; - fuel handling performance; - derived emission of radioactive effluents to environment; - personnel radiation dose; - industrial safety; - low-level solid radioactive wastes. The paper examines various areas of station activities including management and organization, operations and maintenance, technical support, fuel handling and health physics in order to highlight some of the 'good practices' which are believed to have made a significant contribution towards achieving the demonstrated performance of Point Lepreau G.S. In addition, several areas of potential improvement are discussed in order to maintain and enhance, where practicable, the safety, reliability and economic performance of the station. In this context, a careful review of the operating experiences, both in-house and at other stations, and a judicious application of lessons learned plays a significant role. (author)

  13. Performance assessment of Point Lepreau Generating Station

    Energy Technology Data Exchange (ETDEWEB)

    Alikhan, S [Point Lepreau Generating Station, Lepreau, NB (Canada)

    1991-04-01

    The Point Lepreau Generating Station, a 680 MWe CANDU unit, is located about 40 km southwest of the city of Saint John, New Brunswick, Canada. It was declared in-service on 1 February, 1983 and, since then, has demonstrated an average cross capacity factor of over 93% up to the end of 1990. This paper compared the performance of the station with other sister CANDU units and the Light Water Reactors world-wide using the following ten performance indicators, as applicable: - gross capacity factor; - fuel burn-up; - heavy water upkeep; - unplanned reactor trips while critical; - forced outage rate; - fuel handling performance; - derived emission of radioactive effluents to environment; - personnel radiation dose; - industrial safety; - low-level solid radioactive wastes. The paper examines various areas of station activities including management and organization, operations and maintenance, technical support, fuel handling and health physics in order to highlight some of the 'good practices' which are believed to have made a significant contribution towards achieving the demonstrated performance of Point Lepreau G.S. In addition, several areas of potential improvement are discussed in order to maintain and enhance, where practicable, the safety, reliability and economic performance of the station. In this context, a careful review of the operating experiences, both in-house and at other stations, and a judicious application of lessons learned plays a significant role. (author)

  14. Numerical analyses of the effect of a biphasic thermosyphon vapor channel sizes on the heat transfer intensity when heat removing from a power transformer of combined heat and power station

    Directory of Open Access Journals (Sweden)

    Nurpeiis Atlant

    2017-01-01

    Full Text Available Numerical analyses of the effect of a biphasic thermosyphon vapor channel sizes on the heat transfer intensity was conducted when heat removing from an oil tank of a power transformer of combined heat and power station (CHP. The power transformer cooling system by the closed biphasic thermosyphon was proposed. The mathematical modeling of heat transfer and phase transitions of coolant in the thermosyphon was performed. The problem of heat transfer is formulated in dimensionless variables “velocity vorticity vector – current function – temperature” and solved by finite difference method. As a result of numerical simulation it is found that an increase in the vapor channel length from 0.15m to 1m leads to increasing the temperature difference by 3.5 K.

  15. Waste Heat to Power Market Assessment

    Energy Technology Data Exchange (ETDEWEB)

    Elson, Amelia [ICF International, Fairfax, VA (United States); Tidball, Rick [ICF International, Fairfax, VA (United States); Hampson, Anne [ICF International, Fairfax, VA (United States)

    2015-03-01

    Waste heat to power (WHP) is the process of capturing heat discarded by an existing process and using that heat to generate electricity. In the industrial sector, waste heat streams are generated by kilns, furnaces, ovens, turbines, engines, and other equipment. In addition to processes at industrial plants, waste heat streams suitable for WHP are generated at field locations, including landfills, compressor stations, and mining sites. Waste heat streams are also produced in the residential and commercial sectors, but compared to industrial sites these waste heat streams typically have lower temperatures and much lower volumetric flow rates. The economic feasibility for WHP declines as the temperature and flow rate decline, and most WHP technologies are therefore applied in industrial markets where waste heat stream characteristics are more favorable. This report provides an assessment of the potential market for WHP in the industrial sector in the United States.

  16. Guidelines for generators of hazardous chemical waste at LBL and guidelines for generators of radioactive and mixed waste at LBL

    International Nuclear Information System (INIS)

    1993-10-01

    The purpose of this document is to provide the acceptance criteria for the transfer of hazardous chemical waste to LBL's Hazardous Waste Handling Facility (HWHF). Hazardous chemical waste is a necessary byproduct of LBL's research and technical support activities. This waste must be handled properly if LBL is to operate safely and provide adequate protection to staff and the environment. These guidelines describe how you, as a generator of hazardous chemical waste, can meet LBL's acceptance criteria for hazardous chemical waste

  17. RELEASE OF DRIED RADIOACTIVE WASTE MATERIALS TECHNICAL BASIS DOCUMENT

    International Nuclear Information System (INIS)

    KOZLOWSKI, D.S.

    2005-01-01

    The body of this document analyzes scenarios involving releases of dried tank waste from the DBVS dried waste transfer system and OGTS HEPA filters. Analyses of dried waste release scenarios from the CH-TRUM WPU are included as Appendix D

  18. Natural radionuclides near a coal-fired power station

    International Nuclear Information System (INIS)

    Smith-Briggs, J.L.

    1984-01-01

    A previous assessment of the radiological consequences of the emission of natural radionuclides from coal-fired power stations had indicated that 210 Pb was the main contributor to the maximum individual dose. This dose arose from the consumption of foodstuffs particularly cattle liver contaminated by deposited fly ash. Uncertainty surrounded some of the factors used in the assessment, and a limited environmental monitoring programme was recommended to improve it. An experiment has been performed to measure the specific activities of 210 Pb and 210 Po in livers from cattle that had grazed in a field near Didcot power station. Livers from cattle in the Cotswold region have been measured for comparison. The specific activities of 210 Pb and 210 Po in soil and grass samples from both areas have also been measured at three-monthly intervals over a year. No statistically significant increases were observed in the 210 Pb and 210 Po levels in liver, soil or grass samples which could be attributed to the operation of the power station. Transfer coefficients for 210 Pb from forage to liver were about two orders of magnitude less than that used in the original assessment, and the transfer coefficients for 210 Po about a factor a two less. (orig.)

  19. Space Station Freedom regenerative water recovery system configuration selection

    Science.gov (United States)

    Reysa, R.; Edwards, J.

    1991-01-01

    The Space Station Freedom (SSF) must recover water from various waste water sources to reduce 90 day water resupply demands for a four/eight person crew. The water recovery system options considered are summarized together with system configuration merits and demerits, resource advantages and disadvantages, and water quality considerations used to select the SSF water recovery system.

  20. Plasma arc and cold crucible furnace vitrification for medium level waste: a review

    International Nuclear Information System (INIS)

    Poitou, S.; Fiquet, O.; Bourdeloie, C.; Gramondi, P.; Rebollo, F.; Girold, C.; Charvillat, J.P.; Boen, R.; Jouan, A.; Ladirat, C.; Nabot, J.P.; Ochem, D.; Baronnet, J.M.

    2001-01-01

    Initially developed for high-level waste reprocessing, several vitrification processes have been under study since the 80's at the French Atomic Energy Commission (CEA) for other waste categories. According to the French law concerning waste management research passed on December 30, 1991, vitrification may be applied to mixed medium-level waste. A review of processes developed at CEA is presented: cold crucible furnace heated by induced current, refractory furnace heated by nitrogen transferred arc plasma torch, and coupling of cold crucible furnace with oxygen transferred plasma arc twin torch. Furthermore, gas post-combustion has been studied with an oxygen non-transferred plasma torch. (authors)

  1. Demonstrating Reliable High Level Waste Slurry Sampling Techniques to Support Hanford Waste Processing

    Energy Technology Data Exchange (ETDEWEB)

    Kelly, Steven E.

    2013-11-11

    The Hanford Tank Operations Contractor (TOC) and the Hanford Waste Treatment and Immobilization Plant (WTP) contractor are both engaged in demonstrating mixing, sampling, and transfer system capability using simulated Hanford High-Level Waste (HL W) formulations. This work represents one of the remaining technical issues with the high-level waste treatment mission at Hanford. The TOC must demonstrate the ability to adequately mix and sample high-level waste feed to meet the WTP Waste Acceptance Criteria and Data Quality Objectives. The sampling method employed must support both TOC and WTP requirements. To facilitate information transfer between the two facilities the mixing and sampling demonstrations are led by the One System Integrated Project Team. The One System team, Waste Feed Delivery Mixing and Sampling Program, has developed a full scale sampling loop to demonstrate sampler capability. This paper discusses the full scale sampling loops ability to meet precision and accuracy requirements, including lessons learned during testing. Results of the testing showed that the Isolok(R) sampler chosen for implementation provides precise, repeatable results. The Isolok(R) sampler accuracy as tested did not meet test success criteria. Review of test data and the test platform following testing by a sampling expert identified several issues regarding the sampler used to provide reference material used to judge the Isolok's accuracy. Recommendations were made to obtain new data to evaluate the sampler's accuracy utilizing a reference sampler that follows good sampling protocol.

  2. Demonstrating Reliable High Level Waste Slurry Sampling Techniques to Support Hanford Waste Processing

    International Nuclear Information System (INIS)

    Kelly, Steven E.

    2013-01-01

    The Hanford Tank Operations Contractor (TOC) and the Hanford Waste Treatment and Immobilization Plant (WTP) contractor are both engaged in demonstrating mixing, sampling, and transfer system capability using simulated Hanford High-Level Waste (HL W) formulations. This work represents one of the remaining technical issues with the high-level waste treatment mission at Hanford. The TOC must demonstrate the ability to adequately mix and sample high-level waste feed to meet the WTP Waste Acceptance Criteria and Data Quality Objectives. The sampling method employed must support both TOC and WTP requirements. To facilitate information transfer between the two facilities the mixing and sampling demonstrations are led by the One System Integrated Project Team. The One System team, Waste Feed Delivery Mixing and Sampling Program, has developed a full scale sampling loop to demonstrate sampler capability. This paper discusses the full scale sampling loops ability to meet precision and accuracy requirements, including lessons learned during testing. Results of the testing showed that the Isolok(R) sampler chosen for implementation provides precise, repeatable results. The Isolok(R) sampler accuracy as tested did not meet test success criteria. Review of test data and the test platform following testing by a sampling expert identified several issues regarding the sampler used to provide reference material used to judge the Isolok's accuracy. Recommendations were made to obtain new data to evaluate the sampler's accuracy utilizing a reference sampler that follows good sampling protocol

  3. Low-level radioactive wastes managements in universities, institutes and hospitals

    International Nuclear Information System (INIS)

    Kato, Sadatake

    1979-01-01

    Japan Radioisotope Association, which is distributing radioisotopes, also is collecting radioactive wastes from hospitals and other establishments using radioisotopes across the country. These wastes are then transferred to Japan Atomic Energy Research Institute for treatment. However, the capacity of JAERI is currently insufficient for the quantities transferred from JRA. A main cause for such difficulty as above is the increase in medical isotopes, i.e. radiopharmaceuticals, which are used in vivo and in vitro. From the RI consumptions thus far, the future demands and waste quantities are estimated for the purpose of establishing an overall joint treatment system. The following matters are described; the present situation of waste management in JRA and JAERI; current transitional phase; and radiopharmaceutical wastes (radiopharmaceuticals, their consumptions and future demands, and resultant waste RIs). (J.P.N.)

  4. USING CENTER HOLE HEAT TRANSFER TO REDUCE FORMATION TIMES FOR CERAMIC WASTE FORMS FROM PYROPROCESSING

    International Nuclear Information System (INIS)

    Kenneth J. Bateman; Charles W. Solbrig

    2006-01-01

    The waste produced from processing spent fuel from the EBR II reactor must be processed into a waste form suitable for long term storage in Yucca Mountain. The method chosen produces zeolite granules mixed with glass frit, which must then be converted into a solid. This is accomplished by loading it into a can and heating to 900 C in a furnace regulated at 915 C. During heatup to 900 C, the zeolite and glass frit react and consolidate to produce a sodalite monolith. The resultant ceramic waste form (CWF) is then cooled. The waste is 52 cm in diameter and initially 300 cm long but consolidates to 150 cm long during the heating process. After cooling it is then inserted in a 5-DHLW/DOE SNF Long Canister. Without intervention, the waste takes 82 hours to heat up to 900 C in a furnace designed to geometrically fit the cylindrical waste form. This paper investigates the reduction in heating times possible with four different methods of additional heating through a center hole. The hole size is kept small to maximize the amount of CWF that is processed in a single run. A hole radius of 1.82 cm was selected which removes only 1% of the CWF. A reference computation was done with a specified inner hole surface temperature of 915 C to provide a benchmark for the amount of improvement which can be made. It showed that the heatup time can potentially be reduced to 43 hours with center hole heating. The first method, simply pouring high temperature liquid aluminum into the hole, did not produce any noticeable effect on reducing heat up times. The second method, flowing liquid aluminum through the hole, works well as long as the velocity is high enough (2.5 cm/sec) to prevent solidification of the aluminum during the initial front movement of the aluminum into the center hole. The velocity can be reduced to 1 cm/sec after the initial front has traversed the ceramic. This procedure reduces the formation time to near that of the reference case. The third method, flowing a gas

  5. Waste Treatment Plant - 12508

    Energy Technology Data Exchange (ETDEWEB)

    Harp, Benton; Olds, Erik [US DOE (United States)

    2012-07-01

    equipment, cesium-ion exchange columns, evaporator boilers and recirculation pumps, and various mechanical process pumps for transferring process fluids. During the first phase of pretreatment, the waste will be concentrated using an evaporation process. Solids will be filtered out, and the remaining soluble, highly radioactive isotopes will be removed using an ion-exchange process. The high-level solids will be sent to the High-Level Waste (HLW) Vitrification Facility, and the low activity liquids will be sent to the Low-Activity Waste (LAW) Vitrification Facility for further processing. The high-level waste will be transferred via underground pipes to the HLW Facility from the Pretreatment Facility. The waste first arrives at the wet cell, which rests inside a black-cell area. The pretreated waste is transferred through shielded pipes into a series of melter preparation and feed vessels before reaching the melters. Liquids from various facility processes also return to the wet cell for interim storage before recycling back to the Pretreatment Facility. (authors)

  6. A review of near-field mass transfer in geologic disposal systems

    International Nuclear Information System (INIS)

    Pigford, T.H.; Chambre, P.L.; Lee, W.W.L.

    1990-02-01

    In this report we summarize the analyses of the time-dependent mass transfer of radionuclides from a waste solid into surrounding porous or fractured media that have been developed at the University of California, Berkeley. For each analysis we describe the conceptual model, we present the governing equations and the resulting analytic solutions, and we illustrate the results. Designers of geologic disposal systems for solid waste must predict the long-term time-dependent rate of dissolution of toxic contaminants in ground water, to provide the source term for predicting the later transport of these contaminants to the environment. Mass-transfer analysis is being used to predict rates of dissolution and release of radioactive constituents in future repositories for high-level radioactive waste, and it has been applied to predict the life of a copper container for high-level radioactive waste. Mechanistic analysis of mass-transfer is based on well-established theory of diffusive-convective transport. Its application requires experimental measurement of well-defined parameters such as porosity, solubility, diffusion coefficient, and pore velocity. Our first analysis assumed a waste solid in direct contact with porous rock. Subsequently we analyzed the more realistic situations of backfill between the waste and rock, rock with discrete fractures as well as pores, and the effects of waste constituents of high solubility. Those dealing with specifically with mass transfer in the near field are presented here. In order to have a consistent set of notation within this review, some of the notation here is different than in the reports cited. 71 refs., 47 figs., 7 tabs

  7. Pumps for nuclear power stations

    International Nuclear Information System (INIS)

    Ogura, Shiro

    1979-01-01

    16 nuclear power plants are in commercial operation in Japan, and nuclear power generation holds the most important position among various substitute energies. Hereafter also, it is expected that the construction of nuclear power stations will continue because other advantageous energy sources are not found. In this paper, the outline of the pumps used for BWR plants is described. Nuclear power stations tend to be large scale to reduce the construction cost per unit power output, therefore the pumps used are those of large capacity. The conditions to be taken in consideration are high temperature, high pressure, radioactive fluids, high reliability, hydrodynamic performances, aseismatic design, relevant laws and regulations, and quality assurance. Pumps are used for reactor recirculation system, control rod driving hydraulic system, boric acid solution injecting system, reactor coolant purifying system, fuel pool cooling and purifying system, residual heat removing system, low pressure and high pressure core spraying systems, and reactor isolation cooling system, for condensate, feed water, drain and circulating water systems of turbines, for fresh water, sea water, make-up water and fire fighting services, and for radioactive waste treating system. The problems of the pumps used for nuclear power stations are described, for example, the requirement of high reliability, the measures to radioactivity and the aseismatic design. (Kako, I.)

  8. Environmental assessment of waste incineration in a life-cycle-perspective (EASEWASTE)

    DEFF Research Database (Denmark)

    Riber, Christian; Bhander, Gurbakhash Singh; Christensen, Thomas Højlund

    2008-01-01

    of the wet waste incinerated. Emissions are either process-specific (related to the amount of waste incinerated) or input-specific (related to the composition of the waste incinerated), while mass transfer to solid outputs are governed by transfer coefficients specified by the user. The waste input......A model for life-cycle assessment of waste incinerators is described and applied to a case study for illustrative purposes. As life-cycle thinking becomes more integrated into waste management, quantitative tools for assessing waste management technologies are needed. The presented model...... in identifying the various processes and substances that contributed to environmental loadings as well as to environmental savings. The model was instrumental in demonstrating the importance of the energy recovery system not only for electricity but also heat from the incinerator....

  9. Radioactive wastes: present problems and future prospects

    International Nuclear Information System (INIS)

    Gauvenet, Andre

    1975-01-01

    The main characteristics of radioactive wastes are described and the present problems arising from liquid or gas effluents are considered. It is concluded that nuclear power stations are considerably less pollutant, at equal capacity, than conventional power stations. Programs of investigation are now being developed to meet with the foreseeable increase of activity. The problem is: first, to maintain absorbed doses at their present level and second, to study the problem of long-lived elements the storage of which would, in the long run create a nuisance on a world scale. The different waste storage techniques now in use are described and current investigations and works are exposed some of which, like vitrification, have already begun to be put into application. After having noted that the problem of wastes constitutes doubtless a difficulty in the technical field and, maybe even more so in the psychological field, the conditions are defined which will have to be met in order that this problem should not hinder the short- and long-term development of nuclear energy [fr

  10. 19 CFR 151.15 - Movement of merchandise to a centralized examination station.

    Science.gov (United States)

    2010-04-01

    ... 19 Customs Duties 2 2010-04-01 2010-04-01 false Movement of merchandise to a centralized... General § 151.15 Movement of merchandise to a centralized examination station. (a) Permission to transfer... following bonded movements for the transfer to the CES unless the type of bonded movement to be used is...

  11. Tank waste remediation system (TWRS) privatization contractor samples waste envelope D material 241-C-106

    Energy Technology Data Exchange (ETDEWEB)

    Esch, R.A.

    1997-04-14

    This report represents the Final Analytical Report on Tank Waste Remediation System (TWRS) Privatization Contractor Samples for Waste Envelope D. All work was conducted in accordance with ''Addendum 1 of the Letter of Instruction (LOI) for TWRS Privatization Contractor Samples Addressing Waste Envelope D Materials - Revision 0, Revision 1, and Revision 2.'' (Jones 1996, Wiemers 1996a, Wiemers 1996b) Tank 241-C-1 06 (C-106) was selected by TWRS Privatization for the Part 1A Envelope D high-level waste demonstration. Twenty bottles of Tank C-106 material were collected by Westinghouse Hanford Company using a grab sampling technique and transferred to the 325 building for processing by the Pacific Northwest National Laboratory (PNNL). At the 325 building, the contents of the twenty bottles were combined into a single Initial Composite Material. This composite was subsampled for the laboratory-scale screening test and characterization testing, and the remainder was transferred to the 324 building for bench-scale preparation of the Privatization Contractor samples.

  12. Waste Management Program. Technical progress report, Aporil-June 1983

    Energy Technology Data Exchange (ETDEWEB)

    None

    1984-02-01

    This quarterly report provides current information on operations and development programs for the management of radioactive wastes from operation of the Savannah River Plant. The studies on environmental and safety assessments, process and equipment development, TRU waste, and low-level waste are a part of the Long-Term Waste Management Technology Program. The following studies are reported for the SR Interim Waste Operations Program: surveillance and maintenance, waste concentration, low-level effluent waste, tank replacement/waste transfer, and solid waste storage and related activities.

  13. Commissioning and operation of the CEBAF end station refrigeration system

    International Nuclear Information System (INIS)

    Arenius, D.; Bevins, B.; Chronis, W.C.; Ganni, V.

    1996-01-01

    The CEBAF End Station Helium Refrigerator (ESR) System provides refrigeration at 80 K, 20 K and 4.5 K to three End Station experimental halls. The facility consists of a two stage helium screw compressor system, 4.5 K refrigerator, cryogen distribution valve box, and transfer lines to the individual experimental halls. The 4.5 K cold box and compressors were originally part of the ESCAR 1500 W, 4 K refrigeration system at Lawrence Berkeley Laboratory which was first commissioned in 1977. The compressors, 4.5 K cold box, and control system design were modified to adapt the plant for the requirements of the CEBAF experimental halls. Additional subsystems of cryogen distribution, transfer lines, warm gas management, and computer control interface were added. This paper describes the major plant subsystems, modifications, operational experiences and performance

  14. Effects of prevailing conditions during second Palestinian uprising on solid waste management system in Nablus city in Palestine.

    Science.gov (United States)

    Arafat, Hassan A; Al-Khatib, Issam A; Zahra, Abdulsalam Abu

    2006-08-01

    Since the start of the second Palestinian uprising (Al-Aqsa Intifada), and due to the Israeli activities, curfews, closures, and military checkpoints imposed since 2000, the quality of social services rendered by Nablus city has been gradually deteriorating. Solid waste management in Nablus city was badly affected by these conditions, and this situation is negatively affecting health and damaging the environment. Most of these cases were due to reasons beyond the capability of the municipality with its limited resources. This study revealed that some of the important municipal solid waste (MSW) equipment had been damaged during the uprising. The workforce in the MSW system was reduced and certain MSW-related development projects and activities have been frozen due to the current conditions. The city's medical waste incinerator had been phased out and the number of special medical containers had been reduced from 16 to 10. Some MSW compressing trucks had been out of use with no substitute. Another important figure is the number of waste collection workers which decreased from 420 to 301, although the city is growing in premises as well as population. The created unsanitary solid waste transfer station is now a pollution source on its own, causing an ugly scene at the eastern entrance of Nablus city. There should be a comprehensive and urgent solution for this problem and the needed resources should be invested.

  15. Process equipment waste and process waste liquid collection systems

    International Nuclear Information System (INIS)

    1990-06-01

    The US DOE has prepared an environmental assessment for construction related to the Process Equipment Waste (PEW) and Process Waste Liquid (PWL) Collection System Tasks at the Idaho Chemical Processing Plant. This report describes and evaluates the environmental impacts of the proposed action (and alternatives). The purpose of the proposed action would be to ensure that the PEW and PWL collection systems, a series of enclosed process hazardous waste, and radioactive waste lines and associated equipment, would be brought into compliance with applicable State and Federal hazardous waste regulations. This would be accomplished primarily by rerouting the lines to stay within the buildings where the lined floors of the cells and corridors would provide secondary containment. Leak detection would be provided via instrumented collection sumps locate din the cells and corridors. Hazardous waste transfer lines that are routed outside buildings will be constructed using pipe-in-pipe techniques with leak detection instrumentation in the interstitial area. The need for the proposed action was identified when a DOE-sponsored Resource Conservation and Recovery Act (RCRA) compliance assessment of the ICPP facilities found that singly-contained waste lines ran buried in the soil under some of the original facilities. These lines carried wastes with a pH of less than 2.0, which were hazardous waste according to the RCRA standards. 20 refs., 7 figs., 1 tab

  16. Contamination movement around a permeable reactive barrier at Solid Waste Management Unit 12, Naval Weapons Station Charleston, North Charleston, South Carolina, 2009

    Science.gov (United States)

    Vroblesky, Don A.; Petkewich, Matthew D.; Conlon, Kevin J.

    2010-01-01

    The U.S. Geological Survey and the Naval Facilities Engineering Command Southeast investigated natural and engineered remediation of chlorinated volatile organic compound groundwater contamination at Solid Waste Management Unit 12 at the Naval Weapons Station Charleston, North Charleston, South Carolina, beginning in 2000. In early 2004, groundwater contaminants began moving around the southern end of a permeable reactive barrier (PRB) installed by a consultant in December 2002. The PRB is a 130-foot-long and 3-foot-wide barrier consisting of varying amounts of zero-valent iron with or without sand mixture. Contamination moving around the PRB probably has been transported at least 75 feet downgradient from the PRB at a rate of about 15 to 29 feet per year.

  17. Discussion on the methods for calculation release limits for low-level radioactive waste

    International Nuclear Information System (INIS)

    Cao Fengbo; Liu Xiaochao

    2012-01-01

    The release request for low-level radioactive waste are briefly described in this paper. Associating with the conditions of low-level radioactive waste of some radioactive waste processing station, the methods and gist for calculating release limits for low-level radioactive waste with national release limits and annual effective dose limit for the public or the occupation are discussed. Then release limits for the low-level radioactive waste are also proposed. (authors)

  18. Loviisa Power Station - final disposal of reactor waste

    International Nuclear Information System (INIS)

    Vaajasaari, Marja

    1987-01-01

    This report is based on the earlier published results of research into the properties and function of the candidate backfill materials. The results of the backfill material research, and the sealing concepts presented in the literature have been evaluatedand applied to sealing the Loviisa Reactor Waste Repository taking into consideration the local rock and groundwater conditions. It is emphasised that the applicability of the presented backfill materials and plugs to repository sealing must still be carefully evaluated on the basis of detailed studies and the local environment. 24 refs

  19. Report on the state of radiation contamination in disaster waste

    International Nuclear Information System (INIS)

    Onishi, Yuko; Sasaki, Satoru; Yamada, Norikazu; Kawasaki, Satoru

    2011-09-01

    Fukushima Prefecture faces extreme difficulties in disposing of waste generated from the tsunami disaster (hereinafter referred to as disaster waste) and contaminated with radioactive material released from the crippled Fukushima Dai-ichi Nuclear Power Station. Although the waste should be treated according to the level of radioactivity, there are only air dose rates and radionuclide analyses of soil due to monitoring around the Fukushima Dai-ichi Nuclear Power Station and there has been no information on the radioactivity concentration of the disaster waste. The radioactivity concentration of the disaster waste was investigated by sampling measurement and in-situ Ge measurement at 20 temporary disaster waste storages in Fukushima Prefecture excluding the evacuation zone and 'deliberate evacuation zone.' JNES carried out this investigation upon a request from the Nuclear and Industrial Safety Agency. The investigation revealed that the measured radioactivity concentrations of the disaster waste lumps were enveloped within the soil monitoring readings in Fukushima Prefecture and also within a correlated curve between the air dose rates obtained from air dose rate readings around the disaster waste and the radioactivity concentrations of it. With these correlation curves, the radioactivity concentration of the disaster waste is estimated to be less than 8,000 Bq/kg at almost all places in the affected area excluding the evacuation zone and 'deliberate evacuation zone.' Measurements by in-situ Ge showed that the radioactivity of the disaster waste which had been expected to be more than 8,000 Bq/kg was less than 8,000 Bq/kg. (author)

  20. Mass transfer of CO2 to groundwaters from a near-surface waste disposal site

    International Nuclear Information System (INIS)

    Caron, F.; Wilkinson, S.R.; Manni, G.; Torok, J.

    1995-01-01

    Gaseous 14 CO 2 originating from buried low-level radioactive wastes (LLRW) in a near-surface disposal site can be released to the environment via two major paths: gas-phase diffusion through soils to the atmosphere, and dissolution in groundwater, followed by aqueous migration. Aqueous migration would give the highest dose to an individual, especially if C-14 was converted to an organic form and ingested. Gaseous diffusion would give a lower dose, largely because of atmospheric dispersion and dilution. The objective of this study was to develop the capability to estimate which of the two paths will likely be dominant for typical near-surface disposal facilities. The main missing parameter for making this estimate was a mass-transfer coefficient (K L ) of 14 CO 2 to groundwaters, which was determined experimentally using a large sand box. The K L thus determined was approximately 10 to 20 times smaller than for an open liquid surface. This suggests that there is a potential resistance to mass transfer, probably caused by the capillary fringe. The value obtained was incorporated into a simple model of CO 2 transport around a typical near-surface disposal site. The model suggests that CO 2 transport via both gaseous release and aqueous migration paths are of similar magnitude for a repository located ∼2 m above the water table. (author). 11 refs., 2 tabs., 2 figs