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Sample records for incineration research facility

  1. Consolidated incineration facility technical support

    International Nuclear Information System (INIS)

    Burns, D.; Looper, M.G.

    1993-01-01

    In 1996, the Savannah River Site plans to begin operation of the Consolidated Incineration Facility (CIF) to treat solid and liquid RCRA hazardous and mixed wastes. The Savannah River Technology Center (SRTC) leads an extensive technical support program designed to obtain incinerator and air pollution control equipment performance data to support facility start-up and operation. Key components of this technical support program include recently completed waste burn tests at both EPA's Incineration Research Facility and at Energy and Environmental Research Corporation's Solid Waste Incineration Test Facility. The main objectives for these tests were determining the fate of heavy metals, measuring organics destruction and removal efficiencies, and quantifying incinerator offgas particulate loading and size distribution as a function of waste feed characteristics and incineration conditions. In addition to these waste burning tests, the SRTC has recently completed installations of the Offgas Components Test Facility (OCTF), a 1/10 scale CIF offgas system pilot plant. This pilot facility will be used to demonstrate system operability and maintainability, evaluate and optimize equipment and instrument performance, and provide direct CIF start-up support. Technical support programs of this type are needed to resolve technical issues related with treatment and disposal of combustible hazardous, mixed, and low-level radioactive waste. Implementation of this program will minimize facility start-up problems and help insure compliance with all facility performance requirements

  2. SRL incinerator components test facility

    International Nuclear Information System (INIS)

    Freed, E.J.

    1982-08-01

    A full-scale (5 kg waste/hour) controlled-air incinerator, the ICTF, is presently being tested with simulated waste as part of a program to develop technology for incineration of Savannah River Plant solid transuranic wastes. This unit is designed specifically to incinerate relatively small quantities of solid combustible waste that are contaminated up to 10 5 times the present nominal 10 nCi/g threshold value for such isotopes as 238 Pu, 239 Pu, 242 Cm, and 252 Cf. Automatic incinerator operation and control has been incorporated into the design, simulating the future plant design which minimizes operator radiation exposure. Over 3000 kg of nonradioactive wastes characteristic of plutonium finishing operations have been incinerated at throughputs exceeding 5 kg/hr. Safety and reliability were the major design objectives. In addition to the incinerator tests, technical data were gathered on two different off-gas systems: a wet system composed of three scrubbers in series, and a dry system employing sintered metal filters

  3. Incineration facilities for treatment of radioactive wastes: a review

    Energy Technology Data Exchange (ETDEWEB)

    Perkins, B.L.

    1976-02-01

    A description is given of incinerator installations in the US and in foreign countries. Included are descriptions of inactive incinerators, incinerator facilities currently in operation, and incinerator installations under construction. Special features of each installation and operational problems of each facility are emphasized. Problems in the incineration of radioactive waste are discussed in relation to the composition of the waste and the amount and type of radioactive contaminant.

  4. Incineration facilities for treatment of radioactive wastes: a review

    International Nuclear Information System (INIS)

    Perkins, B.L.

    1976-02-01

    A description is given of incinerator installations in the US and in foreign countries. Included are descriptions of inactive incinerators, incinerator facilities currently in operation, and incinerator installations under construction. Special features of each installation and operational problems of each facility are emphasized. Problems in the incineration of radioactive waste are discussed in relation to the composition of the waste and the amount and type of radioactive contaminant

  5. ORGDP RCRA/PCB incinerator facility

    International Nuclear Information System (INIS)

    Rogers, T.

    1987-01-01

    A dual purpose solid/liquid incinerator is currently being constructed at the Oak Ridge Gaseous Diffusion Plant [ORGDP (K-25)] to destroy uranium contaminated, hazardous organic wastes in compliance with the Toxic Substances Control Act (TSCA) and the Resource Conservation and Recovery Act (RCRA). These wastes are generated by the gaseous diffusion plants in Oak Ridge, TN; Paducah, KY; and Portsmouth, OH. In addition, waste will also be received from the Y-12 Plant, Oak Ridge National Laboratory (ORNL), and the Feed Materials Production Center (FMPC). Destruction of PCBs and hazardous liquid organic wastes will be accomplished in a rotary kiln incinerator with an afterburner. This system was selected faster a study of various alternatives. Incineration was chosen because it is dependable, permanent, detoxifies organics, and reduces volume. The rotary kiln incinerator was selected because it can thermally destroy organic constituents of liquids, solids, and sludges to produce an organically inert ash. In addition to the incineration off-gas treatment system, the facility includes a tank farm, drum storage buildings, a solids preparation area, a control room, and a data management system. The incineration system, off-gas treatment system, and related instrumentation and controls are being provided by International Waste Energy Systems (IWES) which is responsible for design, construction, startup, and performances testing

  6. Consolidated Incineration Facility waste burn test. Final report

    International Nuclear Information System (INIS)

    Burns, D.B.

    1995-01-01

    The Savannah River Technology Center (SRTC) is Providing technical support for start-up and operation of the Consolidated Incineration Facility. This support program includes a series of pilot incineration tests performed at the Environmental Protection Agency's (EPA's) Incineration Research Facility (MF) using surrogate CIF mixed wastes. The objectives for this test program included measuring incinerator offgas particulate loading and size distributions as a function of several operating variables, characterizing kiln bottom ash and offgas particulates, determining heavy metal partition between the kiln bottom ash and incinerator stack gas, and measuring kiln organics emissions (particularly polychlorinated dioxins and furans). These tests were designed to investigate the effect of the following operating parameters: Incineration Temperature; Waste Feed Rate; Waste Density; Kiln Solids Residence Time; and Waste Composition. Tests were conducted at three kiln operating temperatures. Three solid waste simulants were burned, two waste mixtures (paper, plastic, latex, and PVC) with one containing spiked toxic organic and metal compounds, and one waste type containing only paper. Secondary Combustion Chamber (SCC) offgases were sampled for particulate loading and size distribution, organic compounds, polychlorinated dibenzo[p]dioxins and polychlorinated dibenzofurans (PCDD/PCDF), metals, and combustion products. Kiln bottom ash and offgas particulates were characterized to determine the principal elements and compounds comprising these secondary wastes

  7. Exposure dose evaluation of worker at radioactive waste incineration facility on KAERI

    International Nuclear Information System (INIS)

    Park, Sang Kyu; Jeon, Jong Seon; Kim, Youn Hwa; Lee, Jae Min; Lee, Gi Won

    2011-01-01

    An incineration treatment of inflammable radioactive wastes leads to have a reduction effect of disposal cost and also to contribute an enhancement of safety at a disposal site by taking the advantage of stabilization of the wastes which is accomplished by converting organic materials into inorganic materials. As it was required for an incineration technology, KAERI (Korea Atomic Energy Research Institute) has developed a pilot incineration process and then constructed a demonstration incineration facility having based on the operating experiences of the pilot process. In this study, worker exposure doses were evaluated to confirm safety of workers before the demonstration incineration facility will commence a commercial. (author)

  8. The Savannah River Plant Consolidated Incineration Facility

    International Nuclear Information System (INIS)

    Weber, D.A.

    1987-01-01

    A full scale incinerator is proposed for construction at the Savannah River Plant (SRP) beginning in August 1989 for detoxifiction and volume reduction of liquid and solid low-level radioactive, mixed and RCRA hazardous waste. Wastes to be burned include drummed liquids, sludges and solids, liquid process wastes, and low-level boxed job control waste. The facility will consist of a rotary kiln primary combustion chamber followed by a tangentially fired cylindrical secondary combustion chamber (SCC) and be designed to process up to 12 tons per day of solid and liquid waste. Solid waste packaged in combustible containers will be fed to the rotary kiln incinerator using a ram feed system and liquid wastes will be introduced to the rotary kiln through a burner nozzle. Liquid waste will also be fed through a high intensity vortex burner in the SCC. Combustion gases will exit the SCC and be cooled to saturation in a spray quench. Particulate and acid gas are removed in a free jet scrubber. The off-gas will then pass through a cyclone separator, mist eliminator, reheater high efficiency particulate air (HEPA) filtration and induced draft blowers before release to the atmosphere. Incinerator ash and scrubber blowdown will be immobilized in a cement matrix and disposed of in an onsite RCRA permitted facility. The Consolidated Incineration Facility (CIF) will provide detoxification and volume reduction for up to 560,000 CUFT/yr of solid waste and up to 35,700 CUFT/yr of liquid waste. Up to 50,500 CUFT/yr of cement stabilized ash and blowdown will beproduced for an average overall volume reduction fator of 22:1. 3 figs., 2 tabs

  9. Project No. 4 - Waste incineration facility

    International Nuclear Information System (INIS)

    2000-01-01

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

  10. Initial emission assessment of hazardous-waste-incineration facilities

    International Nuclear Information System (INIS)

    Harrington, E.S.; Holton, G.A.; O'Donnell, F.R.

    1982-01-01

    Health and Safety Research Division, sponsored by EPA, conducted a study to quantify emission factors from stacks, spills, fugitives, storage, and treatment for a typical hazardous waste incinerator facility. Engineering participated in preparing flowsheets and providing calculations for fugitive emissions. Typical block-flow diagrams were developed two types of hazardous waste incinerators (rotary kiln and liquid-injector) and for three capacities (small: 1 MM Btu/hr, median: 10 MM Btu/hr, and large: 150 MM Btu/hr). Storage reqirements and support services were determined in more detail. Using the properties of a typical waste, fugitive emissions were determined, including emissions from pump leaks, valve leaks, flange leaks, and tank vents. An atmospheric dispersion model was then employed to calculate atmospheric concentration and population exposure estimates. With these estimates, an assessment was performed to determine the percentage of concentrations and exposure associated with selected emissions from each source at the incineration facility. Results indicated the relative importance of each source at the incineration facility. Results indicated the relative importance of each source both in terms of public health and pollution control requirements

  11. CIF---Design basis for an integrated incineration facility

    International Nuclear Information System (INIS)

    Bennett, G.F.

    1991-01-01

    This paper discusses the evolution of chosen technologies that occurred during the design process of the US Department of Energy (DOE) incineration system designated the Consolidated Incineration Facility (CIF) as the Savannah River Plant, Aiken, South Carolina. The Plant is operated for DOE by the Westinghouse Savannah River Company. The purpose of the incineration system is to treat low level radioactive and/or hazardous liquid and solid wastes by combustion. The objective for the facility is to thermally destroy toxic constituents and volume reduce waste material. Design criteria requires operation be controlled within the limits of RCRA's permit envelope

  12. Design and operation of radioactive waste incineration facilities

    International Nuclear Information System (INIS)

    1992-01-01

    The purpose of this guide is to provide safety guidance for the design and operation of radioactive waste incineration facilities. The guide emphasizes the design objectives and system requirements to be met and provides recommendations for the procedure of process selection and equipment design and operation. It is recognized that some incinerators may handle only very low or 'insignificant' levels of radioactivity, and in such cases some requirements or recommendations of this guide may not fully apply. Nevertheless, it is expected that any non-compliance with the guide will be addressed and justified in the licensing process. It is also recognized that the regulatory body may place a limit on the level of the radioactivity of the waste to be incinerated at a specific installation. For the purpose of this guide an insignificant level of release of radioactivity may typically be defined as either the continuous or single event release of the design basis radionuclide inventory that represents a negligible risk to the population, the operating personnel, and/or the environment. The guidance on what constitutes a negligible risk and how to translate negligible risk or dose into level of activity can be found in Safety Series No. 89, IAEA, Vienna. 20 refs, 1 fig

  13. Incineration

    International Nuclear Information System (INIS)

    Holmes, R.G.G.

    1988-01-01

    One of the methods of destroying organics in radwaste is incineration. This presentation will summarise some of the advantages and problems associated with incineration and will illustrate some of these points by discussing progress in an options study into methods of treating plutonium contaminated material waste, being carried out by British Nuclear Fuels plc. The wastes amenable for treatment, fall into two categories, low-level wastes and intermediate-level wastes. (author)

  14. Waste Incinerator

    International Nuclear Information System (INIS)

    1994-05-01

    This book deals with plan and design of waste incinerator, which includes process outline of waste, method of measure, test, analysis, combustion way and classification of incineration facilities, condition of combustion and incineration, combustion calculation and heat calculation, ventilation and flow resistivity, an old body and component materials of supplementary installation, attached device, protection of pollution of incineration ash and waste gas, deodorization, prevention of noise in incineration facility, using heat and electric heat, check order of incineration plan.

  15. Commercial regional incinerator facility for treatment of low-level radioactive waste

    International Nuclear Information System (INIS)

    Sauer, R.E.

    1984-01-01

    In 1981, US Ecology, Inc. began studies on the feasibility of constructing and operating a regional radioactive waste incinerator facility. In December, 1982, US Ecology requested turnkey quotations from several vendors for engineering, procurement, and construction of the new facility. After technical and commercial evaluations, a contract was awarded to Associated Technologies, Inc., of Charlotte, North Carolina, in June, 1983. In June, 1984, US Ecology made a public announcement that they were studying two sites in North Carolina for location of the facility. This same month, they submitted their permit application for a radioactive material license to the North Carolina Department of Human Resources. The facility will accept wastes from power reactors, medical and research institutions and other industrial users, and will incinerate dry solid waste, pathological waste, scintillation fluids, and turbine oils. The incinerator will be a dual chamber controlled air design, rated at 600 lbs/hr, with a venturi scrubber, packed column, HEPA, and charcoal filters for pollution control. The stack will have a continuous monitor

  16. Commercial regional incinerator facility for treatment of low-level radioactive waste

    International Nuclear Information System (INIS)

    Sauer, R.E.; Jessop, D.; Associated Technologies, Inc., Charlotte, NC)

    1985-01-01

    In 1981, US Ecology, Inc. began studies on the feasibility of constructing and operating a regional radioactive waste incinerator facility. In December, 1982, US Ecology requested turnkey quotations from several vendors for engineering, procurement, and construction of the new facility. After technical and commercial evaluations, a contract was awarded to Associated Technologies, Inc., of Charlotte, North Carolina, in June, 1983. In June, 1984, US Ecology made a public announcement that they were studying two sites in North Carolina for location of the facility. This same month, they submitted their permit application for a radioactive material license to the North Carolina Department of Human Resources. The facility will accept wastes from power reactors, medical and research institutions and other industrial users, and will incinerate dry solid waste, pathological waste, scintillation fluids, and turbine oils. The incinerator will be a dual chamber controlled air design, rated at 600 lbs/h, with a venturi scrubber, packed column, HEPA, and charcoal filters for pollution control. The stack will have a continuous monitor. 4 figs

  17. Suitability of oil bioremediation in an Artic soil using surplus heating from an incineration facility

    DEFF Research Database (Denmark)

    Couto, Nazare; Fritt-Rasmussen, Janne; Jensen, Pernille Erland

    2014-01-01

    A 168-day period field study, carried out in Sisimiut, Greenland, assessed the potential to enhance soil remediation with the surplus heating from an incineration facility. This approach searches a feasible ex situ remediation process that could be extended throughout the year with low costs. Ind...... with low maintenance and using "waste heating" from an incineration facility....

  18. Opportunities for artificial intelligence application in computer- aided management of mixed waste incinerator facilities

    International Nuclear Information System (INIS)

    Rivera, A.L.; Ferrada, J.J.; Singh, S.P.N.

    1992-01-01

    The Department of Energy/Oak Ridge Field Office (DOE/OR) operates a mixed waste incinerator facility at the Oak Ridge K-25 Site. It is designed for the thermal treatment of incinerable liquid, sludge, and solid waste regulated under the Toxic Substances Control Act (TSCA) and the Resource Conservation and Recovery Act (RCRA). This facility, known as the TSCA Incinerator, services seven DOE/OR installations. This incinerator was recently authorized for production operation in the United States for the processing of mixed (radioactively contaminated-chemically hazardous) wastes as regulated under TSCA and RCRA. Operation of the TSCA Incinerator is highly constrained as a result of the regulatory, institutional, technical, and resource availability requirements. These requirements impact the characteristics and disposition of incinerator residues, limits the quality of liquid and gaseous effluents, limit the characteristics and rates of waste feeds and operating conditions, and restrict the handling of the waste feed inventories. This incinerator facility presents an opportunity for applying computer technology as a technical resource for mixed waste incinerator operation to facilitate promoting and sustaining a continuous performance improvement process while demonstrating compliance. Demonstrated computer-aided management systems could be transferred to future mixed waste incinerator facilities

  19. Waste incineration and immobilization for nuclear facilities. Status report, October 1977--March 1978

    International Nuclear Information System (INIS)

    Johnson, A.J.; Burkhardt, S.C.; Ledford, J.A.; Williams, P.M.

    1979-01-01

    Fluidized bed incineration and processes for immobilization of wastes generated at nuclear facilities are undergoing development. After minor piping modifications to eliminate dust collecting points, a pilot plant fluidized bed incinerator run of 225 continuous hours was successfully completed in a demonstration of component reliability. Vitrification of incinerator ash and other wastes is now being accomplished using a pilot scale unit developed as a continuous flow process

  20. DEMOLITION OF HANFORD'S 232-Z WASTE INCINERATION FACILITY

    International Nuclear Information System (INIS)

    LLOYD, E.R.

    2006-01-01

    The 232-Z Plutonium Incinerator Facility was a small, highly alpha-contaminated, building situated between three active buildings located in an operating nuclear complex. Approximately 500 personnel worked within 250 meters (800 ft) of the structure and expectations were that the project would neither impact plant operations nor result in any restrictions when demolition was complete. Precision demolition and tight controls best describe the project. The team used standard open-air demolition techniques to take the facility to slab-on-grade. Several techniques were key to controlling contamination and confining it to the demolition area: spraying fixatives before demolition began; using misting systems, frequently applying fixatives, and using a methodical demolition sequence and debris load-out process. Detailed air modeling was done before demolition to determine necessary facility source-term levels, establish radiological boundaries, and confirm the adequacy of the proposed demolition approach. By only removing the major source term in equipment, HEPA filters, gloveboxes, and the like, and leaving fixed contamination on the walls, ceilings and floors, the project showed considerable savings and reduced worker hazards and exposure. The ability to perform this demolition safely and without the spread of contamination provides confidence that similar operations can be performed successfully. By removing the major source terms, fixing the remaining contamination in the building, and using controlled demolition and contamination control techniques, similar structures can be demolished cost effectively and safely

  1. 78 FR 34918 - Direct Final Approval of Sewage Sludge Incinerators State Plan for Designated Facilities and...

    Science.gov (United States)

    2013-06-11

    ... Approval of Sewage Sludge Incinerators State Plan for Designated Facilities and Pollutants; Indiana AGENCY... to control air pollutants from ``Sewage Sludge Incinerators'' (SSI). The Indiana Department of... unit,'' in part, as any device that combusts sewage sludge for the purpose of reducing the volume of...

  2. The estimation of N2O emissions from municipal solid waste incineration facilities: The Korea case

    International Nuclear Information System (INIS)

    Park, Sangwon; Choi, Jun-Ho; Park, Jinwon

    2011-01-01

    The greenhouse gases (GHGs) generated in municipal solid waste (MSW) incineration are carbon dioxide (CO 2 ), methane (CH 4 ), and nitrous oxide (N 2 O). In South Korea case, the total of GHGs from the waste incineration facilities has been increasing at an annual rate 10%. In these view, waste incineration facilities should consider to reduce GHG emissions. This study is designed to estimate the N 2 O emission factors from MSW incineration plants, and calculate the N 2 O emissions based on these factors. The three MSW incinerators examined in this study were either stoker or both stoker and rotary kiln facilities. The N 2 O concentrations from the MSW incinerators were measured using gas chromatography-electron capture detection (GC-ECD) equipment. The average of the N 2 O emission factors for the M01 plant, M02 plant, and M03 plant are 71, 75, and 153 g-N 2 O/ton-waste, respectively. These results showed a significant difference from the default values of the intergovernmental panel on climate change (IPCC), while approaching those values derived in Japan and Germany. Furthermore, comparing the results of this study to the Korea Energy Economics Institute (KEEI) (2007) data on waste incineration, N 2 O emissions from MSW incineration comprised 19% of the total N 2 O emissions.

  3. The estimation of N2O emissions from municipal solid waste incineration facilities: The Korea case.

    Science.gov (United States)

    Park, Sangwon; Choi, Jun-Ho; Park, Jinwon

    2011-08-01

    The greenhouse gases (GHGs) generated in municipal solid waste (MSW) incineration are carbon dioxide (CO(2)), methane (CH(4)), and nitrous oxide (N(2)O). In South Korea case, the total of GHGs from the waste incineration facilities has been increasing at an annual rate 10%. In these view, waste incineration facilities should consider to reduce GHG emissions. This study is designed to estimate the N(2)O emission factors from MSW incineration plants, and calculate the N(2)O emissions based on these factors. The three MSW incinerators examined in this study were either stoker or both stoker and rotary kiln facilities. The N(2)O concentrations from the MSW incinerators were measured using gas chromatography-electron capture detection (GC-ECD) equipment. The average of the N(2)O emission factors for the M01 plant, M02 plant, and M03 plant are 71, 75, and 153g-N(2)O/ton-waste, respectively. These results showed a significant difference from the default values of the intergovernmental panel on climate change (IPCC), while approaching those values derived in Japan and Germany. Furthermore, comparing the results of this study to the Korea Energy Economics Institute (KEEI) (2007) data on waste incineration, N(2)O emissions from MSW incineration comprised 19% of the total N(2)O emissions. Crown Copyright © 2011. Published by Elsevier Ltd. All rights reserved.

  4. Beta-gamma contaminated solid waste incinerator facility

    Energy Technology Data Exchange (ETDEWEB)

    Hootman, H.E.

    1979-10-01

    This technical data summary outlines a reference process to provide a 2-stage, 400 lb/hour incinerator to reduce the storage volume of combustible process waste contaminated with low-level beta-gamma emitters in response to DOE Manual 0511. This waste, amounting to more than 200,000 ft/sup 3/ per year, is presently buried in trenches in the burial ground. The anticipated storage volume reduction from incineration will be a factor of 20. The incinerator will also dispose of 150,000 gallons of degraded solvent from the chemical separations areas and 5000 gallons per year of miscellaneous nonradioactive solvents which are presently being drummed for storage.

  5. Waste incineration and immobilization for nuclear facilities, April--September 1977

    International Nuclear Information System (INIS)

    Johnson, A.J.; Fong, L.Q.

    1978-01-01

    Fluidized bed incineration and waste immobilization processes are being developed to process the types of waste expected from nuclear facilities. An air classification system has been developed to separate tramp metal from shredded combustible solid waste prior to the waste being fed to a fluidized-bed pilot-plant incinerator. Used organic ion exchange resin with up to 55 percent water has been effectively burned in the fluidized bed incinerator. Various methods of feeding waste into the incinerator were investigated as alternatives to the present compression screw; an extrusion ram was found to suffer extensive damage from hard particles in tested waste. A bench-scale continuous waste immobilization process has been operated and has produced glass from incinerator residue and other types of waste materials

  6. Waste incineration and immobilization for nuclear facilities. Status report, April-September 1978

    International Nuclear Information System (INIS)

    Johnson, A.J.; Williams, P.M.; Burkhardt, S.C.; Ledford, J.A.; Gallagher, K.Y.

    1980-01-01

    The fluidized bed incinerator and waste immobilization processes are being developed to process various liquid and solid wastes that are generated by a nuclear facility. The versatility of the incinerator liquid waste handling system has been enhanced by recent changes made in the pumping and related piping system. Tributyl phosphate-solvent incineration has been evaluated thoroughly using the pilot plant fluidized bed incinerator. Vitrified glass pellets were made to determine operating parameters of a resistance-heated reactor and to produce samples for testing. Procedures were developed for testing the product pellets. A simplified start-up procedure was devised as development continued on a second type of reactor, the Joule-heated melter

  7. Facility status and progress of the INEL's WERF MLLW and LLW incinerator

    International Nuclear Information System (INIS)

    Conley, D.; Corrigan, S.

    1996-01-01

    The Idaho National Engineering Laboratory's (INEL) Waste Experimental Reduction Facility (WERF) incinerator began processing beta/gamma- emitting low-level waste (LLW) in September 1984. A Resource Conservation and Recovery Act (RCRA) trial burn for the WERF incinerator was conducted in 1986, and in 1989 WERF began processing (hazardous and low-level radioactive) waste known as mixed low-level waste (MLLW). On February 14, 1991 WERF operations were suspended to improve operating procedures and configuration management. On July 12, 1995, WERF initiated incineration of LLW; and on September 20, 1995 WERF resumed its primary mission of incinerating MLLW. MLLW incineration is proceeding under RCRA interim status. State of Idaho issuance of the Part B permit is one of the State's highest permitting priorities. The State of Idaho's Division of Environmental Quality is reviewing the permit application along with a revised trial burn plan that was also submitted with the application. The trial burn has been proposed to be performed in 1996 to demonstrate compliance with the current incinerator guidance. This paper describes the experiences and problems associated with WERF's operations, incineration of MLLW, and the RCRA Part B Permit Application. Some of the challenges that have been overcome include waste characterization, waste repackaging, repackaged waste storage, and implementation of RCRA interim status requirements. A number of challenges remain. They include revision of the RCRA Part B Permit Application and the Trial Burn Plan in response to comments from the state permit application reviewers as well as facility and equipment upgrades required to meet RCRA Permitted Status

  8. A Strategy for Quantifying Radioactive Material in a Low-Level Waste Incineration Facility

    International Nuclear Information System (INIS)

    Hochel, R.C.

    1997-03-01

    One of the methods proposed by the U.S. Department of Energy (DOE) for the volume reduction and stabilization of a variety of low-level radioactive wastes (LLW) is incineration. Many commercial incinerators are in operation treating both non-hazardous and hazardous wastes. These can obtain volume reductions factors of 50 or more for certain wastes, and produce a waste (ash) that can be easily stabilized if necessary by vitrification or cementation. However, there are few incinerators designed to accommodate radioactive wastes. One has been recently built at the Savannah River Site (SRS) near Aiken, SC and is burning non-radioactive hazardous waste and radioactive wastes in successive campaigns. The SRS Consolidated Incineration Facility (CIF) is RCRA permitted as a Low Chemical Hazard, Radiological facility as defined by DOE criteria (Ref. 1). Accordingly, the CIF must operate within specified chemical, radionuclide, and fissile material inventory limits (Ref. 2). The radionuclide and fissile material limits are unique to radiological or nuclear facilities, and require special measurement and removal strategies to assure compliance, and the CIF may be required to shut down periodically in order to clean out the radionuclide inventory which builds up in various parts of the facility

  9. Overview of a conceptualized waste water treatment facility for the Consolidated Incinerator Facility

    International Nuclear Information System (INIS)

    McCabe, D.J.

    1992-01-01

    The offgas system in the Consolidated Incinerator Facility (CIF) will generate an aqueous waste stream which is expected to contain hazardous, nonhazardous, and radioactive components. The actual composition of this waste stream will not be identified until startup of the facility, and is expected to vary considerably. Wastewater treatment is being considered as a pretreatment to solidification in order to make a more stable final waste form and to reduce disposal costs. A potential treatment scenario has been defined which may allow disposition of this waste in compliance with all applicable regulations. The conceptualized wastewater treatment plant is based on literature evaluations for treating hazardous metals. Laboratory tests hwill be run to verify the design for its ability to remove the hazardous and radioactive components from this waste stream. The predominant mechanism employed for removal of the hazardous and radioactive metal ions is coprecipitation. The literature indicates that reasonably low quantities of hazardous metals can be achieved with this technique. The effect on the radioactive metal ions is not predictable and has not been tested. The quantity of radioactive metal ions predicted to be present in the waste is significantly less than the solubility limit of those ions, but is higher than the discharge guidelines established by DOE Order 5400.5

  10. Basic Research Firing Facility

    Data.gov (United States)

    Federal Laboratory Consortium — The Basic Research Firing Facility is an indoor ballistic test facility that has recently transitioned from a customer-based facility to a dedicated basic research...

  11. Potential applications of artificial intelligence in computer-based management systems for mixed waste incinerator facility operation

    International Nuclear Information System (INIS)

    Rivera, A.L.; Singh, S.P.N.; Ferrada, J.J.

    1991-01-01

    The Department of Energy/Oak Ridge Field Office (DOE/OR) operates a mixed waste incinerator facility at the Oak Ridge K-25 Site, designed for the thermal treatment of incinerable liquid, sludge, and solid waste regulated under the Toxic Substances Control Act (TSCA) and the Resource Conversion and Recovery Act (RCRA). Operation of the TSCA Incinerator is highly constrained as a result of the regulatory, institutional, technical, and resource availability requirements. This presents an opportunity for applying computer technology as a technical resource for mixed waste incinerator operation to facilitate promoting and sustaining a continuous performance improvement process while demonstrating compliance. This paper describes mixed waste incinerator facility performance-oriented tasks that could be assisted by Artificial Intelligence (AI) and the requirements for AI tools that would implement these algorithms in a computer-based system. 4 figs., 1 tab

  12. Environmental impact monitoring methods in the vicinity of waste incineration and co-incineration facilities - State-of-the-art. State-of-the-art of environmental impact monitoring methods in the vicinity of waste incineration and co-incineration facilities. Synthesis

    International Nuclear Information System (INIS)

    Chassagnac, T.; Cornet, C.; Mathieu, L.

    2005-10-01

    Since the beginning of the 70's, the growing concern from the public opinion and the scientific community for the waste incineration issue made people aware of a number of difficulties of the process and the potential risks linked to it. For example checking the good functioning conditions of the facilities has been made compulsory through the continuous emission monitoring of a number of parameters. The ministerial decree from the 20 September 2002 brings something new: the monitoring of the impact of the facilities on its nearby environment. This monitoring comes in addition to the existing continuous monitoring of some gaseous compounds of the incineration process, and widens the scale of the monitoring to the environment of the incineration facilities. But there is no further information in the ministerial decree about the methods available to match this requirement. Incineration facilities' managers have to face a close deadline (28 December 2005) and have to make the optimal choice of a technique matching these requirements but also the needs of their facilities. The aim of this study is to help incineration facilities' managers thanks to an overview as large as possible of the different techniques available. Managers will have to take into account the characteristics of the methods and their adequacy with the local contexts of their sites. This document is meant to be a support for dealing with this issue. (authors)

  13. Research and development plan for the Slagging Pyrolysis Incinerator

    International Nuclear Information System (INIS)

    Hedahl, T.G.; McCormack, M.D.

    1979-01-01

    Objective is to develop an incinerator for processing disposed transuranium waste. This R and D plan describes the R and D efforts required to begin conceptual design of the Slagging Pyrolysis Incinerator (Andco-Torrax). The program includes: incinerator, off-gas treatment, waste handling, instrumentation, immobilization analyses, migration studies, regulations, Belgium R and D test plan, Disney World test plan, and remote operation and maintenance

  14. Decontamination and decommissioning assessment for the Waste Incineration Facility (Building 232-Z) Hanford Site, [Hanford], WA

    International Nuclear Information System (INIS)

    Dean, L.N.

    1994-02-01

    Building 232-Z is an element of the Plutonium Finishing Plant (PFP) located in the 200 West Area of the Hanford Site. From 1961 until 1972, plutonium-bearing combustible materials were incinerated in the building. Between 1972 and 1983, following shutdown of the incinerator, the facility was used for waste segregation activities. The facility was placed in retired inactive status in 1984 and classified as a Limited Control Facility pursuant to DOE Order 5480.5, Safety of Nuclear Facilities, and 6430.1A, General Design Criteria. The current plutonium inventory within the building is estimated to be approximately 848 grams, the majority of which is retained within the process hood ventilation system. As a contaminated retired facility, Building 232-Z is included in the DOE Surplus Facility Management Program. The objective of this Decontamination and Decommissioning (D ampersand D) assessment is to remove Building 232-Z, thereby elmininating the radiological and environmental hazards associated with the plutonium inventory within the structure. The steps to accomplish the plan objectives are: (1) identifying the locations of the most significant amounts of plutonium, (2) removing residual plutonium, (3) removing and decontaminating remaining building equipment, (4) dismantling the remaining structure, and (5) closing out the project

  15. Decontamination and decommissioning assessment for the Waste Incineration Facility (Building 232-Z) Hanford Site, [Hanford], WA

    Energy Technology Data Exchange (ETDEWEB)

    Dean, L.N. [Advanced Sciences, Inc., (United States)

    1994-02-01

    Building 232-Z is an element of the Plutonium Finishing Plant (PFP) located in the 200 West Area of the Hanford Site. From 1961 until 1972, plutonium-bearing combustible materials were incinerated in the building. Between 1972 and 1983, following shutdown of the incinerator, the facility was used for waste segregation activities. The facility was placed in retired inactive status in 1984 and classified as a Limited Control Facility pursuant to DOE Order 5480.5, Safety of Nuclear Facilities, and 6430.1A, General Design Criteria. The current plutonium inventory within the building is estimated to be approximately 848 grams, the majority of which is retained within the process hood ventilation system. As a contaminated retired facility, Building 232-Z is included in the DOE Surplus Facility Management Program. The objective of this Decontamination and Decommissioning (D&D) assessment is to remove Building 232-Z, thereby elmininating the radiological and environmental hazards associated with the plutonium inventory within the structure. The steps to accomplish the plan objectives are: (1) identifying the locations of the most significant amounts of plutonium, (2) removing residual plutonium, (3) removing and decontaminating remaining building equipment, (4) dismantling the remaining structure, and (5) closing out the project.

  16. The incineration of absorbed liquid wastes in the INEL's [Idaho National Engineering Laboratory] WERF [Waste Experimental Reduction Facility] incinerator

    International Nuclear Information System (INIS)

    Steverson, E.M.; McFee, J.N.

    1987-01-01

    The concept of burning absorbed flammable liquids in boxes in the WERF incinerator was evaluated as a waste treatment method. The safety and feasibility of this procedure were evaluated in a series of tests. In the testing, the effect on incinerator operations of burning various quantities of absorbed flammable liquids was measured and compared to normal operations conducted on low-level radioactive waste (LLW). The test results indicated that the proposed procedure is safe and practical for use on a wide variety of solvents with quantities as high as one liter per box. No adverse or unacceptable operating conditions resulted from burning any of the solvents tested. Incineration of the solvents in this fashion was no different than burning LLW during normal incineration. 6 refs., 7 figs., 3 tabs

  17. Guide to research facilities

    Energy Technology Data Exchange (ETDEWEB)

    1993-06-01

    This Guide provides information on facilities at US Department of Energy (DOE) and other government laboratories that focus on research and development of energy efficiency and renewable energy technologies. These laboratories have opened these facilities to outside users within the scientific community to encourage cooperation between the laboratories and the private sector. The Guide features two types of facilities: designated user facilities and other research facilities. Designated user facilities are one-of-a-kind DOE facilities that are staffed by personnel with unparalleled expertise and that contain sophisticated equipment. Other research facilities are facilities at DOE and other government laboratories that provide sophisticated equipment, testing areas, or processes that may not be available at private facilities. Each facility listing includes the name and phone number of someone you can call for more information.

  18. Environmental Toxicology Research Facility

    Data.gov (United States)

    Federal Laboratory Consortium — Fully-equipped facilities for environmental toxicology researchThe Environmental Toxicology Research Facility (ETRF) located in Vicksburg, MS provides over 8,200 ft...

  19. 1993 RCRA Part B permit renewal application, Savannah River Site: Volume 10, Consolidated Incineration Facility, Section C, Revision 1

    International Nuclear Information System (INIS)

    Molen, G.

    1993-08-01

    This section describes the chemical and physical nature of the RCRA regulated hazardous wastes to be handled, stored, and incinerated at the Consolidated Incineration Facility (CIF) at the Savannah River Site. It is in accordance with requirements of South Carolina Hazardous Waste Management Regulations R.61-79.264.13(a) and(b), and 270.14(b)(2). This application is for permit to store and teat these hazardous wastes as required for the operation of CIF. The permit is to cover the storage of hazardous waste in containers and of waste in six hazardous waste storage tanks. Treatment processes include incineration, solidification of ash, and neutralization of scrubber blowdown

  20. High Combustion Research Facility

    Data.gov (United States)

    Federal Laboratory Consortium — At NETL's High-Pressure Combustion Research Facility in Morgantown, WV, researchers can investigate new high-pressure, high-temperature hydrogen turbine combustion...

  1. Test Operation of Oxygen-Enriched Incinerator for Wastes From Nuclear Fuel Fabrication Facility

    International Nuclear Information System (INIS)

    Kim, J.-G.; Yang, H.cC.; Park, G.-I.; Kim, I.-T.; Kim, J.-K.

    2002-01-01

    The oxygen-enriched combustion concept, which can minimize off-gas production, has been applied to the incineration of combustible uranium-containing wastes from a nuclear fuel fabrication facility. A simulation for oxygen combustion shows the off-gas production can be reduced by a factor of 6.7 theoretically, compared with conventional air combustion. The laboratory-scale oxygen enriched incineration (OEI) process with a thermal capacity of 350 MJ/h is composed of an oxygen feeding and control system, a combustion chamber, a quencher, a ceramic filter, an induced draft fan, a condenser, a stack, an off-gas recycle path, and a measurement and control system. Test burning with cleaning paper and office paper in this OEI process shows that the thermal capacity is about 320 MJ/h, 90 % of design value and the off-gas reduces by a factor of 3.5, compared with air combustion. The CO concentration for oxygen combustion is lower than that of air combustion, while the O2 concentration in off-gas is kept above 25 vol % for a simple incineration process without any grate. The NOx concentration in an off-gas stream does not reduce significantly due to air incoming by leakage, and the volume and weight reduction factors are not changed significantly, which suggests a need for an improvement in sealing

  2. Operational improvement to the flue gas cleaning system in radioactive waste incineration facilities

    International Nuclear Information System (INIS)

    Zheng Bowen; Li Xiaohai; Wang Peiyi

    2012-01-01

    After years of operation, some problems, such as corrosion and waste water treatment, have been found in the first domestic whole-scale radioactive waste incineration facility. According to the origin of the problems, the flue gas cleaning system has been optimized and improved in terms of technical process, material and structure. It improves the operational stability, extends the equipment life-time, and also reduces the amount of secondary waste. In addition, as major sources of problems, waste management, operational experiences and information exchange deserve more attention. (authors)

  3. Criticality calculations and criticality monitoring studies of the slagging pyrolysis incinerator facility

    International Nuclear Information System (INIS)

    Close, D.A.; Booth, T.E.; Caldwell, J.T.

    1981-01-01

    It was determined that the criticality hazard associated with the Slagging Pyrolysis Incinerator (SPI) Facility would be minimal if a three-level criticality-hazard prevention program were implemented. The first strategy consists of screening all incoming wastes for fissile content. The second prevention level is provided by introducing a small concentration of a neutron-absorbing compound, such as B 2 O 3 , into the input waste stream. The third prevention level is provided by direct criticality-hazard monitoring using sensitive neutron detectors in all regions of the facility where a significant hazard has been identified - principally the drying, pyrolysis, and slag regions. The facility could be shut down rapidly for cleanout if the measurements indicate an unsafe condition is developing. The criticality safety provided by the product of these three independent measures should reduce the hazard to a negligible level

  4. Transonic Experimental Research Facility

    Data.gov (United States)

    Federal Laboratory Consortium — The Transonic Experimental Research Facility evaluates aerodynamics and fluid dynamics of projectiles, smart munitions systems, and sub-munitions dispensing systems;...

  5. Geodynamics Research Facility

    Data.gov (United States)

    Federal Laboratory Consortium — This GSL facility has evolved over the last three decades to support survivability and protective structures research. Experimental devices include three gas-driven...

  6. Magnetics Research Facility

    Data.gov (United States)

    Federal Laboratory Consortium — The Magnetics Research Facility houses three Helmholtz coils that generate magnetic fields in three perpendicular directions to balance the earth's magnetic field....

  7. Suitability of oil bioremediation in an Artic soil using surplus heating from an incineration facility.

    Science.gov (United States)

    Couto, Nazaré; Fritt-Rasmussen, Janne; Jensen, Pernille E; Højrup, Mads; Rodrigo, Ana P; Ribeiro, Alexandra B

    2014-05-01

    A 168-day period field study, carried out in Sisimiut, Greenland, assessed the potential to enhance soil remediation with the surplus heating from an incineration facility. This approach searches a feasible ex situ remediation process that could be extended throughout the year with low costs. Individual and synergistic effects of biostimulation were also tested, in parallel. An interim evaluation at the end of the first 42 days showed that biostimulation and active heating, as separate treatments, enhanced petroleum hydrocarbon (PHC) removal compared to natural attenuation. The coupling of both technologies was even more effective, corroborating the benefits of both techniques in a remediation strategy. However, between day 42 and day 168, there was an opposite remediation trend with all treatments suggesting a stabilization except for natural attenuation, where PHC values continued to decrease. This enforces the "self-purification" capacity of the system, even at low temperatures. Coupling biostimulation with active heating was the best approach for PHC removal, namely for a short period of time (42 days). The proposed remediation scheme can be considered a reliable option for faster PHC removal with low maintenance and using "waste heating" from an incineration facility.

  8. Combustion Research Facility

    Data.gov (United States)

    Federal Laboratory Consortium — For more than 30 years The Combustion Research Facility (CRF) has served as a national and international leader in combustion science and technology. The need for a...

  9. Concrete Research Facility

    Data.gov (United States)

    Federal Laboratory Consortium — This is a 20,000-sq ft laboratory that supports research on all aspects of concrete and materials technology. The staff of this facility offer wide-ranging expertise...

  10. Field Research Facility

    Data.gov (United States)

    Federal Laboratory Consortium — The Field Research Facility (FRF) located in Duck, N.C. was established in 1977 to support the U.S. Army Corps of Engineers' coastal engineering mission. The FRF is...

  11. Frost Effects Research Facility

    Data.gov (United States)

    Federal Laboratory Consortium — Full-scale study in controlled conditionsThe Frost Effects Research Facility (FERF) is the largest refrigerated warehouse in the United States that can be used for a...

  12. Geophysical Research Facility

    Data.gov (United States)

    Federal Laboratory Consortium — The Geophysical Research Facility (GRF) is a 60 ft long × 22 ft wide × 7 ft deep concrete basin at CRREL for fresh or saltwater investigations and can be temperature...

  13. A research on dioxin generation from the industrial waste incineration.

    Science.gov (United States)

    Yoneda, Kenichi; Ikeguchi, Takasi; Yagi, Yoshio; Tamade, Yoshinori; Omori, Kosaku

    2002-03-01

    By using fluidized-bed furnace and rotary-kiln+stoker furnace and four different kinds of industrial wastes such as waste wood, coffee mill, waste oils and waste plastics, we have drawn the following conclusions: (1) A relationship between H6CBz and DXN is acquired, which is DXN = 0.34 x H6CBz(1.1) (2) The following means of emission reduction can be considered. (a) Reduction of DXN and Cl accumulation within the furnace, (b) control by the incinerated object, (c) control through the precursors of H6CBz, (d) improvement through operational control, (e) ammonia injection into the high-temperature zone of the furnace seems to be effective in reducing DXN and (f) DXN concentration is high with CO above 1,800 ppm, though it decreases with CO below approximately 10 ppm.

  14. The comparison of fossil carbon fraction and greenhouse gas emissions through an analysis of exhaust gases from urban solid waste incineration facilities.

    Science.gov (United States)

    Kim, Seungjin; Kang, Seongmin; Lee, Jeongwoo; Lee, Seehyung; Kim, Ki-Hyun; Jeon, Eui-Chan

    2016-10-01

    In this study, in order to understand accurate calculation of greenhouse gas emissions of urban solid waste incineration facilities, which are major waste incineration facilities, and problems likely to occur at this time, emissions were calculated by classifying calculation methods into 3 types. For the comparison of calculation methods, the waste characteristics ratio, dry substance content by waste characteristics, carbon content in dry substance, and (12)C content were analyzed; and in particular, CO2 concentration in incineration gases and (12)C content were analyzed together. In this study, 3 types of calculation methods were made through the assay value, and by using each calculation method, emissions of urban solid waste incineration facilities were calculated then compared. As a result of comparison, with Calculation Method A, which used the default value as presented in the IPCC guidelines, greenhouse gas emissions were calculated for the urban solid waste incineration facilities A and B at 244.43 ton CO2/day and 322.09 ton CO2/day, respectively. Hence, it showed a lot of difference from Calculation Methods B and C, which used the assay value of this study. It is determined that this was because the default value as presented in IPCC, as the world average value, could not reflect the characteristics of urban solid waste incineration facilities. Calculation Method B indicated 163.31 ton CO2/day and 230.34 ton CO2/day respectively for the urban solid waste incineration facilities A and B; also, Calculation Method C indicated 151.79 ton CO2/day and 218.99 ton CO2/day, respectively. This study intends to compare greenhouse gas emissions calculated using (12)C content default value provided by the IPCC (Intergovernmental Panel on Climate Change) with greenhouse gas emissions calculated using (12)C content and waste assay value that can reflect the characteristics of the target urban solid waste incineration facilities. Also, the concentration and (12)C content

  15. The solid waste contaminated incineration technique used incinerator

    International Nuclear Information System (INIS)

    Sukosrono; Prayitno; Isman, M. T.

    1996-01-01

    The research of the incinerator radioactive waste used incinerator has been done. The aim of the experiment is to determine the number of the organic liquid waste which added on the incineration of the solid radioactive waste. The research was done by incinerate waste in the incinerator prototype which was designed for capacity 2500 gram, and the investigated variables are capacity of the incinerator, specific of the waste, and the method of the incineration. Simulated waste was used in the experiment, the waste specific which was used in the experiment was the mixture between liquid organic waste (TBPK-10%) with solid waste was coming from rice paper, tissue, carton. Two way method were investigated in the experiment, were direct incineration and indirect incineration. The direct incineration was done by incineration solid waste and organic liquid waste in the incinerator together. The indirect incineration was done by incineration of solid waste which have been used to absorb organic liquid waste. The result showed that either direct or indirect incineration independent to the incineration result. The best result have taken place on the 2250 gram capacity of the incinerator, ratio liquid organic waste to solid waste 1% - 20%. In the condition will be found reduction of volume = 43.90 - 35.91 and reduction of the waste = 13.85% - 12.15% and the ash which was resulted from incineration colored white silver with contain a little color black. (author)

  16. Biomedical waste management: Incineration vs. environmental safety

    Directory of Open Access Journals (Sweden)

    Gautam V

    2010-01-01

    Full Text Available Public concerns about incinerator emissions, as well as the creation of federal regulations for medical waste incinerators, are causing many health care facilities to rethink their choices in medical waste treatment. As stated by Health Care Without Harm, non-incineration treatment technologies are a growing and developing field. Most medical waste is incinerated, a practice that is short-lived because of environmental considerations. The burning of solid and regulated medical waste generated by health care creates many problems. Medical waste incinerators emit toxic air pollutants and toxic ash residues that are the major source of dioxins in the environment. International Agency for Research on Cancer, an arm of WHO, acknowledged dioxins cancer causing potential and classified it as human carcinogen. Development of waste management policies, careful waste segregation and training programs, as well as attention to materials purchased, are essential in minimizing the environmental and health impacts of any technology.

  17. Air pollutant emissions and their control with the focus on waste incineration facilities

    Energy Technology Data Exchange (ETDEWEB)

    Loeschau, Margit [Wandschneider + Gutjahr, Hamburg (Germany)

    2017-07-01

    This text and practical handbook thoroughly presents the control of air pollutant emissions from combustion processes focusing on waste incinerators. Special characteristics are emphasised and the differences to emission control from combustion processes with other fuels are explained. The author illustrates the origin and effects of air pollutants from incineration processes, the mechanics of their appearance in the incineration process, primary and secondary measures for their reduction, processes of measuring the emissions as well as the methods of disposing the residues. In particular, the pros and cons of procedural steps and their appropriate combination under various conditions are emphasised. Moreover, the book contains information and analyses of the emissions situation, the consumption of operating materials and of backlog quantities as well as of the cost structure of waste incinerators with regard to their applied control system. Furthermore, the author explicates the contemporary legal, scientific and technological developments and their influence on air pollutant emission control. An evaluation of the status quo of air pollutant control at waste incinerators in Germany, practical examples about possible combinations and typical performance data complete the content. Accordingly, this book is a guideline for planing a reasonable overall concept of an air pollutant control that takes the location and the segregation tasks into consideration.

  18. Analysis of operating costs a Low-Level Mixed Waste Incineration Facility

    International Nuclear Information System (INIS)

    Loghry, S.L.; Salmon, R.; Hermes, W.H.

    1995-01-01

    By definition, mixed wastes contain both chemically hazardous and radioactive components. These components make the treatment and disposal of mixed wastes expensive and highly complex issues because the different regulations which pertain to the two classes of contaminants frequently conflict. One method to dispose of low-level mixed wastes (LLMWs) is by incineration, which volatizes and destroys the organic (and other) hazardous contaminants and also greatly reduces the waste volume. The US Department of Energy currently incinerates liquid LLMW in its Toxic Substances Control Act (TSCA) Incinerator, located at the K-25 Site in Oak Ridge, Tennessee. This incinerator has been fully permitted since 1991 and to date has treated approximately 7 x 10 6 kg of liquid LLMW. This paper presents an analysis of the budgeted operating costs by category (e.g., maintenance, plant operations, sampling and analysis, and utilities) for fiscal year 1994 based on actual operating experience (i.e., a ''bottoms-up'' budget). These costs provide benchmarking guidelines which could be used in comparing incinerator operating costs with those of other technologies designed to dispose of liquid LLMW. A discussion of the current upgrade status and future activities are included in this paper. Capital costs are not addressed

  19. Shock Thermodynamic Applied Research Facility

    Data.gov (United States)

    Federal Laboratory Consortium — The Shock Thermodynamic Applied Research Facility (STAR) facility, within Sandia’s Solid Dynamic Physics Department, is one of a few institutions in the world with a...

  20. Research paper 2000-B-8: the implementation of the municipal waste incineration directives

    Energy Technology Data Exchange (ETDEWEB)

    Lulofs, K. [Twente Univ., Center for Clean Technology and Environmental Policy, Enschede (Netherlands)

    2000-07-01

    Directives had the highest impact on goal attainment in the countries that defined lower ambition levels. In those countries allocation of abatement costs was done more efficient. The presented analysis is predominately withdrawn from the national case studies by Bueltman and Waetzold (2000), Eames (2000), Lulofs (1999) and Schucht (2000). The analysis on the plant level was focused on the approximately 400 existing incinerators for municipal waste in the four IMPOL countries. The research period covers the years 1989-1999 with a focus on the years 1989-1996. (author)

  1. Robotics Research Facility

    Data.gov (United States)

    Federal Laboratory Consortium — This 60 feet x 100 feet structure on the grounds of the Fort Indiantown Gap Pennsylvania National Guard (PNG) Base is a mixed-use facility comprising office space,...

  2. Incineration facility for combustible solid and liquid radioactive wastes in IPEN-CNEN - Sao Paulo

    International Nuclear Information System (INIS)

    Krutman, I.; Grosche Filho, C.E.; Chandra, U.; Suarez, A.A.

    1987-01-01

    A system for incinerating the combustible solid and liquid radioactive wastes was developed in order to achieve higher mass and volume reduction of the wastes generated at IPEN-CNEN/SP or received from other institutions. The radioactive wastes for incineration are: animal carcasses, ion-exchange resins, contaminated lubricant oils, cellulosic materials, plastics, etc. The optimization of the process was achieved by considering the following factors: selection of better construction and insulating material; dimensions; modular design of combustion chambers to increase burning capacity in future; applicability for various types of wastes; choise of gas cleaning system. The off-gas system utilizes dry treatment. The operation is designed to function with a negative pressure. (Author) [pt

  3. Engine Environment Research Facility (EERF)

    Data.gov (United States)

    Federal Laboratory Consortium — Description: This facility supports research and development testing of the behavior of turbine engine lubricants, fuels and sensors in an actual engine environment....

  4. Materials Engineering Research Facility (MERF)

    Data.gov (United States)

    Federal Laboratory Consortium — Argonne?s Materials Engineering Research Facility (MERF) enables engineers to develop manufacturing processes for producing advanced battery materials in sufficient...

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

    Science.gov (United States)

    Othman, Jamal; Khee, Pek Chuen

    2014-05-01

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

  6. Stabilization of high and low solids Consolidated Incinerator Facility (CIF) waste with super cement

    International Nuclear Information System (INIS)

    Walker, B.W.

    2000-01-01

    This report details solidification activities using selected Mixed Waste Focus Area technologies with the High and Low Solid waste streams. Ceramicrete and Super Cement technologies were chosen as the best possible replacement solidification candidates for the waste streams generated by the SRS incinerator from a list of several suggested Mixed Waste Focus Area technologies. These technologies were tested, evaluated, and compared to the current Portland cement technology being employed. Recommendation of a technology for replacement depends on waste form performance, process flexibility, process complexity, and cost of equipment and/or raw materials

  7. LAMPF: a nuclear research facility

    International Nuclear Information System (INIS)

    Livingston, M.S.

    1977-09-01

    A description is given of the recently completed Los Alamos Meson Physics Facility (LAMPF) which is now taking its place as one of the major installations in this country for the support of research in nuclear science and its applications. Descriptions are given of the organization of the Laboratory, the Users Group, experimental facilities for research and for applications, and procedures for carrying on research studies

  8. Navy Fuel Research Facility

    Data.gov (United States)

    Federal Laboratory Consortium — FUNCTION: Performs basic and applied research to understand the underlying chemistry that impacts the use, handling, and storage of current and future Navy mobility...

  9. CSER 94-013: Classification and access to PFP 232-Z Incinerator Facility and limits on characterization and disassembly activities in 232-Z burning hood

    Energy Technology Data Exchange (ETDEWEB)

    Miller, E.M.

    1995-01-12

    This CSER justifies the Limited Control Facility designation for the closed Burning Hood in the PFP 232-Z Incinerator Facility. If the Burning Hood is opened to characterize the plutonium distribution and geometric integrity of the internals or for disassembly of the internals, then the more rigorous Fissionable Material Facility classification is required. Two sets of requirements apply for personnel access, criticality firefighting category for water use, and fissile material movement for the two states of the Burning Hood. The parameters used in the criticality analysis are listed to establish the limits under which this CSER is valid. Determination that the Burning Hood fissile material, moderation, or internal arrangements are outside these limits requires reevaluation of these parameter values and activities at the 232-Z Incinerator Facility. When the Burning Hood is open, water entry is to be prevented by two physical barriers for each water source.

  10. Detonation Engine Research Facility (DERF)

    Data.gov (United States)

    Federal Laboratory Consortium — Description: This facility is configured to safely conduct experimental pressuregain combustion research. The DERF is capable of supporting up to 60,000 lbf thrust...

  11. Research and development and its importance for eco-efficient waste incineration - a review and an outlook

    International Nuclear Information System (INIS)

    Vehlow, Jurgen

    2010-01-01

    Research and development played a paramount role for waste incineration from the early beginning. The development of suited combustion systems, of measures to control dioxin formation in and emission from waste incineration plants, the simplification of gas cleaning processes while maintaining their environmental quality and the inertnesses of hazardous residues like filter ashes are few examples to illustrate this importance. There are still areas which need further research and development support, e.g. the optimisation of energy recovery or the final disposal of soluble APC residues. (author)

  12. The Radiological Research Accelerator Facility

    International Nuclear Information System (INIS)

    Hall, E.J.; Marino, S.A.

    1990-07-01

    The Radiological Research Accelerator Facility (RARAF) is based on a 4-MV Van de Graaff accelerator, which is used to generate a variety of well-characterized radiation beams for research in radiobiology, radiological physics, and radiation chemistry. It is part of the Center for Radiological Research (CRR) -- formerly the Radiological Research Laboratory (RRL) -- of Columbia University, and its operation is supported as a National Facility by the US Department of Energy (DOE). Fifteen different experiments were run during these 12 months, approximately the same as the previous two years. Brief summaries of each experiment are included. Accelerator usage is summarized and development activities are discussed. 7 refs., 4 tabs

  13. CO-incineration

    International Nuclear Information System (INIS)

    Boehmer, S.; Rumplmayr, A.

    2001-01-01

    'Co-incineration plant means a stationary or mobile plant whose main purpose is the generation of energy or production of material products and which uses wastes as a regular or additional fuel; or in which waste is thermally treated for the purpose of disposal. This definition covers the site and the entire plant including all incineration lines, waste reception, storage, an site pre-treatment facilities; its waste-, fuel- and air-supply systems; the boiler; facilities for treatment or storage of the residues, exhaust gas and waste water; the stack; devices and systems for controlling incineration operations, recording and monitoring incineration conditions (proposal for a council directive an the incineration of waste - 98/C 372/07). Waste incinerators primarily aim at rendering waste inert, at reduction of its volume and at the generation of energy from waste. The main aim of co-incineration an the other hand is either the recovery of energy from waste, the recovery of its material properties or a combination of the latter in order to save costs for primary energy. Two main groups of interest have lately been pushing waste towards co-incineration: conventional fossil fuels are getting increasingly scarce and hence expensive and generate carbon dioxide (greenhouse gas). The use of high calorific waste fractions is considered as an alternative. In many countries land filling of waste is subject to increasingly strict regulations in order to reduce environmental risk and landfill volume. The Austrian Landfill Ordinance for instance prohibits the disposal of untreated waste from the year 2004. Incineration seems to be the most effective treatment option to destroy organic matter. However the capacities of waste incinerators are limited, giving rise to a search for additional incineration capacity. The obvious advantages of co-incineration, such as the saving of fossil fuels and raw materials, the thermal treatment of waste fractions and possible economic benefits by

  14. Solidification/stabilization of fly and bottom ash from medical waste incineration facility.

    Science.gov (United States)

    Anastasiadou, Kalliopi; Christopoulos, Konstantinos; Mousios, Epameinontas; Gidarakos, Evangelos

    2012-03-15

    In the present work, the stabilization/solidification of fly and bottom ash generated from incinerated hospital waste was studied. The objectives of the solidification/stabilization treatment were therefore to reduce the leachability of the heavy metals present in these materials so as to permit their disposal in a sanitary landfill requiring only a lower degree of environmental protection. Another objective of the applied treatment was to increase the mechanical characteristics of the bottom ash using different amounts of Ordinary Portland Cement (OPC) as a binder. The solidified matrix showed that the cement is able to immobilize the heavy metals found in fly and bottom ash. The TCLP leachates of the untreated fly ash contain high concentrations of Zn (13.2 mg/l) and Pb (5.21 mg/l), and lesser amounts of Cr, Fe, Ni, Cu, Cd and Ba. Cement-based solidification exhibited a compressive strength of 0.55-16.12 MPa. The strength decreased as the percentage of cement loading was reduced; the compressive strength was 2.52-12.7 MPa for 60% cement mixed with 40% fly ash and 6.62-16.12 MPa for a mixture of 60% cement and 40% bottom ash. The compressive strength reduced to 0.55-1.30 MPa when 30% cement was mixed with 70% fly ash, and to 0.90-7.95 MPa when 30% cement was mixed with 70% bottom ash, respectively. Copyright © 2011 Elsevier B.V. All rights reserved.

  15. Research Summary Multipollutant Control Research Facility (MPCRF)

    Science.gov (United States)

    The U.S. Environmental Protection Agency’s (EPA) Multipollutant Control Research Facility (MPCRF) is located at their Research Triangle Park, North Carolina, campus. The MPCRF combustor is a pulverized coal-, natural gas-, and biomass-fired furnace with a maximum firing rat...

  16. Performance evaluation of non-incineration treatment facilities for disinfection of medical infectious and sharps wastes in educational hospitals of Shahid Beheshti University of Medical Sciences in 2013

    Directory of Open Access Journals (Sweden)

    Anooshiravan Mohseni Band-pay

    2015-06-01

    Full Text Available Background: In 2007, a rule prohibiting the use of incinerators was ratified by the Iranian Islamic Parliament. Based on this rule, the Ministry of Health emphasized the sterilization of infectious waste at its production source by means of non-incineration equipment and methods. This research examined the performance of non-incineration technologies in treating medical infectious and sharps wastes at educational hospitals affiliated with Shahid Beheshti University of Medical Sciences. Methods: This cross-sectional descriptive study was conducted in 12 educational hospitals of Shahid Beheshti University of Medical Sciences. First, a questionnaire was designed and its validity approved. Then the required data was gathered during visits to participating hospitals. Finally, the collected data were analyzed using Microsoft Excel and SPSS version 16. Results: Findings showed that the daily production of infectious and sharps wastes in the studied hospitals generally equaled 3387 kg. All hospitals were equipped with non-incineration systems; however, only 83.3% of them were active. Some infectious waste was disposed of along with urban wastes without being sterilized. Monthly biological assessments of treatment equipment were implemented for only 41.7% of the equipment. Conclusion: The failures of the non-incineration systems demand that appropriate investigations be conducted prior to the purchase of these devices. Monthly biological assessments are essential to ensure the accuracy of the systems’ performance in hospitals.

  17. Volume reduction by the incineration of the combustible radioactive solid samples from radioisotope usage at the utilization facility. Estimation of the distribution of low energy β-emitter using the imaging plate

    International Nuclear Information System (INIS)

    Yumoto, Yasuhiro; Hanafusa, Tadashi; Nagamatsu, Tomohiro; Okada, Shigeru

    1999-01-01

    We want to establish a system of volume reduction by the incineration of the combustible radioactive solid wastes from radioisotope usage at the utilization facility. We have been performing experiments using an experimental incineration system to examine the distribution of radionuclides during incineration and to collect basic data. To reproduce the realistic conditions of incineration of low-level radioactive wastes in an experimental system, we adopted new incineration methods in this study. Low level radioactive samples (LLRS) were set up in a mesh container of stainless steel and incinerated at high temperature (over 800 degC) generated by two sets of high calorie gas burners. Low energy β-emitters 35 S, 45 Ca, 33 P, and a high energy β-emitter 32 P were used for the experiment. Their translocation percentages in exhaust air and dust were estimated using the Imaging Plate. Distribution of radionuclides during the incineration was similar to that estimated by conventional methods by our study or to that reported in incineration of liquid scintillation cocktail waste. We concluded that the use of the Imaging Plates is a simple and reliable method for estimation of the distribution of low energy β-emitters in incineration gas and ash. (author)

  18. Experimentation with a prototype incinerator for beta-gamma waste

    International Nuclear Information System (INIS)

    Farber, M.G.; Lewandowski, K.E.; Becker, G.W.

    1982-01-01

    A test facility for the incineration of suspect and low-level beta-gamma waste has been built and operated at the Savannah River Laboratory. The processing steps include waste feeding, incineration, ash residue packaging, and off-gas cleanup. Demonstration of the full-scale (180 kg/hr) facility with nonradioactive, simulated waste is currently in progress. At the present time, over nine metric tons of material including rubber, polyethylene, and cellulose have been incinerated during three burning campaigns. A comprehensive test program of solid and liquid waste incineration is being implemented. The data from the research program is providing the technical basis for a phase of testing with low-level beta-gamma waste generated at the Savannah River Plant

  19. Greenhouse gas accounting of the proposed landfill extension and advanced incineration facility for municipal solid waste management in Hong Kong.

    Science.gov (United States)

    Woon, K S; Lo, Irene M C

    2013-08-01

    The burgeoning of municipal solid waste (MSW) disposal issue and climate change have drawn massive attention from people. On the one hand, Hong Kong is facing a controversial debate over the implementation of proposed landfill extension (LFE) and advanced incineration facility (AIF) to curb the MSW disposal issue. On the other hand, the Hong Kong Special Administrative Region Government is taking concerted efforts to reduce the carbon intensity in this region. This paper discusses the greenhouse gas (GHG) emissions from four proposed waste disposal scenarios, covering the proposed LFE and AIF within a defined system boundary. On the basis of the data collected, assumptions made, and system boundary defined in this study, the results indicate that AIF releases less GHG emissions than LFE. The GHG emissions from LFE are highly contributed by the landfill methane (CH4) emissions but offset by biogenic carbon storage, while the GHG emissions from AIF are mostly due to the stack discharge system but offset by the energy recovery system. Furthermore, parametric sensitivity analyses show that GHG emissions are strongly dependent on the landfill CH4 recovery rate, types of electricity displaced by energy recovery systems, and the heating value of MSW, altering the order of preferred waste disposal scenarios. This evaluation provides valuable insights into the applicability of a policy framework for MSW management practices in reducing GHG emissions. Copyright © 2013 Elsevier B.V. All rights reserved.

  20. Incineration technologies

    CERN Document Server

    Buekens, Alfons

    2013-01-01

    Waste incineration is the art of completely combusting waste, while maintaining or reducing emission levels below current emission standards. Where possible, objectives include the recovering of energy as well as the  combustion residues.  Successful waste incineration makes it possible to achieve a deep reduction in waste volume, obtain a compact and sterile residue, and eliminate a wide array of pollutants. This book places waste incineration within the wider context of waste management, and demonstrates that, in contrast to landfills and composting, waste incineration can eliminate objectionable and hazardous properties such as flammability and toxicity, result in a significant reduction in volume, and destroy gaseous and liquid waste streams leaving little or no residues beyond those linked to flue gas neutralization and treatment. Moreover, waste incineration sterilizes and destroys putrescible matter, and produces usable heat.  Incineration Technologies first appeared as a peer-reviewed contribution ...

  1. Waste incineration

    International Nuclear Information System (INIS)

    McCormack, M.D.

    1981-01-01

    As a result of the information gained from retrieval projects, the decision was made to perform an analysis of all the available incinerators to determine which was best suited for processing the INEL waste. A number of processes were evaluated for incinerators currently funded by DOE and for municipal incinerators. Slagging pyrolysis included the processes of three different manufacturers: Andco-Torrax, FLK and Purox

  2. Research facility access & science education

    Energy Technology Data Exchange (ETDEWEB)

    Rosen, S.P. [Univ. of Texas, Arlington, TX (United States); Teplitz, V.L. [Southern Methodist Univ., Dallas, TX (United States). Physics Dept.

    1994-10-01

    As Congress voted to terminate the Superconducting Super Collider (SSC) Laboratory in October of 1993, the Department of Energy was encouraged to maximize the benefits to the nation of approximately $2 billion which had already been expended to date on its evolution. Having been recruited to Texas from other intellectually challenging enclaves around the world, many regional scientists, especially physicists, of course, also began to look for viable ways to preserve some of the potentially short-lived gains made by Texas higher education in anticipation of {open_quotes}the SSC era.{close_quotes} In fact, by November, 1993, approximately 150 physicists and engineers from thirteen Texas universities and the SSC itself, had gathered on the SMU campus to discuss possible re-uses of the SSC assets. Participants at that meeting drew up a petition addressed to the state and federal governments requesting the creation of a joint Texas Facility for Science Education and Research. The idea was to create a facility, open to universities and industry alike, which would preserve the research and development infrastructure and continue the educational mission of the SSC.

  3. Oxygen enrichment incineration

    International Nuclear Information System (INIS)

    Kim, Jeong Guk; Yang, Hee Chul; Park, Geun Il; Kim, Joon Hyung

    2000-10-01

    Oxygen enriched combustion technology has recently been used in waste incineration. To apply the oxygen enrichment on alpha-bearing waste incineration, which is being developed, a state-of-an-art review has been performed. The use of oxygen or oxygen-enriched air instead of air in incineration would result in increase of combustion efficiency and capacity, and reduction of off-gas product. Especially, the off-gas could be reduced below a quarter, which might reduce off-gas treatment facilities, and also increase an efficiency of off-gas treatment. However, the use of oxygen might also lead to local overheating and high nitrogen oxides (NOx) formation. To overcome these problems, an application of low NOx oxy-fuel burner and recycling of a part of off-gas to combustion chamber have been suggested

  4. Oxygen enrichment incineration

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Jeong Guk; Yang, Hee Chul; Park, Geun Il; Kim, Joon Hyung

    2000-10-01

    Oxygen enriched combustion technology has recently been used in waste incineration. To apply the oxygen enrichment on alpha-bearing waste incineration, which is being developed, a state-of-an-art review has been performed. The use of oxygen or oxygen-enriched air instead of air in incineration would result in increase of combustion efficiency and capacity, and reduction of off-gas product. Especially, the off-gas could be reduced below a quarter, which might reduce off-gas treatment facilities, and also increase an efficiency of off-gas treatment. However, the use of oxygen might also lead to local overheating and high nitrogen oxides (NOx) formation. To overcome these problems, an application of low NOx oxy-fuel burner and recycling of a part of off-gas to combustion chamber have been suggested.

  5. Controlled air incineration

    International Nuclear Information System (INIS)

    Seitz, K.A.

    1991-01-01

    From 1960 to 1970, incineration was recognized as an economical method of solid waste disposal with many incinerators in operation through the country. During this period a number of legislation acts began to influence the solid waste disposal industry, namely, the Solid Waste Disposal Act of 1965; Resource Conservation Recovery Act (RCRA) of 1968; Resource Recovery Act of 1970; and Clean Air Act of 1970. This period of increased environmental awareness and newly created regulations began the closure of many excess air incineration facilities and encouraged the development of new controlled air, also known as Starved-Air incinerator systems which could meet the more stringent air emission standards without additional emission control equipment. The Starved-Air technology initially received little recognition because it was considered unproven and radically different from the established and accepted I.I.A. standards. However, there have been many improvements and developments in the starved-air incineration systems since the technology was first introduced and marketed, and now these systems are considered the proven technology standard

  6. SUPERFUND TREATABILITY CLEARINGHOUSE: BDAT INCINERATION OF CERCLA SARMS AT THE JOHN ZINK COMPANY TEST FACILITY (FINAL PROJECT REPORT)

    Science.gov (United States)

    This report presents the results of a treatability study of rotary kiln incineration of a synthetic "Superfund soil" bearing a wide range of chemical contaminants typically occurring at Superfund sites. This surrogate soil is referred to as a synthetic analytical reference ...

  7. Controlled air incinerator conceptual design study

    International Nuclear Information System (INIS)

    1982-01-01

    This report presents a conceptual design study for a controlled air incinerator facility for incineration of low level combustible waste at Three Mile Island Unit 2 (TMI-2). The facility design is based on the use of a Helix Process Systems controlled air incinerator. Cost estimates and associated engineering, procurement, and construction schedules are also provided. The cost estimates and schedules are presented for two incinerator facility designs, one with provisions for waste ash solidification, the other with provisions for packaging the waste ash for transport to an undefined location

  8. Waste incineration

    International Nuclear Information System (INIS)

    Rumplmayr, A.; Sammer, G.

    2001-01-01

    Waste incineration can be defined as the thermal conversion processing of solid waste by chemical oxidation. The types of wastes range from solid household waste and infectious hospital waste through to toxic solid, liquid and gaseous chemical wastes. End products include hot incineration gases, composed primarily of nitrogen, carbon dioxide, water vapor and to a smaller extend of non-combustible residue (ash) and air pollutants (e. g. NO x ). Energy can be recovered by heat exchange from the hot incineration gases, thus lowering fossil fuel consumption that in turn can reduce emissions of greenhouse gases. Burning of solid waste can fulfil up to four distinctive objectives (Pera, 2000): 1. Volume reduction: volume reduction of about 90 %, weight reduction of about 70 %; 2. Stabilization of waste: oxidation of organic input; 3. Recovery of energy from waste; 4. Sanitization of waste: destruction of pathogens. Waste incineration is not a means to make waste disappear. It does entail emissions into air as well as water and soil. The generated solid residues are the topic of this task force. Unlike other industrial processes discussed in this platform, waste incineration is not a production process, and is therefore not generating by-products, only residues. Residues that are isolated from e. g. flue gas, are concentrated in another place and form (e. g. air pollution control residues). Hence, there are generally two groups of residues that have to be taken into consideration: residues generated in the actual incineration process and others generated in the flue gas cleaning system. Should waste incineration finally gain public acceptance, it will be necessary to find consistent regulations for both sorts of residues. In some countries waste incineration is seen as the best option for the treatment of waste, whereas in other countries it is seen very negative. (author)

  9. Stockbridge Antenna Measurement and Research Facility

    Data.gov (United States)

    Federal Laboratory Consortium — The Stockbridge Antenna Measurement Facility is located 23 miles southwest of AFRL¹s Rome Research Site. This unique measurement facility is designed to evaluate the...

  10. Radiation safety for incineration of radioactive waste contaminated by cesium

    International Nuclear Information System (INIS)

    Veryuzhs'kij, Yu.V.; Gryin'ko, O.M.; Tokarevs'kij, V.V.

    2016-01-01

    Problems in the treatment of radioactive waste contaminated by cesium nuclides are considered in the paper. Chornobyl experience in the management of contaminated soil and contaminated forests is analyzed in relation to the accident at Fukushima-1. The minimization of release of cesium aerosols into atmosphere is very important. Radiation influence of inhaling atmosphere aerosols polluted by cesium has damage effect for humans. The research focuses on the treatment of forests contaminated by big volumes of cesium. One of the most important technologies is a pyro-gasification incineration with chemical reactions of cesium paying attention to gas purification problems. Requirements for process, physical and chemical properties of treatment of radioactive waste based on the dry pyro-gasification incineration facilities are considered in the paper together with the discussion of details related to incineration facilities. General similarities and discrepancies in the environmental pollution caused by the accidents at Chornobyl NPP and Fukushima-1 NPP in Japan are analyzed

  11. Separation of CO2 in a Solid Waste Management Incineration Facility Using Activated Carbon Derived from Pine Sawdust

    Directory of Open Access Journals (Sweden)

    Inés Durán

    2017-06-01

    Full Text Available The selective separation of CO2 from gas mixtures representative of flue gas generated in waste incineration systems is studied on two activated carbons obtained from pine sawdust and compared to a commercial activated carbon. Dynamic adsorption experiments were conducted in a fixed-bed adsorption column using a binary mixture (N2/CO2 with a composition representative of incineration streams at temperatures from 30 to 70 °C. The adsorption behavior of humid mixtures (N2/CO2/H2O was also evaluated in order to assess the influence of water vapor in CO2 adsorption at different relative humidity in the feed gas: 22% and 60%. Moreover, CO2 adsorption was studied in less favorable conditions, i.e., departing from a bed initially saturated with H2O. In addition, the effect of CO2 on H2O adsorption was examined. Experimental results showed that the CO2 adsorption capacity can be reduced significantly by the adsorption of H2O (up to 60% at high relative humidity conditions. On the other hand, the breakthrough tests over the adsorbent initially saturated with water vapor indicated that H2O is little affected by CO2 adsorption. The experimental results pointed out the biomass based carbons as best candidates for CO2 separation under incineration flue gas conditions.

  12. Experience with radioactive waste incineration at Chalk River Nuclear Laboratories

    International Nuclear Information System (INIS)

    Le, V.T.; Beamer, N.V.; Buckley, L.P.

    1988-06-01

    Chalk River Nuclear Laboratories is a nuclear research centre operated by Atomic Energy of Canada Limited. A full-scale waste treatment centre has been constructed to process low- and intermediate-level radioactive wastes generated on-site. A batch-loaded, two-stage, starved-air incinerator for solid combustible waste is one of the processes installed in this facility. The incinerator has been operating since 1982. It has consistently reduced combustible wastes to an inert ash product, with an average volume reduction factor of about 150:1. The incinerator ash is stored in 200 L drums awaiting solidification in bitumen. The incinerator and a 50-ton hydraulic baler have provided treatment for a combined volume of about 1300 m 3 /a of solid low-level radioactive waste. This paper presents a review of the performance of the incinerator during its six years of operation. In addition to presenting operational experience, an assessment of the starved-air incineration technique will also be discussed

  13. Incineration process fire and explosion protection

    International Nuclear Information System (INIS)

    Ziegler, D.L.

    1975-01-01

    Two incinerators will be installed in the plutonium recovery facility under construction at the Rocky Flats Plant. The fire and explosion protection features designed into the incineration facility are discussed as well as the nuclear safety and radioactive material containment features. Even though the incinerator system will be tied into an emergency power generation system, a potential hazard is associated with a 60-second delay in obtaining emergency power from a gas turbine driven generator. This hazard is eliminated by the use of steam jet ejectors to provide normal gas flow through the incinerator system during the 60 s power interruption. (U.S.)

  14. Design and operation of a prototype incinerator for beta-gamma waste

    International Nuclear Information System (INIS)

    Farber, M.G.; Hootman, H.E.; Becker, G.W. Jr.; Makohon, P.A.

    1981-01-01

    A full-scale test incinerator has been built at the Savannah River Laboratory to provide a design basis for a radioactive facility that will burn low-level beta-gamma contaminated waste. The processing steps include waste feed loading, incineration, ash residue packaging, and off-gas cleanup. Both solid and liquid waste will be incinerated during the test program. The components of the solid waste are cellulose, latex, polyethylene, and PVC; the solvent is composed of n-paraffin and TBP. A research program will confirm the feasibility of the design and determine the operating parameters

  15. Incineration as a radioactive waste volume reduction process for CEA nuclear centers

    International Nuclear Information System (INIS)

    Atabek, R.; Chaudon, L.

    1994-01-01

    Incineration processes represent a promising solution for waste volume reduction, and will be increasingly used in the future. The features and performance specifications of low-level waste incinerators with capacities ranging from 10 to 20 kg - h -1 at the Fontenay-aux-Roses, Grenoble and Cadarache nuclear centers in France are briefly reviewed. More extensive knowledge of low-level wastes produced in facilities operated by the Commissariat a l'Energie Atomique (CEA) has allowed us to assess the volume reduction obtained by processing combustible waste in existing incinerators. Research and development work is in progress to improve management procedures for higher-level waste and to build facilities capable of incinerating α - contaminated waste. (authors). 6 refs., 5 figs., 1 tab

  16. Meson facility. Powerful new research tool

    International Nuclear Information System (INIS)

    Lobashev, V.M.; Tavkhelidze, A.N.

    A meson facility is being built at the Institute of Nuclear Research, USSR Academy of Sciences, in Troitsk, where the Scientific Center, USSR Academy of Sciences is located. The facility will include a linear accelerator for protons and negative hydrogen ions with 600 MeV energy and 0.5-1 mA beam current. Some fundamental studies that can be studied at a meson facility are described in the areas of elementary particles, neutron physics, solid state physics, and applied research. The characteristics of the linear accelerator are given and the meson facility's experimental complex is described

  17. Incineration and monitoring of low-level 3H and 14C wastes at a biological research institution

    International Nuclear Information System (INIS)

    Hamrick, P.E.; Knapp, S.J.; Parker, M.G.; Watson, J.E. Jr.

    1986-01-01

    Low-level radioactive waste containing liquid scintillation fluid and known amounts of 14 C and 3 H has been incinerated in a modified pathological incinerator with the incinerator effluent, refractory surface and ash being monitored. The study relates the activity monitored to that incinerated and discusses how this relation was affected by a modification of the incinerator and monitoring conditions. No significant activity was found to be associated with the ash, particulates or the refractory surface. These data suggest that most of the activity is released as tritiated water vapor and 14 C-labeled carbon dioxide. However, incomplete oxidation may occur for short periods of time depending on the amount of liquid scintillation fluid incinerated, with the possible release of 14 C-labeled carbon monoxide

  18. Access to major overseas research facilities

    International Nuclear Information System (INIS)

    Bolderman, J. W.

    1997-01-01

    This paper will describe four schemes which have been established to permit Australian researchers access to some of the most advanced overseas research facilities. These include, access to Major Research Facilities Program, the Australian National Beamline Facility at the Photon Factory, the Australian Synchrotron Research Program and the ISIS Agreement. The details of each of these programs is discussed and the statistics on the scientific output provided. All programs are managed on behalf of the Department of Industry, Science and Tourism by the Australian Nuclear Science and Technology Organisation. One hundred and thirteen senior scientists plus forty, one postgraduate, students were supported through these schemes during the 1996-1997 financial year

  19. Research on Toxicity Evaluation of Waste Incineration Residues of Printed Circuit Boards

    Directory of Open Access Journals (Sweden)

    Rasa Volungevičienė

    2014-10-01

    Full Text Available Recycling waste printed circuit boards (PCB is an extremely complicated process, because PCBs consist of a number of complex components – hazardous and non-hazardous materials sets. Pyrolysis and combustion are currently the most effective treatment technologies for waste printed circuit boards. Pyrolysis can be used for thermally decomposing PCBs allowing for the simultaneous recovery of valuable materials. Following the extraction of valuable materials, the problem of residual ash utilization is encountered. Determining the qualitative and quantitative characteristics of incineration residue helps with choosing effective ash management technologies. This paper analyzes PCB ash generated at three different temperatures of 400 °C, 500 °C and 600 °C. Ash residues have been analysed to determine the quantity and type of metals present. Furthermore, the experiment of leaching heavy metals from ash has been described.

  20. FUEL-EFFICIENT SEWAGE SLUDGE INCINERATION

    Science.gov (United States)

    A study was performed to evaluate the status of incineration with low fuel use as a sludge disposal technology. The energy requirements, life-cycle costs, operation and maintenance requirements, and process capabilities of four sludge incineration facilities were evaluated. These...

  1. Flood Fighting Products Research Facility

    Data.gov (United States)

    Federal Laboratory Consortium — A wave research basin at the ERDC Coastal and Hydraulics Laboratory has been modified specifically for testing of temporary, barrier-type, flood fighting products....

  2. A comparative assessment of waste incinerators in the UK

    Energy Technology Data Exchange (ETDEWEB)

    Nixon, J.D., E-mail: j.nixon@kingston.ac.uk [Sustainable Environment Research Group, School of Engineering and Applied Science, Aston University, Aston Triangle, Birmingham B4 7ET (United Kingdom); Wright, D.G.; Dey, P.K. [Aston Business School, Aston University, Aston Triangle, Birmingham B4 7ET (United Kingdom); Ghosh, S.K. [Mechanical Engineering Department, Centre for Quality Management System, Jadavpur University, Kolkata 700 032 (India); Davies, P.A. [Sustainable Environment Research Group, School of Engineering and Applied Science, Aston University, Aston Triangle, Birmingham B4 7ET (United Kingdom)

    2013-11-15

    Highlights: • We evaluate operational municipal solid waste incinerators in the UK. • The supply chain of four case study plants are examined and compared in detail. • Technical, financial and operational data has been gathered for the four plants. • We suggest the best business practices for waste incinerators. • Appropriate strategy choices are the major difficulties for waste to energy plants. - Abstract: The uptake in Europe of Energy from Waste (EfW) incinerator plants has increased rapidly in recent years. In the UK, 25 municipal waste incinerators with energy recovery are now in operation; however, their waste supply chains and business practices vary significantly. With over a hundred more plant developments being considered it is important to establish best business practices for ensuring efficient environmental and operational performance. By reviewing the 25 plants we identify four suitable case study plants to compare technologies (moving grate, fluidised bed and rotary kiln), plant economics and operations. Using data collected from annual reports and through interviews and site visits we provide recommendations for improving the supply chain for waste incinerators and highlight the current issues and challenges faced by the industry. We find that plants using moving grate have a high availability of 87–92%. However, compared to the fluidised bed and rotary kiln, quantities of bottom ash and emissions of hydrogen chloride and carbon monoxide are high. The uptake of integrated recycling practices, combined heat and power, and post incineration non-ferrous metal collections needs to be increased among EfW incinerators in the UK. We conclude that one of the major difficulties encountered by waste facilities is the appropriate selection of technology, capacity, site, waste suppliers and heat consumers. This study will be of particular value to EfW plant developers, government authorities and researchers working within the sector of waste

  3. A comparative assessment of waste incinerators in the UK

    International Nuclear Information System (INIS)

    Nixon, J.D.; Wright, D.G.; Dey, P.K.; Ghosh, S.K.; Davies, P.A.

    2013-01-01

    Highlights: • We evaluate operational municipal solid waste incinerators in the UK. • The supply chain of four case study plants are examined and compared in detail. • Technical, financial and operational data has been gathered for the four plants. • We suggest the best business practices for waste incinerators. • Appropriate strategy choices are the major difficulties for waste to energy plants. - Abstract: The uptake in Europe of Energy from Waste (EfW) incinerator plants has increased rapidly in recent years. In the UK, 25 municipal waste incinerators with energy recovery are now in operation; however, their waste supply chains and business practices vary significantly. With over a hundred more plant developments being considered it is important to establish best business practices for ensuring efficient environmental and operational performance. By reviewing the 25 plants we identify four suitable case study plants to compare technologies (moving grate, fluidised bed and rotary kiln), plant economics and operations. Using data collected from annual reports and through interviews and site visits we provide recommendations for improving the supply chain for waste incinerators and highlight the current issues and challenges faced by the industry. We find that plants using moving grate have a high availability of 87–92%. However, compared to the fluidised bed and rotary kiln, quantities of bottom ash and emissions of hydrogen chloride and carbon monoxide are high. The uptake of integrated recycling practices, combined heat and power, and post incineration non-ferrous metal collections needs to be increased among EfW incinerators in the UK. We conclude that one of the major difficulties encountered by waste facilities is the appropriate selection of technology, capacity, site, waste suppliers and heat consumers. This study will be of particular value to EfW plant developers, government authorities and researchers working within the sector of waste

  4. A comparative assessment of waste incinerators in the UK.

    Science.gov (United States)

    Nixon, J D; Wright, D G; Dey, P K; Ghosh, S K; Davies, P A

    2013-11-01

    The uptake in Europe of Energy from Waste (EfW) incinerator plants has increased rapidly in recent years. In the UK, 25 municipal waste incinerators with energy recovery are now in operation; however, their waste supply chains and business practices vary significantly. With over a hundred more plant developments being considered it is important to establish best business practices for ensuring efficient environmental and operational performance. By reviewing the 25 plants we identify four suitable case study plants to compare technologies (moving grate, fluidised bed and rotary kiln), plant economics and operations. Using data collected from annual reports and through interviews and site visits we provide recommendations for improving the supply chain for waste incinerators and highlight the current issues and challenges faced by the industry. We find that plants using moving grate have a high availability of 87-92%. However, compared to the fluidised bed and rotary kiln, quantities of bottom ash and emissions of hydrogen chloride and carbon monoxide are high. The uptake of integrated recycling practices, combined heat and power, and post incineration non-ferrous metal collections needs to be increased among EfW incinerators in the UK. We conclude that one of the major difficulties encountered by waste facilities is the appropriate selection of technology, capacity, site, waste suppliers and heat consumers. This study will be of particular value to EfW plant developers, government authorities and researchers working within the sector of waste management. Copyright © 2013 Elsevier Ltd. All rights reserved.

  5. Pilot incineration plant for solid, combustible, and low-level wastes

    International Nuclear Information System (INIS)

    Francioni, W.M.

    Radioactively contaminated wastes are formed in the handling of radioactive materials at the Federal Institute for Reactor Research (FIRR) and in other facilities, hospitals, sanitoria, industry, and nuclear power plants. A large part of the wastes are combustible and only very slightly radioactive. Incineration of these wastes is obvious. A pilot incineration plant, henceforth called the PIP, for radioactive combustible wastes of the FIRR is surveyed. The plant and its individual components are described. The production costs of the plant and experience gained in operation available at present are reviewed. Solid combustible radioactive waste can be incinerated in the PIP. The maximum possible reduction in volume of these wastes is achieved by incineration. Subsequently the chemically sterile ashes can be consolidated in a stable block suitable for long-term storage mixing with cement

  6. Incinerators, Hazardous Waste, To identify and locate abandoned oil production facilities and apparatus which pose a potential threat for creating an oil spill through either natural or accidental causes., Published in 1998, 1:24000 (1in=2000ft) scale, Louisiana State University (LSU).

    Data.gov (United States)

    NSGIC Education | GIS Inventory — Incinerators, Hazardous Waste dataset current as of 1998. To identify and locate abandoned oil production facilities and apparatus which pose a potential threat for...

  7. Pilot solid-waste incinerator

    International Nuclear Information System (INIS)

    Farber, M.G.; Hootman, H.E.; Trapp, D.J.

    1982-01-01

    An experimental program to develop and confirm technology for incinerating solid radioactive waste is in progress at the Savannah River Laboratory (SRL) in support of the short-term and long-term waste management objectives of the Savannah River Plant (SRP). This report reviews the experience of a pilot incinerator with a capacity of 1.0 lb/hr. The facility was tested with nonradioactive materials similar to the radioactive waste generated at the Savannah River site. The experimental program included determining operating parameters, testing wet and dry off-gas treatment systems, and evaluating materials of construction

  8. Incineration demonstration at Savannah River

    International Nuclear Information System (INIS)

    Lewandowski, K.E.; Becker, G.W.; Mersman, K.E.; Roberson, W.A.

    1983-01-01

    A full-scale incineration process for Savannah River Plant (SRP) low level beta-gamma combustible waste was demonstrated at the Savannah River Laboratory (SRL) using nonradioactive wastes. From October 1981 through September 1982, 15,700 kilograms of solid waste and 5.7 m 3 of solvent were incinerated. Emissions of off-gas components (NO/sub x/, SO 2 , CO, and particulates) were well below South Carolina state standards. Volume reductions of 20:1 for solid waste and 7:1 for Purex solvent/lime slurry were achieved. Presently, the process is being upgraded by SRP to accept radioactive wastes. During a two-year SRP demonstration, the facility will be used to incinerate slightly radioactive ( 3 ) solvent and suspect level (<1 mR/hr at 0.0254 meter) solid wastes

  9. Savannah River Plant incinerator demonstration

    International Nuclear Information System (INIS)

    Lewandowski, K.E.

    1983-01-01

    A full-scale incineration process was demonstrated at the Savannah River Laboratory (SRL) using nonradioactive waste. From October 1981 through September 1982, 15,700 kilograms of solid waste and 5.7 m 3 of solvent were incinerated. Emissions of off-gas components (NO/sub x/, SO 2 , CO, and particulates) were well below South Carolina state standards. Volume reductions of 20:1 for solid waste and 7:1 for Purex solvent/lime slurry were achieved. The process has been relocated and upgraded by the Savannah River Plant to accept low-level beta-gamma combustibles. During a two-year demonstration, the facility will incinerate slightly radioactive ( 3 ) solvent and suspect level (< 1 mR/h at 0.0254 meter) solid wastes. This demonstration will begin in early 1984

  10. USDOE radioactive waste incineration technology: status review

    International Nuclear Information System (INIS)

    Borduin, L.C.; Taboas, A.L.

    1980-01-01

    Early attempts were made to incinerate radioactive wastes met with operation and equipment problems such as feed preparation, corrosion, inadequate off-gas cleanup, incomplete combustion, and isotope containment. The US Department of Energy (DOE) continues to sponsor research, development, and the eventual demonstration of radioactive waste incineration. In addition, several industries are developing proprietary incineration system designs to meet other specific radwaste processing requirements. Although development efforts continue, significant results are available for the nuclear community and the general public to draw on in planning. This paper presents an introduction to incineration concerns, and an overview of the prominent radwaste incineration processes being developed within DOE. Brief process descriptions, status and goals of individual incineration systems, and planned or potential applications are also included

  11. Financing Academic Research Facilities: A National Need.

    Science.gov (United States)

    Norris, Julie T.

    1990-01-01

    This article examines possible changes to provide increased federal funding for university-based research facilities. The difficulties of converting between depreciation and use allowances are discussed, as is the possibility of using current market value versus acquisition cost as a basis for costing calculations and splitting the indirect cost…

  12. Waste processing building with incineration technology

    Science.gov (United States)

    Wasilah, Wasilah; Zaldi Suradin, Muh.

    2017-12-01

    In Indonesia, waste problem is one of major problem of the society in the city as part of their life dynamics. Based on Regional Medium Term Development Plan of South Sulawesi Province in 2013-2018, total volume and waste production from Makassar City, Maros, Gowa, and Takalar Regency estimates the garbage dump level 9,076.949 m3/person/day. Additionally, aim of this design is to present a recommendation on waste processing facility design that would accommodate waste processing process activity by incineration technology and supported by supporting activity such as place of education and research on waste, and the administration activity on waste processing facility. Implementation of incineration technology would reduce waste volume up to 90% followed by relative negative impact possibility. The result planning is in form of landscape layout that inspired from the observation analysis of satellite image line pattern of planning site and then created as a building site pattern. Consideration of building orientation conducted by wind analysis process and sun path by auto desk project Vasari software. The footprint designed by separate circulation system between waste management facility interest and the social visiting activity in order to minimize the croos and thus bring convenient to the building user. Building mass designed by inseparable connection series system, from the main building that located in the Northward, then connected to a centre visitor area lengthways, and walked to the waste processing area into the residue area in the Southward area.

  13. Offgas treatment for radioactive waste incinerators

    International Nuclear Information System (INIS)

    Stretz, L.A.; Koenig, R.A.

    1980-01-01

    Incineration of radioactive materials for resource recovery or waste volume reduction is recognized as an effective waste treatment method that will increase in usage and importance throughout the nuclear industry. The offgas cleanup subsystem of an incineration process is essential to ensure radionuclide containment and protection of the environment. Several incineration processes and associated offgas cleanup systems are discussed along with potential application of commercial pollution control components to radioactive service. Problems common to radioactive waste incinerator offgas service are identified and areas of needed research and development effort are noted

  14. Numerical model for a watering plan to wash out organic matter from the municipal solid waste incinerator bottom ash layer in closed system disposal facilities.

    Science.gov (United States)

    Ishii, Kazuei; Furuichi, Toru; Tanikawa, Noboru

    2009-02-01

    Bottom ash from municipal solid waste incineration (MSWI) is a main type of waste that is landfilled in Japan. The long-term elution of organic matter from the MSWI bottom ash layers is a concern because maintenance and operational costs of leachate treatment facilities are high. In closed system disposal facilities (CSDFs), which have a roof to prevent rainfall from infiltrating into the waste layers, water must be supplied artificially and its quantity can be controlled. However, the quantity of water needed and how to apply it (the intensity, period and frequency) have not been clearly defined. In order to discuss an effective watering plan, this study proposes a new washout model to clarify a fundamental mechanism of total organic carbon (TOC) elution behavior from MSWI bottom ash layers. The washout model considers three phases: solid, immobile water and mobile water. The parameters, including two mass transfer coefficients of the solid-immobile water phases and immobile-mobile water phases, were determined by one-dimensional column experiments for about 2 years. The intensity, period and frequency of watering and other factors were discussed based on a numerical analysis using the above parameters. As a result, our washout model explained adequately the elution behavior of TOC from the MSWI bottom ash layer before carbonation occurred (pH approximately 8.3). The determined parameters and numerical analysis suggested that there is a possibility that the minimum amount of water needed for washing out TOC per unit weight of MSWI bottom ash layer could be determined, which depends on the two mass transfer coefficients and the depth of the MSWI bottom ash layer. Knowledge about the fundamental mechanism of the elution behavior of TOC from the MSWI bottom ash layer before carbonation occurs, clarified by this study, will help an effective watering plan in CSDFs.

  15. Unique life sciences research facilities at NASA Ames Research Center

    Science.gov (United States)

    Mulenburg, G. M.; Vasques, M.; Caldwell, W. F.; Tucker, J.

    1994-01-01

    The Life Science Division at NASA's Ames Research Center has a suite of specialized facilities that enable scientists to study the effects of gravity on living systems. This paper describes some of these facilities and their use in research. Seven centrifuges, each with its own unique abilities, allow testing of a variety of parameters on test subjects ranging from single cells through hardware to humans. The Vestibular Research Facility allows the study of both centrifugation and linear acceleration on animals and humans. The Biocomputation Center uses computers for 3D reconstruction of physiological systems, and interactive research tools for virtual reality modeling. Psycophysiological, cardiovascular, exercise physiology, and biomechanical studies are conducted in the 12 bed Human Research Facility and samples are analyzed in the certified Central Clinical Laboratory and other laboratories at Ames. Human bedrest, water immersion and lower body negative pressure equipment are also available to study physiological changes associated with weightlessness. These and other weightlessness models are used in specialized laboratories for the study of basic physiological mechanisms, metabolism and cell biology. Visual-motor performance, perception, and adaptation are studied using ground-based models as well as short term weightlessness experiments (parabolic flights). The unique combination of Life Science research facilities, laboratories, and equipment at Ames Research Center are described in detail in relation to their research contributions.

  16. Holifield Heavy Ion Research Facility: Users handbook

    International Nuclear Information System (INIS)

    Auble, R.L.

    1987-01-01

    The primary objective of this handbook is to provide information for those who plan to carry out research programs at the Holifield Heavy Ion Research Facility (HHIRF) at Oak Ridge National Laboratory. The accelerator systems and experimental apparatus available are described. The mechanism for obtaining accelerator time and the responsibilities of those users who are granted accelerator time are described. The names and phone numbers of ORNL personnel to call for information about specific areas are given

  17. Technical Meeting (Research Coordination Meeting) of the Coordinated Research Project (CRP) on 'Studies of advanced reactor technology options for effective incineration of radioactive waste'. Working material

    International Nuclear Information System (INIS)

    2005-01-01

    The Technical Meeting held at the Institute of Plasma Physics, Chinese Academy of Sciences (ASIPP) in Hefei was the second Research Coordination Meeting (RCM) of the CRP on 'Studies of Innovative Reactor Technology Options for Effective Incineration of Radioactive Waste'. All but one Member States participating in the CRP were attending: in all, 26 participants from 13 Member States and three international organizations. The overall objective of the CRP is to increase the capability of Member States in developing and applying advanced nuclear technologies in the area of long-lived radioactive waste utilization and transmutation. The final goal of the CRP is to deepen the understanding of the dynamics of transmutation systems, e.g., the accelerator driven system, especially of systems with deteriorated safety parameters, to qualify the available methods, specify the range of validity of these methods, and formulate requirements for future theoretical developments. Should transient experiments be available, the CRP will pursue experimental benchmarking work. Based on the results, the CRP will conclude on the potential need of transient experiments and make appropriate proposals for experimental programs. The scope of the second RCM was to review the progress achieved with regard on the technical work of the CRP. In particular, the main objectives of the RCM were to (a) analyse and inter-compare the individual results; (b) identify of eventual changes/improvements to the tasks and/or work plans; (c) plan the next stage(s); and (d) start preparation of the final CRP report. The participants were given a brief overview of the Institute's mission and accomplishments. ASIPP (Academia Sinica, Institute of Plasma Physics) was founded in 1978 as the leading centre for high temperature plasma physics, magnetically confined fusion technology, as well as R and D in related technological areas. ASIPP employs nearly 500 staff, of which more than 70% are scientists or engineers

  18. Status report on the fluidized bed incineration system for U.S. Energy Research and Development Administration transuranic waste, January--June 1976

    International Nuclear Information System (INIS)

    Ziegler, D.L.; Richey, L.L.; Johnson, A.J.; Teter, A.L.; Feng, P.K.; Peterson, D.J.; Meile, L.J.

    1977-01-01

    A fluidized-bed incineration facility is being designed for installation at the Rocky Flats Plant to develop and demonstrate the process for the combustion of transuranic waste. The unit capacity will be about 82 kg/hr of combustible waste. The combustion process will utilize in situ neutralization of acid gases generated in the process. The equipment design is based on data generated on a pilot scale unit and represents a scale-up factor of nine. Title II engineering is at least 70 percent complete and construction work has begun

  19. Facilities Management research in the Nordic Countries

    DEFF Research Database (Denmark)

    Jensen, Per Anker

    2011-01-01

    to the establishment of the Centre for Facilities Management – Realdania Research (CFM), and updated information from keynote contributions to CFM’s Nordic FM Conference on 22-23 August 2011 by Suvi Nenonen (Finland), Jan Bröchner (Sweden), Geir K Hansen (Norway) and Per Anker Jensen (Denmark).......This article provides a brief overview of the short history of FM research in Denmark, Norway, Sweden and Finland, and presents current research topics and trends in these countries. It is based on information originally collected as part of the planning for the Danish research programme that led...

  20. Controlled air pyrolysis incinerator

    International Nuclear Information System (INIS)

    Dufrane, K.H.; Wilke, M.

    1982-01-01

    An advanced controlled air pyrolysis incinerator has been researched, developed and placed into commercial operation for both radioactive and other combustible wastes. Engineering efforts cocentrated on providing an incinerator which emitted a clean, easily treatable off-gas and which produced a minimum amount of secondary waste. Feed material is continuously fed by gravity into the system's pyrolysis chamber without sorting, shredding, or other such pretreatment. Metal objects, liquids such as oil and gasoline, or solid products such as resins, blocks of plastic, tire, animal carcasses, or compacted trash may be included along with normal processed waste. The temperature of the waste is very gradually increased in a reduced oxygen atmosphere. Volatile pyrolysis gases are produced, tar-like substances are cracked and the resulting product, a relatively uniform, easily burnable material, is introduced into the combustion chamber. Steady burning is thus accomplished under easily controlled excess air conditions with the off-gasthen passing through a simple dry clean-up system. Gas temperatures are then reduced by air dilution before passing through final HEPA filters. Both commercial and nuclear installations have been operated with the most recent application being the central incinerator to service West Germany's nuclear reactors

  1. A feasibility study of adaptive plasma-assisted incineration

    Science.gov (United States)

    Filion, Julie

    Rising awareness in the need for environmental protection has brought into question the adequacy of conventional hazardous waste treatment operations. Regulatory standards are increasingly strict, and there is growing concern over the safety of incineration facilities. This research project examines the technoeconomic potential of thermal plasma technology in this context. Adaptive Plasma-Assisted Incineration (APAI) is a novel concept for secondary gas treatment in hazardous waste incineration. As an energy source for waste destruction, a thermal plasma can provide conditions far higher in temperature and in reactivity than those obtained using a combustion flame. Thus, the plasma is more effective at destroying hazardous materials, albeit at a higher cost. APAI features a thermal plasma afterburner with continual on-line optical monitoring of the gas product and feedback optimization of the plasma conditions. This approach allows complete destruction of persistent organic compounds and cost-effective response to feed load variations. The process supplements conventional incineration techniques with the effectiveness and flexibility of thermal plasma treatment. The main objectives are to reduce the risk of harmful emissions during hazardous waste incineration and to facilitate compliance with new environmental regulations. In this project, the technical feasibility of APAI was demonstrated experimentally using a laboratory-scale plasma afterburner model. The work focused on the development of a spectroscopic monitoring procedure and on the application of optimization techniques for cost-effective operation of the model system. The techno-economic potential and limitations of APAI were addressed in a conceptual study. Preliminary designs and cost estimates were developed for specific applications. The costs of plasma-assisted and conventional methods were compared for contaminated soil remediation (by incineration and desorption) and for organic liquid waste

  2. MYRRHA: A multipurpose nuclear research facility

    Science.gov (United States)

    Baeten, P.; Schyns, M.; Fernandez, Rafaël; De Bruyn, Didier; Van den Eynde, Gert

    2014-12-01

    MYRRHA (Multi-purpose hYbrid Research Reactor for High-tech Applications) is a multipurpose research facility currently being developed at SCK•CEN. MYRRHA is based on the ADS (Accelerator Driven System) concept where a proton accelerator, a spallation target and a subcritical reactor are coupled. MYRRHA will demonstrate the ADS full concept by coupling these three components at a reasonable power level to allow operation feedback. As a flexible irradiation facility, the MYRRHA research facility will be able to work in both critical as subcritical modes. In this way, MYRRHA will allow fuel developments for innovative reactor systems, material developments for GEN IV and fusion reactors, and radioisotope production for medical and industrial applications. MYRRHA will be cooled by lead-bismuth eutectic and will play an important role in the development of the Pb-alloys technology needed for the LFR (Lead Fast Reactor) GEN IV concept. MYRRHA will also contribute to the study of partitioning and transmutation of high-level waste. Transmutation of minor actinides (MA) can be completed in an efficient way in fast neutron spectrum facilities, so both critical reactors and subcritical ADS are potential candidates as dedicated transmutation systems. However critical reactors heavily loaded with fuel containing large amounts of MA pose reactivity control problems, and thus safety problems. A subcritical ADS operates in a flexible and safe manner, even with a core loading containing a high amount of MA leading to a high transmutation rate. In this paper, the most recent developments in the design of the MYRRHA facility are presented.

  3. Lewis Research Center R and D Facilities

    Science.gov (United States)

    1991-01-01

    The NASA Lewis Research Center (LeRC) defines and develops advanced technology for high priority national needs. The work of the Center is directed toward new propulsion, power, and communications technologies for application to aeronautics and space, so that U.S. leadership in these areas is ensured. The end product is knowledge, usually in a report, that is made fully available to potential users--the aircraft engine industry, the energy industry, the automotive industry, the space industry, and other NASA centers. In addition to offices and laboratories for almost every kind of physical research in such fields as fluid mechanics, physics, materials, fuels, combustion, thermodynamics, lubrication, heat transfer, and electronics, LeRC has a variety of engineering test cells for experiments with components such as compressors, pumps, conductors, turbines, nozzles, and controls. A number of large facilities can simulate the operating environment for a complete system: altitude chambers for aircraft engines; large supersonic wind tunnels for advanced airframes and propulsion systems; space simulation chambers for electric rockets or spacecraft; and a 420-foot-deep zero-gravity facility for microgravity experiments. Some problems are amenable to detection and solution only in the complete system and at essentially full scale. By combining basic research in pertinent disciplines and generic technologies with applied research on components and complete systems, LeRC has become one of the most productive centers in its field in the world. This brochure describes a number of the facilities that provide LeRC with its exceptional capabilities.

  4. 40 years of experience in incineration of radioactive waste in Belgium

    International Nuclear Information System (INIS)

    Vanbrabant, R.; Deckers, J.; Luycx, P.; Detilleux, M.; Beguin, Ph.

    2001-01-01

    Since the very beginning of the nuclear activities in Belgium, the incineration of radioactive waste was chosen as a suitable technique for achieving an optimal volume reduction of the produced waste quantities; several R and D projects were realised in this specific field and different facilities were erected and operated. An experimental furnace ''Evence Coppee'' was built in 1960 for treatment of LLW produced by the Belgian Research Centre (SCK/CEN). Regularly this furnace has been modified, improved and equipped with additional installations to obtain better combustion conditions and a more efficient gas cleaning system. Based on the 35 years experience gained by the operation of the ''Evence Coppee'', a completely new industrial incineration installation has been designed in the nineties and commissioned in May 1995, in the frame of the erection of the Belgian Centralised Treatment/Conditioning Facility CILVA. At the end of 1998, the new furnace has burnt 455 tons of solid waste and 246 tons of liquid waste. Besides the conventional incineration process, a High Temperature Slagging Incinerator (HTSI) has been developed, constructed and operated for 10 years in the past. This installation was the combination of an incinerator and a melter producing melted granulated material instead of ashes, and provided experience in the incineration of hazardous waste, such as chlorinated organic compounds and waste with PCB content. The paper presents ''the Belgian Experience'' accumulated year after year with the design and the operation of the above mentioned facilities and demonstrates how the needs required today for a modern installation are met. The paper covers the following aspects; design particularities and description of the systems, operational results for different solid waste categories (bulk waste, precompacted waste, ion exchange resins) and for different liquid waste categories (organic, aqueous, oil), required pretreatment of the waste, ashes conditioning

  5. Radwaste incineration, is it ready for use

    International Nuclear Information System (INIS)

    Coplan, B.W.

    1982-01-01

    The incinerator installed at JAERI in 1973 has the record of being operated continually for eight years without noticeable damage even in the refractories. We are convinced that it can be used for along period of time. These incinerators in Japan are now regarded as the useful and reliable waste management facilities, though they are processing the restricted sorts of wastes, such as low level ombustible solids and oils. In the future, incinerators of these types are supposed to increase in number in Japan, and they will continue to contribute as an important volume reduction measure which can also convert the wastes to chemically stable substances

  6. 3. Research Coordination Meeting (RCM) of the Coordinated Research Project (CRP) on 'Studies of advanced reactor technology options for effective incineration of radioactive waste'. Working material

    International Nuclear Information System (INIS)

    2007-01-01

    To meet expressed Member States' needs, the IAEA has initiated a Coordinated Research Project (CRP) on 'Studies of Advanced Reactor Technology Options for Effective Incineration of Radioactive Waste'. The final goal of the CRP is to deepen the understanding of the dynamics of transmutation systems, e.g. the accelerator driven system, especially systems with deteriorated safety parameters, qualify the available methods, specify the range of validity of methods, and formulate requirements for future theoretical developments. Should transient experiments be available, the CRP will pursue experimental benchmarking work. In any case, based on the results, the CRP will conclude on the potential need of transient experiments and make appropriate proposals for experimental programs. The Technical Meeting in Chennai was the 3rd Research Coordination Meeting (RCM) of the CRP The man objectives of the RCM were to: - Discuss and perform inter-comparisons of the various benchmark results; - Prepare the first draft of the final CRP Report Status of the analyses and inter-comparisons of the results. The main objective of the CRP was to study innovative technology options for incinerating/utilizing radioactive wastes. The CRP's benchmarking exercises focused on eight innovative transmutation 'Domains', which correspond to different critical and sub-critical concepts or groups of concepts: I. Critical fast reactor, solid fuel, with fertile; II. Critical fast reactor, solid fuel, fertile-free; III. ADS, solid fuel, with fertile; IV. ADS, solid fuel, fertile-free; V. Critical reactor and ADS, molten salt fuel, with fertile; VI. Critical reactor and ADS, molten salt fuel, fertile-free; VII. Critical fast reactor and ADS, gas cooled; VIII. Fusion/fission hybrid system. For each of these Domains, the discussions and inter-comparisons considered the following issues: - Reactor-models; - Scenarios/phenomena; - Static analyses; - Dynamic analyses; - Methods; - Codes; - Neutronic data base

  7. A US Based Ultrafast Interdisciplinary Research Facility

    Science.gov (United States)

    Gueye, Paul; Hill, Wendell; Johnson, Anthony

    2006-10-01

    The US scientific competitiveness on the world arena has substantially decreased due to the lack of funding and training of qualified personnel. Most of the potential workforce found in higher education is composed of foreign students and post-docs. In the specific field of low- and high-field science, the European and Asian communities are rapidly catching-up with the US, even leading in some areas. To remain the leader in ultrafast science and technology, new visions and commitment must be embraced. For that reason, an international effort of more than 70 countries for a US-based interdisciplinary research facility using ultrafast laser technology is under development. It will provide research and educational training, as well as new venues for a strong collaboration between the fields of astrophysics, nuclear/high energy physics, plasma physics, optical sciences, biological and medical physics. This facility will consist of a uniquely designed high contrast multi-lines concept housing twenty experimental rooms shared between four beams:[0.1 TW, 1 kHz], [10 TW, 9 kHz], [100-200 TW, 10 Hz] and [500 TW, 10 Hz]. The detail schematic of this multi-laser system, foreseen research and educational programs, and organizational structure of this facility will be presented.

  8. MYRRHA: A multipurpose nuclear research facility

    Directory of Open Access Journals (Sweden)

    Baeten P.

    2014-01-01

    As a flexible irradiation facility, the MYRRHA research facility will be able to work in both critical as subcritical modes. In this way, MYRRHA will allow fuel developments for innovative reactor systems, material developments for GEN IV and fusion reactors, and radioisotope production for medical and industrial applications. MYRRHA will be cooled by lead-bismuth eutectic and will play an important role in the development of the Pb-alloys technology needed for the LFR (Lead Fast Reactor GEN IV concept. MYRRHA will also contribute to the study of partitioning and transmutation of high-level waste. Transmutation of minor actinides (MA can be completed in an efficient way in fast neutron spectrum facilities, so both critical reactors and subcritical ADS are potential candidates as dedicated transmutation systems. However critical reactors heavily loaded with fuel containing large amounts of MA pose reactivity control problems, and thus safety problems. A subcritical ADS operates in a flexible and safe manner, even with a core loading containing a high amount of MA leading to a high transmutation rate. In this paper, the most recent developments in the design of the MYRRHA facility are presented.

  9. Operating large controlled thermonuclear fusion research facilities

    International Nuclear Information System (INIS)

    Gaudreau, M.P.J.; Tarrh, J.M.; Post, R.S.; Thomas, P.

    1987-01-01

    The MIT Tara Tandem Mirror is a large, state of the art controlled thermonuclear fusion research facility. Over the six years of its design, implementation, and operation, every effort was made to minimize cost and maximize performance by using the best and latest hardware, software, and scientific and operational techniques. After reviewing all major DOE fusion facilities, an independent DOE review committee concluded that the Tara operation was the most automated and efficient of all DOE facilities. This paper includes a review of the key elements of the Tara design, construction, operation, management, physics milestones, and funding that led to this success. The authors emphasize a chronological description of how the system evolved from the proposal stage to a mature device with an emphasis on the basic philosophies behind the implementation process. This description can serve both as a qualitative and quantitative database for future large experiment planning. It includes actual final costs and manpower spent as well as actual run and maintenance schedules, number of data shots, major system failures, etc. The paper concludes with recommendations for the next generation of facilities

  10. Operating large controlled thermonuclear fusion research facilities

    International Nuclear Information System (INIS)

    Gaudreau, M.P.J.; Tarrh, J.M.; Post, R.S.; Thomas, P.

    1987-10-01

    The MIT Tara Tandem Mirror is a large, state of the art controlled thermonuclear fusion research facility. Over the six years of its design, implementation, and operation, every effort was made to minimize cost and maximize performance by using the best and latest hardware, software, and scientific and operational techniques. After reviewing all major DOE fusion facilities, an independent DOE review committee concluded that the Tara operation was the most automated and efficient of all DOE facilities. This paper includes a review of the key elements of the Tara design, construction, operation, management, physics milestones, and funding that led to this success. We emphasize a chronological description of how the system evolved from the proposal stage to a mature device with an emphasis on the basic philosophies behind the implementation process. This description can serve both as a qualitative and quantitative database for future large experiment planning. It includes actual final costs and manpower spent as well as actual run and maintenance schedules, number of data shots, major system failures, etc. The paper concludes with recommendations for the next generation of facilities. 13 refs., 15 figs., 3 tabs

  11. Oxygen incineration process for treatment of alpha-contaminated wastes

    International Nuclear Information System (INIS)

    Kim, Jeong Guk; Yang, Hee Chul; Park, Geun Il; Kim, In Tae; Kim, Joon Hyung

    2001-07-01

    As a part of development of a treatment technology for burnable alpha-bearing (or -contaminated) wastes using an oxygen incineration process, which would be expected to produce in Korea, the off-gas volume and compositions were estimated form mass and heat balance, and then compared to those of a general air incineration process. A laboratory-scale oxygen incineration process, to investigate a burnable wastes from nuclear fuel fabricatin facility, was designed, constructed, and then operated. The use of oxygen instead of air in incineratin would result in reduction on off-gas product below one seventh theoretically. In addition, the trends on incineration and melting processes to treat the radioactive alpha-contaminated wastes, and the regulations and guide lines, related to design, construction, and operation of incineration process, were reviewed. Finallu, the domestic regulations related incineration, and the operation and maintenance manuals for oxy-fuel burner and oxygen incineration process were shown in appendixes

  12. Experimental facilities for Generation IV reactors research

    International Nuclear Information System (INIS)

    Krecanova, E.; Di Gabriele, F.; Berka, J.; Zychova, M.; Macak, J.; Vojacek, A.

    2013-06-01

    Centrum Vyzkumu Rez (CVR) is research and development Company situated in Czech Republic and member of the UJV group. One of its major fields is material research for Generation IV reactor concepts, especially supercritical water-cooled reactor (SCWR), very high temperature/gas-cooled fast reactor (VHTR/GFR) and lead-cooled fast reactor (LFR). The CVR is equipped by and is building unique experimental facilities which simulate the environment in the active zones of these reactor concepts and enable to pre-qualify and to select proper constructional materials for the most stressed components of the facility (cladding, vessel, piping). New infrastructure is founded within the Sustainable Energy project focused on implementation the Generation IV and fusion experimental facilities. The research of SCWR concept is divided to research and development of the constructional materials ensured by SuperCritical Water Loop (SCWL) and fuel components research on Fuel Qualification Test loop (SCWL-FQT). SCWL provides environment of the primary circuits of European SCWR, pressure 25 MPa, temperature 600 deg. C and its major purpose is to simulate behavior of the primary medium and candidate constructional materials. On-line monitoring system is included to collect the operational data relevant to experiment and its evaluation (pH, conductivity, chemical species concentration). SCWL-FQT is facility focused on the behavior of cladding material and fuel at the conditions of so-called preheater, the first pass of the medium through the fuel (in case of European SCWR concept). The conditions are 450 deg. C and 25 MPa. SCWL-FQT is unique facility enabling research of the shortened fuel rods. VHTR/GFR research covers material testing and also cleaning methods of the medium in primary circuit. The High Temperature Helium Loop (HTHL) enables exposure of materials and simulates the VHTR/GFR core environment to analyze the behavior of medium, especially in presence of organic compounds and

  13. Research paper 2000-B-1: the implementation of the municipal waste incineration directive (89/429) in France

    Energy Technology Data Exchange (ETDEWEB)

    Schucht, S.

    2000-07-01

    This paper constitutes a contribution to the project 'IMPOL - The Implementation of EU Environmental Policies: Efficiency Issues'. The paper deals with the implementation of the EU Directives directed at atmospheric emissions from new (89/369/EEC) and existing (89/429/EEC) municipal waste incineration plants in France. The goal of this paper is twofold: a historic review of the implementation processes and their evaluation following economic criteria of environmental effectiveness and economic efficiency. The focus is on the implementation of the Directives' requirements towards existing municipal waste incineration plants, i.e. those plants having received their operation licence after December 1, 1990. For France we find a general picture of poor compliance. This result has to be differentiated, though: the current compliance rate of plants of a capacity above 6 t/h is almost 100% (although compliance often came late) while the majority of smaller plants does not comply with the Directive's requirements. With a waste incineration park of about 250 plants currently, many of which are very small plants and only treat weak amounts of waste, France constitutes an exception compared to other European countries. A further specific characteristic of France is the high share of waste incineration in total waste treatment (especially in the big cities) which amounts to almost 40%. The outline of the paper is the following: chapter two gives some context information on the French municipal waste incineration plant park and its structure, on the development of waste quantities, on the legal framework and on available subsidy schemes. Chapter three assesses environmental effectiveness, i.e. goal attainment and factors explaining the results. Chapter four comprises the assessment of cost efficiency. Chapter five contains the historic review, i.e. a characterisation of the implementation process, and chapter six concludes, linking the characterisation of

  14. How Large-Scale Research Facilities Connect to Global Research

    DEFF Research Database (Denmark)

    Lauto, Giancarlo; Valentin, Finn

    2013-01-01

    Policies for large-scale research facilities (LSRFs) often highlight their spillovers to industrial innovation and their contribution to the external connectivity of the regional innovation system hosting them. Arguably, the particular institutional features of LSRFs are conducive for collaborati...... with domestic universities or government laboratories. Policies conceiving LSRFs as “knowledge attractors” therefore should consider the complementarities between research at a LSRF and in its academic context at a regional or national level....

  15. ARM Climate Research Facility Annual Report 2005

    Energy Technology Data Exchange (ETDEWEB)

    J. Voyles

    2005-12-31

    Through the ARM Program, the DOE funded the development of several highly instrumented ground stations for studying cloud formation processes and their influence on radiative transfer, and for measuring other parameters that determine the radiative properties of the atmosphere. This scientific infrastructure, and resultant data archive, is a valuable national and international asset for advancing scientific knowledge of Earth systems. In fiscal year (FY) 2003, the DOE designated ARM sites as a national scientific user facility: the ARM Climate Research (ACRF). The ACRF has enormous potential to contribute to a wide range interdisciplinary science in areas such as meteorology, atmospheric aerosols, hydrology, biogeochemical cycling, and satellite validation, to name only a few.

  16. Corium melt researches at VESTA test facility

    OpenAIRE

    Hwan Yeol Kim; Sang Mo An; Jaehoon Jung; Kwang Soon Ha; Jin Ho Song

    2017-01-01

    VESTA (Verification of Ex-vessel corium STAbilization) and VESTA-S (-small) test facilities were constructed at the Korea Atomic Energy Research Institute in 2010 to perform various corium melt experiments. Since then, several tests have been performed for the verification of an ex-vessel core catcher design for the EU-APR1400. Ablation tests of an impinging ZrO2 melt jet on a sacrificial material were performed to investigate the ablation characteristics. ZrO2 melt in an amount of 65–70 kg w...

  17. NSTX: Facility/Research Highlights and Near Term Facility Plans

    International Nuclear Information System (INIS)

    Ono, M.

    2008-01-01

    The National Spherical Torus Experiment (NSTX) is a collaborative mega-ampere-class spherical torus research facility with high power heating and current drive systems and the state-of-the-art comprehensive diagnostics. For the 2008 experimental campaign, the high harmonic fast wave (HHFW) heating efficiency in deuterium improved significantly with lithium evaporation and produced a record central Te of 5 keV. The HHFW heating of NBI-heated discharges was also demonstrated for the first time with lithium application. The EBW emission in H-mode was also improved dramatically with lithium which was shown to be attributable to reduced edge collisional absorption. Newly installed FIDA energetic particle diagnostic measured significant transport of energetic ions associated with TAE avalanche as well as n=1 kink activities. A full 75 channel poloidal CHERS system is now operational yielding tantalizing initial results. In the near term, major upgrade activities include a liquid-lithium divertor target to achieve lower collisionality regime, the HHFW antenna upgrades to double its power handling capability in H-mode, and a beam-emission spectroscopy diagnostic to extend the localized turbulence measurements toward the ion gyro-radius scale from the present concentration on the electron gyro-radius scale. For the longer term, a new center stack to significantly expand the plasma operating parameters is planned along with a second NBI system to double the NBI heating and CD power and provide current profile control. These upgrades will enable NSTX to explore fully non-inductive operations over a much expanded plasma parameter space in terms of higher plasma temperature and lower collisionality, thereby significantly reducing the physics parameter gap between the present NSTX and the projected next-step ST experiments

  18. SINP MSU accelerator facility and applied research

    International Nuclear Information System (INIS)

    Chechenin, N.G.; Ishkhanov, B.S.; Kulikauskas, V.S.; Novikov, L.S.; Pokhil, G.P.; Romanovskii, E.A.; Shvedunov, V.I.; Spasskii, A.V.

    2004-01-01

    Full text: SINP accelerator facility includes 120 cm cyclotron, electrostatic generator with the upper voltage 3.0 MeV, electrostatic generator with the upper voltage 2.5 MeV, Cocroft -Walton generator with the upper voltage 500 keV, 150 keV accelerator for solid microparticles. A new generation of electron beam accelerators has been developed during the last decade. The SINP accelerator facility will be shortly described in the report. A wide range of basic research in nuclear and atomic physics, physics of ion-beam interactions with condensed matter is currently carried out. SINP activity in the applied research is concentrated in the following areas of materials science: - Materials diagnostics with the Rutherford backscattering techniques (RBS) and channeling of ions (RBS/C). A large number of surface ad-layers and multilayer systems for advanced micro- and nano-electronic technology have been investigated. A selected series of examples will be illustrated. - Concentration depth profiles of hydrogen by the elastic recoils detection techniques (ERD). Primarily, the hydrogen depth profiles in perspective materials for thermonuclear reactors have been investigated. - Lattice site locations of hydrogen by a combination of ERD and channeling techniques. This is a new technique which was successfully applied for investigation of hydrogen and hydrogen-defect complexes in silicon for the smart-cut technology. - Light element diagnostics by RBS and nuclear backscattering techniques (NBS). The technique is illustrated by applications for nitrogen concentration profiling in steels. Nitrogen take-up and release, nitrides precipitate formation will be illustrated. - New medium energy ion scattering (MEIS) facility and applications. Ultra-high vacuum and superior energy resolution electrostatic toroidal analyzer is designed to be applied for characterization of composition and structure of several upper atomic layers of materials

  19. Incineration of contaminated oil from Sellafield - 16246

    International Nuclear Information System (INIS)

    Broadbent, Craig; Cassidy, Helen; Stenmark, Anders

    2009-01-01

    Studsvik have been incinerating Low Level Waste (LLW) at its licensed facility in Sweden since the mid-1970's. This process not only enables the volume of waste to be significantly reduced but also produces an inert residue suitable for final disposal. The facility has historically incinerated only solid dry LLW, however in 2008 an authorisation was obtained to permit the routine incineration of LLW contaminated oil at the facility. Prior to obtaining the authorisation to incinerate oils and other organic liquids - both from clean-up activities on the Studsvik site and on a commercial basis - a development program was established. The primary aims of this were to identify the optimum process set-up for the incinerator and also to demonstrate to the regulatory authorities that the appropriate environmental and radiological parameters would be maintained throughout the new process. The final phase of the development program was to incinerate a larger campaign of contaminated oil from the nuclear industry. A suitable accumulation of oil was identified on the Sellafield site in Cumbria and a commercial contract was established to incinerate approximately 40 tonnes of oil from the site. The inventory of oil chosen for the trial incineration represented a significant challenge to the incineration facility as it had been generated from various facilities on-site and had degraded significantly following years of storage. In order to transport the contaminated oil from the Sellafield site in the UK to the Studsvik facility in Sweden several challenges had to be overcome. These included characterisation, packaging and international transportation (under a Transfrontier Shipment (TFS) authorisation) for one of the first transports of liquid radioactive wastes outside the UK. The incineration commenced in late 2007 and was successfully completed in early 2008. The total volume reduction achieved was greater than 97%, with the resultant ash packaged and returned to the UK (for

  20. Solar Energy Research Center Instrumentation Facility

    Energy Technology Data Exchange (ETDEWEB)

    Meyer, Thomas, J.; Papanikolas, John, P.

    2011-11-11

    SOLAR ENERGY RESEARCH CENTER INSTRUMENTATION FACILITY The mission of the Solar Energy Research Center (UNC SERC) at the University of North Carolina at Chapel Hill (UNC-CH) is to establish a world leading effort in solar fuels research and to develop the materials and methods needed to fabricate the next generation of solar energy devices. We are addressing the fundamental issues that will drive new strategies for solar energy conversion and the engineering challenges that must be met in order to convert discoveries made in the laboratory into commercially available devices. The development of a photoelectrosynthesis cell (PEC) for solar fuels production faces daunting requirements: (1) Absorb a large fraction of sunlight; (2) Carry out artificial photosynthesis which involves multiple complex reaction steps; (3) Avoid competitive and deleterious side and reverse reactions; (4) Perform 13 million catalytic cycles per year with minimal degradation; (5) Use non-toxic materials; (6) Cost-effectiveness. PEC efficiency is directly determined by the kinetics of each reaction step. The UNC SERC is addressing this challenge by taking a broad interdisciplinary approach in a highly collaborative setting, drawing on expertise across a broad range of disciplines in chemistry, physics and materials science. By taking a systematic approach toward a fundamental understanding of the mechanism of each step, we will be able to gain unique insight and optimize PEC design. Access to cutting-edge spectroscopic tools is critical to this research effort. We have built professionally-staffed facilities equipped with the state-of the-art instrumentation funded by this award. The combination of staff, facilities, and instrumentation specifically tailored for solar fuels research establishes the UNC Solar Energy Research Center Instrumentation Facility as a unique, world-class capability. This congressionally directed project funded the development of two user facilities: TASK 1: SOLAR

  1. In Vivo Radiobioassay and Research Facility

    International Nuclear Information System (INIS)

    Lynch, Timothy P.

    2011-01-01

    Bioassay monitoring for intakes of radioactive material is an essential part of the internal dosimetry program for radiation workers at the Department of Energy's (DOE) Hanford Site. This monitoring program includes direct measurements of radionuclides in the body by detecting photons that exit the body and analyses of radionuclides in excreta samples. The specialized equipment and instrumentation required to make the direct measurements of these materials in the body are located at the In Vivo Radiobioassay and Research Facility (IVRRF). The IVRRF was originally built in 1960 and was designed expressly for the in vivo measurement of radioactive material in Hanford workers. Most routine in vivo measurements are performed annually and special measurements are performed as needed. The primary source terms at the Hanford Site include fission and activation products (primarily 137Cs and 90Sr), uranium, uranium progeny, and transuranic radionuclides. The facility currently houses five shielded counting systems, men's and women's change rooms and an instrument maintenance and repair shop. Four systems include high purity germanium detectors and one system utilizes large sodium iodide detectors. These systems are used to perform an average of 7,000 measurements annually. This includes approximately 5000 whole body measurements analyzed for fission and activation products and 2000 lung measurements analyzed for americium, uranium, and plutonium. Various other types of measurements are performed periodically to estimate activity in wounds, the thyroid, the liver, and the skeleton. The staff maintains the capability to detect and quantify activity in essentially any tissue or organ. The in vivo monitoring program that utilizes the facility is accredited by the Department of Energy Laboratory Accreditation Program for direct radiobioassay.

  2. Metal leachability, heavy metals, polycyclic aromatic hydrocarbons and polychlorinated biphenyls in fly and bottom ashes of a medical waste incineration facility.

    Science.gov (United States)

    Valavanidis, Athanasios; Iliopoulos, Nikiforos; Fiotakis, Konstantinos; Gotsis, George

    2008-06-01

    Medical waste from hospitals and other healthcare institutions has become an imperative environmental and public safety problem. Medical waste in Greece has become one of the most urgent environmental problems, because there are 14,000 tons produced annually, of which only a small proportion is incinerated. In the prefecture of Attica there is only one modern municipal medical waste incinerator (started 2004) burning selected infectious hospital waste (5-6 tons day(-1)). Fly and bottom residues (ashes) are collected and stored temporarily in barrels. High values of metal leachability prohibit the landfilling of these ashes, as imposed by EU directives. In the present study we determined quantitatively the heavy metals and other elements in the fly and bottom ashes of the medical waste incinerator, by inductively coupled plasma emission spectrometry (ICP) and by energy dispersive X-ray analysis (EDAX). Heavy metals, which are very toxic, such as Pb, Cd, Ni, Cr, Cu and Zn were found in high concentrations in both fly and bottom ashes. Metal leachability of fly and bottom ashes by water and kerosene was measured by ICP and the results showed that toxic metals in both ashes, such as Pb, Cr, Cd, Cu and Zn, have high leaching values. These values indicate that metals can become soluble and mobile if ash is deposited in landfills, thus restricting their burial according to EU regulations. Analysis of polychlorinated biphenyls and polycyclic aromatic hydrocarbons in fly and bottom ashes showed that their concentrations were very low. This is the first known study in Greece and the results showed that incineration of medical waste can be very effective in minimizing the most hazardous and infectious health-care waste. The presence of toxic metals with high leachability values remains an important draw back of incineration of medical waste and various methods of treating these residues to diminish leaching are been considered at present to overcome this serious technical

  3. Addition of liquid waste incineration capability to the INEL's low-level waste incinerator

    International Nuclear Information System (INIS)

    Steverson, E.M.; Clark, D.P.; McFee, J.N.

    1986-01-01

    A liquid waste system has recently been installed in the Waste Experimental Reduction Facility (WERF) incinerator at the Idaho National Engineering Laboratory (INEL). In this paper, aspects of the incineration system such as the components, operations, capabilities, capital cost, EPA permit requirements, and future plans are discussed. The principal objective of the liquid incineration system is to provide the capability to process hazardous, radioactively contaminated, non-halogenated liquid wastes. The system consists primarily of a waste feed system, instrumentation and controls, and a liquid burner, which were procured at a capital cost of $115,000

  4. MYRRHA. An innovative and unique research facility

    International Nuclear Information System (INIS)

    Fernandez, Rafaeol; Neerdael, Bernard; Schyns, Marc; Dyck, Steven Van; Michiels, Sidney; Ait Abderrahim, Hamid

    2012-01-01

    The MYRRHA project started in 1998 by SCK·CEN in collaboration with Ion Beam Applications (IBA, Louvain-la-Neuve), as an upgrade of the ADONIS project. MYRRHA is designed as a multi-purpose irradiation facility in order to support research programmes on fission and fusion reactor structural materials and nuclear fuel development. Applications of these are found in Accelerator Driven Systems (ADS) systems and in present generation as well as in next generation critical reactors. The first objective of MYRRHA however, will be to demonstrate on one hand the ADS concept at a reasonable power level and on the other hand the technological feasibility of transmutation of Minor Actinides (MA) and Long-Lived Fission Products (LLFP) arising from the reprocessing of radioactive waste. MYRRHA will also help the development of the Pb-alloys technology needed for the LFR (Lead Fast Reactor) Gen.IV concept. Transmutation of MA can be completed in an efficient way in fast neutron spectrum facilities. Both critical reactors and sub-critical ADS are potential candidates as dedicated transmutation systems. However, critical reactors, heavily loaded with fuel containing large amounts of MA, pose safety problems caused by unfavourable reactivity coefficients due to the little delayed neutron fraction. A sub-critical ADS operates in a flexible and safe manner even with a core loading containing a high amount of MA leading to achieve a high efficient transmutation. Thus, the sub-criticality is not a virtue but rather a necessity for an efficient and economical burning of the MA. Besides the reduction of the HLW burden, the MYRRHA project will serve the purpose of developing the lead alloys technology as a reactor coolant that can be used in one of the Generation IV reactor concepts namely the Lead Fast Reactor (LFR). Although carrying out the MYRRHA project will lead to the demonstration of the efficient and safe transmutation of MA in ADS systems as the ultimate goal the implementation

  5. Europlanet Research Infrastructure: Planetary Simulation Facilities

    Science.gov (United States)

    Davies, G. R.; Mason, N. J.; Green, S.; Gómez, F.; Prieto, O.; Helbert, J.; Colangeli, L.; Srama, R.; Grande, M.; Merrison, J.

    2008-09-01

    EuroPlanet The Europlanet Research Infrastructure consortium funded under FP7 aims to provide the EU Planetary Science community greater access for to research infrastructure. A series of networking and outreach initiatives will be complimented by joint research activities and the formation of three Trans National Access distributed service laboratories (TNA's) to provide a unique and comprehensive set of analogue field sites, laboratory simulation facilities, and extraterrestrial sample analysis tools. Here we report on the infrastructure that comprises the second TNA; Planetary Simulation Facilities. 11 laboratory based facilities are able to recreate the conditions found in the atmospheres and on the surfaces of planetary systems with specific emphasis on Martian, Titan and Europa analogues. The strategy has been to offer some overlap in capabilities to ensure access to the highest number of users and to allow for progressive and efficient development strategies. For example initial testing of mobility capability prior to the step wise development within planetary atmospheres that can be made progressively more hostile through the introduction of extreme temperatures, radiation, wind and dust. Europlanet Research Infrastructure Facilties: Mars atmosphere simulation chambers at VUA and OU These relatively large chambers (up to 1 x 0.5 x 0.5 m) simulate Martian atmospheric conditions and the dual cooling options at VUA allows stabilised instrument temperatures while the remainder of the sample chamber can be varied between 220K and 350K. Researchers can therefore assess analytical protocols for instruments operating on Mars; e.g. effect of pCO2, temperature and material (e.g., ± ice) on spectroscopic and laser ablation techniques while monitoring the performance of detection technologies such as CCD at low T & variable p H2O & pCO2. Titan atmosphere and surface simulation chamber at OU The chamber simulates Titan's atmospheric composition under a range of

  6. High Energy Solid State Laser Research Facility

    Data.gov (United States)

    Federal Laboratory Consortium — A suite of laboratories with advanced spectroscopic and laser equipment, this facility develops materials and techniques for advanced solid state high energy lasers....

  7. Pilot-scale incineration of comtaminated soils from the drake chemical superfund site. Final report

    International Nuclear Information System (INIS)

    King, C.; Lee, J.W.; Waterland, L.R.

    1993-03-01

    A series of pilot-scale incineration tests were performed at the U.S. Environmental Protection Agency's (EPA's) Incineration Research Facility to evaluate the potential of incineration as an option to treat contaminated soils from the Drake Chemical Superfund site in Lock Haven, Pennsylvania. The soils at the Drake site are reported to be contaminated to varying degrees with various organic constituents and several hazardous constituent trace metals. The purpose of the test program was to evaluate the incinerability of selected site soils in terms of the destruction of contaminant organic constituents and the fate of contaminant trace metals. All tests were conducted in the rotary kiln incineration system at the IRF. Test results show that greater than 99.995 percent principal organic hazardous constituent (POHC) destruction and removal efficiencies (DRE) can be achieved at kiln exit gas temperatures of nominally 816 C (1,500 F) and 538 C (1,000 F). Complete soil decontamination of semivolatile organics was achieved; however, kiln ash levels of three volatile organic constituents remained comparable to soil levels

  8. Conventional incinerator redesign for the incineration of low level radioactive solid wastes

    International Nuclear Information System (INIS)

    Lara Z, L.E.C.

    1997-01-01

    From several years ago have been detected some problems with the storage of low level radioactive solids wastes, they are occasioned growth in volume and weight, one of most effective treatment for its reduction, the incineration has been. In the work was designed an incinerator of low level radioactive solid wastes, the characteristics, range of temperatures, that operate and the excess of air in order to get a near incineration at 100 %; thickness of refractory material in the combustion chamber, materials and forms of installation, the balances of mass, energy and radioactive material necessary for the design of the auxiliary peripheral equipment is discussed. In theory the incineration is a viable option for the treatment of low level radioactive solid wastes, upon getting an approximate reduction to 95 % of the wastes introduced to the incinerator in the Department of Radioactive Wastes of the National Institute of Nuclear Research, avoiding the dispersion of combustion gases and radioactive material at the environment. (Author)

  9. Research in artificial intelligence for nuclear facilities

    International Nuclear Information System (INIS)

    Uhrig, R.E.

    1990-01-01

    The application of artificial intelligence, in the form of expert systems and neural networks, to the control room activities in a nuclear power plant has the potential to reduce operator error and increase plant safety, reliability, and efficiency. Furthermore, artificial intelligence can increase efficiency and effectiveness in a large number of nonoperating activities (testing, routine maintenance, outage planning, equipment diagnostics, and fuel management) and in research facility experiments. Recent work at the University of Tennessee has demonstrated the feasibility of using neural networks to identify six different transients introduced into the simulation of a steam generator of a nuclear power plant. This work is now being extended to utilize data from a nuclear power plant training simulator. In one configuration, the inputs to the neural network are a subset of the quantities that are typical of those available from the safety parameter display system. The outputs of the network represent the various states of the plant (e.g., normal operation, coolant leakage, inadequate core flow, excessive peak fuel temperature, etc.). Training of the neural network is performed by introducing various faults or conditions to be diagnosed into the simulator. The goal of this work is to demonstrate a neural network diagnostic system that could provide advice to the operators in accordance with the emergency operating procedures

  10. Sanford Underground Research Facility - The United State's Deep Underground Research Facility

    Science.gov (United States)

    Vardiman, D.

    2012-12-01

    The 2.5 km deep Sanford Underground Research Facility (SURF) is managed by the South Dakota Science and Technology Authority (SDSTA) at the former Homestake Mine site in Lead, South Dakota. The US Department of Energy currently supports the development of the facility using a phased approach for underground deployment of experiments as they obtain an advanced design stage. The geology of the Sanford Laboratory site has been studied during the 125 years of operations at the Homestake Mine and more recently as part of the preliminary geotechnical site investigations for the NSF's Deep Underground Science and Engineering Laboratory project. The overall geology at DUSEL is a well-defined stratigraphic sequence of schist and phyllites. The three major Proterozoic units encountered in the underground consist of interbedded schist, metasediments, and amphibolite schist which are crosscut by Tertiary rhyolite dikes. Preliminary geotechnical site investigations included drift mapping, borehole drilling, borehole televiewing, in-situ stress analysis, laboratory analysis of core, mapping and laser scanning of new excavations, modeling and analysis of all geotechnical information. The investigation was focused upon the determination if the proposed site rock mass could support the world's largest (66 meter diameter) deep underground excavation. While the DUSEL project has subsequently been significantly modified, these data are still available to provide a baseline of the ground conditions which may be judiciously extrapolated throughout the entire Proterozoic rock assemblage for future excavations. Recommendations for facility instrumentation and monitoring were included in the preliminary design of the DUSEL project design and include; single and multiple point extensometers, tape extensometers and convergence measurements (pins), load cells and pressure cells, smart cables, inclinometers/Tiltmeters, Piezometers, thermistors, seismographs and accelerometers, scanners (laser

  11. Incineration of radioactive waste

    International Nuclear Information System (INIS)

    Eid, C.

    1985-01-01

    The incineration process currently seems the most appropriate way to solve the problems encountered by the increasing quantities of low and medium active waste from nuclear power generation waste. Although a large number of incinerators operate in the industry, there is still scope for the improvement of safety, throughput capacity and reduction of secondary waste. This seminar intends to give opportunity to scientists working on the different aspects of incineration to present their most salient results and to discuss the possibilities of making headway in the management of LL/ML radioactive waste. These proceedings include 17 contributions ranging over the subjects: incineration of solid β-γ wastes; incineration of other radwastes; measurement and control of wastes; off-gas filtration and release. (orig./G.J.P.)

  12. Decommissioning and dismantling of nuclear research facilities in Switzerland: lessons learned

    International Nuclear Information System (INIS)

    Leibundgut, Fritz

    2017-01-01

    Paul Scherrer Institute is the largest research institute for natural and engineering science in Switzerland. It operated various nuclear facilities from 1960 to 2011: Research reactors DIORIT, SAPHIR and PROTEUS, and an incineration plant for low and medium level radioactive waste. Concerning SAPHIR research reactor: in operation from 1958 to 1993, planning of decommissioning from 1998 to 2000. Decommissioning work started in 2004. Finishing is planned for 2019. Concerning DIORIT research reactor: operation as DIORIT I (20 MWth) from 1960 to 1967, then reconstruction to DIORIT II (30 MWth) and operation from 1970 until 1977. Planning of decommissioning from 1992 to 1994. Decommissioning work started in 1994 and was finished in 2012. Concerning PROTEUS research reactor: in operation from 1966 to 2011. Planning of decommissioning from 2013 to 2014. Starting of decommissioning work is planned for 2017, finishing is planned for the end of 2018 Incineration plant: In operation from 1974 to 2002. Planning of decommissioning from 2011 to 2012. Starting of decommissioning work in 2016. Finishing planned for end of 2019. Treatment of various material categories from dismantling: Concerning aluminum: because of the production of H 2 during solidification in concrete, it was necessary to minimize the surface area. When dismantling research reactors, the aluminum removed was melted in an induction furnace and poured into a 4.5 m 3 concrete container to solidify. Cutting the metal and handling it was largely accomplished remote control, using conventional technology. Concerning Steel/Cast-iron: the storage containers to be filled determined the method used for reducing the size of these materials, and the technique used for handling them. The goal was to optimize the packing density to reduce repository costs. The selected method of reducing the size of components is to cut them up using diamond-tipped tools, like saw blades. Concerning Graphite: for graphite, grinding was the

  13. Evaluation of Heavy Metals Contamination at CFAD Dundurn Resulting from Small-Arms Ammunition Incineration

    National Research Council Canada - National Science Library

    Thiboutot, S

    2001-01-01

    .... The safety concerns associated with these pollutants are so serious that the United Kingdom requires stringent environmental licensing of ammunition incineration facilities, and several US states...

  14. Shock Thermodynamic Applied Research Facility (STAR)

    Data.gov (United States)

    Federal Laboratory Consortium — The STAR facility, within Sandia's Solid Dynamic Physics Department, is one of a few institutions in the world with a major shock-physics program. This is the only...

  15. Permitting a hazardous waste incinerator

    International Nuclear Information System (INIS)

    Ambrose, M.L.

    1987-01-01

    In recent years, changes in the laws and regulations have produced an increased emphasis on proper solid waste disposal. Experience with various types of industrial wastes has shown that a large segment of these materials should not go to a landfill. If these wastes are prohibited from landfills, an effective alternative is incineration. The Department of Energy (DOE) has seen the need to build an incinerator at the Oak Ridge Gaseous Diffusion Plant to treat wastes that are generated at the DOE-Oak Ridge Operations facilities, many of which are contaminated with low levels of radioactivity. An extensive effort has been put forth to bring this project to reality. Several permits from the Environmental Protection Agency and the Tennessee Department of Health and Environment are required before the facility can operate. These permits include: (1) Resource Conservation and Recovery Act Part B Permit, (2) Toxic Substances Control Act Permit, (3) National Pollutant Discharge Elimination System Permit, (4) Tennessee State Air Permit, and (5) National Emission Standard for Hazardous Air Pollutants Approval Letter. The permitting process has been very long and involved and has taken nearly three years to complete. Currently, plans are to have the facility fully operational by January 1988

  16. Performance and design requirements for a graphics display research facility

    International Nuclear Information System (INIS)

    Tillitt, D.N.; Petersen, R.J.; Smith, R.L.

    1982-06-01

    Performance and design requirements for a Graphics Display Research Facility (GDRF) are presented. The GDRF is an evolutionary, computer-based, human-engineering experimentation center that is specifically designed to address long-term research issues associated with automation, human performance, and risk in the operation of nuclear facilities. Research capabilities provided by this facility will directly support the licensing and regulation of nuclear facilities within the United States. Research provided by this facility is intended to satisfy the Nuclear Regulatory Commission's (NRC) needs to: (a) confirm design adequacy of, and develop evaluation criteria for, computerized graphic displays and other information presentation mechanisms proposed for use in nuclear power plants, and (b) assess the possible effects on operator performance of computer-based operator-support concepts. The ultimate goal of this research is to support regulatory directives for minimizing the risk of human error in the operation of nuclear facilities

  17. The selection, licensing, and operation of a low-level radioactive waste incinerator

    International Nuclear Information System (INIS)

    Arrowsmith, H.W.; Dalton, D.

    1990-01-01

    The Scientific Ecology Group has just completed the selection, procurement, licensing, and start-up of a low-level radioactive waste incinerator. This incinerator is the only commercial radioactive waste incinerator in the US and was licensed by the Environmental Protection Agency, the State of Tennessee, the City of Oak Ridge, and the Tennessee Valley Authority. This incinerator has a thermal capacity of 13,000,000 BTUs and can burn approximately 1,000 pounds per hour of typical radioactive waste. Waste to be incinerated is sorted in a new waste sorting system at the SEG facility. The sorting is essential to assure that the incinerator will not be damaged by any unexpected waste and to maintain the purity of the incinerator off-gas. The volume reduction expected for typical waste is approximately 100:1. After burning, the incinerator ash is compacted or vitrified before shipment to burial sites

  18. Nuclear waste incineration technology status

    International Nuclear Information System (INIS)

    Ziegler, D.L.; Lehmkuhl, G.D.; Meile, L.J.

    1981-01-01

    The incinerators developed and/or used for radioactive waste combustion are discussed and suggestions are made for uses of incineration in radioactive waste management programs and for incinerators best suited for specific applications. Information on the amounts and types of radioactive wastes are included to indicate the scope of combustible wastes being generated and in existence. An analysis of recently developed radwaste incinerators is given to help those interested in choosing incinerators for specific applications. Operating information on US and foreign incinerators is also included to provide additional background information. Development needs are identified for extending incinerator applications and for establishing commercial acceptance

  19. Study allowing a decision-making from the activity calculation of a iodine 131 source detected in a dump at the incineration facility

    International Nuclear Information System (INIS)

    Houy, J.C.; Laugle, S.

    2000-01-01

    This study is divided in six parts: the first one details the determination of the different threshold in order to make the decision; the second part is the description of the gantry placed at the incineration factory; the third part is devoted to the gantry calibration by detector; the fourth part concerns the theoretical determination of the rates ratio in function of the source position in the truck; the fifth part makes the concordance between the theoretical calculations and the practice measures; the sixth part expresses the source activity and position determination in the truck with the decision-making. To conclude, the alarm threshold adjustment of the Rennes incineration factory is set to twice the background noise without taking into account of the source position in the domestic wastes truck. The alarm setting off can be carried out for a low activity source situated close to the truck wall and conversely, do not detect a MBq source situated in the middle of the truck. This alarm should be set off from a calculation program, taking into account the detectors report, in order to estimate the activity and the position of the source in the truck and to determine the decision making for the management of these wastes. (N.C.)

  20. DOE research and development and field facilities

    Energy Technology Data Exchange (ETDEWEB)

    1979-06-01

    This report describes the roles of DOE's headquarters, field offices, major multiprogram laboratories, Energy Technology and Mining Operations Centers, and other government-owned, contractor-operated facilities which are located in all regions of the United States. It gives brief descriptions of resources, activities, and capabilities of each field facility (sections III through V). These represent a cumulative capital investment of $12 billion and involve a work force of approximately 12,000 government (field) employees and approximately 100,000 contractor employees.

  1. Corium melt researches at VESTA test facility

    Directory of Open Access Journals (Sweden)

    Hwan Yeol Kim

    2017-10-01

    Full Text Available VESTA (Verification of Ex-vessel corium STAbilization and VESTA-S (-small test facilities were constructed at the Korea Atomic Energy Research Institute in 2010 to perform various corium melt experiments. Since then, several tests have been performed for the verification of an ex-vessel core catcher design for the EU-APR1400. Ablation tests of an impinging ZrO2 melt jet on a sacrificial material were performed to investigate the ablation characteristics. ZrO2 melt in an amount of 65–70 kg was discharged onto a sacrificial material through a well-designed nozzle, after which the ablation depths were measured. Interaction tests between the metallic melt and sacrificial material were performed to investigate the interaction kinetics of the sacrificial material. Two types of melt were used: one is a metallic corium melt with Fe 46%, U 31%, Zr 16%, and Cr 7% (maximum possible content of U and Zr for C-40, and the other is a stainless steel (SUS304 melt. Metallic melt in an amount of 1.5–2.0 kg was delivered onto the sacrificial material, and the ablation depths were measured. Penetration tube failure tests were performed for an APR1400 equipped with 61 in-core instrumentation penetration nozzles and extended tubes at the reactor lower vessel. ZrO2 melt was generated in a melting crucible and delivered down into an interaction crucible where the test specimen is installed. To evaluate the tube ejection mechanism, temperature distributions of the reactor bottom head and in-core instrumentation penetration were measured by a series of thermocouples embedded along the specimen. In addition, lower vessel failure tests for the Fukushima Daiichi nuclear power plant are being performed. As a first step, the configuration of the molten core in the plant was investigated by a melting and solidification experiment. Approximately 5 kg of a mixture, whose composition in terms of weight is UO2 60%, Zr 10%, ZrO2 15%, SUS304 14%, and B4C 1%, was melted in a

  2. Commercial incineration demonstration

    International Nuclear Information System (INIS)

    Vavruska, J.S.; Borduin, L.C.

    1982-01-01

    Low-level radioactive wastes (LLW) generated by nuclear utilities presently are shipped to commercial burial grounds for disposal. Increasing transportation and disposal costs have caused industry to consider incineration as a cost-effective means of volume reduction of combustible LLW. Repeated inquiries from the nuclear industry regarding the applicability of the Los Alamos controlled air incineration (CAI) design led the DOE to initiate a commercial demonstration program in FY-1980. Development studies and results in support of this program involving ion exchange resin incineration and fission/activation product distributions within the Los Alamos CAI are described

  3. Radwaste incineration at CRNL

    International Nuclear Information System (INIS)

    Beamer, N.V.

    A Waste Treatment Centre (WTC) is being constructed at CRNL to develop and demonstrate processes to convert reactor wastes to a form suitable for disposal. Combustible wastes can be reduced in volume to a stable ash by incineration. A prototype starved-air incinerator in the WTC is currently being commissioned on inactive waste. Overall performance to date is good. Satisfactory control of main process flows and temperatures has been achieved. Checking of system response to process failures has begun. So far, problems with a similar incinerator during initial operation at Ontario Hydro have not been encountered

  4. Northwestern University Facility for Clean Catalytic Process Research

    Energy Technology Data Exchange (ETDEWEB)

    Marks, Tobin Jay [Northwestern University

    2013-05-08

    Northwestern University with DOE support created a Facility for Clean Catalytic Process Research. This facility is designed to further strengthen our already strong catalysis research capabilities and thus to address these National challenges. Thus, state-of-the art instrumentation and experimentation facility was commissioned to add far greater breadth, depth, and throughput to our ability to invent, test, and understand catalysts and catalytic processes, hence to improve them via knowledge-based design and evaluation approaches.

  5. Research paper 2000-B-6: adjustments in the Dutch domestic waste incineration sector in the context of the European directive 89/429/EEC. A case study on national implementation, environmental effectiveness, allocative efficiency, productive efficiency and administrative costs

    Energy Technology Data Exchange (ETDEWEB)

    Lulofs, K. [Twente Univ., Center for Clean Technology and Environmental Policy, Enschede (Netherlands)

    2000-07-01

    Within the context of the IMPOL project several fields of European environmental policy are studied on aspects as national implementation and environmental and efficiency outcomes. For the IMPOL project a case study was done on the transformation of the Dutch sector of domestic waste incineration in the context of the European Directive Directives 89/369/EEC and 89/429/ EEC. The case study was done and indicators for environmental effectiveness, allocative efficiency, productive efficiency and administrative costs were chosen in line with a document to coordinate the efforts in the four IMPOL countries. The European Directives 89/369/EEC and 89/429/ EEC regulate Plants for Domestic waste Incineration on the emissions of several pollutants. These emissions are relevant for air quality in general, acidification and the spreading of toxic substances. In the empirical part of this report emphasis is laid on 'existing' incineration plants, being permitted before 1990. In chapter 2 of this report the implementation of the directives 89/369/EEC and 89/429/EEC in the Netherlands is described. In section 2.1 already existing 'older' Dutch policy and regulation is presented. In paragraph 2.2 the integration of the European Directives into Dutch national law is described. In chapter 2.3 the efforts and outcomes on monitoring and enforcement are presented. Chapter 3 goes into the environmental effectiveness. Section 3.1 describes the abatement performance of the whole municipal waste incineration sector during the period of research. Section 3.2 goes into factors that explain the environmental outcomes. Within the IMPOL research-team the decision was taken to concentrate on a number of pollutants of existing waste incinerators. In section 3.3 the data for the existing incinerators are given. In chapter 4 the allocative efficiency of adjustments is elaborated. In section 4.1 the abatement patterns of existing municipal waste incineration plants are presented

  6. Coordinated research project (CRP) on studies of advanced reactor technology options for effective incineration of radioactive waste - Scope and objectives

    International Nuclear Information System (INIS)

    Stanculescu, A.

    2002-01-01

    The overall objective of the CRP is to perform R and D tasks contributing towards the proof of practicality for long-lived waste transmutation. For a sound assessment of the transient and accident behaviour, the neutron kinetics and dynamics have to be qualified, especially as the margins for the safety relevant neutronics parameters are becoming small in a 'dedicated' transmuter. The CRP will integrate benchmarking of transient/accident simulation codes focussing on the phenomena and effects relevant to various critical and sub-critical systems under severe neutron flux changes and rearrangements. The CRP will investigate future needs both for theoretical means (data, codes) and experimental information related to the various transmutation systems. The final goals of the CRP are to (a) deepen the understanding of the dynamics of transmutation systems, e.g., the accelerator driven system, especially systems with deteriorated safety parameters, (b) qualify the available methods and specify their range of validity, and (c) formulate requirements for future theoretical developments. Should transient experiments be available, the CRP might also pursue experimental benchmarking work. In any case, based on the results, the CRP will conclude on the potential need of transient experiments and make appropriate proposals for experimental programs. The CRP will consider various transmuter and actinides incinerator concepts, from traditional to very advanced, both critical and sub-critical. No optimization will be performed, experience and good engineering judgment is used to define the design parameters of the various concepts. The generic dynamic behavior of the different systems will be assessed and inter-comparisons will be performed. The concepts are derived from those proposed by the participants in this RCM. Later additions might be considered. The studies will include static, kinetics and dynamics calculations. Influence of burnup on transient behavior will be

  7. The Studsvik incinerator

    International Nuclear Information System (INIS)

    Hetzler, F.

    1988-01-01

    The Studsvik Incinerator is a Faurholdt designed, multi-stage, partial pyrolysis, controlled-air system taken into operation in 1976. The incinerator was initially operated without flue-gas filtration from 1976 until 1979 and thereafter with a bag-house filter. The Studsvik site has been host to radioactive activities for approximately 30 years. The last 10 years have included on site incineration of more than 3,000 tons of LLW. During this time routine sampling for activity has been performed, of releases and in the environment, to carefully monitor the area. The author discusses records examined to determine levels of activity prior to incinerator start-up, without and with filter

  8. Decontamination Technology Development for Nuclear Research Facilities

    International Nuclear Information System (INIS)

    Oh, Won Zin; Jung, Chong Hun; Choi, Wang Kyu; Won, Hui Jun; Kim, Gye Nam

    2004-02-01

    Technology development of surface decontamination in the uranium conversion facility before decommissioning, technology development of component decontamination in the uranium conversion facility after decommissioning, uranium sludge treatment technology development, radioactive waste soil decontamination technology development at the aim of the temporary storage soil of KAERI, Optimum fixation methodology derivation on the soil and uranium waste, and safety assessment methodology development of self disposal of the soil and uranium waste after decontamination have been performed in this study. The unique decontamination technology applicable to the component of the nuclear facility at room temperature was developed. Low concentration chemical decontamination technology which is very powerful so as to decrease the radioactivity of specimen surface under the self disposal level was developed. The component decontamination technology applicable to the nuclear facility after decommissioning by neutral salt electro-polishing was also developed. The volume of the sludge waste could be decreased over 80% by the sludge waste separation method by water. The electrosorption method on selective removal of U(VI) to 1 ppm of unrestricted release level using the uranium-containing lagoon sludge waste was tested and identified. Soil decontamination process and equipment which can reduce the soil volume over 90% were developed. A pilot size of soil decontamination equipment which will be used to development of real scale soil decontamination equipment was designed, fabricated and demonstrated. Optimized fixation methodology on soil and uranium sludge was derived from tests and evaluation of the results. Safety scenario and safety evaluation model were development on soil and uranium sludge aiming at self disposal after decontamination

  9. CRNL active waste incinerator

    International Nuclear Information System (INIS)

    McQuade, D.W.

    1965-02-01

    At CRNL the daily collection of 1200 pounds of active combustible waste is burned in a refractory lined multi-chamber incinerator. Capacity is 500-550 pounds per hour; volume reduction 96%. Combustion gases are cooled by air dilution and decontaminated by filtration through glass bags in a baghouse dust collector. This report includes a description of the incinerator plant, its operation, construction and operating costs, and recommendations for future designs. (author)

  10. Experimental geothermal research facilities study (Phase 0). Volume 1

    Energy Technology Data Exchange (ETDEWEB)

    1974-01-01

    The study comprises Phase 0 of a project for Experimental Geothermal Research Facilities. The study focuses on identification of a representative liquid-dominated geothermal reservoir of moderate temperature and salinity, preliminary engineering design of an appropriate energy conversion system, identification of critical technology, and planning for implementation of experimental facilities. The objectives included development of liaison with the industrial sector, to ensure responsiveness to their views in facility requirements and planning, and incorporation of environmental and socioeconomic factors. This Phase 0 report covers problem definition and systems requirements. Facilities will incorporate capability for research in component, system, and materials technology and a nominal 10 MWe experimental, binary cycle, power generating plant.

  11. An Advanced Free Flight Research Facility

    National Research Council Canada - National Science Library

    Sforza, P

    2003-01-01

    ...). The objective of this research grant was to provide new insights into fluid dynamic research and design since this technology has the ability to characterize the spatial and temporal density profiles...

  12. National facility for neutron beam research

    Indian Academy of Sciences (India)

    In this talk, the growth of neutron beam research (NBR) in India over the past five decades is traced beginning with research at Apsara. A range of problems in condensed matter physics could be studied at CIRUS, followed by sophisticated indegenous instrumentation and research at Dhruva. The talk ends with an overview ...

  13. Incineration of wastes from nuclear installations with the Juelich incineration process

    International Nuclear Information System (INIS)

    Wilke, M.

    1979-01-01

    In the Juelich Research Center a two-stage incineration process has been developed which, due to an integral thermal treatment stage, is most suitable for the incineration of heterogeneous waste material. The major advantages of this technique are to be seen in the fact that mechanical treatment of the waste material is no longer required and that off gas treatment is considerably facilitated. (orig.) [de

  14. Nuclear incineration method for long life radioactive wastes

    International Nuclear Information System (INIS)

    Matsumoto, Takaaki; Uematsu, Kunihiko.

    1987-01-01

    Nuclear incineration method is the method of converting the long life radioactive nuclides in wastes to short life or stable nuclides by utilizing the nuclear reaction caused by radiation, unlike usual chemical incineration. By the nuclear incineration, the radioactivity of wastes increases in a short period, but the problems at the time of the disposal are reduced because of the decrease of long life radioactive nuclides. As the radiation used for the nuclear incineration, the neutron beam from fission and fusion reactors and accelerators, the proton beam and gamma ray from accelerators have been studied. The object of the nuclear incineration is actinide, Sr-90, Cs-137, I-129 and Tc-99. In particular, waste actinide emits alpha ray, and is strongly toxic, accordingly, the motive of attempting the nuclear incineration is strong. In Japan, about 24t of waste actinide will accumulate by 2000. The principle of the nuclear incineration, and the nuclear incineration using nuclear fission and fusion reactors and accelerators are described. The nuclear incineration using fission reactors was examined for the first time in 1972 in USA. It is most promising because it is feasible by the present technology without particular research and development. (Kako, I.)

  15. A study of the operation of selected national research facilities

    Science.gov (United States)

    Eisner, M.

    1974-01-01

    The operation of national research facilities was studied. Conclusions of the study show that a strong resident scientific staff is required for successful facility operation. No unique scheme of scientific management is revealed except for the obvious fact that the management must be responsive to the users needs and requirements. Users groups provide a convenient channel through which these needs and requirements are communicated.

  16. Profiles of facilities used for HTR research and testing

    International Nuclear Information System (INIS)

    1980-05-01

    This report contains a current description of facilities supporting HTR research and development submitted by countries participating in the IWGFR. It has the purpose of providing an overview of the facilities available for use and of the types of experiments that can be conducted therein

  17. Radiation applications research and facilities in AECL Research Company

    International Nuclear Information System (INIS)

    Iverson, S.L.

    1988-01-01

    In the 60's and 70's Atomic Energy of Canada had a very active R and D program to discover and develop applications of ionizing radiation. Widespread interest in the use of radiation for food processing and the possibility of developing reliable and competitive machine sources of radiation hold out the promise of a major increase in industrial use of radiation. In March 1985 a new branch, Radiation Applications Research, began operations with the objective of working closely with industry to develop and assist the introduction of new uses of ionizing radiation. The Branch is equipped with appropriate analytical equipment including HPLC (high performance liquid chromatograph) and GC/MS (gas chromatograph/mass spectrometer) as well as a Gammacell 220 and an I-10/1, one kilowatt 10 MeV electron accelerator. The accelerator is located in a specially designed facility equipped for experimental irradiation of the test quantities of packaged products as well as solids, liquids and gases in various configurations. A conveyor system moves the packaged products from the receiving area, through a maze, past the electron beam at a controlled rate and finally to the shipping area. Other necessary capabilities, such as gamma and electron dosimetry and a microbiology laboratory, have also been developed. Initial projects in areas ranging from food through environmental and industrial applications have been assessed and the most promising have been selected for further work. As an example, the use of charcoal absorbent beds to concentrate the components of gas or liquid waste streams requiring treatment is showing promise as a method of significantly reducing the cost of radiation treatment for some effluents. A number of other projects are described. (author)

  18. Organizational culture, safety culture, and safety performance at research facilities

    Energy Technology Data Exchange (ETDEWEB)

    Brown, William S.

    2000-07-30

    Organizational culture surveys of research facilities conducted several years ago and archival occupational injury reports were used to determine whether differences in safety performance are related to general organizational factors or to ''safety culture'' as reflected in specific safety-related dimensions. From among the organizations surveyed, a pair of facilities was chosen that were similar in size and scientific mission while differing on indices of work-related injuries. There were reliable differences in organizational style between the facilities, especially among workers in environment, safety, and health functions; differences between the facilities (and among job categories) on the safety scale were more modest and less regular.

  19. National facility for neutron beam research

    Indian Academy of Sciences (India)

    ... past five decades is traced beginning with research at Apsara. A range of problems in condensed matter physics could be studied at CIRUS, followed by sophisticated indegenous instrumentation and research at Dhruva. The talk ends with an overview of current scenario of NBR world-wide and future of Indian activities.

  20. Assessing potential health effects from municipal sludge incinerators: screening methodology

    Energy Technology Data Exchange (ETDEWEB)

    Fradkin, L.; Bruins, J.F.; Lutkenhoff, S.D.; Stara, J.F.; Lomnitz, E.; Rubin, A.

    1987-04-01

    This paper describes a risk assessment methodology for preliminary assessment of municipal sludge incineration. The methodology is a valuable tool in that it can be used for determining the hazard indices of chemical contaminants that might be present in sewage sludge used in incineration. The paper examines source characteristics (i.e., facility design), atmospheric dispersion of emission, and resulting human exposure and risk from sludge incinerators. Seven of the ten organics were screened for further investigation. An example of the calculations are presented for cadmium.

  1. Operation of chemical incinerator for disposal of legacy chemicals

    International Nuclear Information System (INIS)

    Singhal, R.K.; Basu, H.; Saha, S.; Pimple, M.V.; Naik, P.D.

    2017-01-01

    For safe disposal of age-old legacy and unused chemicals in BARC, Trombay, oil-fired chemical incinerator with a capacity of 20 kg h -1 for solid and liquid chemical is installed adjacent to trash incinerator near RSMS, Gamma Field. The Incinerator was supplied by M/s B. L. Engineering Works, Ahmedabad. Commission of the same at Trombay site was carried out, under the supervision of Civil Engineering (CED), Technical Services Division (TSD) and Analytical Chemistry Division (custodian of the facility)

  2. Environment for Auditory Research Facility (EAR)

    Data.gov (United States)

    Federal Laboratory Consortium — EAR is an auditory perception and communication research center enabling state-of-the-art simulation of various indoor and outdoor acoustic environments. The heart...

  3. Small Multi-Purpose Research Facility (SMiRF)

    Data.gov (United States)

    Federal Laboratory Consortium — The Small Multi-Purpose Research Facility (SMiRF) evaluates the performance of the thermal protection systems required to provide long-term storage (up to 10 years)...

  4. Research Support Facility - Zero Energy Building Moves Closer to Reality

    Energy Technology Data Exchange (ETDEWEB)

    None

    2010-04-01

    The DOE's Research Support Facility showcases high-performance design features, passive energy strategies, and renewable energy. It is a prototype for future large-scale net-zero energy buildings.

  5. Direct Connect Supersonic Combustion Facility (Research Cell 22)

    Data.gov (United States)

    Federal Laboratory Consortium — Description: RC22 is a continuous-flow, direct-connect supersonic-combustion research facility that is capable of simulating flight conditions from Mach 3.0 to Mach...

  6. A Survey of Research Performed at NASA Langley Research Center's Impact Dynamics Research Facility

    Science.gov (United States)

    Jackson, K. E.; Fasanella, E. L.

    2003-01-01

    The Impact Dynamics Research Facility (IDRF) is a 240-ft-high gantry structure located at NASA Langley Research Center in Hampton, Virginia. The facility was originally built in 1963 as a lunar landing simulator, allowing the Apollo astronauts to practice lunar landings under realistic conditions. The IDRF was designated a National Historic Landmark in 1985 based on its significant contributions to the Apollo Program. In 1972, the facility was converted to a full-scale crash test facility for light aircraft and rotorcraft. Since that time, the IDRF has been used to perform a wide variety of impact tests on full-scale aircraft and structural components in support of the General Aviation (GA) aircraft industry, the US Department of Defense, the rotorcraft industry, and NASA in-house aeronautics and space research programs. The objective of this paper is to describe most of the major full-scale crash test programs that were performed at this unique, world-class facility since 1974. The past research is divided into six sub-topics: the civil GA aircraft test program, transport aircraft test program, military test programs, space test programs, basic research, and crash modeling and simulation.

  7. A facility for using cluster research to study environmental problems

    International Nuclear Information System (INIS)

    1991-11-01

    This report begins by describing the general application of cluster based research to environmental chemistry and the development of a Cluster Structure and Dynamics Research Facility (CSDRF). Next, four important areas of cluster research are described in more detail, including how they can impact environmental problems. These are: surface-supported clusters, water and contaminant interactions, time-resolved dynamic studies in clusters, and cluster structures and reactions. These facilities and equipment required for each area of research are then presented. The appendices contain workshop agenda and a listing of the researchers who participated in the workshop discussions that led to this report

  8. Leak testing requirements at a research facility

    International Nuclear Information System (INIS)

    Conner, J.B.

    1979-01-01

    Since September, 1952, Lawrence Livermore Laboratory has conducted pioneering research in applied science. A vital part of this activity has been the development of a variety of high vacuum and ultrahigh vacuum systems. Leaks occur in everything, including vacuum systems. The mass spectrometer leak detection equipment is described

  9. ARM Climate Research Facility Annual Report 2004

    Energy Technology Data Exchange (ETDEWEB)

    Voyles, J.

    2004-12-31

    Like a rock that slowly wears away beneath the pressure of a waterfall, planet earth?s climate is almost imperceptibly changing. Glaciers are getting smaller, droughts are lasting longer, and extreme weather events like fires, floods, and tornadoes are occurring with greater frequency. Why? Part of the answer is clouds and the amount of solar radiation they reflect or absorb. These two factors clouds and radiative transfer represent the greatest source of error and uncertainty in the current generation of general circulation models used for climate research and simulation. The U.S. Global Change Research Act of 1990 established an interagency program within the Executive Office of the President to coordinate U.S. agency-sponsored scientific research designed to monitor, understand, and predict changes in the global environment. To address the need for new research on clouds and radiation, the U.S. Department of Energy (DOE) established the Atmospheric Radiation Measurement (ARM) Program. As part of the DOE?s overall Climate Change Science Program, a primary objective of the ARM Program is improved scientific understanding of the fundamental physics related to interactions between clouds and radiative feedback processes in the atmosphere.

  10. Nuclear Safety Research and Facilities Department annual report 1999

    DEFF Research Database (Denmark)

    Majborn, B.; Damkjær, A.; Jensen, Per Hedemann

    2000-01-01

    The report presents a summary of the work of the Nuclear Safety Research and Facilities Department in 1999. The department´s research and development activities were organized in two research programmes: "Radiation Protection and Reactor Safety" and"Radioecology and Tracer Studies". The nuclear...... facilities operated by the department include the research reactor DR 3, the Isotope Laboratory, the Waste Management Plant, and the educational reactor DR 1. Lists of staff and publications are includedtogether with a summary of the staff´s participation in national and international committees....

  11. Nuclear Safety Research and Facilities Department annual report 1998

    International Nuclear Information System (INIS)

    Majborn, B.; Brodersen, K.; Damkjaer, A.; Hedemann Jensen, P.; Nielsen, S.P.; Nonboel, E.

    1999-04-01

    The report present a summary of the work of the Nuclear Safety Research and Facilities Department in 1998. The department's research and development activities were organized in two research programmes: 'Radiation Protection and Reactor Safety' and 'Radioecology and Tracer Studies'. The nuclear facilities operated by the department include the research reactor DR3, the Isotope Laboratory, the Waste Treatment plant, and the educational reactor DR1. Lsits of staff and publications are included together with a summary of the staff's participation in national and international committees. (au)

  12. Nuclear Safety Research and Facilities Department annual report 1998

    Energy Technology Data Exchange (ETDEWEB)

    Majborn, B.; Brodersen, K.; Damkjaer, A.; Hedemann Jensen, P.; Nielsen, S.P.; Nonboel, E

    1999-04-01

    The report present a summary of the work of the Nuclear Safety Research and Facilities Department in 1998. The department`s research and development activities were organized in two research programmes: `Radiation Protection and Reactor Safety` and `Radioecology and Tracer Studies`. The nuclear facilities operated by the department include the research reactor DR3, the Isotope Laboratory, the Waste Treatment plant, and the educational reactor DR1. Lsits of staff and publications are included together with a summary of the staff`s participation in national and international committees. (au)

  13. Nuclear Safety Research and Facilities Department annual report 1997

    International Nuclear Information System (INIS)

    Majborn, B.; Aarkrog, A.; Brodersen, K.

    1998-04-01

    The report presents a summary of the work of the Nuclear Safety Research and Facilities Department in 1997. The department's research and development activities were organized in four research programmes: Reactor Safety, Radiation protection, Radioecology, and Radioanalytical Chemistry. The nuclear facilities operated by the department include the research reactor DR3, the Isotope Laboratory, the Waste Treatment Plant, and the educational reactor DR1. Lists of staff and publications are included together with a summary of the staff's participation in national and international committees. (au)

  14. Neutron Imaging Facility Development and Research Trend at NIST

    Science.gov (United States)

    Arif, M.; Hussey, D. S.; Baltic, E. M.; Jacobson, D. L.

    The National Institute of Standards and Technology (NIST)maintains a sustained focus in the development of advanced neutron imaging facilities and hardware components to enable breakthrough research with vastly improved spatial and temporal resolutions, and to identify and employ research practices important to a wide variety of industrial and scientific applications. NIST's main focus is to enable research with broad appeal and commercial impacts. In this article we will give a brief overview of the NIST facility, select examples of current research, and finally comment on emerging technologies including advance manufacturing where neutron imaging has the potential to play an important role.

  15. Nuclear Safety Research and Facilities department annual report 1996

    International Nuclear Information System (INIS)

    Majborn, B.; Brodersen, K.; Damkjaer, A.; Floto, H.; Heydorn, K.; Oelgaard, P.L.

    1997-04-01

    The report presents a summary of the work of the Nuclear Safety Research and Facilities Department in 1996. The Department's research and development activities are organized in three research programmes: Radiation Protection, Reactor Safety, and Radioanalytical Chemistry. The nuclear facilities operated by the department include the Research Reactor DR3, the Isotope Laboratory, the Waste Treatment Plant, and the Educational Reactor DR1. Lists of staff and publications are included together with a summary of the staff's participation in national and international committees. (au) 2 tabs., 28 ills

  16. Nuclear Safety Research and Facilities Department annual report 1997

    Energy Technology Data Exchange (ETDEWEB)

    Majborn, B.; Aarkrog, A.; Brodersen, K. [and others

    1998-04-01

    The report presents a summary of the work of the Nuclear Safety Research and Facilities Department in 1997. The department`s research and development activities were organized in four research programmes: Reactor Safety, Radiation protection, Radioecology, and Radioanalytical Chemistry. The nuclear facilities operated by the department include the research reactor DR3, the Isotope Laboratory, the Waste Treatment Plant, and the educational reactor DR1. Lists of staff and publications are included together with a summary of the staff`s participation in national and international committees. (au) 11 tabs., 39 ills.; 74 refs.

  17. Nuclear Safety Research and Facilities Department. Annual report 1999

    International Nuclear Information System (INIS)

    Majborn, B.; Damkjaer, A.; Hedemann Jensen, P.; Nielsen, S.P.; Nonboel, E.

    2000-04-01

    The report presents a summary of the work of the Nuclear Safety Research and Facilities Department in 1999. The department's research and development activities were organized in two research programmes: 'Radiation Protection and Reactor Safety' and 'Radioecology and Tracer Studies'. The nuclear facilities operated by the department include the research reactor DR 3, the Isotope Laboratory, the Waste Management Plant, and the educational reactor DR 1. Lists of staff and publications are included together with a summary of the staff's participation in national and international committees. (au)

  18. Nuclear Safety Research and Facilities Department. Annual report 1999

    Energy Technology Data Exchange (ETDEWEB)

    Majborn, B.; Damkjaer, A.; Hedemann Jensen, P.; Nielsen, S.P.; Nonboel, E. [eds.

    2000-04-01

    The report presents a summary of the work of the Nuclear Safety Research and Facilities Department in 1999. The department's research and development activities were organized in two research programmes: 'Radiation Protection and Reactor Safety' and 'Radioecology and Tracer Studies'. The nuclear facilities operated by the department include the research reactor DR 3, the Isotope Laboratory, the Waste Management Plant, and the educational reactor DR 1. Lists of staff and publications are included together with a summary of the staff's participation in national and international committees. (au)

  19. Conceptual design report for alpha waste incinerator

    International Nuclear Information System (INIS)

    1979-04-01

    The Alpha Waste Incinerator, a new facility in the SRP H-Area, will process transuranic or alpha-contaminated combustible solid wastes. It will seal the radioactive ash and scrubbing salt residues in cans for interim storage in drums on site burial ground pads. This report includes objectives, project estimate, schedule, standards and criteria, excluded costs, safety evaluation, energy consumption, environmental assessment, and key drawings

  20. Electrically fired incineration of combustible radioactive waste

    International Nuclear Information System (INIS)

    Charlesworth, D.; Hill, M.

    1985-01-01

    Du Pont Company and Shirco, Inc. are developing a process to incinerate plutonium-contaminated combustible waste in an electrically fired incineration system. Preliminary development was completed at Shirco, Inc. prior to installing an incineration system at the Savannah River Laboratory (SRL), which is operated by Du Pont for the US Department of Energy (DOE). The waste consists of disposable protective clothing, cleaning materials, used filter elements, and miscellaneous materials exposed to plutonium contamination. Incinerator performance testing, using physically representative nonradioactive materials, was completed in March 1983 at Shirco's Pilot Test Facility in Dallas, TX. Based on the test results, equipment sizing and mechanical begin of a full-scale process were completed by June 1983. The full-scale unit is being installed at SRL to confirm the initial performance testing and is scheduled to begin in June 1985. Remote operation and maintenance of the system is required, since the system will eventually be installed in an isolated process cell. Initial operation of the process will use nonradioactive simulated waste. 2 figs., 2 tabs

  1. Pretreatment and utilization of waste incineration bottom ashes

    DEFF Research Database (Denmark)

    Astrup, Thomas

    2007-01-01

    Within recent years, researchers and authorities have had increasing focus on leaching properties from waste incineration bottom ashes. Researchers have investigated processes such as those related to carbonation, weathering, metal complexation, and leaching control. Most of these investigations...

  2. Effects on ambient air caused by emissions from the Clean Harbors incinerator and underground water treatment facility in Mercier : evaluation by atmospheric dispersion modeling; Effets sur l'air ambiant des emissions de l'incinerateur Clean Harbors et de l'Unite de traitement des eaux souterraines (UTES) a Mercier : evaluation par modelisation de la dispersion atmospherique

    Energy Technology Data Exchange (ETDEWEB)

    Boulet, G.; Walsh, P.; Brault, M.P.; Couture, Y.; Briere, J.F. [Quebec Ministere du Developpement durable, de l' Environnement et des Parcs, Quebec, PQ (Canada). Direction du suivi de l' etat de l' environnement; Guay, F.; Longpre, L. [Quebec Ministere du Developpement durable, de l' Environnement et des Parcs, Quebec, PQ (Canada). Direction regionale de l' analyse et de l' expertise de l' Estrie de la Monteregie; Lemire, R.; Busque, D. [Quebec Ministere du Developpement durable, de l' Environnement et des Parcs, Quebec, PQ (Canada). Service de l' information sur le milieu atmospherique

    2010-09-15

    Clean Harbors is a leading provider of high-tech, high-temperature destruction of hazardous and industrial waste. The Quebec Ministry of Sustainable Development, Environment and Parks created an atmospheric dispersion model to determine the impact of the Clean Harbors incinerator and underground water treatment facility on air quality in Mercier, Quebec. This document described the dispersion model and its inputs, including emissions of polychlorinated dibenzodioxin, dibenzofurans, polychlorinated biphenyls, polycyclic aromatic hydrocarbons, fine particulates, mercury, lead and arsenic. The effects of these emissions on air quality were evaluated by considering meteorological data, source characteristics, topography and land use zoning. The modeling study showed that emissions from the incinerator were well below criteria levels and do not cause significant deterioration in air quality. However, higher than allowable limits of polyvinyl chloride and benzene emissions were found 700 m from the underground water treatment facility. Nearby residential areas were not affected. 21 refs., 9 tabs., 10 figs., 1 appendix.

  3. Decommissioning Technology Development for Nuclear Research Facilities

    International Nuclear Information System (INIS)

    Lee, K. W.; Kang, Y. A.; Kim, G. H.

    2007-06-01

    It is predicted that the decommissioning of a nuclear power plant would happen in Korea since 2020 but the need of partial decommissioning and decontamination for periodic inspection and life extension still has been on an increasing trend and its domestic market has gradually been extended. Therefore, in this project we developed following several essential technologies as a decommissioning R and D. The measurement technology for in-pipe radioactive contamination was developed for measuring alpha/beta/gamma emitting nuclides simultaneously inside a in-pipe and it was tested into the liquid waste transfer pipe in KRR-2. And the digital mock-up system for KRR-1 and 2 was developed for choosing the best scenarios among several scenarios on the basis of various decommissioning information(schedule, waste volume, cost, etc.) that are from the DMU and the methodology of decommissioning cost estimation was also developed for estimating a research reactor's decommissioning cost and the DMU and the decommissioning cost estimation system were incorporated into the decommissioning information integrated management system. Finally the treatment and management technology of the irradiated graphites that happened after decommissioning KRR-2 was developed in order to treat and manage the irradiated graphites safely

  4. Radiation monitoring in high energy research facility

    International Nuclear Information System (INIS)

    Miyajima, Mitsuhiro

    1975-01-01

    In High Energy Physics Research Laboratory, construction of high energy proton accelerator is in progress. The accelerator is a cascaded machine comprising Cockcroft type (50 keV), linac (20 MeV), booster synchrotron (500 MeV), and synchrotron (8-12 GeV). Its proton beam intensity is 1x10 13 photons/pulse, and acceleration is carried out at the rate of every 2 minutes. The essential problems of radiation control in high energy accelerators are those of various radiations generated secondarily by proton beam and a number of induced radiations simultaneously originated with such secondary particles. In the Laboratory, controlled areas are divided into color-coded four regions, red, orange, yellow and green, based on each dose-rate. BF 3 counters covered with thick paraffin are used as neutron detectors, and side-window GM tubes, NaI (Tl) scintillators and ionization chambers as γ-detectors. In red region, however, ionization chambers are applied to induced radiation detection, and neutrons are not monitored. NIM standards are adopted for the circuits of all above monitors considering easy maintenance, economy and interchangeability. Notwithstanding the above described systems, these monitors are not sufficient to complete the measurement of whole radiations over wide energy region radiated from the accelerators. Hence separate radiation field measurement is required periodically. An example of the monitoring systems in National Accelerator Laboratory (U.S.) is referred at the last section. (Wakatsuki, Y.)

  5. Decommissioning Technology Development for Nuclear Research Facilities

    Energy Technology Data Exchange (ETDEWEB)

    Lee, K. W.; Kang, Y. A.; Kim, G. H. (and others)

    2007-06-15

    It is predicted that the decommissioning of a nuclear power plant would happen in Korea since 2020 but the need of partial decommissioning and decontamination for periodic inspection and life extension still has been on an increasing trend and its domestic market has gradually been extended. Therefore, in this project we developed following several essential technologies as a decommissioning R and D. The measurement technology for in-pipe radioactive contamination was developed for measuring alpha/beta/gamma emitting nuclides simultaneously inside a in-pipe and it was tested into the liquid waste transfer pipe in KRR-2. And the digital mock-up system for KRR-1 and 2 was developed for choosing the best scenarios among several scenarios on the basis of various decommissioning information(schedule, waste volume, cost, etc.) that are from the DMU and the methodology of decommissioning cost estimation was also developed for estimating a research reactor's decommissioning cost and the DMU and the decommissioning cost estimation system were incorporated into the decommissioning information integrated management system. Finally the treatment and management technology of the irradiated graphites that happened after decommissioning KRR-2 was developed in order to treat and manage the irradiated graphites safely.

  6. Volume Reduction of Decommissioning Burnable Waste with Oxygen Enrich Incinerator

    Energy Technology Data Exchange (ETDEWEB)

    Min, B. Y.; Yang, D. S.; Lee, K. W.; Choi, J. W. [KAERI, Daejeon (Korea, Republic of)

    2016-05-15

    The incineration technology is an effective treatment method that contains hazardous chemicals as well as radioactive contamination. The volume reduction of the combustible wastes through the incineration technologies has merits from the view point of a decrease in the amount of waste to be disposed of resulting in a reduction of the disposal cost. Incineration is generally accepted as a method of reducing the volume of radioactive waste. The incineration technology is an effective treatment method that contains hazardous chemicals as well as radioactive contamination. This paper covers the general facility operation of an oxygen-enriched incinerator for the treatment of decommissioning wastes generated from a decommissioning project. The combustible wastes have been treated by the utilization of incinerator the capacity of the average 20 kg/hr. The decommissioning combustible waste of about 31 tons has been treated using Oxygen Enriched incinerator by at the end of 2016. The off-gas flow and temperature were maintained constant or within the desired range. The measured gases and particulate materials in the stack were considerably below the regulatory limits.

  7. Volume Reduction of Decommissioning Burnable Waste with Oxygen Enrich Incinerator

    International Nuclear Information System (INIS)

    Min, B. Y.; Yang, D. S.; Lee, K. W.; Choi, J. W.

    2016-01-01

    The incineration technology is an effective treatment method that contains hazardous chemicals as well as radioactive contamination. The volume reduction of the combustible wastes through the incineration technologies has merits from the view point of a decrease in the amount of waste to be disposed of resulting in a reduction of the disposal cost. Incineration is generally accepted as a method of reducing the volume of radioactive waste. The incineration technology is an effective treatment method that contains hazardous chemicals as well as radioactive contamination. This paper covers the general facility operation of an oxygen-enriched incinerator for the treatment of decommissioning wastes generated from a decommissioning project. The combustible wastes have been treated by the utilization of incinerator the capacity of the average 20 kg/hr. The decommissioning combustible waste of about 31 tons has been treated using Oxygen Enriched incinerator by at the end of 2016. The off-gas flow and temperature were maintained constant or within the desired range. The measured gases and particulate materials in the stack were considerably below the regulatory limits.

  8. Irradiation Facilities of the Takasaki Advanced Radiation Research Institute

    Directory of Open Access Journals (Sweden)

    Satoshi Kurashima

    2017-03-01

    Full Text Available The ion beam facility at the Takasaki Advanced Radiation Research Institute, the National Institutes for Quantum and Radiological Science and Technology, consists of a cyclotron and three electrostatic accelerators, and they are dedicated to studies of materials science and bio-technology. The paper reviews this unique accelerator complex in detail from the viewpoint of its configuration, accelerator specification, typical accelerator, or irradiation technologies and ion beam applications. The institute has also irradiation facilities for electron beams and 60Co gamma-rays and has been leading research and development of radiation chemistry for industrial applications in Japan with the facilities since its establishment. The configuration and utilization of those facilities are outlined as well.

  9. Radwaste requirements at a biomedical research facility

    International Nuclear Information System (INIS)

    Brannegan, D.P.; Wolter, W.; Merenda, J.M.; Figdor, S.K.

    1993-01-01

    The low-level radioactive waste (LLRW) federal legislation that was passed during the 1980s was intended to provide an orderly system of LLRW disposal as the country's three waste sites proceeded toward excluding out-of-state generators. The system was based on a regional interstate compact system. As originally envisioned, several contiguous states were to form an association (compact) with one state receiving radwaste from the compact. Everyone is aware of the difficulties that followed as attempts were made to implement these laws and to meet the prescribed milestones to avoid financial penalties. Although the states (compacts) have labored for over 12 yr along this rocky road, no compact has developed and licensed a new disposal site prior to the January 1, 1993 deadline. A recent report by the Center for the Study of American Business at Washington University in St. Louis states that open-quotes The current regional interstate compact system for disposal of low-level radioactive waste is fatally flawed on both technical and practical political grounds.close quotes Thus, the system has broken down and the three original LLRW sites closed their gates (with the possible exception of Barnwell) as planned on January 1, 1993. It would appear that the fate of LLRW will be the same as that of high-level waste (HLW); it will be stored at the site of the generator until a solution to the problem is found. For the nonutility generator, storage is an entirely new problem. It must be appreciated that almost all nonutility generators are in the business of research or medical treatment and not in the business of storing LLRW. Thus, storage represents a new turn of events and a new aspect of doing business. It also means the diversion of limited resources to a problem that should not exist. Lastly, on-site LLRW storage for the nonutility generator will also require additional regulatory approval for the handling, storage, and ongoing monitoring of this waste

  10. Fluidized bed incinerator development

    International Nuclear Information System (INIS)

    Ziegler, D.L.; Johnson, A.J.

    1976-01-01

    A fluidized bed incinerator is being developed for burning rad contaminated solid and liquid waste materials. In situ neutralization of acid gases by the bed material, catalytic afterburning, and gas filtration are used to produce a clean flue gas without the use of aqueous scrubbing

  11. PERMITTING HAZARDOUS WASTE INCINERATORS

    Science.gov (United States)

    This publication is a compilation of information presented at a seminar series designed to address the issues that affect the issuance of hazardous waste incineration permits and to improve the overall understanding of trial burn testing. pecifically, the document provides guidan...

  12. Space syntax in healthcare facilities research: a review.

    Science.gov (United States)

    Haq, Saif; Luo, Yang

    2012-01-01

    Space Syntax is a theory and method that has been developing for the last 40 years. Originally conceived as a theory of "society and space," it has expanded to other areas. An important aspect of this is technical; it allows the quantification of layouts, and unit spaces within a layout, so that the environment itself can produce independent variables in quantitative research. Increasingly, it is being used to study healthcare facilities. Space Syntax has thereby become relevant to healthcare facilities researchers and designers. This paper attempts to explain Space Syntax to a new audience of healthcare designers, administrators, and researchers; it provides a literature review on the use of Space Syntax in healthcare facility research and suggests some possibilities for future application.

  13. Simulation at Dryden Flight Research Facility from 1957 to 1982

    Science.gov (United States)

    Smith, John P.; Schilling, Lawrence J.; Wagner, Charles A.

    1989-01-01

    The Dryden Flight Research Facility has been a leader in developing simulation as an integral part of flight test research. The history of that effort is reviewed, starting in 1957 and continuing to the present time. The contributions of the major program activities conducted at Dryden during this 25-year period to the development of a simulation philosophy and capability is explained.

  14. Facilities for Research and Development of Medical Radioisotopes

    Energy Technology Data Exchange (ETDEWEB)

    Shin, Byung Chul; Choung, Won Myung; Park, Jin Ho

    2003-03-15

    This study is carried out by KAERI(Korea Atomic Energy Research Institute) to construct the basic facilities for development and production of medical radioisotope. For the characteristics of radiopharmaceuticals, the facilities should be complied with the radiation shield and GMP(Good Manufacturing Practice) guideline. The KAERI, which has carried out the research and development of the radiopharmaceuticals, made a design of these facilities and built them in the HANARO Center and opened the technique and facilities to the public to give a foundation for research and development of the radiopharmaceuticals. In the facilities, radiation shielding utilities and GMP instruments were set up and their operating manuals were documented. Every utilities and instruments were performed the test to confirm their efficiency and the approval for use of the facilities will be achieved from MOST(Ministry of Science and Technology). It is expected to be applied in development of therapeutic radioisotope such as Re-188 generator and Ho-166, as well as Tc-99m generator and Sr-89 chloride for medical use. And it also looks forward to the contribution to the related industry through the development of product in high demand and value.

  15. Analysis of Discharged Gas from Incinerator using Simulated Organic Solution

    International Nuclear Information System (INIS)

    Kim, Seungil; Kim, Hyunki; Heo, Jun; Kang, Dukwon; Kim, Yunbok; Kwon, Youngbock

    2014-01-01

    Korea has no experience of treatment of RI organic waste and appropriate measures for treatment of organic waste did not suggested. RI organic wastes which are occurring in KOREA are stored at the RI waste storage building of KORAD. But they can't no more receive the RI organic waste because the storage facility for RI organic waste was saturated with these organic wastes. In case of Japan, they recognized the dangerousness of long-term storage for RI organic wastes. In case of Korea, the released concentration of gaseous pollutant from the incinerator is regulated by attached table No.1 of the Notification No. 2012-60 of Nuclear Safety Commission and attached table No.8 of Clean Air Conservation Act. And the dioxin from the incinerator is regulated by attached table No.3 of Persistent Organic Pollutants Control Act. This experiment was performed to examine whether the incinerator introduced from Japan is manufactured suitably for municipal law regulation and to confirm the compliance about the gaseous pollutant released from incinerator with the above-mentioned laws especially attached table No.1 of NSC using simulated organic waste solution. In this experiment, we examined whether the incinerator was manufactured suitably for municipal law regulation and confirmed the compliance about the gaseous pollutant released from incinerator with the above-mentioned laws using simulated organic waste solution. The design requirement of incinerator for RI organic waste in the municipal law regulation is proposed briefly but the requirements for more detail about the incinerator are proposed in regulation of Japan. The incinerator used in this experiment is satisfied with all clauses of the domestic as well as Japan. Multiple safety functions were installed in the incinerator such as air purge system to remove unburned inflammable gases in the furnace and earthquake detector. Also, perfect combustion of RI organic waste is achieved because the temperature in the furnace

  16. Space facilities: Meeting future needs for research, development, and operations

    Science.gov (United States)

    1994-01-01

    The National Facilities Study (NFS) represents an interagency effort to develop a comprehensive and integrated long-term plan for world-class aeronautical and space facilities that meet current and projected needs for commercial and government aerospace research and development and space operations. At the request of NASA and the DOD, the National Research Council's Committee on Space Facilities has reviewed the space related findings of the NFS. The inventory of more than 2800 facilities will be an important resource, especially if it continues to be updated and maintained as the NFS report recommends. The data in the inventory provide the basis for a much better understanding of the resources available in the national facilities infrastructure, as well as extensive information on which to base rational decisions about current and future facilities needs. The working groups have used the inventory data and other information to make a set of recommendations that include estimates of cast savings and steps for implementation. While it is natural that the NFS focused on cost reduction and consolidations, such a study is most useful to future planning if it gives equal weight to guiding the direction of future facilities needed to satisfy legitimate national aspirations. Even in the context of cost reduction through facilities closures and consolidations, the study is timid about recognizing and proposing program changes and realignments of roles and missions to capture what could be significant savings and increased effectiveness. The recommendations of the Committee on Space Facilities are driven by the clear need to be more realistic and precise both in recognizing current incentives and disincentives in the aerospace industry and in forecasting future conditions for U.S. space activities.

  17. Nitrous Oxide Emissions from Waste Incineration

    Czech Academy of Sciences Publication Activity Database

    Svoboda, Karel; Baxter, D.; Martinec, J.

    2006-01-01

    Roč. 60, č. 1 (2006), s. 78-90 ISSN 0366-6352 R&D Projects: GA AV ČR(CZ) IAA4072201 Institutional research plan: CEZ:AV0Z40720504 Keywords : nitrous oxide * waste * incineration Subject RIV: CI - Industrial Chemistry, Chemical Engineering Impact factor: 0.360, year: 2006

  18. Emission of greenhouse gases from waste incineration in Korea.

    Science.gov (United States)

    Hwang, Kum-Lok; Choi, Sang-Min; Kim, Moon-Kyung; Heo, Jong-Bae; Zoh, Kyung-Duk

    2017-07-01

    Greenhouse gas (GHG) emission factors previously reported from various waste incineration plants have shown significant variations according to country-specific, plant-specific, and operational conditions. The purpose of this study is to estimate GHG emissions and emission factors at nine incineration facilities in Korea by measuring the GHG concentrations in the flue gas samples. The selected incineration plants had different operation systems (i.e., stoker, fluidized bed, moving grate, rotary kiln, and kiln & stoker), and different nitrogen oxide (NO x ) removal systems (i.e., selective catalytic reduction (SCR) and selective non-catalytic reduction (SNCR)) to treat municipal solid waste (MSW), commercial solid waste (CSW), and specified waste (SW). The total mean emission factors for A and B facilities for MSW incineration were found to be 134 ± 17 kg CO 2 ton -1 , 88 ± 36 g CH 4 ton -1 , and 69 ± 16 g N 2 O ton -1 , while those for CSW incineration were 22.56 g CH 4 ton -1 and 259.76 g N 2 O ton -1 , and for SW incineration emission factors were 2959 kg CO 2 ton -1 , 43.44 g CH 4 ton -1 and 401.21 g N 2 O ton -1 , respectively. Total emissions calculated using annual incineration for MSW were 3587 ton CO 2 -eq yr -1 for A facility and 11,082 ton CO 2 -eq yr -1 for B facility, while those of IPCC default values were 13,167 ton CO 2- eq yr -1 for A facility and 32,916 ton CO 2- eq yr -1 , indicating that the emissions of IPCC default values were estimated higher than those of the plant-specific emission factors. The emission of CSW for C facility was 1403 ton CO 2 -eq yr -1 , while those of SW for D to I facilities was 28,830 ton CO 2 -eq yr -1 . The sensitivity analysis using a Monte Carlo simulation for GHG emission factors in MSW showed that the GHG concentrations have a greater impact than the incineration amount and flow rate of flue gas. For MSW incineration plants using the same stoker type in operation, the estimated emissions and

  19. FAIR - Facility, Research Program and Status of the Project

    International Nuclear Information System (INIS)

    Majka, Z.

    2011-01-01

    The international Facility for Antiproton and Ion Research (FAIR) in Europe will provide a worldwide science community with a unique and technically innovative accelerator system to perform forefront research in the sciences concerned with the basic structure of matter, and in intersections with other fields. The facility will deliver an extensive range of primary and secondary particle beams from protons and their antimatter partners, antiprotons, to ion beams of all chemical elements up to the heaviest, uranium, with in many respects unique properties and intensities. The paper will include overview of the new facility design and research programs to be carried out there. The current status of the FAIR project will be also presented. (author)

  20. Atmospheric Radiation Measurement (ARM) Climate Research Facility Management Plan

    Energy Technology Data Exchange (ETDEWEB)

    Mather, James [Pacific Northwest National Lab. (PNNL), Richland, WA (United States)

    2016-04-01

    Mission and Vision Statements for the U.S. Department of Energy (DOE)’s Atmospheric Radiation Measurement (ARM) Climate Research Facility Mission The ARM Climate Research Facility, a DOE scientific user facility, provides the climate research community with strategically located in situ and remote-sensing observatories designed to improve the understanding and representation, in climate and earth system models, of clouds and aerosols as well as their interactions and coupling with the Earth’s surface. Vision To provide a detailed and accurate description of the Earth atmosphere in diverse climate regimes to resolve the uncertainties in climate and Earth system models toward the development of sustainable solutions for the nation's energy and environmental challenges.

  1. Earthquake research for the safer siting of critical facilities

    Energy Technology Data Exchange (ETDEWEB)

    Cluff, J.L. (ed.)

    1980-01-01

    The task of providing the necessities for living, such as adequate electrical power, water, and fuel, is becoming more complicated with time. Some of the facilities that provide these necessities would present potential hazards to the population if serious damage were to occur to them during earthquakes. Other facilities must remain operable immediately after an earthquake to provide life-support services to people who have been affected. The purpose of this report is to recommend research that will improve the information available to those who must decide where to site these critical facilities, and thereby mitigate the effects of the earthquake hazard. The term critical facility is used in this report to describe facilities that could seriously affect the public well-being through loss of life, large financial loss, or degradation of the environment if they were to fail. The term critical facility also is used to refer to facilities that, although they pose a limited hazard to the public, are considered critical because they must continue to function in the event of a disaster so that they can provide vital services.

  2. NATIONAL INCINERATOR TESTING AND EVALUATION PROGRAM: THE ENVIRONMENTAL CHARACTERIZATION OF REFUSE-DERIVED FUEL (RDF) COMBUSTION TECHNOLOGY - MID-CONNECTICUT FACILITY,

    Science.gov (United States)

    The report gives results of an environmental characterization of refuse-derived, semi-suspension burning technology at a facility in Hartford, CT, that represents state-of-the-art technology, including a spray dryer/fabric filter flue gas cleaning (FGC) system for each unit. The ...

  3. In-pile experimental facility needs for LMFR safety research

    International Nuclear Information System (INIS)

    Kawata, Norio; Niwa, Hajime

    1994-01-01

    Although the achievement of the safety research during the past years has been significant, there still exists a strong need for future research, especially when there is prospect for future LMFR commercialization. In this paper, our current views are described on future research needs especially with a new in-pile experimental facility. The basic ideas and progress are outlined of a preliminary feasibility study. (author)

  4. Neutron beam facilities at Australia's replacement research reactor

    International Nuclear Information System (INIS)

    Robinson, R.A.

    2003-01-01

    Full text: The 20-MW Australian Replacement Research Reactor represents possibly the greatest single research infrastructure investment in Australia's history. Construction of the facility has commenced, following award of the construction contract in July 2000, and the construction licence in April 2002. The project includes a large state-of-the-art liquid deuterium cold-neutron source and supermirror guides feeding a large modern guide hall, in which most of the instruments are placed. Alongside the guide hall, there is good provision of laboratory, office and space for support activities. While the facility has 'space' for up to 18 instruments, the project has funding for an initial set of 8 instruments, which will be ready when the reactor is fully operational in January 2006. Instrument performance will be competitive with the best research-reactor facilities anywhere, and our goal is to be in the top 3 such facilities worldwide. Staff to lead the design effort and man these instruments have been hired on the international market from leading overseas facilities, and from within Australia, and 6 out of 8 instruments have been specified and costed. At present the instrumentation project carries ∼15% contingency. An extensive dialogue has taken place with the domestic user community and our international peers, via various means including a series of workshops over the last 2 years covering all 8 instruments, emerging areas of application like biology and the earth sciences, and computing infrastructure for the instruments. In December 2002, ANSTO formed the Bragg Institute, with the intent of nurturing strong external partnerships, and covering all aspects of neutron and X-ray scattering, including research using synchrotron radiation. I will discuss the present status and predicted performance of the neutron-beam facilities at the Replacement Reactor, and the opportunities that all of this presents for scientific research in Australia, with particular

  5. New research facilities at the University of Missouri research reactor

    International Nuclear Information System (INIS)

    McKibben, J.C.; Rhyne, J.J.

    1992-01-01

    The University of Missouri-Columbia is investing its resources for a significant expansion of the research capabilities and utilization of MURR to provide it the opportunity to deliver on its obligation to become the nation's premier educational institution in nuclear-related fields and so that it can provide scientific personnel and a state-of-the-art research test bed to support the national need for highly trained graduates in nuclear science and engineering

  6. Decommissioning of small medical, industrial and research facilities

    International Nuclear Information System (INIS)

    2003-01-01

    Most of the technical literature on decommissioning addresses the regulatory, organizational, technical and other aspects for large facilities such as nuclear power plants, reprocessing plants and relatively large prototype, research and test reactors. There are, however, a much larger number of licensed users of radioactive material in the fields of medicine, research and industry. Most of these nuclear facilities are smaller in size and complexity and may present a lower radiological risk during their decommissioning. Such facilities are located at research establishments, biological and medical laboratories, universities, medical centres, and industrial and manufacturing premises. They are often operated by users who have not been trained or are unfamiliar with the decommissioning, waste management and associated safety aspects of these types of facility at the end of their operating lives. Also, for many small users of radioactive material such as radiation sources, nuclear applications are a small part of the overall business or process and, although the operating safety requirements may be adhered to, concern or responsibility may not go much beyond this. There is concern that even the minimum requirements of decommissioning may be disregarded, resulting in avoidable delays, risks and safety implications (e.g. a loss of radioactive material and a loss of all records). Incidents have occurred in which persons have been injured or put at risk. It is recognized that the strategies and specific requirements for small facilities may be much less onerous than for large ones such as nuclear power plants or fuel processing facilities, but many of the same principles apply. There has been considerable attention given to nuclear facilities and many IAEA publications are complementary to this report. This report, however, attempts to give specific guidance for small facilities. 'Small' in this report does not necessarily mean small in size but generally modest in terms

  7. Low-level waste incineration: experience at the Idaho National Engineering Laboratory

    International Nuclear Information System (INIS)

    Bohrer, H.A.; Dalton, J.D.

    1987-01-01

    The Waste Experimental Reduction Facility (WERF) is a low level radioactive waste treatment facility being operated at the Idaho National Engineering Laboratory (INEL). A key component of the facility is a dual chambered controlled air incinerator with a dry off-gas treatment system. The incinerator began processing radioactive waste in September, 1984. Limited operations continued from that data until October, 1985, at which time all INEL generators began shipping combustible waste for incineration. The incinerator is presently processing all available INEL combustible Dry Active Waste (DAW) (approximately 1700 m 3 per year) operating about five days per month. Performance to date has demonstrated the effectiveness, viability and safety of incineration as a volume reduction method of DAW. 3 figures

  8. Development of the new Canadian Irradiation-Research Facility

    International Nuclear Information System (INIS)

    Lidstone, R.F.; Lee, A.G.; Bishop, W.E.; Talbot, E.F.; MCilwain, H.

    1995-01-01

    To replace the aging NRU reactor, AECL has developed the concept for a dual-purpose national Irradiation Research Facility (IRF) that tests fuel and materials for CANDU (Canada Deuterium Uranium) reactors and performs materials research using extracted neutron beams. The IRF includes a MAPLE reactor in a containment building, experimental facilities and support facilities. The reactor concept was developed to provide a realistic environment for irradiating up to nine natural- or enriched-uranium CANDU bundles at powers up to 1 MW p to generate fast-neutron fluxes up to 1.4x10 18 n m -2 s -1 in materials-damage and corrosion specimens, and to match the thermal-neutron fluxes available in NRU for a set of eight thermal beam tubes plus two cold sources equipped with neutron guides. (author)

  9. Research Support Facility (RSF): Leadership in Building Performance (Brochure)

    Energy Technology Data Exchange (ETDEWEB)

    2011-09-01

    This brochure/poster provides information on the features of the Research Support Facility including a detailed illustration of the facility with call outs of energy efficiency and renewable energy technologies. Imagine an office building so energy efficient that its occupants consume only the amount of energy generated by renewable power on the building site. The building, the Research Support Facility (RSF) occupied by the U.S. Department of Energy's National Renewable Energy Laboratory (NREL) employees, uses 50% less energy than if it were built to current commercial code and achieves the U.S. Green Building Council's Leadership in Energy and Environmental Design (LEED{reg_sign}) Platinum rating. With 19% of the primary energy in the U.S. consumed by commercial buildings, the RSF is changing the way commercial office buildings are designed and built.

  10. Safety Research Experiment Facility Project. Conceptual design report. Volume II. Building and facilities

    International Nuclear Information System (INIS)

    1975-12-01

    The conceptual design of Safety Research Experiment Facility (SAREF) site system includes a review and evaluation of previous geotechnical reports for the area where SAREF will be constructed and the conceptual design of access and in-plant roads, parking, experiment-transport-vehicle maneuvering areas, security fencing, drainage, borrow area development and restoration, and landscaping

  11. Management and Development of the RT Research Facilities and Infrastructures

    International Nuclear Information System (INIS)

    Kim, Won Ho; Nho, Young Chang; Kim, Jae Sung

    2009-01-01

    The purpose of this project are to operate the core facilities of the research for the Radiation Technology in stable and to assist the research activities efficiently in the industry, academic, and research laboratory. By developing the infrastructure of the national radio technology industry, we can activate the researching area of the RT and the related industry, and obtain the primary and original technology. The key point in the study of the RT and the assistance of the industry, academic, and research laboratory for the RT area smoothly, is managing the various of unique radiation facilities in our country. The gamma Phytotron and Gene Bank are essential in the agribiology because these facilities are used to preserve and utilize the genes and to provide an experimental field for the environment and biotechnology. The Radiation Fusion Technology research supporting facilities are the core support facilities, and are used to develop the high-tech fusion areas. In addition, the most advanced analytical instruments, whose costs are very high, should be managed in stable and be utilized in supporting works, and the experimental animal supporting laboratory and Gamma Cell have to be maintained in high level and managed in stable also. The ARTI have been developed the 30MeV cyclotron during 2005∼2006, aimed to produce radioisotopes and to research the beam applications as a result of the project, 'Establishment of the Infrastructure for the Atomic Energy Research Expansion', collaborated with the Korea Institute of Radiological and Medical Sciences. In addition, the ARTI is in the progress of establishing cyclotron integrated complex as a core research facility, using a proton beam to produce radioisotopes and to support a various research areas. The measurement and evaluation of the irradiation dose, and irradiation supporting technology of the Good Irradiation Practice(GIP) are essential in various researching areas. One thing to remember is that the publicity

  12. The International Facility for Antiproton and Ion Research FAIR

    International Nuclear Information System (INIS)

    Gutbrod, H. H.

    2008-01-01

    The proposed project FAIR (Facility for Antiproton and Ion Research) is an international accelerator facility of the next generation and will be built as a new company FAIR GmbH next to the site of GSI. About 15 countries have expressed their intention to become shareholders. FAIR builds on the experience and technological developments already made at the existing GSI facility, and at the FAIR partner institutes world wide and incorporates new technological concepts. At its heart is a double ring facility with a circumference of 1100 meters. A system of cooler-storage rings for effective beam cooling at high energies and various experimental halls will be connected to the facility. The existing GSI accelerators - together with the planned proton-linac - serve as injector for the new facility. The double-ring synchrotron will provide ion beams of unprecedented intensities as well as of considerably increased energy. Thereby intense beams of secondary beams - unstable nuclei or antiprotons - can be produced. The system of storage-cooler rings allows the quality of these secondary beams - their energy spread and emittance - to be drastically improved. Moreover, in connection with the double ring synchrotron, an efficient parallel operation of up to four scientific programs can be realized at a time. The project is based on many technological innovations, the most important of which are five beam properties: Highest Beam Intensities, Brilliant Beam Quality, Higher Beam Energies, Highest Beam Power, Parallel Operation

  13. Commercial incineration demonstration

    International Nuclear Information System (INIS)

    Borduin, L.C.; Neuls, A.S.

    1981-01-01

    Low-level radioactive wastes (LLW) generated by nuclear utilities presently are shipped to commercial burial grounds for disposal. Substantially increasing shipping and disposal charges have sparked renewed industry interest in incineration and other advanced volume reduction techniques as potential cost-saving measures. Repeated inquiries from industry sources regarding LLW applicability of the Los Alamos controlled-air incineration (CAI) design led DOE to initiate this commercial demonstration program in FY-1980. The selected program approach to achieving CAI demonstration at a utility site is a DOE sponsored joint effort involving Los Alamos, a nuclear utility, and a liaison subcontractor. Required development tasks and responsibilities of the particpants are described. Target date for project completion is the end of FY-1985

  14. Incineration by accelerator

    International Nuclear Information System (INIS)

    Cribier, M.; FIoni, G.; Legrain, R.; Lelievre, F.; Leray, S.; Pluquet, A.; Safa, H.; Spiro, M.; Terrien, Y.; Veyssiere, Ch.

    1997-01-01

    The use MOX fuel allows to hope a stabilization of plutonium production around 500 tons for the French park. In return, the flow of minor actinides is increased to several tons. INCA (INCineration by Accelerator), dedicated instrument, would allow to transmute several tons of americium, curium and neptunium. It could be able to reduce nuclear waste in the case of stopping nuclear energy use. This project needs: a protons accelerator of 1 GeV at high intensity ( 50 m A), a window separating the accelerator vacuum from the reactor, a spallation target able to produce 30 neutrons by incident proton, an incineration volume where a part of fast neutrons around the target are recovered, and a thermal part in periphery with flows at 2.10 15 n/cm 2 .s; a chemical separation of elements burning in thermal (americium) from the elements needing a flow of fast neutrons. (N.C.)

  15. The DESDEMONA Motion Facility : Applications for Space Research

    NARCIS (Netherlands)

    Bles, W.; Groen, E.

    2009-01-01

    The research facility DESDEMONA features a unique motion platform, combining a fully gimbaled cabin with the capability of producing sustained g-loads. Originally designed for ground-based simulation as well as training of spatial disorientation in aviation, the motion capabilities are also

  16. Detailed description of an SSAC at the facility level for research laboratory facilities

    International Nuclear Information System (INIS)

    Jones, R.J.

    1985-08-01

    The purpose of this document is to provide a detailed description of a system for the accounting for and control of nuclear material in a research laboratory facility which can be used by a facility operator to establish his own system to comply with a national system for nuclear material accounting and control and to facilitate application of IAEA safeguards. The scope of this document is limited to descriptions of the following SSAC elements: (1) Nuclear Material Measurements; (2) Measurement Quality; (3) Records and Reports; (4) Physical Inventory Taking; (5) Material Balance Closing

  17. ARM Climate Research Facility Instrumentation Status and Information March 2010

    Energy Technology Data Exchange (ETDEWEB)

    Voyles, JW

    2010-04-19

    The purpose of this report is to provide a concise but comprehensive overview of Atmospheric Radiation Measurement Climate Research Facility instrumentation status. The report is divided into the following five sections: (1) new instrumentation in the process of being acquired and deployed, (2) field campaigns, (3) existing instrumentation and progress on improvements or upgrades, (4) proposed future instrumentation, and (5) Small Business Innovation Research instrument development.

  18. ARM Climate Research Facility Instrumentation Status and Information February 2010

    Energy Technology Data Exchange (ETDEWEB)

    Voyles, JW

    2010-03-25

    The purpose of this report is to provide a concise but comprehensive overview of Atmospheric Radiation Measurement Climate Research Facility instrumentation status. The report is divided into the following five sections: (1) new instrumentation in the process of being acquired and deployed, (2) field campaigns, (3) existing instrumentation and progress on improvements or upgrades, (4) proposed future instrumentation, and (5) Small Business Innovation Research instrument development.

  19. ARM Climate Research Facility Monthly Instrument Report May 2010

    Energy Technology Data Exchange (ETDEWEB)

    Voyles, JW

    2010-06-21

    The purpose of this report is to provide a concise but comprehensive overview of Atmospheric Radiation Measurement Climate Research Facility instrumentation status. The report is divided into the following five sections: (1) new instrumentation in the process of being acquired and deployed, (2) field campaigns, (3) existing instrumentation and progress on improvements or upgrades, (4) proposed future instrumentation, and (5) Small Business Innovation Research instrument development.

  20. ARM Climate Research Facility Instrumentation Status and Information December 2009

    Energy Technology Data Exchange (ETDEWEB)

    JW Voyles

    2010-12-30

    The purpose of this report is to provide a concise but comprehensive overview of Atmospheric Radiation Measurement Climate Research Facility instrumentation status. The report is divided into the following five sections: (1) new instrumentation in the process of being acquired and deployed, (2) field campaigns, (3) existing instrumentation and progress on improvements or upgrades, (4) proposed future instrumentation, and (5) Small Business Innovation Research instrument development.

  1. ARM Climate Research Facility Instrumentation Status and Information January 2010

    Energy Technology Data Exchange (ETDEWEB)

    JW Voyles

    2010-02-28

    The purpose of this report is to provide a concise but comprehensive overview of Atmospheric Radiation Measurement Climate Research Facility instrumentation status. The report is divided into the following five sections: (1) new instrumentation in the process of being acquired and deployed, (2) field campaigns, (3) existing instrumentation and progress on improvements or upgrades, (4) proposed future instrumentation, and (5) Small Business Innovation Research instrument development.

  2. ARM Climate Research Facility Instrumentation Status and Information April 2010

    Energy Technology Data Exchange (ETDEWEB)

    Voyles, JW

    2010-05-15

    The purpose of this report is to provide a concise but comprehensive overview of Atmospheric Radiation Measurement Climate Research Facility instrumentation status. The report is divided into the following five sections: (1) new instrumentation in the process of being acquired and deployed, (2) field campaigns, (3) existing instrumentation and progress on improvements or upgrades, (4) proposed future instrumentation, and (5) Small Business Innovation Research instrument development.

  3. ARM Climate Research Facility Monthly Instrument Report September 2010

    Energy Technology Data Exchange (ETDEWEB)

    Voyles, JW

    2010-10-18

    The purpose of this report is to provide a concise but comprehensive overview of Atmospheric Radiation Measurement Climate Research Facility instrumentation status. The report is divided into the following five sections: (1) new instrumentation in the process of being acquired and deployed, (2) field campaigns, (3) existing instrumentation and progress on improvements or upgrades, (4) proposed future instrumentation, and (5) Small Business Innovation Research instrument development.

  4. ARM Climate Research Facility Monthly Instrument Report July 2010

    Energy Technology Data Exchange (ETDEWEB)

    Voyles, JW

    2010-08-18

    The purpose of this report is to provide a concise but comprehensive overview of Atmospheric Radiation Measurement Climate Research Facility instrumentation status. The report is divided into the following five sections: (1) new instrumentation in the process of being acquired and deployed, (2) field campaigns, (3) existing instrumentation and progress on improvements or upgrades, (4) proposed future instrumentation, and (5) Small Business Innovation Research instrument development.

  5. ARM Climate Research Facility Monthly Instrument Report June 2010

    Energy Technology Data Exchange (ETDEWEB)

    Voyles, JW

    2010-07-13

    The purpose of this report is to provide a concise but comprehensive overview of Atmospheric Radiation Measurement Climate Research Facility instrumentation status. The report is divided into the following five sections: (1) new instrumentation in the process of being acquired and deployed, (2) field campaigns, (3) existing instrumentation and progress on improvements or upgrades, (4) proposed future instrumentation, and (5) Small Business Innovation Research instrument development.

  6. ARM Climate Research Facility Instrumentation Status and Information October 2009

    Energy Technology Data Exchange (ETDEWEB)

    JW Voyles

    2009-10-01

    The purpose of this report is to provide a concise but comprehensive overview of Atmospheric Radiation Measurement Climate Research Facility instrumentation status. The report is divided into the following five sections: (1) new instrumentation in the process of being acquired and deployed, (2) field campaigns, (3) existing instrumentation and progress on improvements or upgrades, (4) proposed future instrumentation, and (5) Small Business Innovation Research instrument development.

  7. ARM Climate Research Facility Monthly Instrument Report August 2010

    Energy Technology Data Exchange (ETDEWEB)

    Voyles, JW

    2010-09-28

    The purpose of this report is to provide a concise but comprehensive overview of Atmospheric Radiation Measurement Climate Research Facility instrumentation status. The report is divided into the following five sections: (1) new instrumentation in the process of being acquired and deployed, (2) field campaigns, (3) existing instrumentation and progress on improvements or upgrades, (4) proposed future instrumentation, and (5) Small Business Innovation Research instrument development.

  8. Introducing COSS: A new and unique oil spill research facility

    International Nuclear Information System (INIS)

    Kitchen, R. B.; Bonner, J. S.; Autenrieth, R. L.; Donnelly, K. C.; Ernest, A. N. S.

    1997-01-01

    A new oil spill research facility in Corpus Christi, Texas began operation in April 1997 to address the appropriate use, application and effectiveness of chemical, physical and biological oil spill response agents. The Coastal Oil Spill Simulation (COSS) facility consists of nine meso scale wave tanks and will offer to science and industry a unique opportunity to spill oil in a controlled environment and to study fate, transport and remediation of oil releases in simulated coastal, intertidal, lagunal, channel and porous media. 1 ref

  9. Development of an incineration system for radioactive waste

    International Nuclear Information System (INIS)

    Chrubasik, A.

    1989-01-01

    NUKEM GmbH (W. Germany) has developed and built some plants for treatment of radioactive waste. In cooperation with Karlsruhe Nuclear Research Center and on the basis of non-nuclear incineration plants, NUKEM has designed and built a new incineration plant for low level radioactive solid waste. The main features of the plant are improvement of the waste handling during feeding, very low particulate load downstream the incinerator and simple flue-gas cleaning system. This process is suitable for treatment of waste generated above all in nuclear power plants. (author)

  10. The SARAF Project - Soreq Applied Research Accelerator Facility

    International Nuclear Information System (INIS)

    Nagler, A.; Mardor, I.; Berkovits, D.; Piel, C.

    2004-01-01

    The relevance of particle accelerators to society, in the use of their primary and secondary beams for the analysis of physical, chemical and biological samples and for modification of properties of materials, is well recognized and documented. Nevertheless, apart of the construction of small accelerators for nuclear research in the 1960's and 70's, Israel has so far neglected this important and growing field. Furthermore, there is an urgent need in Israel for a state of the art research facility to attract and introduce students to current advanced physics techniques and technologies and to train the next generation of experimental scientists in various branches and disciplines. Therefore, Soreq NRC recently initiated the establishment of a new accelerator facility, named SARAF Soreq Applied Research Accelerator Facility. SARAF will be a continuous wave (CW), proton and deuteron RF superconducting linear accelerator with variable energy (5 - 40 MeV) and current (0.04 -2 mA). SARAF is designed to enable hands-on maintenance, which means that its beam loss will be below 10 -5 for the entire accelerator. These specifications will place SARAF in line with the next generation of accelerators world wide. Soreq expects that this fact will attract the Israeli and international research communities to use this facility extensively. Soreq NRC intends to use SARAF for basic, medical and biological research, and non-destructive testing (NDT). Another major activity will be the research and development of radio-isotopes production techniques. Given the availability of high current (up to 2 mA) protons and deuterons, a major activity will be research and development of high power density (up to 80 kW on a few cm 2 ) irradiation targets

  11. BALU: Largest autoclave research facility in the world

    Directory of Open Access Journals (Sweden)

    Hakan Ucan

    2016-03-01

    Full Text Available Among the large-scale facilities operated at the Center for Lightweight-Production-Technology of the German Aerospace Center in Stade BALU is the world's largest research autoclave. With a loading length of 20m and a loading diameter of 5.8 m the main objective of the facility is the optimization of the curing process operated by components made of carbon fiber on an industrial scale. For this reason, a novel dynamic autoclaving control has been developed that is characterized by peripheral devices to expend the performance of the facility for differential applications, by sensing systems to detect the component state throughout the curing process and by a feedback system, which is capable to intervene into the running autoclave process.

  12. Research Facility for Mechanical Press Closed Gap Adjuster

    Directory of Open Access Journals (Sweden)

    A. A. Ancifirov

    2016-01-01

    Full Text Available The article describes an example of the research facility for closed gap adjustment mechanism based on the KD2128 closed-die forging press. Its rated force with a servo drive used is 630kN. The servo drive consists of a motor with nominal power of 1.57kW and a frequency converter with power of 7.5kW, which has functions of the programmable logic controller.The article notes that such a facility is expedient and useful for practical classes on forging-andstamping machines at the BMSTU Department of «Technology processing by pressure» to demonstrate the capabilities of existing technological facility, learn a design of forging-andstamping machine units, solve the problems of automatic control, monitoring, and diagnostics in blank manufacturing.The article presents a detailed facility diagram of the closed gap adjustment mechanism and its photograph, describes the mechanism and its basic parameters, gives characteristics of the synchronous motor to drive the mechanism, reviews practical works, which the research facility may provide.Based on the four experiments the article estimates an efficiency of the research facilityuse under consideration, especially when modeling a servo motor shaft under the maximum load. The relevant diagrams confirm experimental results, namely: control current, angle of motor shaft and its speed versus time. Thus, upon the diagram analysis it can be noted that the research facility design allows providing kinematics and dynamics of the press closed gap adjuster.This article describes how to determine the closed gap adjusting accuracy of the press. Eight experiments have been conducted to evaluate a working out control signal to the linear movement of the press punch when using the research facility. It is noted that the linear positioning accuracy of the press punch reaches the hundredth parts of a millimeter of the adjustment value that is sufficient to achieve the required precision when performing operations such as

  13. Low-level waste institutional waste incinerator program

    International Nuclear Information System (INIS)

    Thompson, J.D.

    1980-04-01

    Literature surveyed indicated that institutional LLW is composed of organic solids and liquids, laboratory equipment and trash, and some pathological waste. Some toxic and hazardous chemicals are included in the variety of LLW generated in the nation's hospitals, universities, and research laboratories. Thus, the incinerator to be demonstrated in this program should be able to accept each of these types of materials as feedstock. Effluents from the DOE institutional incinerator demonstration should be such that all existing and proposed environmental standards be met. A design requirement was established to meet the most stringent flue gas standards. LLW incineration practice was reviewed in a survey of institutional LLW generators. Incinerator manufacturers were identified by the survey, and operational experience in incineration was noted for institutional users. Manufacturers identified in the survey were contacted and queried with regard to their ability to supply an incinerator with the desired capability. Special requirements for ash removal characteristics and hearth type were imposed on the selection. At the present time, an incinerator type, manufacturer, and model have been chosen for demonstration

  14. Hardware development process for Human Research facility applications

    Science.gov (United States)

    Bauer, Liz

    2000-01-01

    The simple goal of the Human Research Facility (HRF) is to conduct human research experiments on the International Space Station (ISS) astronauts during long-duration missions. This is accomplished by providing integration and operation of the necessary hardware and software capabilities. A typical hardware development flow consists of five stages: functional inputs and requirements definition, market research, design life cycle through hardware delivery, crew training, and mission support. The purpose of this presentation is to guide the audience through the early hardware development process: requirement definition through selecting a development path. Specific HRF equipment is used to illustrate the hardware development paths. .

  15. Neutron beam facilities at the replacement research reactor

    International Nuclear Information System (INIS)

    Kennedy, S.

    1999-01-01

    Full text: On September 3rd 1997 the Australian Federal Government announced their decision to replace the HIFAR research reactor by 2005. The proposed reactor will be a multipurpose reactor with improved capabilities for neutron beam research and for the production of radioisotopes for pharmaceutical, scientific and industrial use. The neutron beam facilities are intended to cater for Australian scientific needs well into the 21st century. In the first stage of planning the neutron Beam Facilities at the replacement reactor, a Consultative Group was formed (BFCG) to determine the scientific capabilities of the new facility. Members of the group were drawn from academia, industry and government research laboratories. The BFCG submitted their report in April 1998, outlining the scientific priorities to be addressed. Cold and hot neutron sources are to be included, and cold and thermal neutron guides will be used to position most of the instruments in a neutron guide hall outside the reactor confinement building. In 2005 it is planned to have eight instruments installed with a further three to be developed by 2010, and seven spare instrument positions for development of new instruments over the life of the reactor. A beam facilities technical group (BFTG) was then formed to prepare the engineering specifications for the tendering process. The group consisted of some members of the BFCG, several scientists and engineers from ANSTO, and scientists from leading neutron scattering centres in Europe, USA and Japan. The BFTG looked in detail at the key components of the facility such as the thermal, cold and hot neutron sources, neutron collimators, neutron beam guides and overall requirements for the neutron guide hall. The report of the BFTG, completed in August 1998, was incorporated into the draft specifications for the reactor project, which were distributed to potential reactor vendors. An assessment of the first stage of reactor vendor submissions was completed in

  16. Recent activities at the ORNL multicharged ion research facility (MIRF)

    International Nuclear Information System (INIS)

    Meyer, F.W.; Bannister, M.E.; Hale, J.W.; Havener, C.C.; Krause, H.F.; Vane, C.R.; Deng, S.; Draganic, I.N.; Harris, P.R.

    2012-01-01

    Recent activities at the ORNL Multicharged Ion Research Facility (MIRF) are summarized. A brief summary of the MIRF high voltage (HV) platform and floating beam line upgrade is provided. An expansion of our research program to the use of molecular ion beams in heavy-particle and electron collisions, as well as in ion surface interactions is described, and a brief description is provided of the most recently added Ion Cooling and Characterization End-station (ICCE) trap. With the expansion to include molecular ion beams, the acronym MIRF for the facility, however, remains unchanged: 'M' can now refer to either 'Multicharged' or 'Molecular'. The paper is followed by the slides of the presentation. (authors)

  17. Basic Design of the Cold Neutron Research Facility in HANARO

    International Nuclear Information System (INIS)

    Kim, Hark Rho; Lee, K. H.; Kim, Y. K.

    2005-09-01

    The HANARO Cold Neutron Research Facility (CNRF) Project has been embarked in July 2003. The CNRF project has selected as one of the radiation technology development project by National Science and Technology Committee in June 2002. In this report, the output of the second project year is summarized as a basic design of cold neutron source and related systems, neutron guide, and neutron scattering instruments

  18. Basic Design of the Cold Neutron Research Facility in HANARO

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Hark Rho; Lee, K. H.; Kim, Y. K. (and others)

    2005-09-15

    The HANARO Cold Neutron Research Facility (CNRF) Project has been embarked in July 2003. The CNRF project has selected as one of the radiation technology development project by National Science and Technology Committee in June 2002. In this report, the output of the second project year is summarized as a basic design of cold neutron source and related systems, neutron guide, and neutron scattering instruments.

  19. ARM Climate Research Facility Quarterly Ingest Status Report

    Energy Technology Data Exchange (ETDEWEB)

    Koontz, A. [DOE ARM Climate Research Facility, Washington, DC (United States); Sivaraman, C. [DOE ARM Climate Research Facility, Washington, DC (United States)

    2016-10-01

    The purpose of this report is to provide a concise status update for ingests maintained by the Atmospheric Radiation Measurement (ARM) Climate Research Facility. The report is divided into the following sections: (1) new ingests for which development has begun, (2) progress on existing ingests, (3) future ingests that have been recently approved, (4) other work that leads to an ingest, and (5) top requested ingests from the ARM Data Archive. New information is highlighted in blue text.

  20. ARM Climate Research Facility Quarterly Ingest Status Report

    Energy Technology Data Exchange (ETDEWEB)

    Koontz, A. [ARM Climate Reesearch Facility, Washington, DC (United States); Sivaraman, C. [ARM Climate Reesearch Facility, Washington, DC (United States)

    2016-07-01

    The purpose of this report is to provide a concise status update for ingests maintained by the Atmospheric Radiation Measurement (ARM) Climate Research Facility. The report is divided into the following sections: (1) new ingests for which development has begun, (2) progress on existing ingests, (3) future ingests that have been recently approved, (4) other work that leads to an ingest, and (5) top requested ingests from the ARM Data Archive. New information is highlighted in blue text.

  1. Development of an Extreme Environment Materials Research Facility at Princeton

    International Nuclear Information System (INIS)

    Cohen, A.B.; Gentile, C.A.; Tully, C.G.; Austin, R.; Calaprice, F.; McDonald, K.; Ascione, G.; Baker, G.; Davidson, R.; Dudek, L.; Grisham, L.; Kugel, H.; Pagdon, K.; Stevenson, T.; Woolley, R.; Zwicker, A.

    2010-01-01

    The need for a fundamental understanding of material response to a neutron and/or high heat flux environment can yield development of improved materials and operations with existing materials. Such understanding has numerous applications in fields such as nuclear power (for the current fleet and future fission and fusion reactors), aerospace, and other research fields (e.g., high-intensity proton accelerator facilities for high energy physics research). A proposal has been advanced to develop a facility for testing various materials under extreme heat and neutron exposure conditions at Princeton. The Extreme Environment Materials Research Facility comprises an environmentally controlled chamber (48 m 3 ) capable of high vacuum conditions, with extreme flux beams and probe beams accessing a central, large volume target. The facility will have the capability to expose large surface areas (1 m 2 ) to 14 MeV neutrons at a fluence in excess of 10 13 n/s. Depending on the operating mode. Additionally beam line power on the order of 15-75 MW/m 2 for durations of 1-15 seconds are planned. The multi-second duration of exposure can be repeated every 2-10 minutes for periods of 10-12 hours. The facility will be housed in the test cell that held the Tokamak Fusion Test Reactor (TFTR), which has the desired radiation and safety controls as well as the necessary loading and assembly infrastructure. The facility will allow testing of various materials to their physical limit of thermal endurance and allow for exploring the interplay between radiation-induced embrittlement, swelling and deformation of materials, and the fatigue and fracturing that occur in response to thermal shocks. The combination of high neutron energies and intense fluences will enable accelerated time scale studies. The results will make contributions for refining predictive failure modes (modeling) in extreme environments, as well as providing a technical platform for the development of new alloys, new

  2. Development of an Extreme Environment Materials Research Facility at Princeton

    Energy Technology Data Exchange (ETDEWEB)

    Cohen, A B; Tully, C G; Austin, R; Calaprice, F; McDonald, K; Ascione, G; Baker, G; Davidson, R; Dudek, L; Grisham, L; Kugel, H; Pagdon, K; Stevenson, T; Woolley, R

    2010-11-17

    The need for a fundamental understanding of material response to a neutron and/or high heat flux environment can yield development of improved materials and operations with existing materials. Such understanding has numerous applications in fields such as nuclear power (for the current fleet and future fission and fusion reactors), aerospace, and other research fields (e.g., high-intensity proton accelerator facilities for high energy physics research). A proposal has been advanced to develop a facility for testing various materials under extreme heat and neutron exposure conditions at Princeton. The Extreme Environment Materials Research Facility comprises an environmentally controlled chamber (48 m^3) capable of high vacuum conditions, with extreme flux beams and probe beams accessing a central, large volume target. The facility will have the capability to expose large surface areas (1 m^2) to 14 MeV neutrons at a fluence in excess of 10^13 n/s. Depending on the operating mode. Additionally beam line power on the order of 15-75 MW/m2 for durations of 1-15 seconds are planned... The multi-second duration of exposure can be repeated every 2-10 minutes for periods of 10-12 hours. The facility will be housed in the test cell that held the Tokamak Fusion Test Reactor (TFTR), which has the desired radiation and safety controls as well as the necessary loading and assembly infrastructure. The facility will allow testing of various materials to their physical limit of thermal endurance and allow for exploring the interplay between radiation-induced embrittlement, swelling and deformation of materials, and the fatigue and fracturing that occur in response to thermal shocks. The combination of high neutron energies and intense fluences will enable accelerated time scale studies. The results will make contributions for refining predictive failure modes (modeling) in extreme environments, as well as providing a technical platform for the development of new alloys, new

  3. Atmospheric Radiation Measurement Climate Research Facility (ACRF) Annual Report 2007

    Energy Technology Data Exchange (ETDEWEB)

    LR Roeder

    2007-12-01

    This annual report describes the purpose and structure of the program, and presents key accomplishments in 2007. Notable achievements include: • Successful review of the ACRF as a user facility by the DOE Biological and Environmental Research Advisory Committee. The subcommittee reinforced the importance of the scientific impacts of this facility, and its value for the international research community. • Leadership of the Cloud Land Surface Interaction Campaign. This multi-agency, interdisciplinary field campaign involved enhanced surface instrumentation at the ACRF Southern Great Plains site and, in concert with the Cumulus Humilis Aerosol Processing Study sponsored by the DOE Atmospheric Science Program, coordination of nine aircraft through the ARM Aerial Vehicles Program. • Successful deployment of the ARM Mobile Facility in Germany, including hosting nearly a dozen guest instruments and drawing almost 5000 visitors to the site. • Key advancements in the representation of radiative transfer in weather forecast models from the European Centre for Medium-Range Weather Forecasts. • Development of several new enhanced data sets, ranging from best estimate surface radiation measurements from multiple sensors at all ACRF sites to the extension of time-height cloud occurrence profiles to Niamey, Niger, Africa. • Publication of three research papers in a single issue (February 2007) of the Bulletin of the American Meteorological Society.

  4. Sustainability in facilities management: an overview of current research

    DEFF Research Database (Denmark)

    Nielsen, Susanne Balslev; Sarasoja, Anna-Liisa; Ramskov Galamba, Kirsten

    2016-01-01

    the emerging sub-discipline of sustainable facilities management (SFM) on research, an overview of current studies is needed. The purpose of this literature review is to provide exactly this overview. Design/methodology/approach: This article identifies and examines current research studies on SFM through...... a comprehensive and systematic literature review. The literature review included screening of 85 identified scientific journals and almost 20,000 articles from the period of 2007-2012. Of the articles reviewed, 151 were identified as key articles and categorised according to topic. Findings: The literature review...... indicated that the current research varies in focus, methodology and application of theory, and it was concluded that the current research primary addresses environmental sustainability, whereas the current research which takes an integrated strategic approach to SFM is limited. The article includes lists...

  5. The crop growth research chamber: A ground-based facility for CELSS research

    Science.gov (United States)

    Bubenheim, David L.

    1990-01-01

    A ground based facility for the study of plant growth and development under stringently controlled environments is being developed by the Closed Ecological Life Support System (CELSS) program at the Ames Research Center. Several Crop Growth Research Chambers (CGRC) and laboratory support equipment provide the core of this facility. The CGRC is a closed (sealed) system with a separate recirculating atmosphere and nutrient delivery systems. The atmospheric environment, hydroponic environment, systems controls, and data acquisition are discussed.

  6. Tracing Scientific Facilities through the Research Literature Using Persistent Identifiers

    Science.gov (United States)

    Mayernik, M. S.; Maull, K. E.

    2016-12-01

    Tracing persistent identifiers to their source publications is an easy task when authors use them, since it is a simple matter of matching the persistent identifier to the specific text string of the identifier. However, trying to understand if a publication uses the resource behind an identifier when such identifier is not referenced explicitly is a harder task. In this research, we explore the effectiveness of alternative strategies of associating publications with uses of the resource referenced by an identifier when it may not be explicit. This project is explored within the context of the NCAR supercomputer, where we are broadly interesting in the science that can be traced to the usage of the NCAR supercomputing facility, by way of the peer-reviewed research publications that utilize and reference it. In this project we explore several ways of drawing linkages between publications and the NCAR supercomputing resources. Identifying and compiling peer-reviewed publications related to NCAR supercomputer usage are explored via three sources: 1) User-supplied publications gathered through a community survey, 2) publications that were identified via manual searching of the Google scholar search index, and 3) publications associated with National Science Foundation (NSF) grants extracted from a public NSF database. These three sources represent three styles of collecting information about publications that likely imply usage of the NCAR supercomputing facilities. Each source has strengths and weaknesses, thus our discussion will explore how our publication identification and analysis methods vary in terms of accuracy, reliability, and effort. We will also discuss strategies for enabling more efficient tracing of research impacts of supercomputing facilities going forward through the assignment of a persistent web identifier to the NCAR supercomputer. While this solution has potential to greatly enhance our ability to trace the use of the facility through

  7. The neutron beam facility at the Australian replacement research reactor

    International Nuclear Information System (INIS)

    Hunter, B.; Kennedy, S.

    1999-01-01

    Full text: The Australian federal government gave ANSTO final approval to build a research reactor to replace HIFAR on August 25th 1999. The replacement reactor is to be a multipurpose reactor with a thermal neutron flux of 3 x 10 14 n.cm -2 .s -1 and having improved capabilities for neutron beam research and for the production of radioisotopes for pharmaceutical, scientific and industrial use. The replacement reactor will commence operation in 2005 and will cater for Australian scientific, industrial and medical needs well into the 21st century. The scientific capabilities of the neutron beams at the replacement reactor are being developed in consultation with representatives from academia, industry and government research laboratories to provide a facility for condensed matter research in physics, chemistry, materials science, life sciences, engineering and earth sciences. Cold, thermal and hot neutron sources are to be installed, and neutron guides will be used to position most of the neutron beam instruments in a neutron guide hall outside the reactor confinement building. Eight instruments are planned for 2005, with a further three to be developed by 2010. A conceptual layout for the neutron beam facility is presented including the location of the planned suite of neutron beam instruments. The reactor and all the associated infrastructure, with the exception of the neutron beam instruments, is to be built by an accredited reactor builder in a turnkey contract. Tenders have been called for December 1999, with selection of contractor planned by June 2000. The neutron beam instruments will be developed by ANSTO and other contracted organisations in consultation with the user community and interested overseas scientists. The facility will be based, as far as possible, around a neutron guide hall that is be served by three thermal and three cold neutron guides. Efficient transportation of thermal and cold neutrons to the guide hall requires the use of modern super

  8. State of art in incineration technology of radioactive combustible solid wastes

    International Nuclear Information System (INIS)

    Karita, Yoichi

    1984-01-01

    The features of incineration treatment as the method of treating radioactive wastes are the effect of volume reduction and inorganic stabilization (change to ash). The process of incineration treatment is roughly divided into dry process and wet process. But that in practical use is dry incineration by excess air combustion or suppressed combustion. The important things in incineration techniques are the techniques of exhaust gas treatment as well as combustion techniques. In Europe and USA, incineration has been practiced in laboratories and reprocessing plants for low level combustible solids, but the example of application in nuclear power stations is few. In Japan, though the fundamental techniques are based on the introduction from Europe, the incineration treatment of combustible solids has been carried out in laboratories, reprocessing plants, nuclear fuel production facilities and also nuclear power stations. The techniques of solidifying ash by incineration and the techniques of incinerating spent ion exchange resin are actively developed, and the development of the treatment of radioactive wastes in the lump including incineration also is in progress. (Kako, I.)

  9. Waste incineration. Final report

    Energy Technology Data Exchange (ETDEWEB)

    Egede Rasmussen, Anja

    2004-06-15

    This prepatory thesis is a literature study on the incineration of waste. It deals with the concepts of municipal solid waste, the composition and combustion of it. A main focus is on the European emission regulations and the formation of dioxins, as well as a big effort is put into the treatment of solid residues from municipal solid waste incineration. In the latter area, concepts of treatment, such as physical and chemical separations, solidification and stabilization techniques, thermal methods, and extraction methods have been discussed. Evaluation of possible methods of treatment has been done, but no conclusions made of which is the best. Though, indications exist that especially two methods have shown positive qualities and must be further investigated. These methods are the acid extraction and sulfide stabilization (AES) process and the phosphate stabilization method of WES-PHix. Economic potentials of the two methods have been evaluated, and with the information obtained, it seems that the price for treatment and later landfilling of a material with improved leaching characteristics, will be approximately the same as the presently most used solution of export to Norway. However, more tests, investigations and economic evaluations are necessary in order for support of the findings in this work. (au)

  10. Psychometric model for safety culture assessment in nuclear research facilities

    International Nuclear Information System (INIS)

    Nascimento, C.S. do; Andrade, D.A.; Mesquita, R.N. de

    2017-01-01

    Highlights: • A psychometric model to evaluate ‘safety climate’ at nuclear research facilities. • The model presented evidences of good psychometric qualities. • The model was applied to nuclear research facilities in Brazil. • Some ‘safety culture’ weaknesses were detected in the assessed organization. • A potential tool to develop safety management programs in nuclear facilities. - Abstract: A safe and reliable operation of nuclear power plants depends not only on technical performance, but also on the people and on the organization. Organizational factors have been recognized as the main causal mechanisms of accidents by research organizations through USA, Europe and Japan. Deficiencies related with these factors reveal weaknesses in the organization’s safety culture. A significant number of instruments to assess the safety culture based on psychometric models that evaluate safety climate through questionnaires, and which are based on reliability and validity evidences, have been published in health and ‘safety at work’ areas. However, there are few safety culture assessment instruments with these characteristics (reliability and validity) available on nuclear literature. Therefore, this work proposes an instrument to evaluate, with valid and reliable measures, the safety climate of nuclear research facilities. The instrument was developed based on methodological principles applied to research modeling and its psychometric properties were evaluated by a reliability analysis and validation of content, face and construct. The instrument was applied to an important nuclear research organization in Brazil. This organization comprises 4 research reactors and many nuclear laboratories. The survey results made possible a demographic characterization and the identification of some possible safety culture weaknesses and pointing out potential areas to be improved in the assessed organization. Good evidence of reliability with Cronbach's alpha

  11. Psychometric model for safety culture assessment in nuclear research facilities

    Energy Technology Data Exchange (ETDEWEB)

    Nascimento, C.S. do, E-mail: claudio.souza@ctmsp.mar.mil.br [Centro Tecnológico da Marinha em São Paulo (CTMSP), Av. Professor Lineu Prestes 2468, 05508-000 São Paulo, SP (Brazil); Andrade, D.A., E-mail: delvonei@ipen.br [Instituto de Pesquisas Energéticas e Nucleares (IPEN/CNEN – SP), Av. Professor Lineu Prestes 2242, 05508-000 São Paulo, SP (Brazil); Mesquita, R.N. de, E-mail: rnavarro@ipen.br [Instituto de Pesquisas Energéticas e Nucleares (IPEN/CNEN – SP), Av. Professor Lineu Prestes 2242, 05508-000 São Paulo, SP (Brazil)

    2017-04-01

    Highlights: • A psychometric model to evaluate ‘safety climate’ at nuclear research facilities. • The model presented evidences of good psychometric qualities. • The model was applied to nuclear research facilities in Brazil. • Some ‘safety culture’ weaknesses were detected in the assessed organization. • A potential tool to develop safety management programs in nuclear facilities. - Abstract: A safe and reliable operation of nuclear power plants depends not only on technical performance, but also on the people and on the organization. Organizational factors have been recognized as the main causal mechanisms of accidents by research organizations through USA, Europe and Japan. Deficiencies related with these factors reveal weaknesses in the organization’s safety culture. A significant number of instruments to assess the safety culture based on psychometric models that evaluate safety climate through questionnaires, and which are based on reliability and validity evidences, have been published in health and ‘safety at work’ areas. However, there are few safety culture assessment instruments with these characteristics (reliability and validity) available on nuclear literature. Therefore, this work proposes an instrument to evaluate, with valid and reliable measures, the safety climate of nuclear research facilities. The instrument was developed based on methodological principles applied to research modeling and its psychometric properties were evaluated by a reliability analysis and validation of content, face and construct. The instrument was applied to an important nuclear research organization in Brazil. This organization comprises 4 research reactors and many nuclear laboratories. The survey results made possible a demographic characterization and the identification of some possible safety culture weaknesses and pointing out potential areas to be improved in the assessed organization. Good evidence of reliability with Cronbach's alpha

  12. Incineration of DOE offsite mixed waste at the Idaho National Engineering and Environmental Laboratory

    International Nuclear Information System (INIS)

    Harris, J.D.; Harvego, L.A.; Jacobs, A.M.; Willcox, M.V.

    1998-01-01

    The Waste Experimental Reduction Facility (WERF) incinerator at the Idaho National Engineering and Environmental Laboratory (INEEL) is one of three incinerators in the US Department of Energy (DOE) Complex capable of incinerating mixed low-level waste (MLLW). WERF has received MLLW from offsite generators and is scheduled to receive more. The State of Idaho supports receipt of offsite MLLW waste at the WERF incinerator within the requirements established in the (INEEL) Site Treatment Plan (STP). The incinerator is operating as a Resource Conservation and Recovery Act (RCRA) Interim Status Facility, with a RCRA Part B permit application currently being reviewed by the State of Idaho. Offsite MLLW received from other DOE facilities are currently being incinerated at WERF at no charge to the generator. Residues associated with the incineration of offsite MLLW waste that meet the Envirocare of Utah waste acceptance criteria are sent to that facility for treatment and/or disposal. WERF is contributing to the treatment and reduction of MLLW in the DOE Complex

  13. Cost calculations for decommissioning and dismantling of nuclear research facilities

    Energy Technology Data Exchange (ETDEWEB)

    Andersson, I. (Studsvik Nuclear AB (Sweden)); Backe, S. (Institute for Energy Technology (Norway)); Cato, A.; Lindskog, S. (Swedish Nuclear Power Inspectorate (Sweden)); Efraimsson, H. (Swedish Radiation Protection Authority (Sweden)); Iversen, Klaus (Danish Decommissioning (Denmark)); Salmenhaara, S. (VTT Technical Research Centre of Finland (Finland)); Sjoeblom, R. (Tekedo AB, (Sweden))

    2008-07-15

    Today, it is recommended that planning of decommission should form an integral part of the activities over the life cycle of a nuclear facility (planning, building and operation), but it was only in the nineteen seventies that the waste issue really surface. Actually, the IAEA guidelines on decommissioning have been issued as recently as over the last ten years, and international advice on finance of decommissioning is even younger. No general international guideline on cost calculations exists at present. This implies that cost calculations cannot be performed with any accuracy or credibility without a relatively detailed consideration of the radiological prerequisites. Consequently, any cost estimates based mainly on the particulars of the building structures and installations are likely to be gross underestimations. The present study has come about on initiative by the Swedish Nuclear Power Inspectorate (SKI) and is based on a common need in Denmark, Finland, Norway and Sweden. The content of the report may be briefly summarised as follows. The background covers design and operation prerequisites as well as an overview of the various nuclear research facilities in the four participating countries: Denmark, Finland, Norway and Sweden. The purpose of the work has been to identify, compile and exchange information on facilities and on methodologies for cost calculation with the aim of achieving an 80 % level of confidence. The scope has been as follows: 1) to establish a Nordic network 2) to compile dedicated guidance documents on radiological surveying, technical planning and financial risk identification and assessment 3) to compile and describe techniques for precise cost calculations at early stages 4) to compile plant and other relevant data A separate section is devoted in the report to good practice for the specific purpose of early but precise cost calculations for research facilities, and a separate section is devoted to techniques for assessment of cost

  14. Atmospheric Radiation Measurement Climate Research Facility Annual Report 2006

    Energy Technology Data Exchange (ETDEWEB)

    LR Roeder

    2005-11-30

    This annual report describes the purpose and structure of the ARM Climate Research Facility and ARM Science programs and presents key accomplishments in 2006. Noteworthy scientific and infrastructure accomplishments in 2006 include: • Collaborating with the Australian Bureau of Meteorology to lead the Tropical Warm Pool-International Cloud Experiment, a major international field campaign held in Darwin, Australia • Successfully deploying the ARM Mobile Facility in Niger, Africa • Developing the new ARM Aerial Vehicles Program (AVP) to provide airborne measurements • Publishing a new finding on the impacts of aerosols on surface energy budget in polar latitudes • Mitigating a long-standing double-Intertropical Convergence Zone problem in climate models using ARM data and a new cumulus parameterization scheme.

  15. Radiological Characterization and Final Facility Status Report Tritium Research Laboratory

    Energy Technology Data Exchange (ETDEWEB)

    Garcia, T.B.; Gorman, T.P.

    1996-08-01

    This document contains the specific radiological characterization information on Building 968, the Tritium Research Laboratory (TRL) Complex and Facility. We performed the characterization as outlined in its Radiological Characterization Plan. The Radiological Characterization and Final Facility Status Report (RC&FFSR) provides historic background information on each laboratory within the TRL complex as related to its original and present radiological condition. Along with the work outlined in the Radiological Characterization Plan (RCP), we performed a Radiological Soils Characterization, Radiological and Chemical Characterization of the Waste Water Hold-up System including all drains, and a Radiological Characterization of the Building 968 roof ventilation system. These characterizations will provide the basis for the Sandia National Laboratory, California (SNL/CA) Site Termination Survey .Plan, when appropriate.

  16. Radiological Characterization and Final Facility Status Report Tritium Research Laboratory

    International Nuclear Information System (INIS)

    Garcia, T.B.; Gorman, T.P.

    1996-08-01

    This document contains the specific radiological characterization information on Building 968, the Tritium Research Laboratory (TRL) Complex and Facility. We performed the characterization as outlined in its Radiological Characterization Plan. The Radiological Characterization and Final Facility Status Report (RC ampersand FFSR) provides historic background information on each laboratory within the TRL complex as related to its original and present radiological condition. Along with the work outlined in the Radiological Characterization Plan (RCP), we performed a Radiological Soils Characterization, Radiological and Chemical Characterization of the Waste Water Hold-up System including all drains, and a Radiological Characterization of the Building 968 roof ventilation system. These characterizations will provide the basis for the Sandia National Laboratory, California (SNL/CA) Site Termination Survey .Plan, when appropriate

  17. Thermal fuel research and development facilities in BNFL

    International Nuclear Information System (INIS)

    Roberts, V.A.; Vickers, J.

    1996-01-01

    BNFL is committed to providing high quality, cost effective nuclear fuel cycle services to customers on a National and International level. BNFL's services, products and expertise span the complete fuel cycle; from fuel manufacture through to fuel reprocessing, transport, waste management and decommissioning and the Company maintains its technical and commercial lead by investment in continued research and development (R and D). This paper discusses BNFL's involvement in R and D and gives an account of the current facilities available together with a description of the advanced R and D facilities constructed or planned at Springfields and Sellafield. It outlines the work being carried out to support the company fuel technology business, to (1) develop more cost effective routes to existing fuel products; (2) maximize the use of recycled uranium, plutonium and tails uranium and (3) support a successful MOX business

  18. Construction of a Solid State Research Facility, Building 3150

    International Nuclear Information System (INIS)

    1993-07-01

    The Department of Energy (DOE) proposes to construct a new facility to house the Materials Synthesis Group (MSG) and the Semiconductor Physics Group (SPG) of the Solid State Division, Oak Ridge National Laboratory (ORNL). The location of the proposed action is Roane County, Tennessee. MSG is involved in the study of crystal growth and the preparation and characterization of advanced materials, such as high-temperature superconductors, while SPG is involved in semiconductor physics research. All MSG and a major pardon of SPG research activities are now conducted in Building 2000, a deteriorating structure constructed in the 1940. The physical deterioration of the roof; the heating, ventilation, and air conditioning (HVAC) system; and the plumbing make this building inadequate for supporting research activities. The proposed project is needed to provide laboratory and office space for MSG and SPG and to ensure that research activities can continue without interruption due to deficiencies in the building and its associated utility systems

  19. The Crop Growth Research Chamber - A ground-based facility for CELSS research

    Science.gov (United States)

    Bubenheim, David L.; Luna, Phil M.; Wagenbach, Kimberly M.; Haslerud, Mark; Straight, Christian L.

    1989-01-01

    Crop Growth Research Chambers (CGRCs) are being developed as CELSS research facilities for the NASA/Ames Research Center. The history of the CGRC project is reviewed, noting the applications of CGRC research for the development of the Space Station. The CGRCs are designed for CELSS research and development, system control and integration, and flight hardware design and experimentation. The atmospheric and hydroponic environments of the CGRC system are described and the science requirements for CGRC environmental control are listed.

  20. Incineration technology for alpha-bearing radioactive waste in Germany

    International Nuclear Information System (INIS)

    Dirks, Friedlich; Pfeiffer, Reinhard

    1997-01-01

    Since 1971 the Karlsruhe Research Center has developed and operated plants for the incineration of radioactive waste. Three incineration plants for pure β/γ solid, α-bearing solid and radioactive liquid waste have been successfully utilized during last two decades. Recently more than 20 year-old β/γ plant was shut down with the economic point of view, mainly due to the recently reduced volume of burnable β/γ waste. Burnable β/γ solid waste is now being treated with α-bearing waste in a α solid incineration plant. The status of incineration technology for α-bearing waste and other radioactive waste treatment technologies, which are now utilized in Karlsruhe Research Center, such as conditioning of incineration ash, supercompaction, scrapping, and decontamination of solid radioactive waste, etc. are introduced in this presentation. Additionally, operational results of the recently installed new dioxin adsorber and fluidized-bed drier for scrubber liquid in α incineration plant are also described in this presentation. (author) 1 tab., 13 figs

  1. Training and research reactor facility longevity extension program

    International Nuclear Information System (INIS)

    Carriveau, G.W.

    1991-01-01

    Since 1943, over 550 training and research reactors have been in operation. According to statistics from the International Atomic Energy Agency, ∼325 training and research reactors are currently in service. This total includes a wide variety of designs covering a range of power and research capabilities located virtually around the world. A program has been established at General Atomics (GA) that is dedicated to the support of extended longevity of training and research reactor facilities. Aspects of this program include the following: (1) new instrumentation and control systems; (2) improved and upgraded nuclear monitoring and control channels; (3) facility testing, repair and upgrade services that include (a) pool or tank integrity, (b) cooling system, and (c) water purification system; (4) fuel element testing procedures and replacement; (5) control rod drive rebuilding and upgrades; (6) control and monitoring system calibration and repair service; (7) training services, including reactor operations, maintenance, instrumentation calibration, and repair; and (8) expanded or new uses such as neutron radiography and autoradiography, isotope production, nuclear medicine, activation analysis, and material properties modification

  2. ARM Climate Research Facility: Outreach Tools and Strategies

    Science.gov (United States)

    Roeder, L.; Jundt, R.

    2009-12-01

    Sponsored by the Department of Energy, the ARM Climate Research Facility is a global scientific user facility for the study of climate change. To publicize progress and achievements and to reach new users, the ACRF uses a variety of Web 2.0 tools and strategies that build off of the program’s comprehensive and well established News Center (www.arm.gov/news). These strategies include: an RSS subscription service for specific news categories; an email “newsletter” distribution to the user community that compiles the latest News Center updates into a short summary with links; and a Facebook page that pulls information from the News Center and links to relevant information in other online venues, including those of our collaborators. The ACRF also interacts with users through field campaign blogs, like Discovery Channel’s EarthLive, to share research experiences from the field. Increasingly, field campaign Wikis are established to help ACRF researchers collaborate during the planning and implementation phases of their field studies and include easy to use logs and image libraries to help record the campaigns. This vital reference information is used in developing outreach material that is shared in highlights, news, and Facebook. Other Web 2.0 tools that ACRF uses include Google Maps to help users visualize facility locations and aircraft flight patterns. Easy-to-use comment boxes are also available on many of the data-related web pages on www.arm.gov to encourage feedback. To provide additional opportunities for increased interaction with the public and user community, future Web 2.0 plans under consideration for ACRF include: evaluating field campaigns for Twitter and microblogging opportunities, adding public discussion forums to research highlight web pages, moving existing photos into albums on FlickR or Facebook, and building online video archives through YouTube.

  3. Research and test facilities for development of technologies and experiments with commercial applications

    Science.gov (United States)

    1989-01-01

    One of NASA'S agency-wide goals is the commercial development of space. To further this goal NASA is implementing a policy whereby U.S. firms are encouraged to utilize NASA facilities to develop and test concepts having commercial potential. Goddard, in keeping with this policy, will make the facilities and capabilities described in this document available to private entities at a reduced cost and on a noninterference basis with internal NASA programs. Some of these facilities include: (1) the Vibration Test Facility; (2) the Battery Test Facility; (3) the Large Area Pulsed Solar Simulator Facility; (4) the High Voltage Testing Facility; (5) the Magnetic Field Component Test Facility; (6) the Spacecraft Magnetic Test Facility; (7) the High Capacity Centrifuge Facility; (8) the Acoustic Test Facility; (9) the Electromagnetic Interference Test Facility; (10) the Space Simulation Test Facility; (11) the Static/Dynamic Balance Facility; (12) the High Speed Centrifuge Facility; (13) the Optical Thin Film Deposition Facility; (14) the Gold Plating Facility; (15) the Paint Formulation and Application Laboratory; (16) the Propulsion Research Laboratory; (17) the Wallops Range Facility; (18) the Optical Instrument Assembly and Test Facility; (19) the Massively Parallel Processor Facility; (20) the X-Ray Diffraction and Scanning Auger Microscopy/Spectroscopy Laboratory; (21) the Parts Analysis Laboratory; (22) the Radiation Test Facility; (23) the Ainsworth Vacuum Balance Facility; (24) the Metallography Laboratory; (25) the Scanning Electron Microscope Laboratory; (26) the Organic Analysis Laboratory; (27) the Outgassing Test Facility; and (28) the Fatigue, Fracture Mechanics and Mechanical Testing Laboratory.

  4. Incineration of hazardous and low-level radioactive waste by a small generator. Final report

    International Nuclear Information System (INIS)

    Dwight, C.C.

    1984-10-01

    The results from Arizona State University's study of the feasibility of a small generator incinerating low-level radioactive waste in a pathological incinerator are reported. The research included various aspects of environmental impact, public relations, cost versus benefit, and licensing procedures. Three years of work resulted in a license amendment authorizing the University to incinerate certain hazardous and low-level radioactive wastes. 13 references, 6 figures, 16 tables

  5. Dampak Pengolahan Limbah Padat Medis pada Petugas Incinerator di RSUP H. Adam Malik Tahun 2014

    OpenAIRE

    Darwin

    2016-01-01

    Adam Malik Central General Hospital causes some complaints from the incinerator operators such as wounded by spuit needles, wounded by broken glasses, and difficult to breathe because they inhale incinerator smoke or gas in the medical solid waste. Therefore, job safety and health in the hospital, especially in managing medical solid waste should be done. The research was qualitative which was aimed to analyze the effect of K3 (Job safety and health) n incinerator operators at H. Adam ...

  6. Neutron beam facilities at the Replacement Research Reactor, ANSTO

    International Nuclear Information System (INIS)

    Kim, S.

    2003-01-01

    The exciting development for Australia is the construction of a modern state-of-the-art 20-MW Replacement Research Reactor which is currently under construction to replace the aging reactor (HIFAR) at ANSTO in 2006. To cater for advanced scientific applications, the replacement reactor will provide not only thermal neutron beams but also a modern cold-neutron source moderated by liquid deuterium at approximately -250 deg C, complete with provision for installation of a hot-neutron source at a later stage. The latest 'supermirror' guides will be used to transport the neutrons to the Reactor Hall and its adjoining Neutron Guide Hall where a suite of neutron beam instruments will be installed. These new facilities will expand and enhance ANSTO's capabilities and performance in neutron beam science compared with what is possible with the existing HIFAR facilities, and will make ANSTO/Australia competitive with the best neutron facilities in the world. Eight 'leading-edge' neutron beam instruments are planned for the Replacement Research Reactor when it goes critical in 2006, followed by more instruments by 2010 and beyond. Up to 18 neutron beam instruments can be accommodated at the Replacement Research Reactor, however, it has the capacity for further expansion, including potential for a second Neutron Guide Hall. The first batch of eight instruments has been carefully selected in conjunction with a user group representing various scientific interests in Australia. A team of scientists, engineers, drafting officers and technicians has been assembled to carry out the Neutron Beam Instrument Project to successful completion. Today, most of the planned instruments have conceptual designs and are now being engineered in detail prior to construction and procurement. A suite of ancillary equipment will also be provided to enable scientific experiments at different temperatures, pressures and magnetic fields. This paper describes the Neutron Beam Instrument Project and gives

  7. A Tether-Based Variable-Gravity Research Facility Concept

    Science.gov (United States)

    Sorensen, Kirk

    2006-01-01

    The recent announcement of a return to the Moon and a mission to Mars has made the question of human response to lower levels of gravity more important. Recent advances in tether technology spurred by NASA s research in MXER tethers has led to a re-examination of the concept of a variable-gravity research facility (xGRF) for human research in low Earth orbit. Breakthroughs in simplified inertial tracking have made it possible to consider eliminating the despun section of previous designs. This, in turn, improves the prospect of a facility based entirely around a tether, with the human module on one end and a countermass on the other. With such a configuration, propellantless spinup and spindown is also possible based on the conservation of angular momentum from a gravity-gradient configuration to a spinning configuration. This not only saves large amounts of propellant but vastly simplifies crew and consumable resupply operations, since these can now be done in a microgravity configuration. The importance of the science to be obtained and the performance improvements in this new design argue strongly for further investigation.

  8. 14MeV facility and research in IPPE

    International Nuclear Information System (INIS)

    Simakov, S.P.; Androsenko, A.A.; Androsenko, P.A.; Devkin, B.V.; Kobozev, M.G.; Lychagin, A.A.; Sinitca, V.V.; Talalaev, V.A.; Chuvilin, D.Yu.; Borisov, A.A.; Zagryadsky, V.A.

    1993-07-01

    Review of experimental facility and research, performed at 14MeV incident neutron energy in the Institute of Physics and Power Engineering, are given. These studies cover the next topics: double differential neutron emission cross sections (DDX), neutron-gamma coincidence experiments (n, n'γ) and neutron leakage spectra for spherical assemblies (benchmark). The paper contains description and main parameters of pulsed neutron generator KG-0.3, fast neutron time of flight spectrometer, measuring and data reduction procedures, review of experimental data. Results of experiments are compared with other data; evaluated data files BROND-2, ENDF/B6, JENDL-3; basic theoretical and transport model calculations. (author)

  9. Nuclear Security Management for Research Reactors and Related Facilities

    International Nuclear Information System (INIS)

    2016-03-01

    This publication provides a single source guidance to assist those responsible for the implementation of nuclear security measures at research reactors and associated facilities in developing and maintaining an effective and comprehensive programme covering all aspects of nuclear security on the site. It is based on national experience and practices as well as on publications in the field of nuclear management and security. The scope includes security operations, security processes, and security forces and their relationship with the State’s nuclear security regime. The guidance is provided for consideration by States, competent authorities and operators

  10. Waste treatment activities incineration

    International Nuclear Information System (INIS)

    Weber, D.A.

    1985-01-01

    The waste management policy at SRP is to minimize waste generation as much as possible and detoxify and/or volume reduce waste materials prior to disposal. Incineration is a process being proposed for detoxification and volume reduction of combustion nonradioactive hazardous, low-level mixed and low-level beta-gamma waste. Present operation of the Solvent Burner Demonstration reduces the amount of solid combustible low-level beta-gamma boxed waste disposed of by shallow land burial by approximately 99,000 ft 3 per year producing 1000 ft 3 per year of ash and, by 1988, will detoxify and volume reduce 150,000 gallons or organic Purex solvent producing approximately 250 ft 3 of ash per year

  11. Disposal of waste or excess high explosives. Final report. [Incineration

    Energy Technology Data Exchange (ETDEWEB)

    1977-01-01

    The ''Disposal of Waste or Excess High Explosives'' project began January 1971. Various methods of disposal were investigated with the conclusion that incineration, at major ERDA facilities, would be the most feasible and safest method with the least cost and development time required. Two independent incinerator concepts were investigated: a rotary type for continuous processing and an enclosed pit type for batch processing. Both concepts are feasible; however, it is recommended that further investigations would be required to render them acceptable. It is felt that a larger effort would be required in the case of the rotary incinerator. The project was terminated (December 1976) prior to completion as a result of a grant of authority by the Texas Air Control Board allowing the ERDA Pantex Plant to continue indefinitely outdoor burning of explosives.

  12. Operation of a pilot incinerator for solid waste

    International Nuclear Information System (INIS)

    Hootman, H.E.; Trapp, D.J.; Warren, J.H.

    1979-01-01

    A laboratory-scale incinerator (0.5 kg waste/hr) was built and operated for more than 18 months as part of a program to adapt and confirm technology for incineration of Savannah River Plant solid wastes, which are contaminated with about 0.3 Ci/kg of alpha-emitting transuranium (TRU) nuclides (Slide 1). About 4000 packages of simulated nonradioactive wastes were burned, including HEPA (high-efficiency particulate air) filters, resins, and other types of solid combustible waste from plutonium finishing operations. Throughputs of more than 3 kg/hr for periods up to 4 hours were demonstrated. The incinerator was oerated at temperatures above 750 0 C for more than 7700 hours during a period of 12 months, for an overall availability of 88%. The incinerator was shut down three times during the year: once to replace the primary combustion chamber electrical heater, and twice to replace oxidized electrical connectors to the secondary chamber heaters. Practical experience with this pilot facility provided the design basis for the full-size (5 kg waste/hr) nonradioactive test incinerator, which began operation in March 1979

  13. Decommissioning of Medical, Industrial and Research Facilities. Safety Guide

    International Nuclear Information System (INIS)

    2010-01-01

    Radioactive waste is produced in the generation of nuclear power and the use of radioactive materials in industry, research and medicine. The importance of the safe management of radioactive waste for the protection of human health and the environment has long been recognized, and considerable experience has been gained in this field. The IAEA's Radioactive Waste Safety Standards Programme aimed at establishing a coherent and comprehensive set of principles and requirements for the safe management of waste and formulating the guidelines necessary for their application. This is accomplished within the IAEA Safety Standards Series in an internally consistent set of publications that reflect an international consensus. The publications will provide Member States with a comprehensive series of internationally agreed publications to assist in the derivation of, and to complement, national criteria, standards and practices. The Safety Standards Series consists of three categories of publications: Safety Fundamentals, Safety Requirements and Safety Guides. With respect to the Radioactive Waste Safety Standards Programme, the set of publications is currently undergoing review to ensure a harmonized approach throughout the Safety Standards Series. This Safety Guide addresses the subject of decommissioning of medical, industrial and research facilities where radioactive materials and sources are produced, received, used and stored. It is intended to provide guidance to national authorities and operating organizations, particularly to those in developing countries (as such facilities are predominant in these countries), for the planning and safe management of the decommissioning of such facilities. The Safety Guide has been prepared through a series of Consultants meetings and a Technical Committee meeting

  14. Decommissioning of medical, industrial and research facilities. Safety guide

    International Nuclear Information System (INIS)

    2005-01-01

    Radioactive waste is produced in the generation of nuclear power and the use of radioactive materials in industry, research and medicine. The importance of the safe management of radioactive waste for the protection of human health and the environment has long been recognized, and considerable experience has been gained in this field. The IAEA's Radioactive Waste Safety Standards Programme aimed at establishing a coherent and comprehensive set of principles and requirements for the safe management of waste and formulating the guidelines necessary for their application. This is accomplished within the IAEA Safety Standards Series in an internally consistent set of publications that reflect an international consensus. The publications will provide Member States with a comprehensive series of internationally agreed publications to assist in the derivation of, and to complement, national criteria, standards and practices. The Safety Standards Series consists of three categories of publications: Safety Fundamentals, Safety Requirements and Safety Guides. With respect to the Radioactive Waste Safety Standards Programme, the set of publications is currently undergoing review to ensure a harmonized approach throughout the Safety Standards Series. This Safety Guide addresses the subject of decommissioning of medical, industrial and research facilities where radioactive materials and sources are produced, received, used and stored. It is intended to provide guidance to national authorities and operating organizations, particularly to those in developing countries (as such facilities are predominant in these countries), for the planning and safe management of the decommissioning of such facilities. The Safety Guide has been prepared through a series of Consultants meetings and a Technical Committee meeting

  15. The starting up of a pilot plant for radioactive incinerator ash conditioning - results of two embedding campaigns

    International Nuclear Information System (INIS)

    Kertesz, C.J.; Chenavas, P.R.; Naud, G.M.

    1990-01-01

    A new pilot plant called 'PICC' designed for radioactive incinerator ash conditioning, by embedding in several matrices, was launched at the Nuclear Research Centre in Cadarache - France - in the middle of 1988. This polyvalent facility can work with the three following embedding products = cement, thermosetting epoxide resin and an epoxide-cement compound. The capacity per day of the plant is two 100 or 200 I drums of solidified ash form. Two embedding campaigns have been carried out on inactive ashes: the first is a cementation campaign, done on phosphated ash coming from incineration of spent tributylphosphate. The second is a polymer cement campaign done on simulated alpha ash coming from technological wastes. Description of the PICC and data on these two campaigns are given

  16. Conditioning processes for incinerator ashes

    International Nuclear Information System (INIS)

    Jouan, A.; Ouvrier, N.; Teulon, F.

    1990-01-01

    Three conditioning processes for alpha-bearing solid waste incineration ashes were investigated and compared according to technical and economic criteria: isostatic pressing, cold-crucible direct-induction melting and cement-resin matrix embedding

  17. Quality Assurance of ARM Program Climate Research Facility Data

    Energy Technology Data Exchange (ETDEWEB)

    Peppler, RA; Kehoe, KE; Sonntag, KL; Bahrmann, CP; Richardson, SJ; Christensen, SW; McCord, RA; Doty, DJ; Wagener, Richard [BNL; Eagan, RC; Lijegren, JC; Orr, BW; Sisterson, DL; Halter, TD; Keck, NN; Long, CN; Macduff, MC; Mather, JH; Perez, RC; Voyles, JW; Ivey, MD; Moore, ST; Nitschke, DL; Perkins, BD; Turner, DD

    2008-03-01

    This report documents key aspects of the Atmospheric Radiation Measurement (ARM) Climate Research Facility (ACRF) data quality assurance program as it existed in 2008. The performance of ACRF instruments, sites, and data systems is measured in terms of the availability, usability, and accessibility of the data to a user. First, the data must be available to users; that is, the data must be collected by instrument systems, processed, and delivered to a central repository in a timely manner. Second, the data must be usable; that is, the data must be inspected and deemed of sufficient quality for scientific research purposes, and data users must be able to readily tell where there are known problems in the data. Finally, the data must be accessible; that is, data users must be able to easily find, obtain, and work with the data from the central repository. The processes described in this report include instrument deployment and calibration; instrument and facility maintenance; data collection and processing infrastructure; data stream inspection and assessment; the roles of value-added data processing and field campaigns in specifying data quality and haracterizing the basic measurement; data archival, display, and distribution; data stream reprocessing; and engineering and operations management processes and procedures. Future directions in ACRF data quality assurance also are presented.

  18. Brain Cancer in Workers Employed at a Laboratory Research Facility.

    Directory of Open Access Journals (Sweden)

    James J Collins

    Full Text Available An earlier study of research facility workers found more brain cancer deaths than expected, but no workplace exposures were implicated.Adding four additional years of vital-status follow-up, we reassessed the risk of death from brain cancer in the same workforce, including 5,284 workers employed between 1963, when the facility opened, and 2007. We compared the work histories of the brain cancer decedents in relationship to when they died and their ages at death.As in most other studies of laboratory and research workers, we found low rates of total mortality, total cancers, accidents, suicides, and chronic conditions such as heart disease and diabetes. We found no new brain cancer deaths in the four years of additional follow-up. Our best estimate of the brain cancer standardized mortality ratio (SMR was 1.32 (95% confidence interval [95% CI] 0.66-2.37, but the SMR might have been as high as 1.69. Deaths from benign brain tumors and other non-malignant diseases of the nervous system were at or below expected levels.With the addition of four more years of follow-up and in the absence of any new brain cancers, the updated estimate of the risk of brain cancer death is smaller than in the original study. There was no consistent pattern among the work histories of decedents that indicated a common causative exposure.

  19. Quality Assurance of ARM Program Climate Research Facility Data

    International Nuclear Information System (INIS)

    Peppler, R.A.; Kehoe, K.E.; Sonntag, K.L.; Bahramann, C.P.; Richardson, S.J.; Christensen, S.W.; McCord, R.A.; Doty, D.J.; Wagener, R.; Eagan, R.C.; Lijegren, J.C.; Orr, B.W.; Sisterson, D.L.; Halter, T.D.; Keck, N.N.; Long, C.N.; Macduff, M.C.; Mather, J.H.; Perez, R.C.; Voyles, J.W.; Ivey, M.D.; Moore, S.T.; Nitschke, D.L.; Perkins, B.D.; Turner, D.D.

    2008-01-01

    This report documents key aspects of the Atmospheric Radiation Measurement (ARM) Climate Research Facility (ACRF) data quality assurance program as it existed in 2008. The performance of ACRF instruments, sites, and data systems is measured in terms of the availability, usability, and accessibility of the data to a user. First, the data must be available to users; that is, the data must be collected by instrument systems, processed, and delivered to a central repository in a timely manner. Second, the data must be usable; that is, the data must be inspected and deemed of sufficient quality for scientific research purposes, and data users must be able to readily tell where there are known problems in the data. Finally, the data must be accessible; that is, data users must be able to easily find, obtain, and work with the data from the central repository. The processes described in this report include instrument deployment and calibration; instrument and facility maintenance; data collection and processing infrastructure; data stream inspection and assessment; the roles of value-added data processing and field campaigns in specifying data quality and characterizing the basic measurement; data archival, display, and distribution; data stream reprocessing; and engineering and operations management processes and procedures. Future directions in ACRF data quality assurance also are presented

  20. Research studies performed using the Cairo Fourier Diffractometer Facility

    International Nuclear Information System (INIS)

    Maayouf, R.M.A.; Ridikas, D.

    2009-12-01

    This report represents the results of the research studies performed using the Cairo Fourier Diffractometer Facility (CFDF), within 10 years after it was installed and put into operation at the beginning of 1996. The main components of the CFDF were supplied by the IAEA according to the technical assistance project EGY/1/022 'Upgrading of Research Reactor Utilization'. The present report is the second published INDC report, while the first one, published at the beginning of 1997, was about the performance of the CFDF and its main characteristic parameters. Plenty of measurements were performed since then, yielding several publications both in local and international scientific periodicals and resulting in 8 M.Sc. and Ph.D. degrees from Egyptian Universities. In addition, a new approach for the analysis of the neutron spectra was implemented using the CFDF. Specially designed interface card with proper software program was applied instead of the reverse time of flight (RTOF) and Finnish made analyzer originally attached to the facility. It has been verified that the new approach can successfully replace the RTOF analyzer, significantly decreasing the time of measurement and saving the reactor's operation time. Besides, a special fault diagnostic system program was developed and tested for caring and handling the possible failures of the CFDF. Moreover, measurements were carried out for the diffraction spectra emitted at different points of one of the samples. The latter was scanned across the neutron beam of the CFDF, for studying the stress after welding; used in industrial applications. (author)

  1. Brookhaven National Laboratory's Accelerator Test Facility: research highlights and plans

    Science.gov (United States)

    Pogorelsky, I. V.; Ben-Zvi, I.

    2014-08-01

    The Accelerator Test Facility (ATF) at Brookhaven National Laboratory has served as a user facility for accelerator science for over a quarter of a century. In fulfilling this mission, the ATF offers the unique combination of a high-brightness 80 MeV electron beam that is synchronized to a 1 TW picosecond CO2 laser. We unveil herein our plan to considerably expand the ATF's floor space with an upgrade of the electron beam's energy to 300 MeV and the CO2 laser's peak power to 100 TW. This upgrade will propel the ATF even further to the forefront of research on advanced accelerators and radiation sources, supporting the most innovative ideas in this field. We discuss emerging opportunities for scientific breakthroughs, including the following: plasma wakefield acceleration studies in research directions already active at the ATF; laser wakefield acceleration (LWFA), where the longer laser wavelengths are expected to engender a proportional increase in the beam's charge while our linac will assure, for the first time, the opportunity to undertake detailed studies of seeding and staging of the LWFA; proton acceleration to the 100-200 MeV level, which is essential for medical applications; and others.

  2. SCARF - The Swarm Satellite Constellation Application and Research Facility

    DEFF Research Database (Denmark)

    Olsen, Nils

    2014-01-01

    Swarm, a three-satellite constellation to study the dynamics of the Earth's magnetic field and its interactions with the Earth system, has been launched in November 2013. The objective of the Swarm mission is to provide the best ever survey of the geomagnetic field and its temporal evolution, which...... will bring new insights into the Earth system by improving our understanding of the Earth's interior and environment. In order to take advantage of the unique constellation aspect of Swarm, considerably advanced data analysis tools have been developed. Scientific users will also benefit significantly from...... derived products, the so-called Level-2 products, that take into account the features of the constellation. The Swarm SCARF (Satellite Constellation Application and Research Facility), a consortium of several research institutions, has been established with the goal of deriving Level-2 products...

  3. Activated carbon for incinerator uses

    International Nuclear Information System (INIS)

    Che Seman Mahmood; Norhayati Alias; Mohd Puad Abu

    2002-01-01

    This paper reports the development of the activated carbon from palm oil kernel shell for use as absorbent and converter for incinerator gas. The procedure is developed in order to prepare the material in bulk quantity and be used in the incinerator. The effect of the use of activating chemicals, physical activation and the preparation parameter to the quality of the carbon products will be discussed. (Author)

  4. Volume reduction of low- and medium-level waste by incineration/calcination

    International Nuclear Information System (INIS)

    Buzonniere, A. de; Gauthey, J.C.

    1993-01-01

    Nuclear installations generate large quantities of low- and medium-level radwaste. This waste comes from various installations in the fuel cycle, reactor operation, research institute, hospitals, nuclear plate dismantling, etc.. TECHNICATOME did the project development work for the incineration plant of PIERRELATE (France) on behalf of COGEMA (Compagnie Generale des d'Etudes Technique). This plant has been in active service since November 1987. In addition, TECHNICATOME was in charge of the incinerator by a turnkey contract. This incinerator was commissioned in 1992. For a number of years, TECHNICATOME has been examining, developing and producing incineration and drying/calcination installations. They are used for precessing low- and medium-level radwaste

  5. Cold Neutron Research Facility begins operating at NIST

    International Nuclear Information System (INIS)

    Zeman, E.J.

    1991-01-01

    Steady-state neutron beams are generally produced by fission in a nuclear reactor, whereas pulsed beams come from spallation neutron sources. Beams from a reactor have a distribution of wavelengths that is roughly Maxwellian, with a peak wavelength that depends on the temperature of the moderator that surrounds the fuel. Cold neutrons can be selected from the low-energy tail of the distribution, but the flux drops as 1/λ 4 . However, by shifting the whole spectrum to longer wavelengths one can dramatically increase the cold neutron flux. This is achieved by replacing part of the core moderator with a cold moderator, or 'cold source,' such as liquid deuterium (at about 30 K) or D 2 O ice (at about 40 K). Neutrons lose energy to the moderator through collisions, producing a shifted spectrum from which one can select lower-energy neutrons with a roughly ten-fold improvement in the flux. Neutrons exhibit optical behavior such as refraction and total reflection. Thus one can use neutron guides - analogous to optical fibers - to conduct intense beams of neutrons from the reactor into a large experimental hall, dubbed a 'guide hall,' where background radiation is low. The Cold Neutron Research Facility was finally funded in 1987 and opened its doors this past June. CNRF is located at the 20-MW NIST research reactor, which began continuous operation in 1969. With some foresight, the designers of the original reactor allowed space for the addition of a cryogenic moderator, which is only now being exploited. NIST will develop 10 experimental stations for use by the research science community. Additional help in financing the facility comes from participating research teams made up of groups from industry, academe and government

  6. CSU's MWV Observatory: A Facility for Research, Education and Outreach

    Science.gov (United States)

    Hood, John; Carpenter, N. D.; McCarty, C. B.; Samford, J. H.; Johnson, M.; Puckett, A. W.; Williams, R. N.; Cruzen, S. T.

    2014-01-01

    The Mead Westvaco Observatory (MWVO), located in Columbus State University's Coca-Cola Space Science Center, is dedicated to education and research in astronomy through hands-on engagement and public participation. The MWVO has recently received funding to upgrade from a 16-inch Meade LX-200 telescope to a PlaneWave CDK 24-inch Corrected Dall-Kirkham Astrograph telescope. This and other technological upgrades will allow this observatory to stream live webcasts for astronomical events, allowing a worldwide public audience to become a part of the growing astronomical community. This poster will explain the upgrades that are currently in progress as well as the results from the current calibrations. The goal of these upgrades is to provide facilities capable of both research-class projects and widespread use in education and public outreach. We will present our initial calibration and tests of the observatory equipment, as well as its use in webcasts of astronomical events, in solar observing through the use of specialized piggy-backed telescopes, and in research into such topics as asteroids, planetary and nebula imaging. We will describe a pilot research project on asteroid orbit refinement and light curves, to be carried out by Columbus State University students. We will also outline many of the K-12 educational and public outreach activities we have designed for these facilities. Support and funding for the acquisition and installation of the new PlaneWave CDK 24 has been provided by the International Museum and Library Services via the Museums for America Award.

  7. LLNL/UC AMS facility and research program

    Science.gov (United States)

    Davis, J. C.; Proctor, I. D.; Southon, J. R.; Caffee, M. W.; Heikkinen, D. W.; Roberts, M. L.; Moore, T. L.; Turteltaub, K. W.; Nelson, D. E.; Loyd, D. H.; Vogel, J. S.

    1990-12-01

    The Lawrence Livermore National Laboratory (LLNL) and the University of California (UC) now have in operation a large AMS spectrometer built as part of a new multiuser laboratory centered on an FN tandem. AMS measurements are expected to use half of the beam time of the accelerator. LLNL use of AMS is in research on consequences of energy usage. Examples include global warming, geophysical site characterization, radiation biology and dosimetry, and study of mutagenic and carcinogenic processes. UC research activities are in clinical applications, archaeology and anthropology, oceanography, and geophysical and geochemical research. Access is also possible for researchers outside the UC system. The technological focus of the laboratory is on achieving high rates of sample throughput, unattended operation, and advances in sample preparation methods. Because of the expected growth in the research programs and the other obligations of the present accelerator, we are designing a follow-on dedicated facility for only AMS and microprobe analysis that will contain at least two accelerators with multiple spectrometers.

  8. Desiccant contamination research: Report on the desiccant contamination test facility

    Energy Technology Data Exchange (ETDEWEB)

    Pesaran, A.A.; Bingham, C.E.

    1991-07-01

    The activity in the cooling systems research involves research on high performance dehumidifiers and chillers that can operate efficiently with the variable thermal outputs and delivery temperatures associated with solar collectors. It also includes work on advanced passive cooling techniques. This report describes the work conducted to improve the durability of solid desiccant dehumidifiers by investigating the causes of degradation of desiccant materials from airborne contaminants and thermal cycling. The performance of a dehumidifier strongly depends on the physical properties and durability of the desiccant material. To make durable and reliable dehumidifiers, an understanding is needed of how and to what degree the performance of a dehumidifier is affected by desiccant degradation. This report, an account of work under Cooling Systems Research, documents the efforts to design and fabricate a test facility to investigate desiccant contamination based on industry and academia recommendations. It also discusses the experimental techniques needed for obtaining high-quality data and presents plans for next year. Researchers of the Mechanical and Industrial Technology Division performed this work at the Solar Energy Research Institute in FY 1988 for DOE's Office of Solar Heat Technologies. 7 refs., 19 figs., 1 tab.

  9. Overview of NSTX Facility Upgrades Status and Research Plans

    Science.gov (United States)

    Ono, M.

    2012-10-01

    The National Spherical Torus eXperiment (NSTX) is undergoing a major facility upgrade. The major mission of NSTX-U is to develop physics basis for an ST-based Fusion Nuclear Science Facility (FNSF). The ST-based FNSF has a promise of achieving high neutron fluence needed for reactor component testing with a relatively modest tritium consumption. At the same time, the unique operating regimes of NSTX-U provide high leverage to address several important issues in the physics of burning plasmas to optimize the performance of ITER. The NSTX-U program further aims to determine the attractiveness of the compact ST for addressing key research needs on the path toward a fusion demonstration power plant (Demo). The upgrade project will double the toroidal field, plasma current, and NBI heating power and increase the pulse length from 1-1.5s to 5-8s. More tangential NBI system is designed to attain full non-inductive operation. Innovative plasma start-up and ramp-up techniques without the central solenoid operation which is needed for a compact FNSF design will be explored. With higher fields and heating power, the NSTX-U plasma collisionality will be reduced by a factor of 3-6 to help explore the transport trend toward the low collisionality regimes expected in FNSF, ITER, and Demo.

  10. Research and Development Program for the PALS Facility

    International Nuclear Information System (INIS)

    Jungwirth, K.

    2001-01-01

    Status of the PALS laser system is given and its upgrades implemented up to now as well as those under preparation are also described. During the first year run the PALS facility has proved to be a reliable tool for generating plasmas by using infrared (1315 nm) 0,4-ns laser pulses, with the energy adjustable over two orders of magnitude ( 10 J - 1 kJ). The current PALS research program concentrates along the following two main lines: development and application of (1) laser driven x-ray sources, including the x-ray lasers, and (2) of laser driven ion sources. Simultaneously, new methods of x-ray diagnostics, of soft x-ray detection and x-ray spectroscopy in particular, are being developed and implemented. During the period September 2000 - June 2001, most of the experiments at PALS have been performed within the EC th FP. Towards the end of this period an x-ray laser on Zn (λ =21.2 nm) has been successfully put into operation and used for interferometric measurements in cooperation with the French colleagues. More detailed information about some of the results briefly summarized in the paper is presented at the Symposium via separate oral papers and posters, too. Experience of the first year of operation is essential also for further upgrading of the PALS facility towards higher power outputs. (author)

  11. The development of a Space Shuttle Research Animal Holding Facility

    Science.gov (United States)

    Jagow, R. B.

    1980-01-01

    The ability to maintain the well being of experiment animals is of primary importance to the successful attainment of life sciences flight experiment goals. To assist scientists in the conduct of life sciences flight experiments, a highly versatile Research Animal Holding Facility (RAHF) is being developed for use on Space Shuttle/Spacelab missions. This paper describes the design of the RAHF system, which in addition to providing general housing for various animal species, approximating the environment found in ground based facilities, is designed to minimize disturbances of the specimens by vehicle and mission operations. Life-sustaining capabilities such as metabolic support and environmental control are provided. RAHF is reusable and is a modular concept to accommodate animals of different sizes. The basic RAHF system will accommodate a combination of 24 500-g rats or 144 mice or a mixed number of rats and mice. An alternative design accommodates four squirrel monkeys. The entire RAHF system is housed in a single ESA rack. The animal cages are in drawers which are removable for easy access to the animals. Each cage contains a waste management system, a feeding system and a watering system all of which will operate in zero or one gravity.

  12. Atmospheric Radiation Measurement Climate Research Facility (ACRF) Annual Report 2008

    Energy Technology Data Exchange (ETDEWEB)

    LR Roeder

    2008-12-01

    The Importance of Clouds and Radiation for Climate Change: The Earth’s surface temperature is determined by the balance between incoming solar radiation and thermal (or infrared) radiation emitted by the Earth back to space. Changes in atmospheric composition, including greenhouse gases, clouds, and aerosols, can alter this balance and produce significant climate change. Global climate models (GCMs) are the primary tool for quantifying future climate change; however, there remain significant uncertainties in the GCM treatment of clouds, aerosol, and their effects on the Earth’s energy balance. In 1989, the U.S. Department of Energy (DOE) Office of Science created the Atmospheric Radiation Measurement (ARM) Program to address scientific uncertainties related to global climate change, with a specific focus on the crucial role of clouds and their influence on the transfer of radiation in the atmosphere. To reduce these scientific uncertainties, the ARM Program uses a unique twopronged approach: • The ARM Climate Research Facility, a scientific user facility for obtaining long-term measurements of radiative fluxes, cloud and aerosol properties, and related atmospheric characteristics in diverse climate regimes; and • The ARM Science Program, focused on the analysis of ACRF and other data to address climate science issues associated with clouds, aerosols, and radiation, and to improve GCMs. This report provides an overview of each of these components and a sample of achievements for each in fiscal year (FY) 2008.

  13. Neutron beam facilities at the Australian Replacement Research Reactor

    International Nuclear Information System (INIS)

    Kennedy, Shane; Robinson, Robert; Hunter, Brett

    2001-01-01

    Australia is building a research reactor to replace the HIFAR reactor at Lucas Heights by the end of 2005. Like HIFAR, the Replacement Research Reactor will be multipurpose with capabilities for both neutron beam research and radioisotope production. It will be a pool-type reactor with thermal neutron flux (unperturbed) of 4 x 10 14 n/cm 2 /sec and a liquid D 2 cold neutron source. Cold and thermal neutron beams for neutron beam research will be provided at the reactor face and in a large neutron guide hall. Supermirror neutron guides will transport cold and thermal neutrons to the guide hall. The reactor and the associated infrastructure, with the exception of the neutron beam instruments, is to be built by INVAP S.E. under contract. The neutron beam instruments will be developed by ANSTO, in consultation with the Australian user community. This status report includes a review the planned scientific capabilities, a description of the facility and a summary of progress to date. (author)

  14. Anti- and Hypermatter Research at the Facility for Antiproton and Ion Research FAIR

    International Nuclear Information System (INIS)

    Steinheimer, J; Xu, Z; Gudima, K; Botvina, A; Mishustin, I; Bleicher, M; Stöcker, H

    2012-01-01

    Within the next six years, the Facility for Antiproton and Ion Research (FAIR) is built adjacent to the existing accelerator complex of the GSI Helmholtz Center for Heavy Ion Research at Darmstadt, Germany. Thus, the current research goals and the technical possibilities are substantially expanded. With its worldwide unique accelerator and experimental facilities, FAIR will provide a wide range of unprecedented fore-front research in the fields of hadron, nuclear, atomic, plasma physics and applied sciences which are summarized in this article. As an example this article presents research efforts on strangeness at FAIR using heavy ion collisions, exotic nuclei from fragmentation and antiprotons to tackle various topics in this area. In particular, the creation of hypernuclei and antimatter is investigated.

  15. ARM Climate Research Facility Quarterly Value-Added Product Report

    Energy Technology Data Exchange (ETDEWEB)

    Sivaraman, C. [DOE ARM Climate Research Facility, Washington, DC (United States)

    2016-10-01

    The purpose of this report is to provide a concise status update for Value-Added Products (VAPs) implemented by the Atmospheric Radiation Measurement (ARM) Climate Research Facility. The report is divided into the following sections: (1) new VAPs for which development has begun; (2) progress on existing VAPs; (3) future VAPs that have been recently approved; (4) other work that leads to a VAP; (5) top requested VAPs from the ARM Data Archive; and (6) a summary of VAP and data releases to production and evaluation. New information is highlighted in blue text. New information about processed data by the developer is highlighted in red text. The upcoming milestones and dates are highlighted in green.

  16. The International Space University's variable gravity research facility design

    Science.gov (United States)

    Bailey, Sheila G.; Chiaramonte, Francis P.; Davidian, Kenneth J.

    1991-09-01

    A manned mission to Mars will require long travel times between Earth and Mars. However, exposure to long-duration zero gravity is known to be harmful to the human body. Some of the harmful effects are loss of heart and lung capacity, inability to stand upright, muscular weakness and loss of bone calcium. A variable gravity research facility (VGRF) that would be placed in low Earth orbit (LEO) was designed by students of the International Space University 1989 Summer Session held in Strasbourg, France, to provide a testbed for conducting experiments in the life and physical sciences in preparation for a mission to Mars. This design exercise was unique because it addressed all aspects concerning a large space project. The VGRF design was described which was developed by international participants specializing in the following areas: the politics of international cooperation, engineering, architecture, in-space physiology, material and life science experimentation, data communications, business, and management.

  17. Irradiation facilities for materials research: IFMIF and small scale installations

    International Nuclear Information System (INIS)

    Perlado, J. M.; Victoria, M.

    2007-01-01

    The research of advance materials in nuclear fields such as new fission reactors (Generation-IV), Accelerator Driven Systems for Transmutation of Radioactive Wastes and Nuclear Fusion, is becoming very much common in the types of low activation and radiation resistant Materials. Ferritic-Martensitic Steels (based in 9-12 Cr) with or without Oxide Dispersion Techniques (Ytria Nanoparticles), Composites materials are becoming the new generation to answer requirements of high temperature, high radiation resistance of structural materials. Special dedication is appearing in general research programmes to this area of Materials. The understanding of their final performance needs a wider knowledge of the mechanisms of radiation damage in these materials from the atomistic scale to the macroscopic responses. New extensive campaigns are being funded to irradiate from simple elements to model alloys and finally the complex materials themselves. That sequence and its state of art will be presented One clear technique for that understanding is the Multi scale Modelling which includes simulation techniques from quantum mechanics, molecular dynamics, defects diffusion, mesoscopic modelling and finally the macroscopic constitutive relations for macroscopic analysis. However, in each one of these steps is necessary a systematic and well established program of experiments that combines the irradiation and the very detailed analysis with techniques such as Transmission Electron Microscope, Positron Annihilation, SIMS, Atom Probe, Nanoindebntation. A key aspect that wants to be presented in this work is the state of art and discussion of Irradiation Facilities for Materials studies. Those facilities goes from ion implantation sources, small accelerator, Experimental Reactors such High Flux Reactor, sophisticated Triple Beams Sources as JANNUS in France to generate at the same time displacements-hydrogen-helium, and projected very large neutron installation such as IFMIF. The role to

  18. Radiation protection planning for decommissioning of research reactor facilities

    International Nuclear Information System (INIS)

    Jackson, Roger; Harman, Neil; Craig, David; Fecitt, Lorna; Lobach, Yuri; Gorlinskij, Juri; Kolyadin, Vyacheslav; Pavlenko, Vytali

    2008-01-01

    The MR reactor at the Russian Research Centre Kurchatov Institute (RRCKI), Moscow was a 50 MW multipurpose material testing and research reactor equipped with nine experimental loop facilities to test prototype fuel for various nuclear power reactors being developed. The reactor was shut down in 1993 and de-fuelled. The experimental loops are located in basement rooms around the reactor. The nature of the research into the characteristics of fuel design and coolant chemistry resulted in fission products and activation products in the test loop equipment. Decommissioning of the loops therefore presents a number of challenges. In addition the city of Moscow has expanded such that the RRC KI is now surrounded by housing which had to be taken into account in the radiological protection planning. This paper describes the techniques proposed to undertake the dismantling operations in order to minimise the radiation exposure to workers and members of the public. Estimates have been made of the worker doses which could be incurred during the dismantling process and the environmental impacts which could occur. These are demonstrated to be as low as reasonably achievable. The work was funded by the UK Department of Business Enterprise and Regulatory Reform (DBERR) (formerly the Department of Trade and Industry) under the Nuclear Safety Programme (NSP) set up to address nuclear safety issues in the Former Soviet Union. (author)

  19. Trends in animal use at US research facilities.

    Science.gov (United States)

    Goodman, Justin; Chandna, Alka; Roe, Katherine

    2015-07-01

    Minimising the use of animals in experiments is universally recognised by scientists, governments and advocates as an ethical cornerstone of research. Yet, despite growing public opposition to animal experimentation, mounting evidence that animal studies often do not translate to humans, and the development of new research technologies, a number of countries have reported increased animal use in recent years. In the USA--one of the world's largest users of animals in experiments--a lack of published data on the species most commonly used in laboratories (eg, mice, rats and fish) has prevented such assessments. The current study aimed to fill this gap by analysing the use of all vertebrate animals by the top institutional recipients of National Institutes of Health research funds over a 15-year period. These data show a statistically significant 72.7% increase in the use of animals at these US facilities during this time period-driven primarily by increases in the use of mice. Our results highlight a need for greater efforts to reduce animal use. We discuss technical, institutional, sociological and psychological explanations for this trend. Published by the BMJ Publishing Group Limited. For permission to use (where not already granted under a licence) please go to http://group.bmj.com/group/rights-licensing/permissions.

  20. Screening methodology for assessing potential health effects from municipal sludge incinerators

    Energy Technology Data Exchange (ETDEWEB)

    Fradkin, L.; Bruins, R.J.F.; Lutkenhoff, S.D.; Stara, J.F.; Lomnitz, E.

    1987-01-01

    This paper describes a risk assessment methodology for preliminary assessment of municipal sludge incineration. The methodology is a valuable tool in that it can be used for determining the hazard indices of chemical contaminants that might be present in sewage sludge used in incineration. The paper examines source characteristics (i.e., facility design), atmospheric dispersion of emission, and resulting human exposure and risk from sludge incinerators. Seven of the ten organics were screened for further investigation. An example of the calculations are presented for cadmium.

  1. Screening methodology for assessing potential health effects from municipal sludge incinerators

    Energy Technology Data Exchange (ETDEWEB)

    Fradkin, L.; Bruins, R.J.F.; Lutkenhoff, S.D.; Stara, J.F.; Lomnitz, E.; Rubin, A.

    1987-04-01

    This paper describes a risk assessment of methodology for preliminary assessment of municipal sludge incineration. The methodology is a valuable tool in that it can be used for determining the hazard indices of chemical contaminants that might be present in sewage sludge used in incineration. The paper examines source characteristics (i.e. facility design), atmospheric dispersion of emission, and resulting human exposure and risk from sludge incinerators. Seven of the ten organics were screened for further investigation. An example of the calculations are presented for cadmium. (Refs. 5).

  2. Alpha waste incineration prototype incinerator and industrial project

    International Nuclear Information System (INIS)

    Caramelle, D.; Meyere, A.

    1988-01-01

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

  3. Incineration of Low Level Radioactive Vegetation for Waste Volume Reduction

    International Nuclear Information System (INIS)

    Malik, N.P.S.; Rucker, G.G.; Looper, M.G.

    1995-01-01

    The DOE changing mission at Savannah River Site (SRS) are to increase activities for Waste Management and Environmental Restoration. There are a number of Comprehensive Environmental Response, Compensation and Liability Act (CERCLA) locations that are contaminated with radioactivity and support dense vegetation, and are targeted for remediation. Two such locations have been studied for non-time critical removal actions under the National Contingency Plan (NCP). Both of these sites support about 23 plant species. Surveys of the vegetation show that radiation emanates mainly from vines, shrubs, and trees and range from 20,000 to 200,000 d/m beta gamma. Planning for removal and disposal of low-level radioactive vegetation was done with two principal goals: to process contaminated vegetation for optimum volume reduction and waste minimization, and for the protection of human health and environment. Four alternatives were identified as candidates for vegetation removal and disposal: chipping the vegetation and packing in carbon steel boxes (lined with synthetic commercial liners) and disposal at the Solid Waste Disposal Facility at SRS; composting the vegetation; burning the vegetation in the field; and incinerating the vegetation. One alternative 'incineration' was considered viable choice for waste minimization, safe handling, and the protection of the environment and human health. Advantages and disadvantages of all four alternatives considered have been evaluated. For waste minimization and ultimate disposal of radioactive vegetation incineration is the preferred option. Advantages of incineration are that volume reduction is achieved and low-level radioactive waste are stabilized. For incineration and final disposal vegetation will be chipped and packed in card board boxes and discharged to the rotary kiln of the incinerator. The slow rotation and longer resident time in the kiln will ensure complete combustion of the vegetative material

  4. Dioxins from medical waste incineration: Normal operation and transient conditions.

    Science.gov (United States)

    Chen, Tong; Zhan, Ming-xiu; Yan, Mi; Fu, Jian-ying; Lu, Sheng-yong; Li, Xiao-dong; Yan, Jian-hua; Buekens, Alfons

    2015-07-01

    Polychlorinated dibenzo-p-dioxins (PCDDs) and polychlorinated dibenzofurans (PCDFs) are key pollutants in waste incineration. At present, incinerator managers and official supervisors focus only on emissions evolving during steady-state operation. Yet, these emissions may considerably be raised during periods of poor combustion, plant shutdown, and especially when starting-up from cold. Until now there were no data on transient emissions from medical (or hospital) waste incineration (MWI). However, MWI is reputed to engender higher emissions than those from municipal solid waste incineration (MSWI). The emission levels in this study recorded for shutdown and start-up, however, were significantly higher: 483 ± 184 ng Nm(-3) (1.47 ± 0.17 ng I-TEQ Nm(-3)) for shutdown and 735 ng Nm(-3) (7.73 ng I-TEQ Nm(-3)) for start-up conditions, respectively. Thus, the average (I-TEQ) concentration during shutdown is 2.6 (3.8) times higher than the average concentration during normal operation, and the average (I-TEQ) concentration during start-up is 4.0 (almost 20) times higher. So monitoring should cover the entire incineration cycle, including start-up, operation and shutdown, rather than optimised operation only. This suggestion is important for medical waste incinerators, as these facilities frequently start up and shut down, because of their small size, or of lacking waste supply. Forthcoming operation should shift towards much longer operating cycles, i.e., a single weekly start-up and shutdown. © The Author(s) 2015.

  5. Corrosion of steel drums containing immobilized ion exchange-resins and incineration ashes

    International Nuclear Information System (INIS)

    Marotta, F.; Schulz Rodriguez, F.M.; Farina, Silvia B.; Duffo, Gustavo S.

    2009-01-01

    The Argentine Atomic Energy Commission (CNEA) is responsible for developing the management nuclear waste disposal programme. This programme contemplates the design and construction of a facility for the final disposal of intermediate-level radioactive wastes. The proposed model is a near-surface monolithic repository similar to those in operation in El Cabril, Spain. The design of this type of repository is based on the use of multiple, independent and redundant barriers. The intermediate radioactive waste consists mostly in spent ionic exchange resins and filters from the nuclear power plants, research reactors and radioisotopes production facilities. The spent resins, as well as the incineration ashes, have to be immobilized before being stored to improve leach resistance of waste matrix and to maintain mechanical stability for safety requirements. Generally, cementation processes have been used as immobilization techniques for economical reasons as well as for being a simple operation. The immobilized resins and incineration ashes are thus contained in steel drums that, in turn, can undergo corrosion depending on the ionic content of the matrix. This work is a part of a systematic study of the corrosion susceptibility of steel drums in contact with immobilized cemented exchange-resins with different types and contents of aggressive species and incineration ashes. To this purpose, a special type of specimen was manufactured to simulate the cemented waste in the drum. The evolution of the corrosion potential and the corrosion current density of the steel, as well as the electrical resistivity of the matrix are being monitored along time. The aggressive species studied were chloride ions (the main ionic species present in nature) and sulphate ions (produced during the radiolysis process of the cationic exchange-resins after cementation). Preliminary results show the strong effect of chloride on the corrosion susceptibility of the steel. Monitoring will continue for

  6. 48 CFR 235.015-70 - Special use allowances for research facilities acquired by educational institutions.

    Science.gov (United States)

    2010-10-01

    ... research facilities acquired by educational institutions. 235.015-70 Section 235.015-70 Federal Acquisition... acquired by educational institutions. (a) Definitions. As used in this subsection— (1) Research facility... 31.3. (b) Policy. (1) Educational institutions are to furnish the facilities necessary to perform...

  7. Anomalous radon concentration in a nuclear research facility

    International Nuclear Information System (INIS)

    Balcazar, M.; Pena, P.

    2014-08-01

    Radon monitoring in more than 60 selected points were part of surveillance radiation activities in the nuclear center of Mexico; three major facilities were inspected, the TRIGA Mark III research reactor, the Tandem Van de Graaff Accelerator and the Pelletron electron Accelerator. During a major maintenance activities in the research reactor, the air extraction system was not functioning for more than a month causing of a radon build up exhaled from the massive concrete of the building, reaching concentrations in some places up to 2.1 kb m -3 . The irradiation room at the Tandem Accelerator presented high radon concentrations up to nearly 5 kb m -3 , manly in the trenches were pipes and electric wires are located, the radon source was identified as originated from small caves under the floor. Low radon concentrations were found inside a similar building where a Pelletron accelerator is located. The reasons for the abnormal radon concentrations and the mitigation actions to remove any risk for the worker are discussed in detail in this paper. (author)

  8. Anomalous radon concentration in a nuclear research facility

    Energy Technology Data Exchange (ETDEWEB)

    Balcazar, M.; Pena, P., E-mail: miguel.balcazar@inin.gob.mx [ININ, Carretera Mexico-Toluca s/n, 52750 Ocoyoacac, Estado de Mexico (Mexico)

    2014-08-15

    Radon monitoring in more than 60 selected points were part of surveillance radiation activities in the nuclear center of Mexico; three major facilities were inspected, the TRIGA Mark III research reactor, the Tandem Van de Graaff Accelerator and the Pelletron electron Accelerator. During a major maintenance activities in the research reactor, the air extraction system was not functioning for more than a month causing of a radon build up exhaled from the massive concrete of the building, reaching concentrations in some places up to 2.1 kb m{sup -3}. The irradiation room at the Tandem Accelerator presented high radon concentrations up to nearly 5 kb m{sup -3}, manly in the trenches were pipes and electric wires are located, the radon source was identified as originated from small caves under the floor. Low radon concentrations were found inside a similar building where a Pelletron accelerator is located. The reasons for the abnormal radon concentrations and the mitigation actions to remove any risk for the worker are discussed in detail in this paper. (author)

  9. Nanosafety practices: results from a national survey at research facilities

    Science.gov (United States)

    Díaz-Soler, Beatriz María; López-Alonso, Mónica; Martínez-Aires, María Dolores

    2017-05-01

    The exposure to engineered nanomaterials (ENMs) is a new emerging risk at work due to an increase in the number of workers potentially exposed to them and the current lack of data on their health and safety risks. This paper reports the findings of a survey designed to study the safety practices employed by workers in Spanish research facilities performing tasks involving the use of ENMs at research level. A questionnaire pretested and validated by an expert panel was sent by e-mail to the target audience. The 425 surveys completed show that most of the respondents handled up to 5 different ENMs, in suspension, in small amounts during short periods of exposure. The implementation of common hygienic practices, such as the use of protection for hands and the implementation of fume hoods, is widely indicated. The selection of the preventive and protective measures does not depend on the characteristics of ENMs handled. Also, the risks posed by ENMs are widely ignored. Besides the performance of risk assessment, hygienic monitoring and the conducting of a specific health surveillance are practically non-existent although some accidents relating to ENMs were identified. In conclusion, workers' exposure to ENMs seems to be low. Even though the best practices and preventive and protective measures reported were employed, most of the respondents could not be correctly protected. Moreover, workers do not associate the measures implemented with the nanorisks. Finally, there is a lack of proactive action underway to protect the workers, and concerns about safety are weakly evidenced.

  10. Multi-Specimen Variable-G Facility for Life and Microgravity Sciences Research Project

    Data.gov (United States)

    National Aeronautics and Space Administration — The Multi-specimen Variable-G Facility (MVF) is a single locker sized centrifuge facility for life and microgravity sciences research on the International Space...

  11. Atmospheric Radiation Measurement program climate research facility operations quarterly report.

    Energy Technology Data Exchange (ETDEWEB)

    Sisterson, D. L.; Decision and Information Sciences

    2006-09-06

    Individual raw data streams from instrumentation at the Atmospheric Radiation Measurement (ARM) Program Climate Research Facility (ACRF) fixed and mobile sites are collected and sent to the Data Management Facility (DMF) at Pacific Northwest National Laboratory (PNNL) for processing in near real time. Raw and processed data are then sent daily to the ACRF Archive, where they are made available to users. For each instrument, we calculate the ratio of the actual number of data records received daily at the Archive to the expected number of data records. The results are tabulated by (1) individual data stream, site, and month for the current year and (2) site and fiscal year dating back to 1998. The U.S. Department of Energy requires national user facilities to report time-based operating data. The requirements concern the actual hours of operation (ACTUAL); the estimated maximum operation or uptime goal (OPSMAX), which accounts for planned downtime; and the VARIANCE [1-(ACTUAL/OPSMAX)], which accounts for unplanned downtime. The OPSMAX time for the third quarter for the Southern Great Plains (SGP) site is 2,074.80 hours (0.95 x 2,184 hours this quarter). The OPSMAX for the North Slope Alaska (NSA) locale is 1,965.60 hours (0.90 x 2,184), and that for the Tropical Western Pacific (TWP) locale is 1,856.40 hours (0.85 x 2,184). The OPSMAX time for the ARM Mobile Facility (AMF) is 2,074.80 hours (0.95 x 2,184). The differences in OPSMAX performance reflect the complexity of local logistics and the frequency of extreme weather events. It is impractical to measure OPSMAX for each instrument or data stream. Data availability reported here refers to the average of the individual, continuous data streams that have been received by the Archive. Data not at the Archive are caused by downtime (scheduled or unplanned) of the individual instruments. Therefore, data availability is directly related to individual instrument uptime. Thus, the average percent of data in the Archive

  12. HANDBOOK: HAZARDOUS WASTE INCINERATION MEASUREMENT GUIDANCE

    Science.gov (United States)

    This publication, Volume III of the Hazardous Waste Incineration Guidance Series, contains general guidance to permit writers in reviewing hazardous waste incineration permit applications and trial burn plans. he handbook is a how-to document dealing with how incineration measure...

  13. Ready, set,...quit exclamation point A review of the controlled-air incinerator

    International Nuclear Information System (INIS)

    Reader, G.E.

    1996-01-01

    The Los Alamos National Laboratory (LANL) Controlled-Air Incinerator (CAI) has had a long and productive past as a research and development tool. It now appears that use of the CAI to treat LANL legacy and other wastes under the Federal Facilities Compliance Act is no longer viable due to numerous programmatic problems. This paper will review the history of the CAI. Various aspects associated with the CAI and how those aspects resulted in the loss of this Department of Energy asset as a viable waste treatment option will also be discussed. Included are past missions and tests-CAI capabilities, emissions, and permits; Federal Facility Compliance Act and associated Agreement; National Environmental Policy Act coverage; cost; budget impacts; public perception; the U.S. Environmental Protection Agency Combustion Strategy; Independent Technical Review open-quotes Redclose quotes Team review; waste treatment alternative technologies; the New Mexico Environment Department; and future options and issues

  14. A new apparatus at hyper irradiation research facility at the Atomic Research Center, University of Tokyo

    International Nuclear Information System (INIS)

    Shibata, Hiromi; Iwai, Takeo; Narui, Makoto; Omata, Takao

    1996-01-01

    In the hyper irradiation research facility at the Atomic Research Center, the University of Tokyo, following apparatuses were newly installed for accelerator relating apparatus on 1995 fiscal year; 1) Hyper ion microbeam analysis apparatus, 2) Fourier conversion infrared microscopy, 3) Pico second two-dimensional fluorescence measuring apparatus, 4) Femto second wave-length reversible pulse laser radiation apparatus, and others. In addition to double irradiation, pulse beam irradiation experiment and so forth characteristic in conventional hyper irradiation research apparatus, upgrading of material irradiation experiments using these new apparatuses are intended. (G.K.)

  15. Application countermeasures of non-incineration technologies for medical waste treatment in China.

    Science.gov (United States)

    Chen, Yang; Ding, Qiong; Yang, Xiaoling; Peng, Zhengyou; Xu, Diandou; Feng, Qinzhong

    2013-12-01

    By the end of 2012, there were 272 modern, high-standard, centralized medical waste disposal facilities operating in various cities in China. Among these facilities nearly 50% are non-incineration treatment facilities, including the technologies of high temperature steam, chemical disinfection and microwave. Each of the non-incineration technologies has its advantages and disadvantages, and any single technology cannot offer a panacea because of the complexity of medical waste disposal. Although non-incineration treatment of medical waste can avoid the release of polychlorinated dibenzo-p-dioxins/dibenzofurans, it is still necessary to decide how to best meet the local waste management needs while minimizing the impact on the environment and public health. There is still a long way to go to establish the sustainable application and management mode of non-incineration technologies. Based on the analysis of typical non-incineration process, pollutant release, and the current tendency for technology application and development at home and abroad, this article recommends the application countermeasures of non-incineration technologies as the best available techniques and best environmental practices in China.

  16. Orange County Government Solar Demonstration and Research Facility

    Energy Technology Data Exchange (ETDEWEB)

    Parker, Renee [Orange County Florida, Orlando, Florida (United States); Cunniff, Lori [Orange County Florida, Orlando, Florida (United States)

    2015-05-12

    Orange County Florida completed the construction of a 20 kilowatt Solar Demonstration and Research Facility in March 2015. The system was constructed at the Orange County/University of Florida Cooperative Extension Center whose electric service address is 6021 South Conway Road, Orlando, Florida 32802. The Solar Demonstration and Research Facility is comprised of 72 polycrystalline photovoltaic modules and 3 inverters which convert direct current from the solar panels to alternating current electricity. Each module produces 270 watts of direct current power, for a total canopy production of just under 20,000 watts. The solar modules were installed with a fixed tilt of 5 degrees and face south, toward the equator to maximize the amount of sunlight captures. Each year, the electricity generated by the solar array will help eliminate 20 metric tons of carbon dioxide emissions as well as provide covered parking for staff and visitors vehicles. The solar array is expected to generate 27,000 kilowatt hours of electricity annually equating to an estimated $266 savings in the monthly electric bill, or $3,180 annually for the Orange County/University of Florida Cooperative Extension Center. In addition to reducing the electric bill for the Extension Center, Orange County’s solar array also takes advantage of a rebate incentive offered by the local utility, Orlando Utility Commission, which provided a meter that measures the amount of power produced by the solar array. The local utility company’s Solar Photovoltaic Production Incentive will pay Orange County $0.05 per kilowatt hour for the power that is produced by the solar array. This incentive is provided in addition to Net Metering benefits, which is an effort to promote the use of clean, renewable energy on the electric grid. The Photovoltaic Solar Demonstration and Research Facility also serves an educational tool to the public; the solar array is tied directly into a data logger that provides real time power

  17. Processing of combustible radioactive waste using incineration techniques

    International Nuclear Information System (INIS)

    Maestas, E.

    1981-01-01

    Among the OECD Nuclear Energy Agency Member countries numerous incineration concepts are being studied as potential methods for conditioning alpha-bearing and other types of combustible radioactive waste. The common objective of these different processes is volume reduction and the transformation of the waste to a more acceptable waste form. Because the combustion processes reduce the mass and volume of waste to a form which is generally more inert than the feed material, the resulting waste can be more uniformly compatible with safe handling, packaging, storage and/or disposal techniques. The number of different types of combustion process designed and operating specifically for alpha-bearing wastes is somewhat small compared with those for non-alpha radioactive wastes; however, research and development is under way in a number of countries to develop and improve alpha incinerators. This paper provides an overview of most alpha-incineration concepts in operation or under development in OECD/NEA Member countries. The special features of each concept are briefly discussed. A table containing characteristic data of incinerators is presented so that a comparison of the major programmes can be made. The table includes the incinerator name and location, process type, capacity throughput, operational status and application. (author)

  18. Report of the research results with JAERI's facilities in fiscal 1975

    International Nuclear Information System (INIS)

    1976-07-01

    Results of the research works by educational institutions using facilities of the Japan Atomic Energy Research Institute in fiscal 1975 are reported in individual summaries. Facilities utilized are research reactors, Co-60 irradiation facilities, hot laboratory, Linac and electron accelerators. Fields of research are the following: nuclear physics, radiation damage/solid-state physics, positron annihilation, activation analysis/nuclear chemistry, hot atom chemistry, irradiation effects, biology, and neutron diffraction; and, cooperative works to JAERI. (Mori, K.)

  19. Savannah River Plant low-level waste incinerator demonstration

    International Nuclear Information System (INIS)

    Tallman, J.A.

    1984-01-01

    A two-year demonstration facility was constructed at the Savannah River Plant (SRP) to incinerate suspect contaminated solid and low-level solvent wastes. Since startup in January 1984, 4460 kilograms and 5300 liters of simulated (uncontaminated) solid and solvent waste have been incinerated to establish the technical and operating data base for the facility. Combustion safeguards have been enhanced, process controls and interlocks refined, some materials handling problems identified and operating experience gained as a result of the 6 month cold run-in. Volume reductions of 20:1 for solid and 25:1 for solvent waste have been demonstrated. Stack emissions (NO 2 , SO 2 , CO, and particulates) were only 0.5% of the South Carolina ambient air quality standards. Radioactive waste processing is scheduled to begin in July 1984. 2 figures, 2 tables

  20. Incinerators and health. guide for the behavior to have during a local demand of sanitary investigations around a domestic refuse incinerator; Incinerateurs et sante. Guide pour la conduite a tenir lors d'une demande locale d'investigations sanitaires autour d'un incinerateur d'ordures menageres

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2003-12-15

    11,4 million tons of municipal solid and assimilated waste were incinerated in France in 2000. The 123 incinerators compliant with the Order in Council of January 25, 1991 have undergone significant modifications in the last years, and the incineration techniques used are of great concern to the public. The backfitting to new regulations and the many research works have answered some of the rightful questions of the population on health risks caused by waste incineration. However, many doubts remain and there has been many requests by the local population for epidemiological investigations to be conducted on this issue. The objectives of this document, requested by the Health General Directorate and presented as 'actions to be taken', are to inform the decentralized services of the government and regional epidemiology units of the health problems caused by waste incineration facilities and to help them grasp on a local level the situation met around these facilities. Therefore, this paper provides some scientific arguments to justify the need (or not) for setting up some specific studies as part of an informed public health management. This document is divided in three parts. The first part describes the actions to be taken at the local level. The methodological framework is based on: i) an analysis of the local situation; ii) finding a new definition in terms of public health to the one or more questions raised, and the usefulness to set up one or more health investigations; iii) the relevance of a specific type of study which would allow to answer these questions; and iv) the feasibility of this type of study. The second part briefly describes the various types of health studies and their use as a decision-making tool on waste-incineration facilities. These results stem mainly from the analysis of studies already put forward and carried out in past local situations. The third part points out what is currently found in today's literature on

  1. Joint Actinide Shock Physics Experimental Research (JASPER) Facility Update

    International Nuclear Information System (INIS)

    Conrad, C. H.; Miller, J.; Cowan, M.; Martinez, M.; Whitcomb, B.

    2003-01-01

    The JASPER Facility utilizes a Two-Stage Light Gas Gun to conduct equation-of-state(EOS) experiments on plutonium and other special nuclear materials. The overall facility will be discussed with emphasis on the Two-Stage Light Gas Gun characteristics and control interfaces and containment. The containment systems that were developed for this project will be presented

  2. A neutron tomography facility at a low power research reactor

    CERN Document Server

    Körner, S; Von Tobel, P; Rauch, H

    2001-01-01

    Neutron radiography (NR) provides a very efficient tool in the field of non-destructive testing as well as for many applications in fundamental research. A neutron beam penetrating a specimen is attenuated by the sample material and detected by a two-dimensional (2D) imaging device. The image contains information about materials and structure inside the sample because neutrons are attenuated according to the basic law of radiation attenuation. Contrary to X-rays, neutrons can be attenuated by some light materials, as for example, hydrogen and boron, but penetrate many heavy materials. Therefore, NR can yield important information not obtainable by more traditional methods. Nevertheless, there are many aspects of structure, both quantitative and qualitative, that are not accessible from 2D transmission images. Hence, there is an interest in three-dimensional neutron imaging. At the 250 kW TRIGA Mark II reactor of the Atominstitut in Austria a neutron tomography facility has been installed. The neutron flux at ...

  3. The NASA Lewis Research Center Internal Fluid Mechanics Facility

    Science.gov (United States)

    Porro, A. R.; Hingst, W. R.; Wasserbauer, C. A.; Andrews, T. B.

    1991-01-01

    An experimental facility specifically designed to investigate internal fluid duct flows is described. It is built in a modular fashion so that a variety of internal flow test hardware can be installed in the facility with minimal facility reconfiguration. The facility and test hardware interfaces are discussed along with design constraints of future test hardware. The plenum flow conditioning approach is also detailed. Available instrumentation and data acquisition capabilities are discussed. The incoming flow quality was documented over the current facility operating range. The incoming flow produces well behaved turbulent boundary layers with a uniform core. For the calibration duct used, the boundary layers approached 10 percent of the duct radius. Freestream turbulence levels at the various operating conditions varied from 0.64 to 0.69 percent of the average freestream velocity.

  4. Research on integral thermal-hydraulic test facilities

    International Nuclear Information System (INIS)

    Liu Yusheng; Zhang Chunming; Ma Shuai; Zhang Pan

    2014-01-01

    Integral thermal-hydraulic test facilities, which have been necessary experimental platforms during the development of nuclear safety technology, could not only test and validate performance of new designed system, but also provide experimental data for development and validation of nuclear safety analysis codes. Typical integral thermal-hydraulic test facilities in the world are studied in this paper, of which the design parameters, system arrangements and functions are emphatically discussed. The results show that those integral thermal-hydraulic test facilities differ with each other in parameter scope and simulation function. Basing the fact that each facility has its advantages and disadvantages, it is better to take more factors into consideration in design of new facility. What is more, the design scheme could be optimized with new measurement technology and analysis software. (authors)

  5. Rapid prototyping facility for flight research in artificial-intelligence-based flight systems concepts

    Science.gov (United States)

    Duke, E. L.; Regenie, V. A.; Deets, D. A.

    1986-01-01

    The Dryden Flight Research Facility of the NASA Ames Research Facility of the NASA Ames Research Center is developing a rapid prototyping facility for flight research in flight systems concepts that are based on artificial intelligence (AI). The facility will include real-time high-fidelity aircraft simulators, conventional and symbolic processors, and a high-performance research aircraft specially modified to accept commands from the ground-based AI computers. This facility is being developed as part of the NASA-DARPA automated wingman program. This document discusses the need for flight research and for a national flight research facility for the rapid prototyping of AI-based avionics systems and the NASA response to those needs.

  6. Charger 1: A New Facility for Z-Pinch Research

    Science.gov (United States)

    Taylor, Brian; Cassibry, Jason; Cortez, Ross; Doughty, Glen; Adams, Robert; DeCicco, Anthony

    2017-01-01

    Charger 1 is a multipurpose pulsed power laboratory located on Redstone Arsenal, with a focus on fusion propulsion relevant experiments involving testing z-pinch diodes, pulsed magnetic nozzle and other related physics experiments. UAH and its team of pulsed power researchers are investigating ways to increase and optimize fusion production from Charger 1. Currently the team has reached high-power testing. Due to the unique safety issues related to high power operations the UAH/MSFC team has slowed repair efforts to develop safety and operations protocols. The facility is expected to be operational by the time DZP 2017 convenes. Charger 1 began life as the Decade Module 2, an experimental prototype built to prove the Decade Quad pinch configuration. The system was donated to UAH by the Defense Threat Reduction Agency (DRTA) in 2012. For the past 5 years a UAH/MSFC/Boeing team has worked to refurbish, assemble and test the system. With completion of high power testing in summer 2017 Charger 1 will become operational for experimentation. Charger 1 utilizes a Marx Bank of 72 100-kV capacitors that are charged in parallel and discharged in series. The Marx output is compressed to a pulse width of approximately 200 ns via a pulse forming network of 32 coaxial stainless steel tubes using water as a dielectric. After pulse compression a set of SF6 switches are triggered, allowing the wave front to propagate through the output line to the load. Charger 1 is capable of storing 572-kJ of energy and time compressing discharge to less than 250 ns discharge time producing a discharge of about 1 TW of discharge with 1 MV and 1 MA peak voltage and current, respectively. This capability will be used to study energy yield scaling and physics from solid density target as applied to advanced propulsion research.

  7. Experimental research on emission and removal of dioxins in flue gas from a co-combustion of MSW and coal incinerator

    International Nuclear Information System (INIS)

    Zhong Zhaoping; Jin Baosheng; Huang Yaji; Zhou Hongcang; Lan Jixiang

    2006-01-01

    This paper describes the experimental study of dioxins removal from flue gas from a co-combustion municipal solid waste and coal incinerator by means of a fluidized absorption tower and a fabric filter. A test rig has been set up. The flow rate of flue gas of the test rig is 150-2000 m 3 /h. The system was composed of a humidification and cooling system, an absorption tower, a demister, a slurry make-up tank, a desilter, a fabric filter and a measurement system. The total height of the absorption tower was 6.5 m, and the diameter of the reactor pool was 1.2 m. When the absorbent was 1% limestone slurry, the recirculation ratio was 3, the jet rate was 5-15 m/s and the submerged depth of the bubbling pipe under the slurry was 0.14 m, the removal efficiency for dioxins was 99.35%. The concentration of dioxins in the treated flue gas was 0.1573 x 10 -13 kg/Nm 3 and the concentration of oxygen was 11%. This concentration is comparable to the emission standards of other developed countries

  8. Controlled-air incineration of transuranic-contaminated solid waste

    International Nuclear Information System (INIS)

    Borduin, L.C.; Draper, W.E.; Koenig, R.A.; Neuls, A.S.; Warner, C.L.

    1976-01-01

    A controlled-air incinerator and an associated high-energy aqueous off-gas cleaning system are being installed at the Los Alamos Scientific Laboratory (LASL) Transuranic Waste Treatment Development Facility (TDF) for evaluation as a low-level transuranic-contaminated (TRU) solid waste volume reduction process. Program objectives are: (1) assembly and operation of a production scale (45 kg/hr) operation of ''off-the-shelf'' components representative of current incineration and pollution control technology; (2) process development and modification to meet radioactive health and safety standards, and (3) evaluation of the process to define the advantages and limitations of conventional technology. The results of the program will be the design specifications and operating procedures necessary for successful incineration of TRU waste. Testing, with nonradioactive waste, will begin in October 1976. This discussion covers commercially available incinerator and off-gas cleaning components, the modifications required for radioactive service, process components performance expectations, and a description of the LASL experimental program

  9. Process modeling study of the CIF incinerator

    International Nuclear Information System (INIS)

    Hang, T.

    1995-01-01

    The Savannah River Site (SRS) plans to begin operating the Consolidated Incineration Facility (CIF) in 1996. The CIF will treat liquid and solid low-level radioactive, mixed and RCRA hazardous wastes generated at SRS. In addition to experimental test programs, process modeling was applied to provide guidance in areas of safety, environmental regulation compliances, process improvement and optimization. A steady-state flowsheet model was used to calculate material/energy balances and to track key chemical constituents throughout the process units. Dynamic models were developed to predict the CIF transient characteristics in normal and abnormal operation scenarios. Predictions include the rotary kiln heat transfer, dynamic responses of the CIF to fluctuations in the solid waste feed or upsets in the system equipments, performance of the control system, air inleakage in the kiln, etc. This paper reviews the modeling study performed to assist in the deflagration risk assessment

  10. Incineration experience at Oconee Nuclear Station

    International Nuclear Information System (INIS)

    Terrell, M.S.

    1986-01-01

    The Radwaste Facility at Oconee Nuclear Station contains a Fluidized Bed Dryer/Incinerator System which will be used to process contaminated trash (DAW), oil, powdex resin, and chemical cleaning waste. This system was designed by Aerojet Energy Conversion Company. The ash and salts resulting from this process will be solidified using the Stock Equipment Company Polymer Solidification System. The purpose of this paper is to discuss the results of start-up and pre-operational testing of these systems, describe the mass balance program the authors will be using to meet the requirements of 10CFR61, and to discuss the sampling of the ash and salts that will be produced as a result of the process. Additionally, tests which are designed to verify the mass balance for the Aeroject System, are discussed

  11. Experimental study of the energy efficiency of an incinerator for medical waste

    International Nuclear Information System (INIS)

    Bujak, J.

    2009-01-01

    The aim of this paper is to explore the flux of usable energy and the coefficient of energy efficiency of an incinerator for medical waste combustion. The incineration facility incorporates a heat recovery system. The installation consists of a loading unit, a combustion chamber, a thermoreactor chamber, and a recovery boiler. The analysis was carried out in the Oncological Hospital in Bydgoszcz (Poland). The primary fuel was comprised of medical waste, with natural gas used as a secondary fuel. The study shows that one can obtain about 660-800 kW of usable energy from 100 kg of medical waste. This amount corresponds to 1000-1200 kg of saturated steam, assuming that the incinerator operates at a heat load above φ > 65%. The average heat flux in additional fuel used for incinerating 100 kg of waste was 415 kW. The coefficient of energy efficiency was set within the range of 47% and 62% depending on the incinerator load. The tests revealed that the flux of usable energy and the coefficient of energy efficiency depend on the incinerator load. In the investigated range of the heat load, this dependence is significant. When the heat load of the incinerator increases, the flux of usable energy and the coefficient of energy efficiency also increase.

  12. The Use of Microwave Incineration to Process Biological Wastes

    Science.gov (United States)

    Sun, Sidney C.; Srinivasan, Venkatesh; Covington, Alan (Technical Monitor)

    1994-01-01

    The handling and disposal of solid waste matter that has biological or biohazardous components is a difficult issue for hospitals, research laboratories, and industry. NASA faces the same challenge as it is developing regenerative systems that will process waste materials into materials that can be used to sustain humans living in space for extended durations. Plants provide critical functions in such a regenerative life support scheme in that they photosynthesize carbon dioxide and water into glucose and oxygen. The edible portions of the plant provide a food source for the crew. Inedible portions can be processed into materials that are more recyclable. The Advanced Life Support Division at NASA Ames Research Center has been evaluating a microwave incinerator that will oxidize inedible plant matter into carbon dioxide and water. The commercially available microwave incinerator is produced by Matsushita Electronic Instruments Corporation of Japan. Microwave incineration is a technology that is simple, safe, and compact enough for home use. It also has potential applications for institutions that produce biological or biohazardous waste. The incinerator produces a sterile ash that has only 13% of the mass of the original waste. The authors have run several sets of tests with the incinerator to establish its viability in processing biological material. One goal of the tests is to show that the incinerator does not generate toxic compounds as a byproduct of the combustion process. This paper will describe the results of the tests, including analyses of the resulting ash and exhaust gases. The significance of the results and their implications on commercial applications of the technology will also be discussed.

  13. Incineration of organic solar cells

    NARCIS (Netherlands)

    Søndergaard, Roar R.; Zimmermann, Yannick Serge; Espinosa, Nieves; Lenz, Markus; Krebs, Frederik

    2016-01-01

    Recovery of silver from the electrodes of roll-to-roll processed organic solar cells after incineration has been performed quantitatively by extraction with nitric acid. This procedure is more than 10 times faster than previous reports and the amount of acid needed for the extraction is reduced

  14. Plutonium waste incineration using pyrohydrolysis

    Energy Technology Data Exchange (ETDEWEB)

    Meyer, M.L.

    1991-12-31

    Waste generated by Savannah River Site (SRS) plutonium operations includes a contaminated organic waste stream. A conventional method for disposing of the organic waste stream and recovering the nuclear material is by incineration. When the organic material is burned, the plutonium remains in the incinerator ash. Plutonium recovery from incinerator ash is highly dependent on the maximum temperature to which the oxide is exposed. Recovery via acid leaching is reduced for a high fired ash (>800{degree}C), while plutonium oxides fired at lower decomposition temperatures (400--800{degrees}C) are more soluble at any given acid concentration. To determine the feasibility of using a lower temperature process, tests were conducted using an electrically heated, controlled-air incinerator. Nine nonradioactive, solid, waste materials were batch-fed and processed in a top-heated cylindrical furnace. Waste material processing was completed using a 19-liter batch over a nominal 8-hour cycle. A processing cycle consisted of 1 hour for heating, 4 hours for reacting, and 3 hours for chamber cooling. The water gas shift reaction was used to hydrolyze waste materials in an atmosphere of 336% steam and 4.4% oxygen. Throughput ranged from 0.14 to 0.27 kg/hr depending on the variability in the waste material composition and density.

  15. Plutonium waste incineration using pyrohydrolysis

    Energy Technology Data Exchange (ETDEWEB)

    Meyer, M.L.

    1991-01-01

    Waste generated by Savannah River Site (SRS) plutonium operations includes a contaminated organic waste stream. A conventional method for disposing of the organic waste stream and recovering the nuclear material is by incineration. When the organic material is burned, the plutonium remains in the incinerator ash. Plutonium recovery from incinerator ash is highly dependent on the maximum temperature to which the oxide is exposed. Recovery via acid leaching is reduced for a high fired ash (>800{degree}C), while plutonium oxides fired at lower decomposition temperatures (400--800{degrees}C) are more soluble at any given acid concentration. To determine the feasibility of using a lower temperature process, tests were conducted using an electrically heated, controlled-air incinerator. Nine nonradioactive, solid, waste materials were batch-fed and processed in a top-heated cylindrical furnace. Waste material processing was completed using a 19-liter batch over a nominal 8-hour cycle. A processing cycle consisted of 1 hour for heating, 4 hours for reacting, and 3 hours for chamber cooling. The water gas shift reaction was used to hydrolyze waste materials in an atmosphere of 336% steam and 4.4% oxygen. Throughput ranged from 0.14 to 0.27 kg/hr depending on the variability in the waste material composition and density.

  16. Plutonium waste incineration using pyrohydrolysis

    International Nuclear Information System (INIS)

    Meyer, M.L.

    1991-01-01

    Waste generated by Savannah River Site (SRS) plutonium operations includes a contaminated organic waste stream. A conventional method for disposing of the organic waste stream and recovering the nuclear material is by incineration. When the organic material is burned, the plutonium remains in the incinerator ash. Plutonium recovery from incinerator ash is highly dependent on the maximum temperature to which the oxide is exposed. Recovery via acid leaching is reduced for a high fired ash (>800 degree C), while plutonium oxides fired at lower decomposition temperatures (400--800 degrees C) are more soluble at any given acid concentration. To determine the feasibility of using a lower temperature process, tests were conducted using an electrically heated, controlled-air incinerator. Nine nonradioactive, solid, waste materials were batch-fed and processed in a top-heated cylindrical furnace. Waste material processing was completed using a 19-liter batch over a nominal 8-hour cycle. A processing cycle consisted of 1 hour for heating, 4 hours for reacting, and 3 hours for chamber cooling. The water gas shift reaction was used to hydrolyze waste materials in an atmosphere of 336% steam and 4.4% oxygen. Throughput ranged from 0.14 to 0.27 kg/hr depending on the variability in the waste material composition and density

  17. Landfilling of waste incineration residues

    DEFF Research Database (Denmark)

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

    2002-01-01

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

  18. Domestic wastes incineration in France situation in 2000 evolution and perspectives the 31.12.2002; Incineration des dechets menagers en France situation en 2000 evolution et perspectives au 31.12.2002

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2003-07-01

    This document presents the analysis and the conclusions of a working group, concerning the domestic wastes incineration. It presents successively the place of the domestic wastes in the wastes management approach, the regulations, the methodology and the corresponding results of an inquiry realized in 2000 and the research programs on the incineration as the Best Available Techniques, the sanitary impacts of the UIOM (domestic wastes incineration plants), the vitrification, the greenhouse effect. (A.L.B.)

  19. Volume reduction and solidification of radioactive waste incineration ash with waste glass

    International Nuclear Information System (INIS)

    Koyama, Hidemi; Kobayashi, Masayuki

    2007-01-01

    The low-level radioactive waste generated from research institutions and hospitals etc. is packed into a container and is kept. The volume reduced state or the unprocessed state by incineration or compression processing are used because neither landfill sites nor disposal methods have been fixed. Especially, because the bulk density is low, and it is easy to disperse, the low-level radioactive waste incineration ash incinerated for the volume reduction is a big issue in security, safety, stability in the inventory location. A safe and appropriate disposal processing method is desired. When the low temperature sintering method in the use of the glass bottle cullet was examined, volume reduction and stabilization of low-level radioactive waste incineration ash were verified. The proposed method is useful for the easy treatment of the low-level radioactive waste incineration ash. (author)

  20. Medical Applications of Non-Medical Research: Applications Derived from BES-Supported Research and Research at BES Facilities

    Science.gov (United States)

    1998-07-01

    This publication contains stories that illustrate how the Office of Basic Energy Sciences (BES) research and major user facilities have impacted the medical sciences in the selected topical areas of disease diagnosis, treatment (including drug development, radiation therapy, and surgery), understanding, and prevention.

  1. Field Research Facility Data Integration Framework Data Management Plan: Survey Lines Dataset

    Science.gov (United States)

    2016-08-01

    ER D C/ CH L SR -1 6- 4 Coastal Ocean Data Systems Program Field Research Facility Data Integration Framework Data Management Plan...Systems Program ERDC/CHL SR-16-4 August 2016 Field Research Facility Data Integration Framework Data Management Plan Survey Lines Dataset Michael F...TITLE AND SUBTITLE Field Research Facility Data Integration Framework Data Management Plan: Survey Lines Dataset 5a. CONTRACT NUMBER 5b. GRANT NUMBER

  2. Material accountancy and control practice at a research reactor facility

    International Nuclear Information System (INIS)

    Bouchard, J.; Maurel, J.J.; Tromeur, Y.

    1982-01-01

    This session surveys the regulations, organization, and accountancy practice that compose the French State System of Accountancy and Control. Practical examples are discussed showing how inventories are verified at a critical assembly facility and at a materials testing reactor

  3. Health physics aspects of incineration of low level radioactive solvent at the Savannah River Plant

    International Nuclear Information System (INIS)

    Strain, C.D.

    1987-01-01

    This document contains the lecture notes and illustrations used in a presentation at the 1987 Health Physics Society Annual Meeting in Salt Lake City, Utah. Included is a description of the radioactive waste disposal facilities at the Savannah River Plant, South Carolina, and of the current use of this facility in incinerating thousands of gallons of radioactive waste. 12 figs

  4. Joint Actinide Shock Physics Experimental Research (JASPER) Facility Overview

    International Nuclear Information System (INIS)

    Konrad, C.H.; Braddy, R.W.; Martinez, Mark

    2001-01-01

    The JASPER Facility will utilize a Two-Stage Light Gas Gun to conduct equation-of-state (EOS) experiments of plutonium and other special nuclear materials. The overall facility will be discussed with emphasis on the Two-Stage Light Gas Gun characteristics and mission. The primary and secondary containment systems that were developed for this project will be presented. Primary gun diagnostics and timing will also be discussed

  5. A neutron tomography facility at a low power research reactor

    International Nuclear Information System (INIS)

    Koerner, S.; Schillinger, B.; Vontobel, P.; Rauch, H.

    2001-01-01

    Neutron radiography (NR) provides a very efficient tool in the field of non-destructive testing as well as for many applications in fundamental research. A neutron beam penetrating a specimen is attenuated by the sample material and detected by a two-dimensional (2D) imaging device. The image contains information about materials and structure inside the sample because neutrons are attenuated according to the basic law of radiation attenuation. Contrary to X-rays, neutrons can be attenuated by some light materials, as for example, hydrogen and boron, but penetrate many heavy materials. Therefore, NR can yield important information not obtainable by more traditional methods. Nevertheless, there are many aspects of structure, both quantitative and qualitative, that are not accessible from 2D transmission images. Hence, there is an interest in three-dimensional neutron imaging. At the 250 kW TRIGA Mark II reactor of the Atominstitut in Austria a neutron tomography facility has been installed. The neutron flux at this beam position is 1.3x10 5 neutrons/cm 2 s and the beam diameter is 8 cm. For a 3D tomographic reconstruction of the sample interior, transmission images of the object taken from different view angles are required. Therefore, a rotary table driven by a step motor connected to a computerized motion control system has been installed at the sample position. In parallel a suitable electronic imaging device based on a neutron sensitive scintillator screen and a CCD-camera has been designed. It can be controlled by a computer in order to synchronize the software of the detector and of the rotary table with the aim of an automation of measurements. Reasonable exposure times can get as low as 20 s per image. This means that a complete tomography of a sample can be performed within one working day. Calculation of the 3D voxel array is made by using the filtered backprojection algorithm

  6. Implementation Plans for a Systems Microbiology and Extremophile Research Facility

    Energy Technology Data Exchange (ETDEWEB)

    Wiley, H. S.

    2009-04-20

    solve DOE problems. Recent advances in whole-genome sequencing for a variety of organisms and improvements in high-throughput instrumentation have contributed to a rapid transition of the biological research paradigm towards understanding biology at a systems level. As a result, biology is evolving from a descriptive to a quantitative, ultimately predictive science where the ability to collect and productively use large amounts of biological data is crucial. Understanding how the ensemble of proteins in cells gives rise to biological outcomes is fundamental to systems biology. These advances will require new technologies and approaches to measure and track the temporal and spatial disposition of proteins in cells and how networks of proteins and other regulatory molecules give rise to specific activities. The DOE has a strong interest in promoting the application of systems biology to understanding microbial function and this comprises a major focus of its Genomics:GTL program. A major problem in pursuing what has been termed “systems microbiology” is the lack of the facilities and infrastructure for conducting this new style of research. To solve this problem, the Genomics:GTL program has funded a number of large-scale research centers focused on either mission-oriented outcomes, such as bioenergy, or basic technologies, such as gene sequencing, high-throughput proteomics or the identification of protein complexes. Although these centers generate data that will be useful to the research community, their scientific goals are relatively narrow and are not designed to accommodate the general community need for advanced capabilities for systems microbiology research.

  7. Strategic planning and marketing research for older, inner-city health care facilities: a case study.

    Science.gov (United States)

    Wood, V R; Robertson, K R

    1992-01-01

    Numerous health care facilities, located in downtown metropolitan areas, now find themselves surrounded by a decaying inner-city environment. Consumers may perceive these facilities as "old," and catering to an "urban poor" consumer. These same consumers may, therefore, prefer to patronize more modern facilities located in suburban areas. This paper presents a case study of such a health care facility and how strategic planning and marketing research were conducted in order to identify market opportunities and new strategic directions.

  8. The Radiological Research Accelerator Facility. Progress report, December 1, 1993--November 30, 1994

    International Nuclear Information System (INIS)

    Hall, E.J.; Marino, S.A.

    1994-04-01

    This document begins with a general description of the facility to include historical and up-to-date aspects of design and operation. A user's guide and a review of research using the facility follows. Next the accelerator utilization and operation and the development of the facilities is given. Personnel currently working at the facility are listed. Lastly, recent publications and literature cited are presented

  9. Effectiveness of incinerators in the management of medical wastes ...

    African Journals Online (AJOL)

    Introduction and Objectives Medical waste incinerators release into the air a host of pollutants that have serious adverse consequences on public health and the environment. This study aimed at determining ... Questionnaires, researcher observation and laboratory investigations of ash samples were used in data collection.

  10. Transformation of Silver Nanoparticles in Fresh, Aged, and Incinerated Biosolids

    Science.gov (United States)

    Abstract The purpose of this research was to assess the chemical transformation of silver nanoparticles (AgNPs) in aged, fresh, and incinerated biosolids in order to provide information for AgNP life cycle analyses. Silver nanoparticles were introduced to the influent of a pilot...

  11. Hardware Development Process for Human Research Facility Applications

    Science.gov (United States)

    Bauer, Liz

    2000-01-01

    The simple goal of the Human Research Facility (HRF) is to conduct human research experiments on the International Space Station (ISS) astronauts during long-duration missions. This is accomplished by providing integration and operation of the necessary hardware and software capabilities. A typical hardware development flow consists of five stages: functional inputs and requirements definition, market research, design life cycle through hardware delivery, crew training, and mission support. The purpose of this presentation is to guide the audience through the early hardware development process: requirement definition through selecting a development path. Specific HRF equipment is used to illustrate the hardware development paths. The source of hardware requirements is the science community and HRF program. The HRF Science Working Group, consisting of SCientists from various medical disciplines, defined a basic set of equipment with functional requirements. This established the performance requirements of the hardware. HRF program requirements focus on making the hardware safe and operational in a space environment. This includes structural, thermal, human factors, and material requirements. Science and HRF program requirements are defined in a hardware requirements document which includes verification methods. Once the hardware is fabricated, requirements are verified by inspection, test, analysis, or demonstration. All data is compiled and reviewed to certify the hardware for flight. Obviously, the basis for all hardware development activities is requirement definition. Full and complete requirement definition is ideal prior to initiating the hardware development. However, this is generally not the case, but the hardware team typically has functional inputs as a guide. The first step is for engineers to conduct market research based on the functional inputs provided by scientists. CommerCially available products are evaluated against the science requirements as

  12. YALINA facility a sub-critical Accelerator- Driven System (ADS) for nuclear energy research facility description and an overview of the research program (1997-2008).

    Energy Technology Data Exchange (ETDEWEB)

    Gohar, Y.; Smith, D. L.; Nuclear Engineering Division

    2010-04-28

    The YALINA facility is a zero-power, sub-critical assembly driven by a conventional neutron generator. It was conceived, constructed, and put into operation at the Radiation Physics and Chemistry Problems Institute of the National Academy of Sciences of Belarus located in Minsk-Sosny, Belarus. This facility was conceived for the purpose of investigating the static and dynamic neutronics properties of accelerator driven sub-critical systems, and to serve as a neutron source for investigating the properties of nuclear reactions, in particular transmutation reactions involving minor-actinide nuclei. This report provides a detailed description of this facility and documents the progress of research carried out there during a period of approximately a decade since the facility was conceived and built until the end of 2008. During its history of development and operation to date (1997-2008), the YALINA facility has hosted several foreign groups that worked with the resident staff as collaborators. The participation of Argonne National Laboratory in the YALINA research programs commenced in 2005. For obvious reasons, special emphasis is placed in this report on the work at YALINA facility that has involved Argonne's participation. Attention is given here to the experimental program at YALINA facility as well as to analytical investigations aimed at validating codes and computational procedures and at providing a better understanding of the physics and operational behavior of the YALINA facility in particular, and ADS systems in general, during the period 1997-2008.

  13. Science and Engineering Research Council Central Laser Facility

    International Nuclear Information System (INIS)

    1981-03-01

    This report covers the work done at, or in association with, the Central Laser Facility during the year April 1980 to March 1981. In the first chapter the major reconstruction and upgrade of the glass laser, which has been undertaken in order to increase the versatility of the facility, is described. The work of the six groups of the Glass Laser Scientific Progamme and Scheduling Committee is described in further chapters entitled; glass laser development, laser plasma interactions, transport and particle emission studies, ablative acceleration and compression studies, spectroscopy and XUV lasers, and theory and computation. Publications based on the work of the facility which have either appeared or been accepted for publication during the year are listed. (U.K.)

  14. Impact of community engagement on public acceptance towards waste-to-energy incineration projects: Empirical evidence from China.

    Science.gov (United States)

    Liu, Yong; Sun, Chenjunyan; Xia, Bo; Cui, Caiyun; Coffey, Vaughan

    2018-02-20

    As one of the most popular methods for the treatment of municipal solid waste (MSW), waste-to-energy (WTE) incineration offers effective solutions to deal with the MSW surge and globe energy issues. Nevertheless, the construction of WTE facilities faces considerable and strong opposition from local communities due to the perceived potential risks. The present study aims to understand whether, and how, community engagement improves local residents' public acceptance towards waste-to-energy (WTE) incineration facilities using a questionnaire survey conducted with nearby residents of two selected WTE incineration plants located in Zhejiang province, China. The results of data analysis using Structural Equation Modeling (SEM) reveal that firstly, a lower level of public acceptance exists among local residents of over the age of 35, of lower education levels, living within 3 km from the WTE Plant and from WTE incineration Plants which are under construction. Secondly, the public trust of local government and other authorities was positively associated with the public acceptance of the WTE incineration project, both directly and indirectly based on perceived risk. Thirdly, community engagement can effectively enhance public trust in local government and other authorities related to the WTE incineration project. The findings contribute to the literature on MSW treatment policy-making and potentially hazardous facility siting, by exploring the determinants of public acceptance towards WTE incineration projects. Copyright © 2018 Elsevier Ltd. All rights reserved.

  15. Current Status and Issues of Nuclear Engineering Research and Educational Facilities in Universities

    International Nuclear Information System (INIS)

    2004-01-01

    It is important to discuss about nuclear engineering research and educational facilities in universities after new educational foundation. 12 universities investigated issues and a countermeasure of them. The results of a questionnaire survey, issues and countermeasure are shown in this paper. The questionnaire on the future nuclear researches, development of education, project, maintenance of nuclear and radioactive facilities and accelerator, control of uranium in subcritical test facilities, use of new corporation facilities, the fixed number of student, number of graduate, student experiments, themes of experiments and researches, the state of educational facilities are carried out. The results of questionnaire were summarized as followings: the fixed number of student (B/M/D) on nuclear engineering, exercise of reactor, education, themes, educational and research facilities, significance of nuclear engineering education in university and proposal. (S.Y.)

  16. Research and development activities of a neutron generator facility

    International Nuclear Information System (INIS)

    Darsono Sudjatmoko; Pramudita Anggraita; Sukarman Aminjoyo

    2000-01-01

    The neutron generator facility at YNRC is used for elemental analysis, nuclear data measurement and education. In nuclear data measurement the focus is on re-evaluating the existing scattered nuclear activation cross-section to obtain systematic data for nuclear reactions such as (n,p), (n,α), and (n,2n). In elemental analysis it is used for analyzing the Nitrogen (N), Phosphor (P) and Potassium (K) contents in chemical and natural fertilizers (compost), protein in rice, soybean, and corn and pollution level in rivers. The neutron generator is also used for education and training of BATAN staff and university students. The facility can also produce neutron generator components. (author)

  17. Development of new irradiation facility for BWR safety research

    International Nuclear Information System (INIS)

    Okada, Yuji; Magome, Hirokatsu; Iida, Kazuhiro; Hanawa, Hiroshi; Ohmi, Masao

    2013-01-01

    In JAEA (Japan Atomic Energy Agency), about the irradiation embrittlement of the reactor pressure vessel and the stress corrosion cracking of reactor core composition apparatus concerning the long-term use of the light water reactor (BWR), in order to check the influence of the temperature, pressure, and water quality, etc on BWR condition. The water environmental control facility which performs irradiation assisted stress corrosion-cracking (IASCC) evaluation under BWR irradiation environment was fabricated in JMTR (Japan Materials Testing Reactor). This report is described the outline of manufacture of the water environmental control facility for doing an irradiation test using the saturation temperature capsule after JMTR re-operation. (author)

  18. Non-European facilities for elementary particle physics research

    International Nuclear Information System (INIS)

    Mann, A.K.

    1983-01-01

    The facilities we now employ in high energy physics cover a broad spectrum of particle energies and intensities and provide therefore a multiplicity of probes with which to study the behavior of elementary particles. In general, the goal has been to achieve ever higher particle energies and intensities, with emphasis on energy, and to develop more versatile and more sensitive detectors with which to study the resultant particle-particle interactions. Most energy regimes that have been explored have yielded new, fundamental information which often becomes clearer and more easily developed when particle energies are further increased. In this talk I shall try to delineate the nature of those facilities in Canada, Japan and the U.S.A. It is useful, I believe, to begin with a brief discussion of the funding and management of facilities in those countries and a short summary of recent history. The main body of the talk concentrates on the present, planned and contemplated facilities of the major non-European accelerator laboratories, and address briefly the status of accelerator development. The concluding section will summarize the salient features of the discussion. (author)

  19. Conference on the research facilities for future nuclear power engineering

    International Nuclear Information System (INIS)

    Arkhangel'skij, N.V.

    1996-01-01

    The activity of the European nuclear society Conference (Belgium, June, 1996) is described. The main topics of 60 presented reports are the following ones: necessity of developing new experimental facilities and their parameters; financing prospects and international cooperation in this field

  20. Research Facilities for Solar Astronomy at ARIES P. Pant

    Indian Academy of Sciences (India)

    a Robot recorder camera for solar patrolling in Hα respectively. With the advancement in solar observing techniques with high temporal and spatial resolution in Hα and other wavelengths, it became inevitable to acquire sophisticated instrumentation for data acquisition. In view of that, the above facilities were upgraded, ...

  1. The Use of Internet Facilities in Teaching and Research by ...

    African Journals Online (AJOL)

    The study investigates the use of internet facilities by the academic staff of School of Management and Information Technology (SMIT) in Modibbo Adama University of Technology (MAUTECH), Yola. Literatures have been reviewed based on the objectives of the study. The findings of the study will be used to improve ...

  2. Experience with high-temperature filtration of incinerator flue gases

    International Nuclear Information System (INIS)

    Carpentier, S.; de Tassigny, C.

    1990-01-01

    It is always preferable to filter incinerator flue gases as close as possible to their origin, i.e. in a high-temperature zone, and means must be provided to destroy the other organic parts of the flyash resulting from these gases by in-filter combustion. The filter also traps a mineral part of the flyash, which eventually causes clogging and requires replacement or regeneration. Such filtration systems are available and can be operated on an industrial scale. They include candles made of micro-expanded refractory alloys supporting filtering media, porous ceramic candles and other devices. Research and subsequent pilot facility testing have enabled development of alumina fiber filter cartridges that offer more advantages than other equipment employed to date. Specifically, these advantages are: ultralight weight, which enables construction of systems that are relatively unaffected by creep and high-temperature deformations; excellent refractory qualities, which permit a use above 1000 degrees C; insensitivity to thermal shocks and in-situ carbon fines combustion capability; anti-acid quality of the material, which enables high-temperature filtration of acidic flue gases (chlorine and hydrochloric acid, SO x , etc.); low initial pressure drop of the cartridges; dimensional stability of the cartridges, which can be machined to a given tolerance with specific contours after casting and drying. This paper reports the results obtained during the last filtration system test campaign. Details are given for operating conditions, grain sizes and real-time monitoring of various parameters

  3. Report on progress of researches by common utilization of JAERI nuclear facilities, for fiscal 1992

    International Nuclear Information System (INIS)

    1993-08-01

    The results of the joint researches by utilizing the facilities of JAERI in 1992 fiscal year were summarized. The number of research themes in 1992 was 247 cases. In this book, 166 reports are collected. (J.P.N.)

  4. Report on progress of researches by common utilization of JAERI nuclear facilities, for fiscal 1993

    International Nuclear Information System (INIS)

    1994-07-01

    The results of the joint researches by utilizing the facilities of JAERI in 1993 fiscal year were summarized. The number of research themes in 1993 was 228 cases. In this book, 243 reports are collected. (J.P.N.)

  5. Direct sunlight facility for testing and research in HCPV

    Energy Technology Data Exchange (ETDEWEB)

    Sciortino, Luisa, E-mail: luisa.sciortino@unipa.it; Agnello, Simonpietro, E-mail: luisa.sciortino@unipa.it; Bonsignore, Gaetano; Cannas, Marco; Gelardi, Franco Mario; Napoli, Gianluca; Spallino, Luisa [Dipartimento di Fisica e Chimica, Università degli Studi di Palermo, Via Archirafi 36, 90123 PA (Italy); Barbera, Marco [Dipartimento di Fisica e Chimica, Università degli Studi di Palermo, Via Archirafi 36, 90123 PA, Italy and Istituto Nazionale di Astrofisica, Osservatorio Astronomico di Palermo G. S. Vaiana, Piazza del Parlamento 1, 90134 PA (Italy); Buscemi, Alessandro; Montagnino, Fabio Maria; Paredes, Filippo [IDEA s.r.l., Contrada Molara, Zona Industriale III Fase, 90018 Termini Imerese (Panama) (Italy); Candia, Roberto; Collura, Alfonso; Di Cicca, Gaspare; Cicero, Ugo Lo; Varisco, Salvo [Istituto Nazionale di Astrofisica, Osservatorio Astronomico di Palermo G. S. Vaiana, Piazza del Parlamento 1, 90134 PA (Italy)

    2014-09-26

    A facility for testing different components for HCPV application has been developed in the framework of 'Fotovoltaico ad Alta Efficienza' (FAE) project funded by the Sicilian Regional Authority (PO FESR Sicilia 2007/2013 4.1.1.1). The testing facility is equipped with an heliostat providing a wide solar beam inside the lab, an optical bench for mounting and aligning the HCPV components, electronic equipments to characterize the I-V curves of multijunction cells operated up to 2000 suns, a system to circulate a fluid in the heat sink at controlled temperature and flow-rate, a data logging system with sensors to measure temperatures in several locations and fluid pressures at the inlet and outlet of the heat sink, and a climatic chamber with large test volume to test assembled HCPV modules.

  6. Phytochrome-mediated responses: Implications for controlled environment research facilities

    Science.gov (United States)

    Smith, Harry

    1994-01-01

    Light is undoubtedly the most important environmental variable for plant growth and development; plants not only use radiant energy in photosynthesis, they also respond to the quantity, quality, direction and timing of incident radiation through photomorphogenic response that can have huge effects on the rate of growth and the pattern of development. It is surprising, therefore, that the manufacturers and suppliers of controlled environment facilities have been singularly uninventive in the design of the lighting assemblies they provide. The consumer has one choice only - a lighting assembly that provides irradiance levels usually only a fraction of sunlight, and a control system that is limited to regulating the timing of the on-off switch. The reasons for these limitations are partly technological, but in the main they result from ignorance on the part of both the consumer and the manufacturer. A specific and powerful example of this ignorance relates to the importance of the so-called far-red wavelengths (FR = 700-800 nm). Because the human eye can hardly detect wavelengths above 700 nm, and photosynthesis also cuts off at about 700 nm, the majority of plant and crop physiologists are still almost completely unaware that FR radiation can have massive effects on growth rate and development. In consequence, most growth cabinets have light sources based on fluorescent tubes, and provide very little FR apart from that emitted by a token number of small incandescent bulbs. Larger growth facilities often use broader spectrum light sources, but growth facilities that provide the capability to vary the FR incident upon the plants are about as abundant as seals in the Sahara. This article sets the background of the significance of FR radiation in the natural environment and its importance for plant growth and development in the hope that it might inform intelligently those concerned with improving the design of plant growth facilities.

  7. Phytochrome-mediated responses implications for controlled environment research facilities

    Energy Technology Data Exchange (ETDEWEB)

    Smith, H. [Univ. of Leicester (United Kingdom)

    1994-12-31

    Light is undoubtedly the most important environmental variable for plant growth and development; plants not only use radiant energy in photosynthesis, they also respond to the quantity, quality, direction and timing of incident radiation through photomorphogenic responses that can have huge effects on the rate of growth and the pattern of development. It is surprising, therefore, that the manufacturers and suppliers of controlled environment facilities have been singularly uninventive in the design of the lighting assemblies they provide. The consumer has one choice only - a lighting assembly that provides irradiance levels usually only a fraction of sunlight, and a control system that is limited to regulating the timing of the on-off switch. The reasons for these limitations are partly technological, but in the main they result from ignorance on the part of both the consumer and the manufacturer. A specific and powerful example of this ignorance relates to the importance of the so-called far-red wavelengths (FR = 700-800 nm). Because the human eye can hardly detect wavelengths above 700 nm, and photosynthesis also cuts off at ca. 700 mn, the majority of plant and crop physiologists are still almost completely unaware that FR radiation can have massive effects on growth rate and development. In consequence, most growth cabinets have light sources based on fluorescent tubes, and provide very little FR apart from that emitted by a token number of small incandescent bulbs. Larger growth facilities often use broader spectrum light sources, but growth facilities that provide the capability to vary the FR incident upon the plants are about as abundant as seals in the Sahara. This article sets the background of the significance of FR radiation in the natural environment and its importance for plant growth and development in the hope that it might inform intelligently those concerned with improving the design of plant growth facilities.

  8. Delivery Order 9 Enhanced Preliminary Assessment, Woodbridge Research Facility, Virginia

    Science.gov (United States)

    1992-03-01

    Development and Readiness Command DCE 1,2-dichloroethylene DEH Department of Engineering and Housing DNA Defense Nuclear Agency DOD Department of...stereos) for the Defense Nuclear Agency ( DNA ). 2.2 DESCRIPTION OF FACILITIES This subsection provides a brief overview of the operations and...Glossy Ibis (Pleggdis falcinellus) Red-shouldered Hawk (Buteo lineatus) Eastern Bluebird (Sialia sialis) Grasshopper Sparrow (Ammodramus savannarum

  9. The new cold neutron research facility at the Budapest Research Reactor

    International Nuclear Information System (INIS)

    Rosta, L.

    2001-01-01

    The new cold neutron research facility is routinely operated at the Budapest Neutron Centre since February 2001. At the 10 MW research reactor a liquid hydrogen cold neutron source (CNS) has been installed. The commissioning of the CNS has been followed by the replacement of the old neutron guides by a new supermirror guide system both for the in-pile and out-of pile part. The ensemble of the CNS and new guides provides an intensity gain of the order of 30-60. The cold neutron channel has a take-off for three beams. The first guide serves for a triple axis spectrometer and a prompt gamma activation analysis station. A small angle scattering spectrometer is installed on the middle guide, and a reflectometer is operated on the third one. (author)

  10. NATO Advanced Research Workshop on Brilliant Light Facilities and Research in Life and Material Sciences

    CERN Document Server

    Tsakanov, Vasili; Brilliant Light in Life and Material Sciences

    2007-01-01

    The present book contains an excellent overview of the status and highlights of brilliant light facilities and their applications in biology, chemistry, medicine, materials and environmental sciences. Overview papers on diverse fields of research by leading experts are accompanied by the highlights in the near and long-term perspectives of brilliant X-Ray photon beam usage for fundamental and applied research. The book includes advanced topics in the fields of high brightness photon beams, instrumentation, the spectroscopy, microscopy, scattering and imaging experimental techniques and their applications. The book is strongly recommended for students, engineers and scientists in the field of accelerator physics, X-ray optics and instrumentation, life, materials and environmental sciences, bio and nanotechnology.

  11. Thermal treatment of historical radioactive solid and liquid waste into the CILVA incinerator

    International Nuclear Information System (INIS)

    Deckers, Jan; Mols, Ludo

    2007-01-01

    Since the very beginning of the nuclear activities in Belgium, the incineration of radioactive waste was chosen as a suitable technique for achieving an optimal volume reduction of the produced waste quantities. Based on the 35 years experience gained by the operation of the old incinerator, a new industrial incineration plant started nuclear operation in May 1995, as a part of the Belgian Centralized Treatment/Conditioning Facility named CILVA. Up to the end of 2006, the CILVA incinerator has burnt 1660 tonne of solid waste and 419 tonne of liquid waste. This paper describes the type and allowable radioactivity of the waste, the incineration process, heat recovery and the air pollution control devices. Special attention is given to the treatment of several hundreds of tonne historical waste from former reprocessing activities such as alpha suspected solid waste, aqueous and organic liquid waste and spent ion exchange resins. The capacity, volume reduction, chemical and radiological emissions are also evaluated. BELGOPROCESS, a company set up in 1984 at Dessel (Belgium) where a number of nuclear facilities were already installed is specialized in the processing of radioactive waste. It is a subsidiary of ONDRAF/NIRAS, the Belgian Nuclear Waste Management Agency. According to its mission statement, the activities of BELGOPROCESS focus on three areas: treatment, conditioning and interim storage of radioactive waste; decommissioning of shut-down nuclear facilities and cleaning of contaminated buildings and land; operating of storage sites for conditioned radioactive waste. (authors)

  12. The Budapest research reactor as an advanced research facility for the early 21st century

    International Nuclear Information System (INIS)

    Vidovszky, I.

    2001-01-01

    The Budapest Research Reactor, Hungary's first nuclear facility was originally put into operation in 1959. The reactor serves for: basic and applied research, technological and commercial applications, education and training. The main goal of the reactor is to serve neutron research. This unique research possibility is used by a broad user community of Europe. Eight instruments for neutron scattering, radiography and activation analyses are already used, others (e.g. time of flight spectrometer, neutron reflectometer) are being installed. The majority of these instruments will get a much improved utilization when the cold neutron source is put into operation. In 1999 the Budapest Research Reactor was operated for 3129 full power hours in 14 periods. The normal operation period took 234 hours (starting Monday noon and finishing Thursday morning). The entire production for the year 1999 was 1302 MW days. This is a slightly reduced value, due to the installation of the cold neutron source. For the year 2000 a somewhat longer operation is foreseen (near to 4000 hours), as the cold neutron source will be operational. The operation of the reactor is foreseen at least up to the end of the first decade of the 21 st century. (author)

  13. 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

  14. Proposal for a seismic facility for reactor safety research

    International Nuclear Information System (INIS)

    Anderson, C.A.; Dove, R.C.; Rhorer, R.L.

    1976-07-01

    Certain problem areas in the seismic analysis and design of nuclear reactors are enumerated and the way in which an experimental program might contribute to each area is examined. The use of seismic simulation testing receives particular attention, especially with regard to the verification of structural response analysis. The importance of scale modeling used in conjunction with seismic simulation is also stressed. The capabilities of existing seismic simulators are summarized, and a proposed facility is described which would considerably extend the ability to conduct, with confidence, confirmatory experiments on the behavior of reactor components when subjected to seismic excitation. Particular applications to gas-cooled and other reactor types are described

  15. Health-care waste incineration and related dangers to public health: case study of the two teaching and referral hospitals in Kenya.

    Science.gov (United States)

    Njagi, Nkonge A; Oloo, Mayabi A; Kithinji, J; Kithinji, Magambo J

    2012-12-01

    There are practically no low cost, environmentally friendly options in practice whether incineration, autoclaving, chemical treatment or microwaving (World Health Organisation in Health-care waste management training at national level, [2006] for treatment of health-care waste. In Kenya, incineration is the most popular treatment option for hazardous health-care waste from health-care facilities. It is the choice practiced at both Kenyatta National Hospital, Nairobi and Moi Teaching and Referral Hospital, Eldoret. A study was done on the possible public health risks posed by incineration of the segregated hazardous health-care waste in one of the incinerators in each of the two hospitals. Gaseous emissions were sampled and analyzed for specific gases the equipment was designed and the incinerators Combustion efficiency (CE) established. Combustion temperatures were also recorded. A flue gas analyzer (Model-Testos-350 XL) was used to sample flue gases in an incinerator under study at Kenyatta National Hospital--Nairobi and Moi Teaching and Referral Hospital--Eldoret to assess their incineration efficiency. Flue emissions were sampled when the incinerators were fully operational. However the flue gases sampled in the study, by use of the integrated pump were, oxygen, carbon monoxide, nitrogen dioxide, nitrous oxide, sulphur dioxide and No(x). The incinerator at KNH operated at a mean stack temperature of 746 °C and achieved a CE of 48.1 %. The incinerator at MTRH operated at a mean stack temperature of 811 °C and attained a CE of 60.8 %. The two health-care waste incinerators achieved CE below the specified minimum National limit of 99 %. At the detected stack temperatures, there was a possibility that other than the emissions identified, it was possible that the two incinerators tested released dioxins, furans and antineoplastic (cytotoxic drugs) fumes should the drugs be subjected to incineration in the two units.

  16. A chemical basis for the partitioning of radionuclides in incinerator operation

    Energy Technology Data Exchange (ETDEWEB)

    Burger, L.L.

    1994-09-01

    For waste containing small amounts of radioactivity, rad waste (RW), or mixed waste (MW) containing both radioactive and chemically hazardous components, incineration is a logical management candidate because of inherent safety, waste volume reduction, and low costs. Successful operation requires that the facility is properly designed and operated to protect workers and to limit releases of hazardous materials. The large decrease in waste volume achieved by incineration also results in a higher concentration of most of the radionuclides and non radioactive heavy metals in the ash products. These concentrations impact subsequent treatment and disposal. The various constituents (chemical elements) are not equal in concentration in the various incinerator feed materials, nor are they equal in their contribution to health risks on subsequent handling, or accidental release. Thus, for management of the wastes it is important to be able to predict how the nuclides partition between the primary combustion residue which may be an ash or a fused slag, the fine particulates or fly ash that is trapped in the burner off-gas by several different techniques, and the airborne fraction that escapes to the atmosphere. The objective of this report is to provide an estimate of how different elements of concern may behave in the chemical environment of the incinerator. The study briefly examines published incinerator operation data, then considers the properties of the elements of concern, and employs thermodynamic calculations, to help predict the fate of these RW and MW constituents. Many types and configurations of incinerators have been designed and tested.

  17. Heat supply from municipal solid waste incineration plants in Japan: Current situation and future challenges.

    Science.gov (United States)

    Tabata, Tomohiro; Tsai, Peii

    2016-02-01

    The use of waste-to-energy technology as part of a municipal solid waste management strategy could reduce the use of fossil fuels and contribute to prevention of global warming. In this study, we examined current heat and electricity production by incineration plants in Japan for external use. Herein, we discuss specific challenges to the promotion of heat utilisation and future municipal solid waste management strategies. We conducted a questionnaire survey to determine the actual conditions of heat production by incineration plants. From the survey results, information of about 498 incineration plants was extracted. When we investigated the relationship between heat production for external use and population density where incineration plants were located, we found that regions with a population density incineration plants have poor performance for heat production because there are few facilities near them to provide demand for the energy. This is the result of redundant capacity, and is reflected in the heat production performance. Given these results, we discussed future challenges to creating energy demand around incineration plants where there is presently none. We also examined the challenges involved in increasing heat supply beyond the present situation. © The Author(s) 2015.

  18. Mercury contamination and potential impacts from municipal waste incinerator on Samui Island, Thailand.

    Science.gov (United States)

    Muenhor, Dudsadee; Satayavivad, Jutamaad; Limpaseni, Wongpun; Parkpian, Preeda; Delaune, R D; Gambrell, R P; Jugsujinda, Aroon

    2009-03-01

    In recent years, mercury (Hg) pollution generated by municipal waste incinerators (MWIs) has become the subject of serious public concern. On Samui Island, Thailand, a large-scale municipal waste incinerator has been in operation for over 7 years with a capacity of 140 tons/day for meeting the growing demand for municipal waste disposal. This research assessed Hg contamination in environmental matrices adjacent to the waste incinerating plant. Total Hg concentrations were determined in municipal solid waste, soil and sediment within a distance of 100 m to 5 km from the incinerator operation in both wet and dry seasons. Hg analyses conducted in municipal solid waste showed low levels of Hg ranging between 0.15-0.56 mg/kg. The low level was due to the type of waste incinerator. Waste such as electrical appliances, motors and spare parts, rubber tires and hospital wastes are not allowed to feed into the plant. As a result, low Hg levels were also found in fly and bottom ashes (0.1-0.4 mg/kg and contaminated from Hg emissions produced by this incinerator. However the increase of Hg measured in downwind direction of the incinerator should be monitored for future potential risk.

  19. Design and construction of an urban runoff research facility.

    Science.gov (United States)

    Wherley, Benjamin G; White, Richard H; McInnes, Kevin J; Fontanier, Charles H; Thomas, James C; Aitkenhead-Peterson, Jacqueline A; Kelly, Steven T

    2014-08-08

    As the urban population increases, so does the area of irrigated urban landscape. Summer water use in urban areas can be 2-3x winter base line water use due to increased demand for landscape irrigation. Improper irrigation practices and large rainfall events can result in runoff from urban landscapes which has potential to carry nutrients and sediments into local streams and lakes where they may contribute to eutrophication. A 1,000 m(2) facility was constructed which consists of 24 individual 33.6 m(2) field plots, each equipped for measuring total runoff volumes with time and collection of runoff subsamples at selected intervals for quantification of chemical constituents in the runoff water from simulated urban landscapes. Runoff volumes from the first and second trials had coefficient of variability (CV) values of 38.2 and 28.7%, respectively. CV values for runoff pH, EC, and Na concentration for both trials were all under 10%. Concentrations of DOC, TDN, DON, PO₄₋P, K(+), Mg(2+), and Ca(2+) had CV values less than 50% in both trials. Overall, the results of testing performed after sod installation at the facility indicated good uniformity between plots for runoff volumes and chemical constituents. The large plot size is sufficient to include much of the natural variability and therefore provides better simulation of urban landscape ecosystems.

  20. Energy-Efficiency & Water Institute Research Facility, Purdue University, (IN)

    Energy Technology Data Exchange (ETDEWEB)

    Nnanna, Agbai [Purdue Univ., West Lafayette, IN (United States)

    2015-01-30

    The renovation of the Schneider Avenue Building to construct two research laboratories within the building is complete. The research laboratories are for the Purdue Calumet Water Institute and the Energy Efficiency and Reliability Center. The Water Institute occupies approximately 1000+ SF of research space plus supporting offices. The Energy-Efficiency Center occupies approximately 1000+ SF that houses the research space. The labs will enhance the Water & Energy Institute’s research capabilities necessary to tackle these issues through the development of practical approaches critical to local government and industry. The addition of these research laboratories to the Purdue University Calumet campus is in both direct support of the University’s Strategic Plan as well as the 2008 Campus Master Plan that identifies a 20% shortage of research space.

  1. Report on progress of researches by common utilization of JAERI nuclear facilities, for fiscal 1982

    International Nuclear Information System (INIS)

    1983-01-01

    The utilization of the facilities in the Japan Atomic Energy Research Institute in common in 1982 has finished in active state, and the results of the researches have reached the stage of publication. The subjects of the researches spread over wide fields, and in 1982 also, extremely diversified researches were carried out. In this report, theses results were collected in one book, and it is desirable to utilize it actively. The number of the research themes is 131. In the field of general researches, the researches on radiochemistry, the utilization of radiation and the effects of irradiation were mostly carried out, while in cooperative researches, the researches were mainly concerned with nuclear reactor engineering and nuclear reactor materials. The total number of visitors was 3025. The facilities offered to the common utilization were JRR-2, JRR-3, JRR-4, Co-60 irradiation facility and others. The abstracts of the papers are reported. (J.P.N.)

  2. Dangerous waste incineration and its impact on air quality. Case study: the incinerator SC Mondeco SRL Suceava

    Directory of Open Access Journals (Sweden)

    Dumitru MIHĂILĂ

    2015-03-01

    Full Text Available Dangerous waste, such as oil residues, pesticides, lacquers, stains, glues, organic solvents, hospital and food industry residues represent a major risk for all components of the environment (water, air, earth, soil, flora, fauna, people as well. Consequently, their incineration with high-performance burning installations lessens the impact on the environment, especially on the air quality, and it gives the possibility to recuperate the warmth of the incineration. This research presents a representative technique of incineration of dangerous waste at S.C. Mondeco S.R.L. Suceava, which runs according to the European standards, located in the industrial zone of Suceava, on the Suceava river valley Suceava. Also it is analysed the impact of this unit on the quality of nearby air. Moreover, not only the concentrations of gases and powders during the action of the incineration process (paramaters that are continuously monitored by highly methods are analysed, but also here are described the dispersions of those pollutants in the air, taking into account the characteristics of the source and the meteorological parametres that are in the riverbed. 

  3. User Facilities of the Office of Basic Energy Sciences: A National Resource for Scientific Research

    Energy Technology Data Exchange (ETDEWEB)

    None

    2009-01-01

    The BES user facilities provide open access to specialized instrumentation and expertise that enable scientific users from universities, national laboratories, and industry to carry out experiments and develop theories that could not be done at their home institutions. These forefront research facilities require resource commitments well beyond the scope of any non-government institution and open up otherwise inaccessible facets of Nature to scientific inquiry. For approved, peer-reviewed projects, instrument time is available without charge to researchers who intend to publish their results in the open literature. These large-scale user facilities have made significant contributions to various scientific fields, including chemistry, physics, geology, materials science, environmental science, biology, and biomedical science. Over 16,000 scientists and engineers.pdf file (27KB) conduct experiments at BES user facilities annually. Thousands of other researchers collaborate with these users and analyze the data measured at the facilities to publish new scientific findings in peer-reviewed journals.

  4. Design of multifunctional floating waste incineration plant. Umi ni ukabu takinogata yojo seisokojo wo koan

    Energy Technology Data Exchange (ETDEWEB)

    Kodama, T. (Shimizu Corp., Tokyo (Japan))

    1991-11-01

    A multifunctional floating waste incineration plant (aqua- amusement land: AAL) with combined health and leisure facilities is designed which can be built in much less time than the conventional plant and can be freely enlarged. The concepts for the AAL are the docking of water park and marine facilities to the floating waste incineration plant high degree reutilization of space materials and energy solving problems of high cost of land and traffic jam at the incineration plant due to environmental problem high price of land and overpopulation of cities. At the facility several waste disposal plant units are integrated various leisure facilities ocean culture facilities etc. are provided in two stages of upper and lower floors and exhaust heat generated by waste incineration is utilized effectively as the power source heat source etc. The feature of the AAL are solving land shortage problem shortening the term of works no necessity for submarine ground improvement flexibility of locational conditions high efficient use of exhaust heat flexibility of throughput performance possibility of marine transportation of wastes etc. 8 refs.

  5. Conceptual designs of near surface disposal facility for radioactive waste arising from the facilities using radioisotopes and research facilities for nuclear energy development and utilization

    International Nuclear Information System (INIS)

    Sakai, Akihiro; Yoshimori, Michiro; Okoshi, Minoru; Yamamoto, Tadatoshi; Abe, Masayoshi

    2001-03-01

    Various kinds of radioactive waste is generating from the utilization of radioisotopes in the field of science, technology, etc. and the utilization and development of nuclear energy. In order to promote the utilization of radionuclides and the research activities, it is necessary to treat and dispose of radioactive waste safely and economically. Japan Nuclear Cycle Development Institute (JNC), Japan Radioisotope Association (JRIA) and Japan Atomic Energy Research Institute (JAERI), which are the major waste generators in Japan in these fields, are promoting the technical investigations for treatment and disposal of the radioactive waste co-operately. Conceptual design of disposal facility is necessary to demonstrate the feasibility of waste disposal business and to determine the some conditions such as the area size of the disposal facility. Three institutes share the works to design disposal facility. Based on our research activities and experiences of waste disposal, JAERI implemented the designing of near surface disposal facilities, namely, simple earthen trench and concrete vaults. The designing was performed based on the following three assumed site conditions to cover the future site conditions: (1) Case 1 - Inland area with low groundwater level, (2) Case 2 - Inland area with high groundwater level, (3) Case 3 - Coastal area. The estimation of construction costs and the safety analysis were also performed based on the designing of facilities. The safety assessment results show that the safety for concrete vault type repository is ensured by adding low permeability soil layer, i.e. mixture of soil and bentonite, surrounding the vaults not depending on the site conditions. The safety assessment results for simple earthen trench also show that their safety is ensured not depending on the site conditions, if they are constructed above groundwater levels. The construction costs largely depend on the depth for excavation to build the repositories. (author)

  6. Scientific user facilities at Oak Ridge National Laboratory: New research capabilities and opportunities

    Science.gov (United States)

    Roberto, James

    2011-10-01

    Over the past decade, Oak Ridge National Laboratory (ORNL) has transformed its research infrastructure, particularly in the areas of neutron scattering, nanoscale science and technology, and high-performance computing. New facilities, including the Spallation Neutron Source, Center for Nanophase Materials Sciences, and Leadership Computing Facility, have been constructed that provide world-leading capabilities in neutron science, condensed matter and materials physics, and computational physics. In addition, many existing physics-related facilities have been upgraded with new capabilities, including new instruments and a high- intensity cold neutron source at the High Flux Isotope Reactor. These facilities are operated for the scientific community and are available to qualified users based on competitive peer-reviewed proposals. User facilities at ORNL currently welcome more than 2,500 researchers each year, mostly from universities. These facilities, many of which are unique in the world, will be reviewed including current and planned research capabilities, availability and operational performance, access procedures, and recent research results. Particular attention will be given to new neutron scattering capabilities, nanoscale science, and petascale simulation and modeling. In addition, user facilities provide a portal into ORNL that can enhance the development of research collaborations. The spectrum of partnership opportunities with ORNL will be described including collaborations, joint faculty, and graduate research and education.

  7. A novel DC Magnetron sputtering facility for space research and synchrotron radiation optics

    DEFF Research Database (Denmark)

    Hussain, A.M.; Christensen, Finn Erland; Pareschi, G.

    1998-01-01

    A new DC magnetron sputtering facility has been build up at the Danish Space Research Institute (DSRI), specially designed to enable uniform coatings of large area curved optics, such as Wolter-I mirror optics used in space telescopes and curved optics used in synchrotron radiation facilities...

  8. Science facilities and stakeholder management: how a pan-European research facility ended up in a small Swedish university town

    Science.gov (United States)

    Thomasson, Anna; Carlile, Colin

    2017-06-01

    This is the story of how a large research facility of broad European and global interest, the European Spallation Source (ESS), ended up in the small university town of Lund in Sweden. This happened in spite of the fact that a number of influential European countries were at one time or another competitors to host the facility. It is also a story about politics which attempts to illustrate how closely intertwined politics and science are, and how the interplay between those interests affects scientific progress. ESS became an arena for individual ambitions and political manoeuvring. The different stakeholders, in their striving to ensure that their own interests were realised, in various ways and with different degrees of success over the years, have influenced the key decisions that, during the already 30 year history of ESS, have driven the course that this project has taken. What emerges is that the interests of the stakeholders and the interests of the project itself are frequently not in harmony. This imposes challenges on the management of large research facilities as they have to not only navigate in the scientific landscape, which they often are more familiar with, but also in the political landscape. This story is therefore an attempt to shed light on the role of managers of large research facilities and the often delicate balancing act they have to perform when trying to comply with the different and often conflicting stakeholder interests. What is especially worthwhile examining, as we do in this paper, is the role that individuals, and the interaction between individuals, have played in the process. This shows that the focus of stakeholder theory on organisations, rather than the people in the organisations, needs to be redirected on to the individuals representing those organisations and their inter-relationships. At the same time it is clear that the developing field of stakeholder management theory has not emerged into the consciousness of science

  9. Research at the BNL Tandem Van de Graaff Facility, 1980

    Energy Technology Data Exchange (ETDEWEB)

    1981-03-01

    Research programs at the Brookhaven Van de Graaff accelerators are summarized. Major accomplishments of the laboratory are discussed including quasielastic reactions, high-spin spectroscopy, yrast spectra, fusion reactions, and atomic physics. The outside user program at the Laboratory is discussed. Research proposed for 1981 is outlined. (GHT)

  10. Research at the BNL Tandem Van de Graaff Facility, 1980

    International Nuclear Information System (INIS)

    1981-01-01

    Research programs at the Brookhaven Van de Graaff accelerators are summarized. Major accomplishments of the laboratory are discussed including quasielastic reactions, high-spin spectroscopy, yrast spectra, fusion reactions, and atomic physics. The outside user program at the Laboratory is discussed. Research proposed for 1981 is outlined

  11. Treatment of off-gas from radioactive waste incinerators

    International Nuclear Information System (INIS)

    1989-01-01

    An effective process reducing volume of radioactive wastes is incineration of combustible wastes. Appropriate design of the off-gas treatment system is necessary to ensure that any releases of airborne radionuclides into the environment are kept below acceptable limits. In many cases, the off-gas system must be designed to accommodate chemical constituents in the gas stream. The purpose of this publication is to provide the most up-to-date information regarding off-gas treatment as well as an account of some of the developments so as to aid users in the selection of an integrated system for a particular application. The choice of incinerator/off-gas system combination depends on the wastes to be treated, as well as other factors, such as regulatory requirements. Current problems and development needs are discussed. Following comprehensive discussions of the various factors affecting a choice, various incinerator and off-gas treatment systems are recommended for the various types of wastes that may be treated: low PVC content solid, high PVC content solid, organic liquid and resins. The economics or costs of the off-gas system and an evaluation of the overall cost effectiveness of incineration or direct burial is not discussed in detail. This publication is specifically directed toward technical aspects and addresses: incineration types and origin, sources and characteristics of off-gas streams; descriptions of available technologies for off-gas treatment; basic component design requirements and component description; operational experience of plants in active operation and their current practices; legal aspects and safety requirements; remaining problems to be solved and development trends in plant design and component structure. This report seeks to broaden and enhance the understanding of the developed technology and to indicate areas where improvements can be made by further research and development. 110 refs

  12. Materials for Waste Incinerators and Biomass Plants

    DEFF Research Database (Denmark)

    Rademakers, P.; Grossmann, G.; Karlsson, A.

    1998-01-01

    This paper reviews the projects of the sub-package on waste incineration and biomass firing carried out within COST 501 Round III, Work Package 13.......This paper reviews the projects of the sub-package on waste incineration and biomass firing carried out within COST 501 Round III, Work Package 13....

  13. High temperature incineration. Densification of granules from high temperature incineration

    International Nuclear Information System (INIS)

    Voorde, N. van de; Claes, J.; Taeymans, A.; Hennart, D.; Gijbels, J.; Balleux, W.; Geenen, G.; Vangeel, J.

    1982-01-01

    The incineration system of radioactive waste discussed in this report, is an ''integral'' system, which directly transforms a definite mixture of burnable and unburnable radioactive waste in a final product with a sufficient insolubility to be safely disposed of. At the same time, a significant volume reduction occurs by this treatment. The essential part of the system is a high temperature incinerator. The construction of this oven started in 1974, and while different tests with simulated inactive or very low-level active waste were carried out, the whole system was progressively and continuously extended and adapted, ending finally in an installation with completely remote control, enclosed in an alpha-tight room. In this report, a whole description of the plant and of its auxiliary installations will be given; then the already gained experimental results will be summarized. Finally, the planning for industrial operation will be briefly outlined. An extended test with radioactive waste, which was carried out in March 1981, will be discussed in the appendix

  14. ANI [American Nuclear Insurers] support and research facility nuclear liability insurance inspection program

    International Nuclear Information System (INIS)

    Ernst, B.

    1988-01-01

    American Nuclear Insurers (ANI), a voluntary association of insurance companies, provides property and nuclear liability insurance protection to the nuclear industry. It generally offers insurance coverage to nuclear facilities, suppliers, and transporters for the following: (1) their liability for damages because of bodily injury and/or property damage caused by the nuclear energy hazard, and (2) all-risk damage to nuclear facilities. Among the range of facilities and suppliers insured by ANI are (a) operators of nuclear power plants that supply electricity for the general public, (b) operators of nuclear testing and research reactors, (c) fuel fabricators that manufacture fuel for use in reactors, (d) operators of facilities that dispose of nuclear waste that cannot be salvaged, (e) facilities that maintain and repair equipment used at nuclear facilities, (f) nuclear laundries, and (g) low-level-waste processors. The fundamental goal of the ANI nuclear engineering inspection program is to provide protection to pool members' assets by reducing insurance risk

  15. Low-level waste incineration at the Idaho National Engineering Laboratory

    International Nuclear Information System (INIS)

    Gillins, R.L.; Davis, J.N.; Maughan, R.Y.; Logan, J.A.

    1985-01-01

    A facility for the incineration of low-level beta/gamma contaminated combustible waste has been constructed at the Waste Experimental Reduction Facility (WERF) at the Idaho National Engineering Laboratory (INEL). The incineration facility was established to: (1) reduce the volume of currently generated contaminated combustible waste being disposed at the INEL's radioactive waste disposal site and thereby prolong the site's useful life; and (2) develop waste processing technology by providing a facility where full-size processes and equipment can be demonstrated and proven during production-scale operations. Cold systems testing has been completed, and contaminated operations began in September of 1984. Currently the facility is processing waste packaged in 2 x 2 x 2 ft cardboard boxes and measuring <10mR/h at contact. 3 figs

  16. Organic household waste - incineration or recycling

    International Nuclear Information System (INIS)

    2003-01-01

    The Danish Environmental Protection Agency has carried out a cost benefit analysis of the consequences of increasing recycling of organic household waste. In the cost benefit analysis both the economic consequences for the affected parties and the welfare-economic consequences for the society as a whole have been investigated. In the welfare-economic analysis the value of the environmental effects has been included. The analysis shows that it is more expensive for the society to recycle organic household waste by anaerobic digestion or central composting than by incineration. Incineration is the cheapest solution for the society, while central composting is the most expensive. Furthermore, technical studies have shown that there are only small environmental benefits connected with anaerobic digestion of organic waste compared with incineration of the waste. The primary reason for recycling being more expensive than incineration is the necessary, but cost-intensive, dual collection of the household waste. Treatment itself is cheaper for recycling compared to incinerating. (BA)

  17. Archive of Geosample Information from the British Ocean Sediment Core Research Facility (BOSCORF)

    Data.gov (United States)

    National Oceanic and Atmospheric Administration, Department of Commerce — The British Ocean Sediment Core Research Facility (BOSCORF), National Oceanography Centre, is a contributor to the Index to Marine and Lacustrine Geological Samples...

  18. Atomic physics at the future facility for antiproton and ion research: a status report

    International Nuclear Information System (INIS)

    Gumberidze, A

    2013-01-01

    The new international accelerator Facility for Antiproton and Ion Research (FAIR) which is currently under construction in Darmstadt has key features that offer a wide range of exciting new opportunities in the field of atomic physics and related fields. The facility will provide highest intensities of relativistic beams of both stable and unstable heavy nuclei, in combination with the strong electromagnetic fields generated by high-power lasers, thus allowing to widen atomic physics research into completely new domains. In the current contribution, a short overview of the SPARC (Stored Particle Atomic physics Research Collaboration) research programme at the FAIR facility is given. Furthermore, we present the current strategy for the realization of the envisioned SPARC physics programme at the modularized start version of the FAIR facility. (paper)

  19. LMFBR safety testing needs and the conceptual design of a new safety research experiment facility

    International Nuclear Information System (INIS)

    Marchaterre, J.F.; Matlock, R.G.; Goldman, A.J.

    1975-09-01

    Experiment needs for the LMFBR safety program are reviewed. The screening of reactor concepts which would meet the needs is described and a conceptual design for a new safety research experiment facility is presented

  20. Research notes : drainage facility asset management : more than an inventory of pipes.

    Science.gov (United States)

    2007-04-01

    The primary objectives for the research project were twofold: 1) To develop and implement an Oregon-specific system for inventorying and evaluating the condition of pipes, culverts, and stormwater facilities based on the FHWA Culvert Management Syste...

  1. Multi-Specimen Variable-G Facility for Life and Microgravity Sciences Research Project

    Data.gov (United States)

    National Aeronautics and Space Administration — Techshot, Inc. proposes to develop a Multi-specimen Variable-G Facility (MVF) for life and microgravity sciences research. The MVF incorporates a generic...

  2. Research Support Facility - Zero Energy Building Moves Closer to Reality (Fact Sheet)

    Energy Technology Data Exchange (ETDEWEB)

    2010-04-01

    The DOE's Research Support Facility showcases high-performance design features, passive energy strategies, and renewable energy. It is a prototype for future large-scale net-zero energy buildings.

  3. Safety Analysis Report: X17B2 beamline Synchrotron Medical Research Facility

    International Nuclear Information System (INIS)

    Gmuer, N.F.; Thomlinson, W.

    1990-02-01

    This report contains a safety analysis for the X17B2 beamline synchrotron medical research facility. Health hazards, risk assessment and building systems are discussed. Reference is made to transvenous coronary angiography

  4. Sub-scale Direct Connect Supersonic Combustion Facility (Research Cell 18)

    Data.gov (United States)

    Federal Laboratory Consortium — Description: RC18 is a continuous-flow, direct-connect, supersonic-combustion research facility that is capable of simulating flight conditions from Mach 3.0 to Mach...

  5. Partnering with Industry to Advance Biofuels, NREL's Integrated Biorefinery Research Facility (Fact Sheet)

    Energy Technology Data Exchange (ETDEWEB)

    2010-10-01

    Fact sheet describing NREL's Integrated Biorefinery Research Facility and its availability to biofuels' industry partners who want to operate, test, and develop biorefining technology and equipment.

  6. Advanced Coal Liquefaction Research and Development Facility, Wilsonville, Alabama

    Energy Technology Data Exchange (ETDEWEB)

    1992-01-01

    This report presents the results of Run 260 performed at the Advanced Coal Liquefaction R D Facility in Wilsonville. The run was started on July 17, 1990 and continued until November 14, 1990, operating in the Close-Coupled Integrated Two-Stage Liquefaction mode processing Black Thunder mine subbituminous coal (Wyodak-Anderson seam from Wyoming Powder River Basin). Both thermal/catalytic and catalytic/thermal tests were performed to determine the methods for reducing solids buildup in a subbituminous coal operation, and to improve product yields. A new, smaller interstage separator was tested to reduce solids buildup by increasing the slurry space velocity in the separator. In order to obtain improved coal and resid conversions (compared to Run 258) full-volume thermal reactor and 3/4-volume catalytic reactor were used. Shell 324 catalyst, 1/16 in. cylindrical extrudate, at a replacement rate of 3 lb/ton of MF coal was used in the catalytic stage. Iron oxide was used as slurry catalyst at a rate of 2 wt % MF coal throughout the run. (TNPS was the sulfiding agent.)

  7. Advanced Coal Liquefaction Research and Development Facility, Wilsonville, Alabama

    Energy Technology Data Exchange (ETDEWEB)

    1992-09-01

    This report presents the results of Run 261 performed at the Advanced Coal Liquefaction R D Facility in Wilsonville, Alabama. The run started on January 12, 1991 and continued until May 31, 1991, operating in the Close-Coupled Integrated Two-Stage Liquefaction mode processing Illinois No. 6 seam bituminous coal (from Burning star No. 2 mine). In the first part of Run 261, a new bimodal catalyst, EXP-AO-60, was tested for its performance and attrition characteristics in the catalytic/catalytic mode of the CC-ITSL process. The main objective of this part of the run was to obtain good process performance in the low/high temperature mode of operation along with well-defined distillation product end boiling points. In the second part of Run 261, Criterion (Shell) 324 catalyst was tested. The objective of this test was to evaluate the operational stability and catalyst and process performance while processing the high ash Illinois No. 6 coal. Increasing viscosity and preasphaltenes made it difficult to operate at conditions similar to EXP-AO-60 catalyst operation, especially at lower catalyst replacement rates.

  8. Aifira: An ion beam facility for multidisciplinary research

    Science.gov (United States)

    Sorieul, S.; Alfaurt, Ph.; Daudin, L.; Serani, L.; Moretto, Ph.

    2014-08-01

    During the last decade, the CENBG (Centre d'Études Nucléaires de Bordeaux Gradignan) commissioned a new facility called AIFIRA (Applications Interdisciplinaires des Faisceaux d'ions en Région Aquitaine). It allowed the development of a multidisciplinary activity based on the "in-house" expertise of CENBG in ion beam analysis. The great flexibility offered by the five beam lines confers a lot of possibilities for chemical analysis and nuclear physics. Indeed, not only the macrobeam and the external beam lines provide the full set of IBA techniques for routine sample analysis but an additional beam line is devoted to the production of monoenergetic neutrons through the interaction of the incoming ion with selected targets. In addition, the two high-resolution microbeam lines are used for chemical analyses, 2D/3D imaging, and targeted cell irradiation. Besides, the combination of the nanobeam line flexibility, the uniqueness of the micro-irradiation design completed by the internal CENBG expertise confers a great specificity to AIFIRA in biomedical field. After a detailed technical overview of the platform, the article focuses on the two high-resolution lines as they tap most of the activity. Thus a quick overview of the most significant results concerning biomedical samples is proposed in order to highlight the analytical possibilities of AIFIRA microbeam lines. A summary of the development status of the micro-irradiation line is also done.

  9. Aifira: An ion beam facility for multidisciplinary research

    Energy Technology Data Exchange (ETDEWEB)

    Sorieul, S., E-mail: sorieul@cenbg.in2p3.fr; Alfaurt, Ph.; Daudin, L.; Serani, L.; Moretto, Ph.

    2014-08-01

    During the last decade, the CENBG (Centre d’Études Nucléaires de Bordeaux Gradignan) commissioned a new facility called AIFIRA (Applications Interdisciplinaires des Faisceaux d’ions en Région Aquitaine). It allowed the development of a multidisciplinary activity based on the “in-house” expertise of CENBG in ion beam analysis. The great flexibility offered by the five beam lines confers a lot of possibilities for chemical analysis and nuclear physics. Indeed, not only the macrobeam and the external beam lines provide the full set of IBA techniques for routine sample analysis but an additional beam line is devoted to the production of monoenergetic neutrons through the interaction of the incoming ion with selected targets. In addition, the two high-resolution microbeam lines are used for chemical analyses, 2D/3D imaging, and targeted cell irradiation. Besides, the combination of the nanobeam line flexibility, the uniqueness of the micro-irradiation design completed by the internal CENBG expertise confers a great specificity to AIFIRA in biomedical field. After a detailed technical overview of the platform, the article focuses on the two high-resolution lines as they tap most of the activity. Thus a quick overview of the most significant results concerning biomedical samples is proposed in order to highlight the analytical possibilities of AIFIRA microbeam lines. A summary of the development status of the micro-irradiation line is also done.

  10. Geomechanical research in the test drift of the Hades underground research facility at Mol

    International Nuclear Information System (INIS)

    Neerdael, B.; Bruyn, D. De

    1989-01-01

    In the framework of the Hades project, managed by the Belgian Nuclear Research Establishment (CEN-SCK), the Underground Research Facility (URF) was extended by the construction of a test drift. This test drift is a gallery of circular cross section composed of a 5.6m long access gallery (2.64m inner diameter), followed by a 42m long test zone (3.5m in diameter) lined with 60 cm- thick precast concrete segments. An alternative gallery lining concept (sliding steel ribs) has been developed by Andra and tested in a 12m long experimental gallery dug in the prolongation of the concrete lined test drift. Based on predictions by models and according to previous investigations at smaller scale, a geotechnical investigation programme, so called mine-by test, was designed and developed in the clay that surrounds the volume to be excavated. One more experiment was performed after the construction period (April 1988). It consists in quantifying the perturbation from the mechanical point of view around the drift by performing Self Boring Pressuremeter Tests at different distances from the gallery. The project is sponsored by the Commission of the European Communities in the frame of part B of the CEC programme on radioactive waste management and disposal and by ONDRAF-NIRAS, the Belgian Waste Management Authority

  11. Process control in municipal solid waste incinerators: survey and assessment.

    Science.gov (United States)

    El Asri, R; Baxter, D

    2004-06-01

    As there is only rare and scattered published information about the process control in industrial incineration facilities for municipal solid waste (MSW), a survey of the literature has been supplemented by a number of waste incineration site visits in Belgium and The Netherlands, in order to make a realistic assessment of the current status of technology in the area. Owing to the commercial character, and therefore, the confidentiality restrictions imposed by plant builders and many of the operators, much of the information collected has either to be presented in a generalized manner, and in any case anonymously. The survey was focused on four major issues: process control strategy, process control systems, monitors used for process control and finally the correlation between the 850 degrees C/2 s rule in the European waste incineration directive and integrated process control. The process control strategies range from reaching good and stable emissions at the stack to stabilizing and maximizing the energy output from the process. The main indicator to be monitored, in cases in which the focus is controlling emissions, is the oxygen content in the stack. Keeping the oxygen concentration in a determined range (usually between 8 and 12 vol.%) ensures stable and tolerated concentrations of the gaseous emissions. In the case for which stabilization of energy production is the principal aim, the main controlled parameter is the steam temperature and flow-rate, which is usually related to the fuel energetic input. A lot of other parameters are used as alarm criteria, the most common of which is the carbon monoxide concentration. The process control systems used most commonly feature partially automated classical proportional integral derivative (PID) controllers. New and innovative process control systems, such as fuzzy-logic control systems, are still unknown to most plant managers while their performance is reported to be unsatisfactory in plants in which such systems

  12. Radiological Research Accelerator Facility. Progress report, April 1, 1984-March 31, 1985

    International Nuclear Information System (INIS)

    Rossi, H.H.

    1985-01-01

    The aim of the Radiological Research Accelerator Facility (RARAF) was to provide a source of monoenergetic neutrons for studies in radiation biology, dosimetry and microdosimetry. The research has provided insight into the biological action of radiation and its relation to energy distribution in the cell as described by the theory of dual radiation action. This status report on the facility includes descriptions of the capabilities and layout, staffing, radiation safety, and a chronological account of the development and use of the facilities. 5 references, 2 figures

  13. An integrated testing facility for bench scale catalyst research

    Energy Technology Data Exchange (ETDEWEB)

    Johnston, H.D.; Hogan, R.J.; McMurtrie, D.E.

    1983-08-01

    Discovering new catalysts and designing new catalytic processes has long been hindered by equipment that is either designed for hand operation with the data acquisition functions in some stage of automation or is patterned after refinery installations to smaller, pilot plant like facilities. The latter approach has required large vessels (and hence large amounts of experimental catalyst and feedstocks) to be used or the use of improperly fitted control equipment with constant attention to the operation of a small reactor system. Constant attention partially negates the intent of the automation effort. Results from some of these systems are often unsatisfactory because of poor material balances and control. The data from some schemes must then be manually transferred into other databases for use in reports, correlations, etc. An earlier paper from this laboratory (1) described an initial attempt to provide a reliable, reproducible method for more productive catalyst screening, but that system still lacked an automatic data management system and was not flexible with regards to wide range changes of pressure and flow. Also, several different types of experiments could not be run concurrently. Recently, several schemes have appeared (2-6) which deal with distributed systems as they apply to various laboratory and pilot plant operations. This paper describes an automated system that allows for up to 21 reactors to be in operation concurrently with a staff of five people. All units are independently run without normal operator intervention and the system is designed fail safe for unattended operation. It has been used extensively for screening exploratory catalysts, catalytic process optimization, kinetic modeling and increasingly in refinery process optimization.

  14. Thermally induced transformations of iron oxide stabilised APC residues from waste incineration

    DEFF Research Database (Denmark)

    Sørensen, Mette Abildgaard; Koch, C.B.

    2001-01-01

    Air pollution control (APC) facilities at waste incinerator plants produce large quantities of solid residues rich in salts and heavy metals. Heavy metals are readily released to water from the residues and it has, therefore, been found suitable to apply a rapid co-precipitation/adsorption process...

  15. Apparatus for incinerating hazardous waste

    Science.gov (United States)

    Chang, R.C.W.

    1994-12-20

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

  16. Suicide by self-incineration

    DEFF Research Database (Denmark)

    Leth, Peter Mygind; Hardt-Madsen, Michael

    1997-01-01

    During a 10-year period (1980-1989), at least 43 cases of self-incineration with lethal outcome took place in Denmark. The incidence seems to be increasing: 11 cases took place in the first 5 years and 32 cases in the last 5 years. An even sex ratio as found (male:female = 23:20). The median age...... was 43 years, with a broad age range (20-87). Many incidents of self-incineration as a form of political protest were reported in the press especially during the 1960s and 1970s, and the press reports often inspired others to commit suicide in the same way. None of the cases in our investigation were...... victims were of Danish origin, and a religious motive played no significant role. Most of the victims were suffering from mental illness, and a majority had tried to commit suicide before. None of the victims left a suicide note. The scene was most often at home and indoors--only a minority committed...

  17. Los Alamos National Laboratory Weapons Neutron Research Facility

    International Nuclear Information System (INIS)

    Woods, R.

    1981-01-01

    The Weapons Neutron Research (WNR) spallation neutron source utilizes 800-MeV protons from the Los Alamos Meson Physics linac. The proton beam transport system, the target systems, and the data acquisition and control system are described. Operating experience, present status, and planned improvements are discussed

  18. Development of thermal conditioning technology for Alpha-containment wastes: Alpha-contaminated waste incineration technology

    International Nuclear Information System (INIS)

    Kim, Joon Hyung; Kim, Jeong Guk; Yang, Hee Chul; Choi, Byung Seon; Jeong, Myeong Soo

    1999-03-01

    As the first step of a 3-year project named 'development of alpha-contaminated waste incineration technology', the basic information and data were reviewed, while focusing on establishment of R and D direction to develop the final goal, self-supporting treatment of α- wastes that would be generated from domestic nuclear industries. The status on α waste incineration technology of advanced states was reviewed. A conceptual design for α waste incineration process was suggested. Besides, removal characteristics of volatile metals and radionuclides in a low-temperature dry off-gas system were investigated. Radiation dose assessments and some modification for the Demonstration-scale Incineration Plant (DSIP) at Korea Atomic Energy Research Institute (KAERI) were also done

  19. Comparative Assessment of Particulate Air Pollution Exposure from Municipal Solid Waste Incinerator Emissions

    Science.gov (United States)

    Ashworth, Danielle C.; Fuller, Gary W.; Toledano, Mireille B.; Font, Anna; Elliott, Paul; Hansell, Anna L.; de Hoogh, Kees

    2013-01-01

    Background. Research to date on health effects associated with incineration has found limited evidence of health risks, but many previous studies have been constrained by poor exposure assessment. This paper provides a comparative assessment of atmospheric dispersion modelling and distance from source (a commonly used proxy for exposure) as exposure assessment methods for pollutants released from incinerators. Methods. Distance from source and the atmospheric dispersion model ADMS-Urban were used to characterise ambient exposures to particulates from two municipal solid waste incinerators (MSWIs) in the UK. Additionally an exploration of the sensitivity of the dispersion model simulations to input parameters was performed. Results. The model output indicated extremely low ground level concentrations of PM10, with maximum concentrations of incinerator characteristics, magnitude of emissions, and surrounding meteorological and topographical conditions are considered. Reducing exposure misclassification is particularly important in environmental epidemiology to aid detection of low-level risks. PMID:23935644

  20. MINT Incineration and Renewable Energy Centre - experience and challenge

    International Nuclear Information System (INIS)

    Mohamad Puad Abu

    2005-01-01

    MIREC is the acronym for MINT Incineration and Renewable Energy Centre which was established in the year 2000 to carry out research and provide services on matters related to incineration technology and renewable energy. Throughout this period, many challenges and experiences has been faced by MIREC. Three research contracts with the value of nearly RM 1 million have been signed. Four laboratory scale burners have been designed and fabricated. Three mathematical models have been developed. Three programs on enhancement image have been published. Three papers have been published in the international journal. In order to achieve all these, many obstacles were faced by MIREC. This paper will discuss on the experiences and challenges that could be shared together with MINT staff. (Author)

  1. High temperature slagging incinerator for alpha contaminated wastes

    International Nuclear Information System (INIS)

    Van de Voorde, N.

    1985-01-01

    This report describes the experiences collected by the treatment of plutonium-contaminated wastes, in the High Temperature Slagging Incinerator at the C.E.N./S.C.K. at Mol, with the support of the Commission of the European Communities. The major objective of the exercise is to demonstrate the operability of this facility for the treatment of mixed transuranic (TRU) and beta-gamma solid waste material. The process will substantially reduce the TRU waste volume by burning the combustibles and converting the non-combustibles into a chemically inert and physically stable basalt-like slag product, suitable for safe transport and final disposal. (Auth.)

  2. Disposal of radioactive waste from nuclear research facilities

    CERN Document Server

    Maxeiner, H; Kolbe, E

    2003-01-01

    Swiss radioactive wastes originate from nuclear power plants (NPP) and from medicine (e.g. radiation sources), industry (e.g. fire detectors) and research (e.g. CERN, PSI). Their conditioning, characterisation and documentation has to meet the demands given by the Swiss regulatory authorities including all information needed for a safe disposal in future repositories. For NPP wastes, arisings as well as the processes responsible for the buildup of short and long lived radionuclides are well known, and the conditioning procedures are established. The radiological inventories are determined on a routinely basis using a combined system of measurements and calculational programs. For waste from research, the situation is more complicated. The wide spectrum of different installations combined with a poorly known history of primary and secondary radiation results in heterogeneous waste sorts with radiological inventories quite different from NPP waste and difficult to measure long lived radionuclides. In order to c...

  3. The research status of induced radioactivity in accelerator facilities

    International Nuclear Information System (INIS)

    Lu Feng; Deng Daping

    2005-01-01

    The hazards of subsequent-radiation produced by high-energy accelerator must be no ignore. The principle of induced radioactivity and the hazards to the people were introduced in this article. The radiation levels around the treatment head and in the air of the treatment room were discussed thor-oughly. Some effects of the induced radioactivity were also mentioned. At last, the article talks about some problems in present researches and some directions for the following study. (authors)

  4. The advanced neutron source - A world-class research reactor facility

    International Nuclear Information System (INIS)

    Thompson, P.B.; Meek, W.E.

    1993-01-01

    The advanced neutron source (ANS) is a new facility being designed at the Oak Ridge National Laboratory that is based on a heavy-water-moderated reactor and extensive experiment and user-support facilities. The primary purpose of the ANS is to provide world-class facilities for neutron scattering research, isotope production, and materials irradiation in the United States. The neutrons provided by the reactor will be thermalized to produce sources of hot, thermal, cold, very cold, and ultracold neutrons usable at the experiment stations. Beams of cold neutrons will be directed into a large guide hall using neutron guide technology, greatly enhancing the number of research stations possible in the project. Fundamental and nuclear physics, materials analysis, and other research pro- grams will share the neutron beam facilities. Sufficient laboratory and office space will be provided to create an effective user-oriented environment

  5. Yearly program of safety research for nuclear facilities and others

    International Nuclear Information System (INIS)

    1987-01-01

    The development of FBRs in Japan has steadily progressed, and subsequently to the experimental reactor 'Joyo' and the prototype reactor 'Monju', by promoting the construction of a demonstration reactor, the stage of verifying and acquiring skill of the electricity generation plant technology of practical scale, improving the performance and establishing the economical efficiency is about to begin. The development of FBRs in Japan has been advanced independently as a national project, and the method of preventing accidents in the actual reactors has been thoroughly taken. 'On the way of thinking in the safety evaluation of FBRs' was decided by the Nuclear Safety Commission. When the safety research from 1987 is systematized, as the constituents of safety logic, the way of thinking of the defense in depth, the way of thinking of the classification according to importance, the way of thinking of multilayer barriers against radioactive substances, and the way of thinking on severe accidents were investigated. The research concerning the decision of safety design and evaluation policy, and the safety research regarding accident prevention and relaxation, accident evaluation and severe accidents are reported. (Kako, I.)

  6. Paul Scherrer Institute Scientific and Technical Report 2000. Volume VI: Large Research Facilities

    International Nuclear Information System (INIS)

    Foroughi, Fereydoun; Bercher, Renate; Buechli, Carmen; Zumkeller, Lotty

    2001-01-01

    The PSI Department Large Research Facilities (GFA) joins the efforts to provide an excellent research environment to Swiss and foreign research groups on the experimental facilities driven by our high intensity proton accelerator complex. Its divisions care for the running, maintenance and enhancement of the accelerator complex, the primary proton beamlines, the targets and the secondary beams as well as the neutron spallation source SINQ. The division for technical support and coordination provides for technical support to the research facility complementary to the basic logistic available from the department for logistics and marketing. Besides running the facilities, the staff of the department is also involved in theoretical and experimental research projects. Some of them address basic scientific questions mainly concerning the properties of micro- or nanostructured materials: experiments as well as large scale computer simulations of molecular dynamics were performed to investigate nonclassical materials properties. Others are related to improvements or extensions of the capabilities of our facilities. We also report on intriguing results from applications of the neutron capture radiography, the prompt gamma activation method and the isotope production facility at SINQ

  7. Paul Scherrer Institute Scientific and Technical Report 2000. Volume VI: Large Research Facilities

    Energy Technology Data Exchange (ETDEWEB)

    Foroughi, Fereydoun; Bercher, Renate; Buechli, Carmen; Zumkeller, Lotty [eds.

    2001-07-01

    The PSI Department Large Research Facilities (GFA) joins the efforts to provide an excellent research environment to Swiss and foreign research groups on the experimental facilities driven by our high intensity proton accelerator complex. Its divisions care for the running, maintenance and enhancement of the accelerator complex, the primary proton beamlines, the targets and the secondary beams as well as the neutron spallation source SINQ. The division for technical support and coordination provides for technical support to the research facility complementary to the basic logistic available from the department for logistics and marketing. Besides running the facilities, the staff of the department is also involved in theoretical and experimental research projects. Some of them address basic scientific questions mainly concerning the properties of micro- or nanostructured materials: experiments as well as large scale computer simulations of molecular dynamics were performed to investigate nonclassical materials properties. Others are related to improvements or extensions of the capabilities of our facilities. We also report on intriguing results from applications of the neutron capture radiography, the prompt gamma activation method and the isotope production facility at SINQ.

  8. Department of Nuclear Safety Research and Nuclear Facilities annual report 1995

    International Nuclear Information System (INIS)

    Majborn, B.; Brodersen, K.; Damkjaer, A.; Floto, H.; Jacobsen, U.; Oelgaard, P.L.

    1996-03-01

    The report presents a summary of the work of the Department of Nuclear Safety Research and Nuclear Facilities in 1995. The department's research and development activities are organized in three research programmes: Radiation Protection, Reactor Safety, and Radioanalytical Chemistry. The nuclear facilities operated by the department include the Research Reactor DR3, the Isotope Laboratory, the Waste Treatment Plant, and the Educational Reactor DR1. Lists of staff and publications are included together with a summary of the staff's participation in national and international committees. (au) 5 tabs., 21 ills

  9. A ''dog gone'' restoration project: Remediation of an AEC research facility

    International Nuclear Information System (INIS)

    Huff, P.E.; Brooks, B.T.

    1994-01-01

    This facility was established in 1958 by the Atomic Energy Commission. Research at the facility originally focused on the health effects from chronic exposures to radionuclides, primarily strontium 90 ( 90 Sr) and radium 226 ( 226 Ra), using beagles to simulate radiation effects on humans. In 1988 the Department of Energy (DOE) decided to close out the research program, shut down the facility and turn it over to the tenant after remediation. This paper examines the remediation activities relative to Animal Hospitals 1 and 2 (AH-1 and AH-2), the cobalt 60 ( 60 Co) source and the Specimen Storage Room. Remediation of this facility took place over one year period beginning in August 1992. Portions of the facility not requiring remediation are now a part of an ongoing research facility. While excluded from areas where remediation took place, facility personnel and others were in close proximity to the remediation, sometimes separated only by a common building wall. This close proximity required remediation techniques that stressed contamination control

  10. Public Facilities Management and Action Research for Sustainability

    DEFF Research Database (Denmark)

    Galamba, Kirsten Ramskov

    ) is analysed in the light of a change process in a Danish Municipal Department of Public Property. Three years of Action Research has given a unique insight in the reality in a Municipal Department of Public Property, and as to how a facilitated change process can lead to a more holistic and sustainable...... practice inspired by the principles of FM. The bottom up change process had an employee perspective, and the work provides answers to the challenges of creating a culture allowing for critical reflections in relation to the impact of FM practice on societal sustainability....

  11. Dedicated Beamline Facilities for Catalytic Research. Synchrotron Catalysis Consortium (SCC)

    Energy Technology Data Exchange (ETDEWEB)

    Chen, Jingguang [Columbia Univ., New York, NY; Frenkel, Anatoly [Yeshiva Univ., New York, NY (United States); Rodriguez, Jose [Brookhaven National Lab. (BNL), Upton, NY (United States); Adzic, Radoslav [Brookhaven National Lab. (BNL), Upton, NY (United States); Bare, Simon R. [UOP LLC, Des Plaines, IL (United States); Hulbert, Steve L. [Brookhaven National Lab. (BNL), Upton, NY (United States); Karim, Ayman [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Mullins, David R. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Overbury, Steve [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)

    2015-03-04

    Synchrotron spectroscopies offer unique advantages over conventional techniques, including higher detection sensitivity and molecular specificity, faster detection rate, and more in-depth information regarding the structural, electronic and catalytic properties under in-situ reaction conditions. Despite these advantages, synchrotron techniques are often underutilized or unexplored by the catalysis community due to various perceived and real barriers, which will be addressed in the current proposal. Since its establishment in 2005, the Synchrotron Catalysis Consortium (SCC) has coordinated significant efforts to promote the utilization of cutting-edge catalytic research under in-situ conditions. The purpose of the current renewal proposal is aimed to provide assistance, and to develop new sciences/techniques, for the catalysis community through the following concerted efforts: Coordinating the implementation of a suite of beamlines for catalysis studies at the new NSLS-II synchrotron source; Providing assistance and coordination for catalysis users at an SSRL catalysis beamline during the initial period of NSLS to NSLS II transition; Designing in-situ reactors for a variety of catalytic and electrocatalytic studies; Assisting experimental set-up and data analysis by a dedicated research scientist; Offering training courses and help sessions by the PIs and co-PIs.

  12. Radioactive-waste incineration at Purdue University

    International Nuclear Information System (INIS)

    1982-11-01

    A study conducted at Purdue University to evaluate the feasibility of using a small (45 kg/h), inexpensive (less than $10K) incinerator for incinerating low-level radioactive waste is described. An oil-fired, dual-chamber pathological waste incinerator was installed on a 12.7-cm-thick concrete floor in a metal quonset building. A standard EPA Method 5 sampling train was used to obtain stack samples. Also, stack gas velocity was measured with a type 5 pitot tube; stack temperature was measured with a thermocouple and pyrometer. The incinerator was tested for emissions from incineration of laboratory animal carcasses, liquid scintillation fluid, and trash. Emissions measured were particulates, SO/sub x/, NO/sub x/, Cl, CO, CO 2 , H 2 O, and unburned hydrocarbons in the particulate fraction. Three analyses were then averaged to arrive at the final determinations. Results of the study demonstrated the feasibility and cost-effectiveness of incinerating radioactive animal carcasses and liquid scintillation fluids, since emissions from those waste types were within EPA and State of Indiana limits. However, emissions from burning of trash exceeded State of Indiana limits. Therefore, incineration of trash alone, particularly if it contains glass or significant amounts of plastic, is not a recommended use of the tested equipment

  13. Fire-protection research for DOE facilities: FY 82 year-end report

    International Nuclear Information System (INIS)

    Hasegawa, H.K.; Alvares, N.J.; Lipska-Quinn, A.E.; Beason, D.G.; Priante, S.J.; Foote, K.L.

    1983-01-01

    We summarize our research in FY 82 for the DOE-sponsored project, Fire Protection Research for DOE Facilities. This research program was initiated in 1977 to advance fire-protection strategies for energy technology facilities to keep abreast of the unique fire problems that develop along with energy technology research. Since 1977, the program has broadened its original scope, as reflected in previous year-end reports. We are developing an analytical methodology through detailed study of fusion energy experiments at Lawrence Livermore National Laboratory (LLNL). Using these experiments as models for methodology development, we are concurrently advancing three major task areas: (1) the identification of fire hazards unique to current fusion energy facilities; (2) the evaluation of accepted fire-management measures to meet and negate hazards; and (3) the performance of unique research into problem areas we have identified to provide input into analytical fire-growth and damage-assessment models

  14. Restoration of the Hypersonic Tunnel Facility at NASA Glenn Research Center, Plum Brook Station

    Science.gov (United States)

    Woodling, Mark A.

    2000-01-01

    The NASA Glenn Research Center's Hypersonic Tunnel Facility (HTF), located at the Plum Brook Station in Sandusky, Ohio, is a non-vitiated, free-jet facility, capable of testing large-scale propulsion systems at Mach Numbers from 5 to 7. As a result of a component failure in September of 1996, a restoration project was initiated in mid- 1997 to repair the damage to the facility. Following the 2-1/2 year effort, the HTF has been returned to an operational condition. Significant repairs and operational improvements have been implemented in order to ensure facility reliability and personnel safety. As of January 2000, this unique, state-of-the-art facility was ready for integrated systems testing.

  15. Life Science Research Facility materials management requirements and concepts

    Science.gov (United States)

    Johnson, Catherine C.

    1986-01-01

    The Advanced Programs Office at NASA Ames Research Center has defined hypothetical experiments for a 90-day mission on Space Station to allow analysis of the materials necessary to conduct the experiments and to assess the impact on waste processing of recyclable materials and storage requirements of samples to be returned to earth for analysis as well as of nonrecyclable materials. The materials include the specimens themselves, the food, water, and gases necessary to maintain them, the expendables necessary to conduct the experiments, and the metabolic products of the specimens. This study defines the volumes, flow rates, and states of these materials. Process concepts for materials handling will include a cage cleaner, trash compactor, biological stabilizer, and various recycling devices.

  16. Scattering chamber for the Holifield Heavy Ion Research Facility

    International Nuclear Information System (INIS)

    Goodman, C.D.; Corum, J.E.

    1977-09-01

    A conceptual design is presented for a 62-in.-diam. general purpose scattering chamber to be used for nuclear research with heavy ions. The detector rotation mechanism is based on large diameter (approx. 58 in.) peripherally driven rings. This leaves the central region open for detectors and other apparatus and permits the use of a perpendicular ring for rotating a detector out of the reaction plane. A precision target slide with provisions for removing the entire slide under vacuum is part of the design. Access and viewing ports on the dished top and in the reaction plane will be provided. Cryogenic pumping will be used to keep the vacuum free from hydrocarbon vapors, water vapor, and oxygen

  17. Current Sandia programs and laboratory facilities for tritium research

    International Nuclear Information System (INIS)

    Swansiger, W.A.; West, L.A.

    1975-01-01

    Currently envisioned fusion reactor systems will contain substantial quantities of tritium. Strict control of the overall tritium inventory and environmental safety considerations require an accurate knowledge of the behavior of this isotope in the presence of Controlled Thermonuclear Reactor (CTR) materials. A 14,000 ft 2 laboratory for tritium research is currently under construction at Sandia Laboratories in Livermore. Details about the laboratory in general are provided. Results from studies of hydrogen isotope diffusion in surface-characterized metals will be presented. Details of two permeation systems (one for hydrogen and deuterium, the other for tritium) will be discussed. Data will also be presented concerning the gettering of hydrogen isotopes and application to CTR collector designs. (auth)

  18. Emissions and dioxins formation from waste incinerators

    International Nuclear Information System (INIS)

    Carbone, A.I.; Zagaroli, M.

    1989-01-01

    This paper describes current knowledge on dioxins formation and emission from waste incinerators. The pertinent Italian law and effects on man health are dealt with, too. The picture of existing municipal incinerators is presented concerning both the actual emission levels and the monitored levels in the environment. Sampling and analysis systems of these organic chlorinated micro-pollutants and current theories on precursors, formation mechanisms, and influence of different parameters are also described. The last section deals with some of the techniques that can be used to reduce dioxins formation and emission from municipal incinerators. (author)

  19. Development and testing of a mobile incinerator

    International Nuclear Information System (INIS)

    Eggett, D.R.

    1986-01-01

    The development and testing of a mobile incinerator for processing of combustible dry active waste (DAW) and contaminated oil generated at Nuclear Power Plants is presented. Topics of discussion include initial thoughts on incineration as applied to nuclear waste; DOE's Aerojet's, and CECo's role in the Project; design engineering concepts; site engineering support; licensability; generation of test data; required reports of the NRC and Illinois and California EPA's; present project schedule for incinerating DAW at Dresden and other CECo Stations; and lessons learned from the project

  20. Incineration of spent ion exchange resins in a triphasic mixture at Belgoprocess

    International Nuclear Information System (INIS)

    Deckers, J.; Luycx, P.

    2003-01-01

    Up to 1998, spent ion exchange resins have been fed to the incinerator in combination with various other solid combustible wastes at Belgoprocess. However, thanks to sustained efforts to reduce radioactive waste production in all nuclear facilities in Belgium, the annual production of solid combustible waste is now much too small to allow this practice to be continued. Since the incinerator at Belgoprocess is not capable of treating spent ion exchange resins as such, it was decided to adopt the use of foam as a carrier to feed the resins to the incinerator. The mixture is a pseudohomogeneous charged foam, ensuring easy handling and allowing incineration in the existing furance, while a number of additives may be included, such as oil to increase the calorific value of the mixture and accelerate combustion. The first incineration campaign of spent ion exchange resins in a triphasic foam mixture, in conjunction with other liquid and solid combustible wastes, will be started in January 2000. The foam, comprising 70% by weight of resins, 29% by weight of water and 1% by weight of surfactant will be pulverized in the incinerator through an injection lance, at a feed rate of 40 to 100 kg/h. The incinerator and associated off-gas treatment system can be operated at standard conditions. Belgoprocess is the subsidiary of the Belgian national agency for the management of radioactive waste, known by its Dutch and French acronyms, NIRAS and ONDRAF respectively. The company ensures the treatment, conditioning and interim storage of nearly all radioactive waste produced in Belgium. (orig.)

  1. The potential impact of municipal solid waste incinerators ashes on the anthropogenic osmium budget

    International Nuclear Information System (INIS)

    Funari, Valerio; Meisel, Thomas; Braga, Roberto

    2016-01-01

    Osmium release from Municipal Solid Waste Incinerators (MSWI), even if acknowledged to occur at least over the last fifteen years, remains overlooked in the majority of recent studies. We present the osmium concentration and 187 Os/ 188 Os isotopic measurements of different kinds of bottom and fly ash samples from MSWI plants and reference materials of incinerator fly ash (BCR176 and BCR176R). The analysis of the unknown ash samples shows a relatively wide range of 187 Os/ 188 Os ratios (0.24–0.70) and Os concentrations (from 0.026 ng/g to 1.65 ng/g). Osmium concentrations and isotopic signatures differ from those of other known Os sources, either natural or manmade, suggesting a mixture of both contributions in the MSWI feedstock material. Furthermore, the comparison between the BCR176 and the renewed BCR176R indicates a decrease in Os concentration of one order of magnitude over the years (from 1 to 0.1 ng/g) due to improved recycling efficiency of Os-bearing waste. The estimated annual amount of Os from a typical incinerator (using average Os values and MSWI mass balance) is 13.4 g/a. The osmium potentially released from MSWI smokestacks is predicted to be from 16 to 38 ng Os/m 2 /a, considering a medium size country having 50 MSWI facilities; therefore much higher than the naturally transported osmium from continental dust in the atmosphere (about 1 pg Os/m 2 /a). MSWI systems are considered one of the best options for municipal solid waste management in industrialised countries, but their contribution to the Os budget can be significant. - Highlights: • Bottom and fly ashes from municipal solid waste incinerators are investigated. • Their Os levels and Os isotopic signatures are discussed. • An estimate of Os release from incinerators and incinerated ashes is given. • Os contamination from incineration plants impacts the geochemical Os cycle.

  2. Cultivation of university students in radiology using research facilities at KAERI

    Energy Technology Data Exchange (ETDEWEB)

    Shin, Byung Chul [Nuclear Training and Education Center, Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2017-09-15

    The purpose of present research is to offer a specialized educational opportunity for potential users, university students in radiology, by developing specific curriculum on site at KAERI, using HANARO research reactor and National radiation research facilities. The specific items of this research accomplished are: First, Development and operation of various curricula for specific research using HANARO and National radiation research facilities to provide university students with opportunities to use the facilities. Second, Operation of the experiment training programs for university students in radiology to foster next generation specialists. Third, through the on-site experiment training for students in radiology, support future potential experts of the radiation research fields, and broaden the base. A textbook and a teaching aid, a questionnaire have been developed to support the program. 714 university students have completed the courses for radiology experiment from 2006 to 2017. It is hoped that these experiments broaden public awareness and acceptance by the present and potential future utilization of the research reactor and national radiation research facilities, thereby bring positive impacts to policy making.

  3. HANARO Neutron Radiography Facility and Fuel Cell Research

    International Nuclear Information System (INIS)

    Kim, Taejoo

    2013-01-01

    Fuel cell which generates electric energy from hydrogen and oxygen is one of noticed renewable energy system because this has high efficiency and free from CO 2 . Especially, PEMFC (Polymer Electrolyte Membrane Fuel Cell) is focused by automotive companies because PEMFC, which has high power rate per volume and low operating temperature (60∼80), is suited due to the compact design and short start-up time. The water management is one of the most critical issues for fuel cell commercialization. In order to make a proper scheme for water management, thein formation of water distribution and behavior is very important. Neutron imaging is the best method to visualize the water at fuel cell and has been applied worldwide with qualitative and quantitative results. Because the NRF has large beam size (350Χ450mm 2 ) and relatively high neutron flux (2Χ107 n/cm 2 sec), it is suitable for large scale fuel cell research. Neutron imaging technique was used to investigate the water distribution and behavior in PEMFC under different operating conditions. The NRF has contributed the improvement of fuel cell performance and is one of the best choices for fuel cell study

  4. RESEARCH AND DEVELOPMENT ACTIVITIES AT SAVANNAH RIVER SITE'S H CANYON FACILITY

    Energy Technology Data Exchange (ETDEWEB)

    Sexton, Lindsay; Fuller, Kenneth

    2013-07-09

    The Savannah River Site's (SRS) H Canyon Facility is the only large scale, heavily shielded, nuclear chemical separations plant still in operation in the U.S. The facility's operations historically recovered uranium-235 (U-235) and neptunium-237 (Np-237) from aluminum-clad, enriched-uranium fuel tubes from Site nuclear reactors and other domestic and foreign research reactors. Today the facility, in conjunction with HB Line, is working to provide the initial feed material to the Mixed Oxide Facility also located on SRS. Many additional campaigns are also in the planning process. Furthermore, the facility has started to integrate collaborative research and development (R&D) projects into its schedule. H Canyon can serve as the appropriate testing location for many technologies focused on monitoring the back end of the fuel cycle, due to the nature of the facility and continued operation. H Canyon, in collaboration with the Savannah River National Laboratory (SRNL), has been working with several groups in the DOE complex to conduct testing demonstrations of novel technologies at the facility. The purpose of conducting these demonstrations at H Canyon will be to demonstrate the capabilities of the emerging technologies in an operational environment. This paper will summarize R&D testing activities currently taking place in H Canyon and discuss the possibilities for future collaborations.

  5. European Facility for Antiproton and Ion Research (FAIR): the new international center for fundamental physics and its research program

    International Nuclear Information System (INIS)

    Fortov, Vladimir E; Sharkov, Boris Yu; Stöker, H

    2012-01-01

    The Facility for Antiproton and Ion Research (FAIR) accelerator center at Darmstadt, Germany, will provide the international scientific community with unique experimental opportunities of a scope and scale out of reach for any other large-scale facility in the world. With its staff of over 2500, it is expected to fundamentally expand our knowledge of hadron, nuclear, and atomic physics and their application to cosmology, astrophysics, and technology. In this review, the design details of the accelerator complex are discussed and the experimental research program for FAIR is presented. Particular attention is paid to experiments on the extreme state of matter arising from the isochoric heating of a material by heavy-ion beams. One of the largest facilities of its kind in Europe, FAIR is a part of the strategic development roadmap for the European Strategic Forum on Research Infrastructures (ESFRI). (physics of our days)

  6. Aluminium alloys in municipal solid waste incineration bottom ash.

    Science.gov (United States)

    Hu, Yanjun; Rem, Peter

    2009-05-01

    With the increasing growth of incineration of household waste, more and more aluminium is retained in municipal solid waste incinerator bottom ash. Therefore recycling of aluminium from bottom ash becomes increasingly important. Previous research suggests that aluminium from different sources is found in different size fractions resulting in different recycling rates. The purpose of this study was to develop analytical and sampling techniques to measure the particle size distribution of individual alloys in bottom ash. In particular, cast aluminium alloys were investigated. Based on the particle size distribution it was computed how well these alloys were recovered in a typical state-of-the-art treatment plant. Assessment of the cast alloy distribution was carried out by wet physical separation processes, as well as chemical methods, X-ray fluorescence analysis and electron microprobe analysis. The results from laboratory analyses showed that cast alloys tend to concentrate in the coarser fractions and therefore are better recovered in bottom ash treatment plants.

  7. Behavior of cesium in municipal solid waste incineration

    International Nuclear Information System (INIS)

    Oshita, Kazuyuki; Aoki, Hiroshi; Fukutani, Satoshi; Shiota, Kenji; Fujimori, Takashi; Takaoka, Masaki

    2015-01-01

    As a result of the Fukushima Daiichi Nuclear Power Plant accident on March 11, 2011 in Japan radioactive nuclides, primarily 134 Cs and 137 Cs were released, contaminating municipal solid waste and sewage sludge in the area. Although stabilizing the waste and reducing its volume is an important issue differing from Chernobyl nuclear power plant accident, secondary emission of radioactive nuclides as a result of any intermediate remediation process is of concern. Unfortunately, there is little research on the behavior of radioactive nuclides during waste treatment. This study focuses on waste incineration in an effort to clarify the behavior of radioactive nuclides, specifically, refuse-derived fuel (RDF) with added 133 Cs (stable nuclide) or 134 Cs (radioactive nuclide) was incinerated in laboratory- and pilot-scale experiments. Next, thermogravimetric (TG) and differential thermal analysis (DTA) of stable Cs compounds, as well as an X-ray absorption fine structure (XAFS) analysis of Cs concentrated in the ashes were performed to validate the behavior and chemical forms of Cs during the combustion. Our results showed that at higher temperatures and at larger equivalence ratios, 133 Cs was distributed to the bottom ash at lower concentration, and the influence of the equivalence ratio was more significant at lower temperatures. 134 Cs behaved in a similar fashion as 133 Cs. We found through TG–DTA and XAFS analysis that a portion of Cs in RDF vaporizes and is transferred to fly ash where it exists as CsCl in the MSW incinerator. We conclude that Cs-contaminated municipal solid wastes could be incinerated at high temperatures resulting in a small amount of fly ash with a high concentration of radioactive Cs, and a bottom ash with low concentrations. - Highlights: • Behaviors of Cs on the incineration of the model waste were investigated. • More Cs was moved to fly ash with increasing of equivalence ratio and temperature. • Chemical forms of Cs in the fly ash

  8. Suicide by self-incineration

    DEFF Research Database (Denmark)

    Leth, Peter Mygind; Hardt-Madsen, Michael

    1997-01-01

    was 43 years, with a broad age range (20-87). Many incidents of self-incineration as a form of political protest were reported in the press especially during the 1960s and 1970s, and the press reports often inspired others to commit suicide in the same way. None of the cases in our investigation were...... victims were of Danish origin, and a religious motive played no significant role. Most of the victims were suffering from mental illness, and a majority had tried to commit suicide before. None of the victims left a suicide note. The scene was most often at home and indoors--only a minority committed...... suicide in remote areas of the countryside. Most were found dead at the scene, and the cause of death was usually heat exposure. Only a minority had a lethal carboxy-hemoglobin (CO-Hb) concentration. It is concluded that close cooperation between police, fire experts, and the forensic pathologist...

  9. Solidification of radioactive incinerator ash

    International Nuclear Information System (INIS)

    Schuler, T.F.; Charlesworth, D.L.

    1986-01-01

    The Ashcrete process will solidify ash generated by the Beta Gamma Incinerator (BGI) at the Savannah River Plant (SRP). The system remotely handles, adds material to, and tumbles drums of ash to produce ashcrete, a stabilized wasteform. Full-scale testing of the Ashcrete unit began at Savannah River Laboratory (SRL) in January 1984, using nonradioactive ash. Tests determined product homogeneity, temperature distribution, compressive strength, and final product formulation. Product formulations that yielded good mix homogeneity and final product compressive strength were developed. Drum pressurization and temperature rise (resulting from the cement's heat of hydration) were also studied to verify safe storage and handling characteristics. In addition to these tests, an expert system was developed to assist process troubleshooting

  10. Comparative life cycle GHG emissions from local electricity generation using heavy oil, natural gas, and MSW incineration in Macau

    DEFF Research Database (Denmark)

    Song, Qingbin; Wang, Zhishi; Li, Jinhui

    2018-01-01

    (MSW) incineration, and coal-dominated mode which is directly imported from China mainland. On the basis of first-hand data from two power plants and one MSW incineration facility, this study performed a Life Cycle Assessment (LCA) process for three kinds of local electricity generation (heavy oil......The electricity generation processes represent a large contribution to the potential greenhouse gases (GHG) emissions. Macau, a Special Administrative Region of China, is not of exception. Macau has multiple electricity generation modes, including heavy oil, natural gas, and municipal solid waste......, natural gas, and MSW incineration) to estimate the greenhouse gas (GHG) emissions under the operating practices used from 2010 to 2014. Results indicate that the mean GHG emissions of electricity production from heavy oil, natural gas, and MSW incineration were 0.71, 0.42, 0.95kg CO2 eq per k...

  11. Multispecies Epidemiologic Surveillance Study after an Outbreak of Yersiniosis at an African Green Monkey Research Facility

    OpenAIRE

    Soto, Esteban; Loftis, Amanda; Boruta, Daniel; Rostad, Sara; Beierschmitt, Amy; McCoy, Matthew; Francis, Stewart; Berezowski, John; Illanes, Oscar; Recinos, Diego; Arauz, Maziel; Spencer, Dustine; Fraites, Trellor; Palmour, Roberta

    2015-01-01

    After an outbreak of Yersinia enterocolitica at a NHP research facility, we performed a multispecies investigation of the prevalence of Yersinia spp. in various mammals that resided or foraged on the grounds of the facility, to better understand the epizootiology of yersiniosis. Blood samples and fecal and rectal swabs were obtained from 105 captive African green monkeys (AGM), 12 feral cats, 2 dogs, 20 mice, 12 rats, and 3 mongooses. Total DNA extracted from swab suspensions served as templa...

  12. Conceptual design of a mirror reactor for a fusion engineering research facility (FERF)

    International Nuclear Information System (INIS)

    Batzer, T.H.; Burleigh, R.C.; Carlson, G.A.; Dexter, W.L.; Hamilton, G.W.; Harvey, A.R.; Hickman, R.G.; Hoffman, M.A.; Hooper, E.B. Jr.; Moir, R.W.; Nelson, R.L.; Pittenger, L.C.; Smith, B.H.; Taylor, C.E.; Werner, R.W.; Wilcox, T.P.

    1975-01-01

    A conceptual design is presented for a small mirror fusion reactor for a Fusion Engineering Research Facility (FERF). The reactor produces 3.4 MW of fusion power and a useful neutron flux of about 10 14 n.cm -2 .s -1 . Superconducting ''yin-yang'' coils are used, and the plasma is sustained by injection of energetic neutral D 0 and T 0 . Conceptual layouts are given for the reactor, its major components, and supporting facilities. (author)

  13. Delegation lobbies Ottawa to simplify funding of large national research facilities

    CERN Document Server

    Henderson, M

    2003-01-01

    "Two respected proponents of a strong national innovation system led a delegation to Ottawa last week for five days of meetings to push for dramatic change in how Ottawa funds Canada's national research facilities. The Saskatchewan delegation met with key ministers, secretaries of state, DMs and opposition parties to argue for a consolidation of funding sources so that they flow to national facilities through one institution" (1 page).

  14. The radiological research accelerator facility: Progress report for the period December 1, 1986-November 30, 1987

    International Nuclear Information System (INIS)

    1987-04-01

    Experiments performed at the Radiological Research Accelerator Facility (RARAF) during the period of July 1986 through April 1987 are listed, as well as experiments run prior to that period and expected to eventually resume. The experiments run since July 1, 1986 or expected to run before November 30, 1987 are briefly described. Accelerator use and operation is summarized, as well as facilities development and activities of the Scientific Advisory Committee

  15. Savannah River Plant low-level waste incinerator: Operational results and technical development

    International Nuclear Information System (INIS)

    Irujo, M.J.; Bucci, J.R.

    1987-04-01

    Volume reduction of solid and liquid low-level waste has been demonstrated at the Savannah River Plant (SRP) in the Waste Management Beta-Gamma Incinerator facility (BGI). The BGI uses a two-stage, controlled-air incinerator capable of processing 180 kg/hr (400 lbs/hr) of solid waste or 150 liters/hr (40 gal/hr) of liquid waste. These wastes are pyrolyzed in a substoichiometric air environment at 900 to 1100 degrees Celsius in the primary chamber. Products of partial combustion from the primary chamber are oxidized at 950 to 1150 degrees Celsius in the secondary chamber. A spray dryer, baghouse,and HEPA filter unit cool and filter the incinerator offgases. 2 refs., 9 tabs

  16. White Mountain Research Station: 25 years of high-altitude research. [organization and functions of test facility for high altitude research

    Science.gov (United States)

    Pace, N.

    1973-01-01

    The organization and functions of a test facility for conducting research projects at high altitudes are discussed. The projects conducted at the facility include the following: (1) bird physiology, (2) cardiorespiratory physiology, (3) endocrinological studies, (4) neurological studies, (5) metabolic studies, and (6) geological studies.

  17. Design study of the underground facilities, the Mizunami Underground Research Laboratory

    International Nuclear Information System (INIS)

    Ishizuka, Mineo; Noda, Masaru; Shiogama, Yukihiro; Adachi, Tetsuya

    1999-02-01

    Geoscientific research on the deep geological environment has been performed by Japan Nuclear Cycle Development Institute (JNC). This research is supported by the 'Long-Term Program for Research, Development and Utilization of Nuclear Energy'. The Mizunami Underground Research Laboratory (MIU) is planned to be constructed at the Shobasama-bora site belonging to JNC. A wide range of geoscientific research and development activities which have been previously performed in and around the Tono mine is planned to be expanded in the laboratory. The MIU consisted of surface and underground facilities excavated to a depth of about 1,000 meters. In this design study, the overall layout and basic design of the underground facility and the composition of the overall research program, includes the construction of the underground facility are studied. Based on the concept of the underground facility which have been developed in 1998, the research activities which will be performed in the MIU are selected and the overall research program is revised in this year. The basic construction method and the construction equipment are also estimated. (author)

  18. Annual report of the CTR Blanket Engineering research facility in 1994

    International Nuclear Information System (INIS)

    1995-09-01

    This is an annual report of the studies on Controlled Thermo-nuclear Reactor(CTR) Blanket Engineering which have been carried out in the Faculty of Engineering, the University of Tokyo, in FY 1994. This research facility on the CTR Blanket Engineering is located in the Nuclear Engineering Research Laboratory, the Tokai-mura branch of the Faculty of Engineering. (author)

  19. Annual report of the CTR Blanket Engineering research facility in 1996

    International Nuclear Information System (INIS)

    1998-02-01

    This is an annual report of the studies on Controlled Thermo-nuclear Reactor (CTR) Blanket Engineering which have been carried out in the Faculty of Engineering, the University of Tokyo, in FY 1996. This research facility on the CTR Blanket Engineering is located in the Nuclear Engineering Research Laboratory, the Tokai-mura branch of the Faculty of Engineering. (J.P.N.)

  20. ARM Climate Research Facility Quarterly Instrument Report Fourth Quarter: October 1–December 30, 2010

    Energy Technology Data Exchange (ETDEWEB)

    Voyles, JW

    2011-01-17

    The purpose of this report is to provide a concise but comprehensive overview of Atmospheric Radiation Measurement Climate Research Facility instrumentation status. The report is divided into the following sections: (1) new instrumentation in the process of being acquired and deployed, (2) existing instrumentation and progress on improvements or upgrades, (3) proposed future instrumentation, and (4) Small Business Innovation Research instrument development.

  1. Atmospheric Radiation Measurement Climate Research Facility (ACRF Instrumentation Status: New, Current, and Future)

    Energy Technology Data Exchange (ETDEWEB)

    JW Voyles

    2008-01-30

    The purpose of this report is to provide a concise but comprehensive overview of Atmospheric Radiation Measurement Climate Research Facility instrumentation status. The report is divided into the following four sections: (1) new instrumentation in the process of being acquired and deployed, (2) existing instrumentation and progress on improvements or upgrades, (3) proposed future instrumentation, and (4) Small Business Innovation Research instrument development.

  2. Annual report of the CTR Blanket Engineering research facility in 1992

    International Nuclear Information System (INIS)

    1993-08-01

    This is an annual report of the studies on Controlled Thermo-nuclear Reactor (CTR) Blanket Engineering which have been carried out in the Faculty of Engineering, the University of Tokyo, in FY 1992. This research facility on the CTR Blanket Engineering is located in the Nuclear Engineering Research Laboratory, the Tokai-mura branch of the Faculty of Engineering. (J.P.N.)

  3. Spacecraft propulsion research facility (B-2) at the Lewis Research Center, Plum Brook Station

    Science.gov (United States)

    Klein, William E.

    1993-01-01

    The B-2 facility is designed to hot fire rocket engines or upper stage launch vehicles with up to 890,000 N thrust, after environmental conditioning of the test article in a simulated thermal vaccum space environment. The facility can handle cryogenic fuels and oxidizers. A steam ejector system maintains vacuum around the test article and on the engine discharge during the test firing. Two high speed computer systems control the test, monitor critical parameters and record all of the desired data.

  4. NASA's GreenLab Research Facility: A Guide for a Self-Sustainable Renewable Energy Ecosystem

    Science.gov (United States)

    Bomani, B. M. McDowell; Hendricks, R. C.; Elbuluk, Malik; Okon, Monica; Lee, Eric; Gigante, Bethany

    2011-01-01

    There is a large gap between the production and demand for energy from alternative fuel and alternative renewable energy sources. The sustainability of humanity, as we know it, directly depends on the ability to secure affordable fuel, food, and freshwater. NASA Glenn Research Center (Glenn) has initiated a laboratory pilot study on using biofuels as viable alternative fuel resources for the field of aviation, as well as utilizing wind and solar technology as alternative renewable energy resources. The GreenLab Research Facility focuses on optimizing biomass feedstock using algae and halophytes as the next generation of renewable aviation fuels. The unique approach in this facility helps achieve optimal biomass feedstock through climatic adaptation of balanced ecosystems that do not use freshwater, compete with food crops, or use arable land. In addition, the GreenLab Research Facility is powered, in part, by alternative and renewable energy sources, reducing the major environmental impact of present electricity sources. The ultimate goal is to have a 100 percent clean energy laboratory that, when combined with biomass feedstock research, has the framework in place for a self-sustainable renewable energy ecosystem that can be duplicated anywhere in the world and can potentially be used to mitigate the shortage of food, fuel, and water. This paper describes the GreenLab Research Facility at Glenn and its power and energy sources, and provides recommendations for worldwide expansion and adoption of the facility s concept.

  5. Effluent testing for the Oak Ridge mixed waste incinerator: Emissions test for August 27, 1990

    International Nuclear Information System (INIS)

    Bostick, W.D.; Bunch, D.H.; Gibson, L.V.; Hoffmann, D.P.; Shoemaker, J.L.

    1990-12-01

    On August 27, 1990, a special emissions test was performed at the K-1435 Toxic Substance Control Act Mixed Waste Incinerator. A sampling and analysis plan was implemented to characterize the incinerator waste streams during a 6 hour burn of actual mixed waste. The results of this characterization are summarized in the present report. Significant among the findings is the observation that less than 3% of the uranium fed to the incinerator kiln was discharged as stack emission. This value is consistent with the estimate of 4% or less derived from long-term mass balance of previous operating experience and with the value assumed in the original Environmental Impact Statement. Approximately 1.4% of the total uranium fed to the incinerator kiln appeared in the aqueous scrubber blowdown; about 85% of the total uranium in the aqueous waste was insoluble (i.e., removable by filtration). The majority of the uranium fed to the incinerator kiln appeared in the ash material, apparently associated with phosphorous as a sparingly-soluble species. Many other metals of potential regulatory concern also appeared to concentrate in the ash as sparingly-soluble species, with minimal partition to the aqueous waste. The aqueous waste was discharged to the Central Neutralization Facility where it was effectively treated by coprecipitation with iron. The treated, filtered aqueous effluent met Environmental Protection Agency interim primary drinking water standards for regulated metals

  6. Summary engineering description of underwater fuel storage facility for foreign research reactor spent nuclear fuel

    Energy Technology Data Exchange (ETDEWEB)

    Dahlke, H.J.; Johnson, D.A.; Rawlins, J.K.; Searle, D.K.; Wachs, G.W.

    1994-10-01

    This document is a summary description for an Underwater Fuel Storage Facility (UFSF) for foreign research reactor (FRR) spent nuclear fuel (SNF). A FRR SNF environmental Impact Statement (EIS) is being prepared and will include both wet and dry storage facilities as storage alternatives. For the UFSF presented in this document, a specific site is not chosen. This facility can be sited at any one of the five locations under consideration in the EIS. These locations are the Idaho National Engineering Laboratory, Savannah River Site, Hanford, Oak Ridge National Laboratory, and Nevada Test Site. Generic facility environmental impacts and emissions are provided in this report. A baseline fuel element is defined in Section 2.2, and the results of a fission product analysis are presented. Requirements for a storage facility have been researched and are summarized in Section 3. Section 4 describes three facility options: (1) the Centralized-UFSF, which would store the entire fuel element quantity in a single facility at a single location, (2) the Regionalized Large-UFSF, which would store 75% of the fuel element quantity in some region of the country, and (3) the Regionalized Small-UFSF, which would store 25% of the fuel element quantity, with the possibility of a number of these facilities in various regions throughout the country. The operational philosophy is presented in Section 5, and Section 6 contains a description of the equipment. Section 7 defines the utilities required for the facility. Cost estimates are discussed in Section 8, and detailed cost estimates are included. Impacts to worker safety, public safety, and the environment are discussed in Section 9. Accidental releases are presented in Section 10. Standard Environmental Impact Forms are included in Section 11.

  7. Improving animal research facility operations through the application of lean principles.

    Science.gov (United States)

    Khan, Nabeel; Umrysh, Brian M

    2008-06-01

    Animal research is a vital component of US research and well-functioning animal research facilities are critical both to the research itself and to the housing and feeding of the animals. The Office of Animal Care (OAC) at Seattle Children's Hospital Research Institute realized it had to improve the efficiency and safety of its animal research facility (ARF) to prepare for expansion and to advance the Institute's mission. The main areas for improvement concerned excessive turnaround time to process animal housing and feeding equipment; the movement and flow of equipment and inventory; and personnel safety. To address these problems, management held two process improvement workshops to educate employees about lean principles. In this article we discuss the application of these principles and corresponding methods to advance Children's Research Institute's mission of preventing, treating, and eliminating childhood diseases.

  8. Overview of the Life Science Glovebox (LSG) Facility and the Research Performed in the LSG

    Science.gov (United States)

    Cole, J. Michael; Young, Yancy

    2016-01-01

    The Life Science Glovebox (LSG) is a rack facility currently under development with a projected availability for International Space Station (ISS) utilization in the FY2018 timeframe. Development of the LSG is being managed by the Marshal Space Flight Center (MSFC) with support from Ames Research Center (ARC) and Johnson Space Center (JSC). The MSFC will continue management of LSG operations, payload integration, and sustaining following delivery to the ISS. The LSG will accommodate life science and technology investigations in a "workbench" type environment. The facility has a.Ii enclosed working volume that is held at a negative pressure with respect to the crew living area. This allows the facility to provide two levels of containment for handling Biohazard Level II and lower biological materials. This containment approach protects the crew from possible hazardous operations that take place inside the LSG work volume. Research investigations operating inside the LSG are provided approximately 15 cubic feet of enclosed work space, 350 watts of28Vdc and l IOVac power (combined), video and data recording, and real time downlink. These capabilities will make the LSG a highly utilized facility on ISS. The LSG will be used for biological studies including rodent research and cell biology. The LSG facility is operated by the Payloads Operations Integration Center at MSFC. Payloads may also operate remotely from different telescience centers located in the United States and different countries. The Investigative Payload Integration Manager (IPIM) is the focal to assist organizations that have payloads operating in the LSG facility. NASA provides an LSG qualification unit for payload developers to verify that their hardware is operating properly before actual operation on the ISS. This poster will provide an overview of the LSG facility and a synopsis of the research that will be accomplished in the LSG. The authors would like to acknowledge Ames Research Center, Johnson

  9. Quantifying capital goods for waste incineration

    DEFF Research Database (Denmark)

    Brogaard, Line Kai-Sørensen; Riber, C.; Christensen, Thomas Højlund

    2013-01-01

    Materials and energy used for the construction of modern waste incineration plants were quantified. The data was collected from five incineration plants (72,000–240,000tonnes per year) built in Scandinavia (Norway, Finland and Denmark) between 2006 and 2012. Concrete for the buildings was the main...... of producing the materials used in the construction, steel for the building and the machinery contributed the most. The material and energy used for the construction corresponded to the emission of 7–14kg CO2 per tonne of waste combusted throughout the lifetime of the incineration plant. The assessment showed...... that, compared to data reported in the literature on direct emissions from the operation of incinerators, the environmental impacts caused by the construction of buildings and machinery (capital goods) could amount to 2–3% with respect to kg CO2 per tonne of waste combusted....

  10. Solid waste combustion for alpha waste incineration

    International Nuclear Information System (INIS)

    Orloff, D.I.

    1981-02-01

    Radioactive waste incinerator development at the Savannah River Laboratory has been augmented by fundamental combustion studies at the University of South Carolina. The objective was to measure and model pyrolysis and combustion rates of typical Savannah River Plant waste materials as a function of incinerator operating conditions. The analytical models developed in this work have been incorporated into a waste burning transient code. The code predicts maximum air requirement and heat energy release as a function of waste type, package size, combustion chamber size, and temperature. Historically, relationships have been determined by direct experiments that did not allow an engineering basis for predicting combustion rates in untested incinerators. The computed combustion rates and burning times agree with measured values in the Savannah River Laboratory pilot (1 lb/hr) and full-scale (12 lb/hr) alpha incinerators for a wide variety of typical waste materials

  11. Los Alamos controlled-air incineration studies

    International Nuclear Information System (INIS)

    Koenig, R.A.; Warner, C.L.

    1983-01-01

    Current regulations of the Environmental Protection Agency (EPA) require that PCBs in concentrations greater than 500 ppM be disposed of in EPA-permitted incinerators. Four commercial incineration systems in the United States have EPA operating permits for receiving and disposing of concentrated PCBs, but none can accept PCBs contaminated with nuclear materials. The first section of this report presents an overview of an EPA-sponsored program for studying PCB destruction in the large-scale Los Alamos controlled-air incinerator. A second major FY 1983 program, sponsored by the Naval Weapons Support Center, Crane, Indiana, is designed to determine operating conditions that will destroy marker smoke compounds without also forming polycyclic aromatic hydrocarbons (PAHs), some of which are known or suspected to be carcinogenic. We discuss the results of preliminary trial burns in which various equipment and feed formulations were tested. We present qualitative analyses for PAHs in the incinerator offgas as a result of these tests

  12. Highly Efficient Fecal Waste Incinerator, Phase I

    Data.gov (United States)

    National Aeronautics and Space Administration — Volume reduction is a critical element of Solid Waste Management for manned spacecraft and planetary habitations. To this end, the proposed fecal waste incinerator...

  13. Quantification of the resource recovery potential of municipal solid waste incineration bottom ashes.

    Science.gov (United States)

    Allegrini, Elisa; Maresca, Alberto; Olsson, Mikael Emil; Holtze, Maria Sommer; Boldrin, Alessio; Astrup, Thomas Fruergaard

    2014-09-01

    Municipal solid waste incineration (MSWI) plays an important role in many European waste management systems. However, increasing focus on resource criticality has raised concern regarding the possible loss of critical resources through MSWI. The primary form of solid output from waste incinerators is bottom ashes (BAs), which also have important resource potential. Based on a full-scale Danish recovery facility, detailed material and substance flow analyses (MFA and SFA) were carried out, in order to characterise the resource recovery potential of Danish BA: (i) based on historical and experimental data, all individual flows (representing different grain size fractions) within the recovery facility were quantified, (ii) the resource potential of ferrous (Fe) and non-ferrous (NFe) metals as well as rare earth elements (REE) was determined, (iii) recovery efficiencies were quantified for scrap metal and (iv) resource potential variability and recovery efficiencies were quantified based on a range of ashes from different incinerators. Recovery efficiencies for Fe and NFe reached 85% and 61%, respectively, with the resource potential of metals in BA before recovery being 7.2%ww for Fe and 2.2%ww for NFe. Considerable non-recovered resource potential was found in fine fraction (below 2mm), where approximately 12% of the total NFe potential in the BA were left. REEs were detected in the ashes, but the levels were two or three orders of magnitude lower than typical ore concentrations. The lack of REE enrichment in BAs indicated that the post-incineration recovery of these resources may not be a likely option with current technology. Based on these results, it is recommended to focus on limiting REE-containing products in waste for incineration and improving pre-incineration sorting initiatives for these elements. Copyright © 2014 Elsevier Ltd. All rights reserved.

  14. Environmental assessment of the Carlsbad Environmental Monitoring and Research Center Facility

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1995-10-01

    This Environmental Assessment has been prepared to determine if the Carlsbad Environmental Monitoring and Research Center (the Center), or its alternatives would have significant environmental impacts that must be analyzed in an Environmental Impact Statement. DOE`s proposed action is to continue funding the Center. While DOE is not funding construction of the planned Center facility, operation of that facility is dependent upon continued funding. To implement the proposed action, the Center would initially construct a facility of approximately 2,300 square meters (25,000 square feet). The Phase 1 laboratory facilities and parking lot will occupy approximately 1.2 hectares (3 acres) of approximately 8.9 hectares (22 acres) of land which were donated to New Mexico State University (NMSU) for this purpose. The facility would contain laboratories to analyze chemical and radioactive materials typical of potential contaminants that could occur in the environment in the vicinity of the DOE Waste Isolation Pilot Plant (WIPP) site or other locations. The facility also would have bioassay facilities to measure radionuclide levels in the general population and in employees of the WIPP. Operation of the Center would meet the DOE requirement for independent monitoring and assessment of environmental impacts associated with the planned disposal of transuranic waste at the WIPP.

  15. Environmental assessment of the Carlsbad Environmental Monitoring and Research Center Facility

    International Nuclear Information System (INIS)

    1995-10-01

    This Environmental Assessment has been prepared to determine if the Carlsbad Environmental Monitoring and Research Center (the Center), or its alternatives would have significant environmental impacts that must be analyzed in an Environmental Impact Statement. DOE's proposed action is to continue funding the Center. While DOE is not funding construction of the planned Center facility, operation of that facility is dependent upon continued funding. To implement the proposed action, the Center would initially construct a facility of approximately 2,300 square meters (25,000 square feet). The Phase 1 laboratory facilities and parking lot will occupy approximately 1.2 hectares (3 acres) of approximately 8.9 hectares (22 acres) of land which were donated to New Mexico State University (NMSU) for this purpose. The facility would contain laboratories to analyze chemical and radioactive materials typical of potential contaminants that could occur in the environment in the vicinity of the DOE Waste Isolation Pilot Plant (WIPP) site or other locations. The facility also would have bioassay facilities to measure radionuclide levels in the general population and in employees of the WIPP. Operation of the Center would meet the DOE requirement for independent monitoring and assessment of environmental impacts associated with the planned disposal of transuranic waste at the WIPP

  16. FINESSE: study of the issues, experiments and facilities for fusion nuclear technology research and development. Interim report. Volume I

    International Nuclear Information System (INIS)

    Abdou, M.

    1984-10-01

    The following chapters are included in this study: (1) fusion nuclear issues, (2) survey of experimental needs, (3) requirements of the experiments, (4) non-fusion facilities, (5) fusion facilities for nuclear experiments, and (6) fusion research and development scenarios

  17. Multi-purpose research facility: 60Co gamma irradiation unit at Centrum vyzkumu Rez

    International Nuclear Information System (INIS)

    Miklos, M.; Namburi, H. K.

    2014-01-01

    It is well know from 1950's till date, that the users, demand and network of gamma irradiation facility centers are growing rapidly to support industries as well as research due to its versatility. At present, its applications are in the fields of biological, chemical, solid state physics, medical, food and sterilization etc. The Gamma Irradiation Facility of the CVREZ is a dry-storage irradiator, which reached source end of life. The facility is now under refurbishment as a multi-purpose research center, fulfilling the requirements of international standards to support primarily the research sector and industries. Apart from the classical usage of gamma irradiation facility there is great scientific interest to use them to characterize the materials that are used in Nuclear Power Plants (NPP's). Electrical system unit in a nuclear power plants consists of several components. For instance some of them are light emitting diodes, pin-type photo-detectors and optical fibers, rubber seals, electrical insulation, thermal insulation, polymeric composites and metallic components etc. Under normal environmental conditions these materials possess good mechanical properties/chemical stability. The qualification of these materials for usage in NPPs under radiation environments and at high temperatures are desired for their better performance. Another feasibility of using gamma irradiation facility in the contest of NPP's is radiation hardening of robots that are used time-to-time in inspection of NPP's. Overall objective of our project is to support research activities aiming to understand the materials modification due to ionizing radiation. Upgraded facility will provide high-fidelity simulation of nuclear radiation environments for materials and component testing. We present our work by providing the information on (i) our objectives in utilizing the gamma facility, (ii) specific experimental test set-up under development to perform tests at elevated

  18. Recycling ampersand incineration: Evaluating the choices

    International Nuclear Information System (INIS)

    Denison, R.A.; Ruston, J.

    1993-01-01

    Conflicts between proponents of municipal solid waste incineration and advocates of recycling have escalated with efforts to reduce the volume of waste that ends up in landfills. Central to this debate is competition for materials that are both combustible and recyclable. Environmental and economic concerns also play a major role. This book, produced by the Environmental Defense Fund, compares recycling and incineration. It is intended for 'citizens, government officials, and business people who want to help resolve the solid-waste crisis.' The book is divided into three parts: recycling and incineration; health and environmental risk of incineration; and planning, public participation, and environmental review requirements. The book does an excellent job of discussing the benefits of recycling and the pitfalls of incineration. It provides helpful information for identifying questions that should be raised about incineration, but it does not raise similar queries about recycling. There is much worthwhile information here, but the book would be more useful if it identified critical issues for all waste reduction and management options

  19. Safety Culture and Best Practices at Japan's Fusion Research Facilities

    Energy Technology Data Exchange (ETDEWEB)

    Rule, Keith [PPPL

    2014-05-01

    The Safety Monitor Joint Working Group (JWG) is one of the magnetic fusion research collaborations between the US Department of Energy and the government of Japan. Visits by occupational safety personnel are made to participating institutions on a biennial basis. In the 2013 JWG visit of US representatives to Japan, the JWG members noted a number of good safety practices in the safety walkthroughs. These good practices and safety culture topics are discussed in this paper. The JWG hopes that these practices for worker safety can be adopted at other facilities. It is a well-known, but unquantified, safety principle that well run, safe facilities are more productive and efficient than other facilities (Rule, 2009). Worker safety, worker productivity, and high quality in facility operation all complement each other (Mottel, 1995).

  20. Feasibility study to develop BNCT facility at the Indonesian research reactor

    International Nuclear Information System (INIS)

    Hastowo, H.

    2001-01-01

    A survey on the Indonesian research reactors and its supporting facilities has been done in order to check the possibility to install BNCT facility. Oncologists from several hospitals have been informing about the BNCT treatment for tumours and they give a positive response to support utilisation of the BNCT facility. Several aspects required to support the BNCT treatment have also been identified and related activities on that matter soon will be initiated. The interim result in our survey indicated that utilisation of the 30 MW Multipurpose reactor would not be possible from the technical point of view. Further study will be concentrated on the TRIGA reactor and an epithermal neutron beam facility at the thermal column of this reactor will be designed for further work. (author)