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Sample records for incinerating radioactive wastes

  1. 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.)

  2. 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

  3. 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

  4. Hazardous and radioactive waste incineration studies

    International Nuclear Information System (INIS)

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

    1981-01-01

    Development and demonstration of a transuranic (TRU) waste volume-reduction process is described. A production-scale controlled air incinerator using commercially available equipment and technology has been modified for solid radioactive waste service. This unit successfully demonstrated the volume reduction of transuranic (TRU) waste with an average TRU content of about 20 nCi/g. The same incinerator and offgas treatment system is being modified further to evaluate the destruction of hazardous liquid wastes such as polychlorinated biphenyls (PCBs) and hazardous solid wastes such as pentachlorophenol (PCP)-treated wood

  5. Secondary incinerator for radioactive gaseous waste

    International Nuclear Information System (INIS)

    Takeda, Tadashi; Masuda, Takashi.

    1997-01-01

    A vessel incorporated with packings, in which at least either of the packings and the vessel is put to induction-heating by high frequency induction coils, is disposed in a flow channel of radioactive gaseous wastes exhausted from a radioactive waste incinerator. The packings include metals such as stainless pipes and electroconductive ceramics such as C-SiC ceramics. Since only electricity is used as an energy source, in the secondary incinerator for the radioactive gaseous wastes, it can be installed in a cell safely. In addition, if ceramics are used, there is no worry of deterioration of the incinerator due to organic materials, and essential functions are not lowered. (T.M.)

  6. 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

  7. 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.

  8. 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

  9. Incineration of Non-radioactive Simulated Waste

    International Nuclear Information System (INIS)

    Ahmed, A.Z.; Abdelrazek, I.D.

    1999-01-01

    An advanced controlled air incinerator has been investigated, developed and put into successful operation for both non radioactive simulated and other combustible solid wastes. Engineering efforts concentrated on providing an incinerator which emitted a clean, easily treatable off-gas and which produced minimum amounts of secondary waste. Feed material is fed by gravity into the gas reactor without shredding or other pretreatment. The temperature of the waste is gradually increased in a reduced oxygen atmosphere as the resulting products are introduced into the combustion chamber. Steady burning is thus accomplished under easily controlled excess air conditions with the off-gas then passing through a simple dry cleaning-up system. Experimental studies showed that, at lower temperature, CO 2 , and CH 4 contents in gas reactor effluent increase by the increase of glowing bed temperature, while H 2 O, H 2 and CO decrease . It was proved that, a burn-out efficiency (for ash residues) and a volume reduction factor appeared to be better than 95.5% and 98% respectively. Moreover, high temperature permits increased volumes of incinerated material and results in increased gasification products. It was also found that 8% by weight of ashes are separated by flue gas cleaning system as it has chemical and size uniformity. This high incineration efficiency has been obtained through automated control and optimization of process variables like temperature of the glowing bed and the oxygen feed rate to the gas reactor

  10. 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

  11. Use plan for demonstration radioactive-waste incinerator

    International Nuclear Information System (INIS)

    Cooley, L.R.; McCampbell, M.R.; Thompson, J.D.

    1982-04-01

    The University of Maryland at Baltimore was awarded a grant from the Department of Energy to test a specially modified incinerator to burn biomedical radioactive waste. In preparation for the incinerator, the Radiation Safety Office devised a comprehensive plan for its safe and effective use. The incinerator plan includes a discussion of regulations regarding on-site incineration of radioactive waste, plans for optimum use in burning four principal waste forms, controlled air incineration technology, and standard health physics safety practices; a use plan, including waste categorization and segregation, processing, and ash disposition; safety procedures, including personnel and area monitoring; and methods to evaluate the incinerator's effectiveness by estimating its volume reduction factors, mass and activity balances, and by determining the cost effectiveness of incineration versus commercial shallow land burial

  12. Incineration system for solid and liquid radioactive wastes

    International Nuclear Information System (INIS)

    Krutman, J.K.Z.; Grosche Filho, C.E.; Alfonso, S.A.

    1986-01-01

    An incineration system that allows the burning of solid and liquid radioactive wastes transforming them to highly insoluble ashes, and volumetric reduction from 30 to 50 times, depending on the incinerated waste. The global factor of activity retention contained in the waste is the order of 99%. The proposed incineration system allows the total combustion of radioactive waste and the generated gases during the burning. The formation of gaseous secondary wastes is minimum and any liquid waste is formed, reducing the costs of installation and operation. (M.C.K.) [pt

  13. 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)

  14. 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)

  15. Method for controlling incineration in combustor for radioactive wastes

    International Nuclear Information System (INIS)

    Takaoku, Y.; Uehara, A.

    1991-01-01

    This invention relates to a method for controlling incineration in a combustor for low-level radioactive wastes. In particular, it relates to a method for economizing in the consumption of supplemental fuel while maintaining a stable incineration state by controlling the amount of fuel and of radioactive wastes fed to the combustor. The amount of fuel supplied is determined by the outlet gas temperature of the combustor. (L.L.)

  16. 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.)

  17. 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

  18. Incinerators for radioactive wastes in Japanese nuclear power stations

    International Nuclear Information System (INIS)

    Karita, Yoichi

    1983-01-01

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

  19. 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

  20. Radioactivity partitioning in incinerators for miscellaneous low-level wastes

    International Nuclear Information System (INIS)

    Kyle, S.; Bellinger, E.

    1988-03-01

    Her Majesty's Inspectorate of Pollution (HMIP) authorises the use of hospital, university and Local Authority incinerators for the disposal of solid radioactive wastes. At present these authorisations are calculated on ''worst case'' assumptions, this report aims to review the experimental data on radioactivity partitioning in these incinerators, in order to improve the accuracy of HMIP predictions. The types of radionuclides used in medicine were presented and it is noted there is no literature on the composition of university waste. The different types of incinerators are detailed, with diagrams. Major differences in design are apparent, particularly the offgas cleaning equipment in nuclear incinerators which hinders comparisons with institutional incinerators. A comprehensive literature review revealed 17 references on institutional radioactive waste incineration, 11 of these contained data sets. The partitioning experiments were described and show a wide range of methodology from incinerating guinea pigs to filter papers. In general, only ash composition data were presented, with no details of emissions or plating out in the incinerator. Thus the data sets were incomplete, often with a poor degree of accuracy. The data sets contained information on 40 elements; those were compared and general trends were apparent such as the absence of H-3, C-14 and I-125 in the ash in contrast to the high retention of Sc-46. Large differences between data sets were noted for P-32, Sr-85 and Sn-113 and within one experiment for S-35. (author)

  1. An incineration technology for low level radioactive solid waste

    International Nuclear Information System (INIS)

    Suyari, Mamoru; Nakanishi, Ryota; Noura, Tsuyoshi; Fujitomi, Masashi; Ano, Shintaroh

    2003-01-01

    Low-level radioactive solid waste, mainly consisting of rag paper and cloth, is usually incinerated. However, polymeric waste, including rubber and polyvinyl chloride plastic, is securely stored in view of safe treatment. Kobe Steel has developed a new kind of incinerator which can be used for polymeric waste. It has the following characteristics: (a) A controlled air type furnace with a unique grate design (b) In order to control dioxin emissions, the furnace wall is refractory-lined to maintain furnace temperatures at 900degC or higher (c) Secondary combustion air is injected into the furnace to mix with gas from the primary combustion zone. In this paper, the following non-radioactive test results using an actual incinerator, (feed rate: 130 kg/hr.) are presented: (1) Polymeric waste, including rubber, polyethylene and polyvinyl chloride plastic, was incinerated under stable operation; (2) Design specifications including treatment capacity, emission limits were satisfactorily achieved. (author)

  2. Operation of low-level radioactive waste incinerator

    International Nuclear Information System (INIS)

    Choi, E.C.; Drolet, T.S.; Stewart, W.B.; Campbell, A.V.

    1979-01-01

    Ontaro Hydro's radioactive waste incinerator designed to reduce the volume of low-level combustible wastes from nuclear generating station's was declared in-service in September 1977. Hiterto about 1500 m 3 of combustible waste have been processed in over 90 separate batches. The process has resulted in 40:1 reduction in the volume and 12.5:1 reduction in the weight of the Type 1 wastes. The ultimate volume reduction factor after storage is 23:1. Airborne emissions has been maintained at the order of 10 -3 to 10 -5 % of the Derived Emission Limits. Incineration of radioactive combustible wastes has been proven feasible, and will remain as one of the most important processes in Ontario Hydro's Radioactive Waste Management Program

  3. 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

  4. 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)

  5. Radioactive waste incineration studies at the Los Alamos Scientific Laboratory

    International Nuclear Information System (INIS)

    Stretz, L.A.; Borduin, L.C.; Draper, W.E.; Koenig, R.A.; Newmyer, J.M.

    1980-01-01

    Development and demonstration of a transuranic (TRU) waste volume-reduction process is described. A controlled-air incinerator, based upon commercially available equipment and technology, was modified for radioactive service and was successfully tested and demonstrated with contaminated waste. Demonstration of the production-scale unit was completed in May 1980 with the incineration of 272 kg of waste with an average TRU content of about 20 nCi/g. Weight and volume reduction factors for the demonstration run were 40:1 and 120:1, respectively

  6. 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

  7. 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

  8. Progress on radioactive waste slurry incineration with oxygen and steam

    International Nuclear Information System (INIS)

    Hoshino, M.; Hayashi, M.; Oda, I.; Nonaka, N.; Kuwayama, K.; Shigeta, T.

    1988-01-01

    The radioactive waste (radwaste) slurry generated from the nuclear power plant operation, such as spent ion-exchange resins (powdered, bead), fire-retardant oils including phosphate ester and concentrated laundry (by the wet method) liquid waste, has been stored in an untreated condition on the plant site. Recently, since the Condensate Filter Demineralizer (CFD) has been applied in advanced BWR plants, the discharged volume of untreated spent powered resin slurry has been increasing steadily. TEE and NCE have been developing an effective new volume reduction system to treat this radwaste slurry based on an innovative incineration concept. The new system is called the IOS process, the feature of which is incineration with oxygen and steam admixture instead of conventional air. The IOS process, which consists mainly of high heat load incineration with slurry atomization, and combustion gas cooling and condensation by the wet method, has several advantages which are summarized in this paper

  9. Volume reduction through incineration of low-activity radioactive wastes

    International Nuclear Information System (INIS)

    Eymeri, J.; Gauthey, J.C.; Chaise, D.; Lafite, G.

    1993-01-01

    The aim of the waste treatment plant, designed by Technicatome (CEA) for an Indonesian Nuclear Research Center, is to reduce through incineration the volume of low-activity radioactive wastes such as technological solids (cotton, PVC, paper board), biological solids (animal bones) and liquids (cutting fluids...). The complete combustion is realized with a total air multi-fuel burner (liquid wastes) and flash pyrolysis-complete combustion (solid wastes). A two stage flue gas filtration system, a flue gas washing system, and an ash recovery system are used. A test platform has been built. 3 figs

  10. Behavior of radioactive cesium during incineration of radioactively contaminated wastes from decontamination activities in Fukushima.

    Science.gov (United States)

    Fujiwara, Hiroshi; Kuramochi, Hidetoshi; Nomura, Kazutaka; Maeseto, Tomoharu; Osako, Masahiro

    2017-11-01

    Large volumes of decontamination wastes (DW) generated by off-site decontamination activities in Fukushima Prefecture have been incinerated since 2015. The behavior of radioactive cesium during incineration of DW was investigated at a working incineration plant. The incineration discharged bottom ash (BA) and fly ash (FA) with similar levels of radiocesium, and the leachability of the radiocesium from both types of ash was very low (incineration of contaminated municipal solid waste (CMSW) reported in earlier studies. The source of radiocesium in DW-FA is chiefly small particles derived from DW and DW-BA blown into the flue gas, not the deposition of gaseous synthesized radiocesium compounds on the surfaces of ash particles in the flue gas as observed in CMSW incineration. This source difference causes the behavior of radiocesium during waste incineration to differ between DW and CMSW. Copyright © 2017 Elsevier Ltd. All rights reserved.

  11. 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)

  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. 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

  14. 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

  15. Current practice of incineration of low-level institutional radioactive waste

    International Nuclear Information System (INIS)

    Cooley, L.R.; McCampbell, M.R.; Thompson, J.D.

    1981-02-01

    During 1972, 142 medical and academic institutions were surveyed to assess the current practice of incineration of low-level radioactive waste. This was one activity carried out by the University of Maryland as part of a contract with EG and G Idaho, Inc., to site a radioactive waste incineration system. Of those surveyed, 46 (approximately 32%) were presently incinerating some type of radioactive waste. All were using controlled-air, multistage incinerators. Incinerators were most often used to burn animal carcasses and other biological wastes (96%). The average size unit had a capacity of 113 kg/h. Disposal of liquid scintillation vials posed special problems; eight institutions incinerated full scintillation vials and five incinerated scintillation fluids in bulk form. Most institutions (87%) used the incinerator to dispose of other wastes in addition to radioactive wastes. About half (20) of the institutions incinerating radioactive wastes reported shortcomings in their incineration process; those most often mentioned were: problems with liquid scintillation wastes, ash removal, melting glass, and visible smoke. Frequently cited reasons for incinerating wastes were: less expensive than shipping for commercial shallow land burial, volume reduction, convenience, and closure of existing disposal sites

  16. Particulate collection in a low level radioactive waste incinerator

    International Nuclear Information System (INIS)

    Rudnick, S.N.; Leith, D.; First, M.W.

    1976-01-01

    As designed, sintered stainless steel filters will clean the gas from the secondary cyclone at a low level radioactive waste incinerator. Using bench scale apparatus, asbestos floats and diatomaceous earth were evaluated as filter aids to prevent clogging of the sintered metal interstices and to decrease filter penetration. Both precoats prevented irreversible pressure drop increase, and decreased cold DOP penetration from 80% to less than 1%. To collect the same quantity of fly ash, less diatomaceous earth was needed than asbestos floats. A back-up study evaluated a moving bed of sodium carbonate pellets in lieu of the sintered metal filters. Since identical sodium carbonate pellets are used to neutralize hydrogen chloride in the incinerator, their use in a moving bed has the advantages of trouble free disposal and cost free replacement. Co, counter, and cross-current beds were studied and gave fly ash penetrations less than 0.1% at moderate pressure drop

  17. 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.

  18. 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

  19. Particulate collection in a low level radioactive waste incinerator

    International Nuclear Information System (INIS)

    Rudnick, S.N.; Leith, D.; First, M.W.

    1976-01-01

    As designed, sintered stainless steel filters will clean the gas from the secondary cyclone at a low level radioactive waste incinerator. Bench-scale apparatus was used to evaluate asbestos floats and diatomaceous earth as filter aids to prevent clogging of the sintered metal interstices and to decrease filter penetration. Both precoats prevented irreversible pressure drop increase, and decreased cold DOP penetration from 80 percent to less than 1 percent. Less diatomaceous earth was needed than asbestos floats, to collect the same quantity of fly ash. A back-up study evaluated a moving bed of sodium carbonate pellets in lieu of the sintered metal filters. Since identical sodium carbonate pellets are used to neutralize hydrogen chloride in the incinerator, their use in a moving bed has the advantages of trouble free disposal and cost free replacement. Co - , counter, and cross-current beds were studied and gave fly ash penetrations less than 0.1 percent at moderate pressure drop. The filter cake which forms on the pellet surfaces decreases penetration greatly

  20. 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)

  1. Treatment of radioactive wastes by incineration; Tratamiento de desechos radiactivos por incineracion

    Energy Technology Data Exchange (ETDEWEB)

    Priego C, E., E-mail: emmanuel.priego@inin.gob.mx [ININ, Carretera Mexico-Toluca s/n, 52750 Ocoyoacac, Estado de Mexico (Mexico)

    2013-10-15

    Great part of the radioactive wastes of low and intermediate level generated during the nuclear fuel cycle, in laboratories and other sites where the radionuclides are used for the research in the industry, in medicine and other activities, are combustible wastes. The incineration of these radioactive wastes provides a very high reduction factor and at the same time converts the wastes in radioactive ashes and no-flammable residuals, chemically inert and much more homogeneous that the initial wastes. With the increment of the costs in the repositories and those every time but strict regulations, the incineration of radioactive wastes has been able to occupy an important place in the strategy of the wastes management. However, in a particular way, the incineration is a complex process of high temperature that demands the execution of safety and operation requirements very specific. (author)

  2. 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)

  3. Combustible radioactive waste treatment by incineration and chemical digestion

    International Nuclear Information System (INIS)

    Stretz, L.A.; Crippen, M.D.; Allen, C.R.

    1980-01-01

    A review is given of present and planned combustible radioactive waste treatment systems in the US. Advantages and disadvantages of various systems are considered. Design waste streams are discussed in relation to waste composition, radioactive contaminants by amount and type, and special operating problems caused by the waste

  4. Incineration of tyres, radioactive and photographic industry waste

    International Nuclear Information System (INIS)

    Carpentier, S.

    1977-01-01

    In the list every day longer of 'industrial' wastes, there is a special place for combustible waste usually presenting a solution for their elimination, i. e. incineration with or without calory recovery. Three categories are well-known as they concern the general public. The overall data of the problem are first considered, then three incineration plants in three different fields are described: motor-car tyres, nuclear industry, photographic industry. In the last field, well-conducted recovery processes may result in surprising results as to the damping of the plant cost, which finally is both pleasant and useful [fr

  5. 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

  6. 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)

  7. 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

  8. The incineration of low-level radioactive waste: A report for the Advisory Committee on Nuclear Waste

    International Nuclear Information System (INIS)

    Long, S.W.

    1990-06-01

    This report is a summary of the contemporary use of incineration technology as a method for volume reduction of LLW. It is intended primarily to serve as an overview of the technology for waste management professionals involved in the use or regulation of LLW incineration. It is also expected that organizations presently considering the use of incineration as part of their radioactive waste management programs will benefit by gaining a general knowledge of incinerator operating experience. Specific types of incineration technologies are addressed in this report, including designation of the kinds of wastes that can be processed, the magnitudes of volume reduction that are achievable in typical operation, and requirements for ash handling and off-gas filtering and scrubbing. A status listing of both US and foreign incinerators provides highlights of activities at government, industry, institutional, and commercial nuclear power plant sites. The Federal and State legislative structures for the regulation of LLW incineration are also described. 84 refs., 33 tabs

  9. 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.)

  10. Bonding material containing ashes after domestic waste incineration for cementation of radioactive waste

    International Nuclear Information System (INIS)

    Dmitriev, S.A.; Varlakov, A.P.; Gorbunova, O.A.; Arustamov, A.E.; Barinov, A.S.

    2007-01-01

    It is known that cement minerals hydration is accompanied with heat emission. Heat of hardening influences formation of a cement compound structure and its properties. It is important to reduce the heat quantity at continuous cementation of waste and filling of compartments of a repository or containers by a cement grout. For reduction of heating, it is necessary to use cement of mineral additives (fuel ashes, slag and hydraulic silica). Properties of ashes after domestic waste incineration can be similar to ones of fly fuel ashes. However, ash after domestic waste incineration is toxic industrial waste as it contains toxic elements (As, Cd, Hg, Pb, Sb, Zn). Utilization of secondary waste (slag and ash) of combustion plants is an important environmental approach to solving cities' issues. Results of the research have shown that ashes of combustion plants can be used for radioactive waste conditioning. Co-processing of toxic and radioactive waste is ecologically and economically effective. At SIA 'Radon', experimental batches of cement compositions are used for cementation of oil containing waste. (authors)

  11. Thermal treatments available for destruction of industrial wastes. Application to the incineration of radioactive wastes

    International Nuclear Information System (INIS)

    Chevalier, Gerard.

    1981-08-01

    Both the collecting and processing circuits and the physicochemical laws of combustion and thermal degradation of industrial wastes are recalled. The various incineration processes are reviewed considering especially conversion of refuse to energy and recovery of raw materials either before or after treatment. Wastes are devided into three classes according to their physical state: solid, liquid or sludge, gas. Some processes based on pyrolysis in the absence of air or at sub-stoichiometric levels are presented. A similar study is carried out on radioactive wastes, taking into account the particular aspects raised by incineration. Operational devices are described and some lines of research about the application of new techniques are summarized. The results derived from laboratory or pilot plant experiments are presented [fr

  12. 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

  13. Incineration of European non-nuclear radioactive waste in the USA

    International Nuclear Information System (INIS)

    Moloney, B. P.; Ferguson, D.; Stephenson, B.

    2013-01-01

    Incineration of dry low level radioactive waste from nuclear stations is a well established process achieving high volume reduction factors to minimise disposal costs and to stabilise residues for disposal. Incineration has also been applied successfully in many European Union member countries to wastes arising from use of radionuclides in medicine, nonnuclear research and industry. However, some nations have preferred to accumulate wastes over many years in decay stores to reduce the radioactive burden at point of processing. After decay and sorting the waste, they then require a safe, industrial scale and affordable processing solution for the large volumes accumulated. This paper reports the regulatory, logistical and technical issues encountered in a programme delivered for Eckert and Ziegler Nuclitec to incinerate safely 100 te of waste collected originally from German research, hospital and industrial centres, applying for the first time a 'burn and return' process model for European waste in the US. The EnergySolutions incinerators at Bear Creek, Oak Ridge, Tennessee, USA routinely incinerate waste arising from the non-nuclear user community. To address the requirement from Germany, EnergySolutions had to run a dedicated campaign to reduce cross-contamination with non-German radionuclides to the practical minimum. The waste itself had to be sampled in a carefully controlled programme to ensure the exacting standards of Bear Creek's license and US emissions laws were maintained. Innovation was required in packaging of the waste to minimise transportation costs, including sea freight. The incineration was inspected on behalf of the German regulator (the BfS) to ensure suitability for return to Germany and disposal. This first 'burn and return' programme has safely completed the incineration phase in February and the arising ash will be returned to Germany presently. The paper reports the main findings and lessons learned on this first

  14. 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)

  15. 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

  16. Solidification of ash from incineration of low-level radioactive waste

    International Nuclear Information System (INIS)

    Roberson, W.A.; Albenesius, E.L.; Becker, G.W.

    1983-01-01

    The safe disposal of both high-level and low-level radioactive waste is a problem of increasing national attention. A full-scale incineration and solidification process to dispose of suspect-level and low-level beta-gamma contaminated combustible waste is being demonstrated at the Savannah River Plant (SRP) and Savannah River Laboratory (SRL). The stabilized wasteform generated by the process will meet or exceed all future anticipated requirements for improved disposal of low-level waste. The incineration process has been evaluated at SRL using nonradioactive wastes, and is presently being started up in SRP to process suspect-level radioactive wastes. A cement solidification process for incineration products is currently being evaluated by SRL, and will be included with the incineration process in SRP during the winter of 1984. The GEM alumnus author conducted research in a related disposal solidification program during the GEM-sponsored summer internship, and upon completion of the Masters program, received full-time responsibility for developing the incineration products solidification process

  17. Los Alamos Controlled Air Incinerator for hazardous chemical and mixed radioactive wastes

    International Nuclear Information System (INIS)

    Vavruska, J.S.; Borduin, L.C.; Hutchins, D.A.; Koenig, R.A.; Warner, C.L.

    1986-01-01

    The Los Alamos Controlled Air Incinerator (CAI) is currently the only radioactive waste incineration facility in the US permitted to treat polychlorinated biphenyls (PCBs). The CAI was developed in the mid-1970's as a demonstration system for volume reduction of transuranic (TRU) contaminated combustible solid wastes. It has since undergone additions and modifications to accommodate hazardous chemical wastes in response to a need within the Department of Energy (DOE) to treat mixed radioactive/chemical wastes. An overview of these additions which include a liquid feed system, a high intensity liquid injection burner, and an activated carbon adsorption unit is presented here. Also included is a discussion of the procedures required for Toxic Substances Control Act (TSCA) and Resource Conservation and Recovery Act (RCRA) permitting of the CAI

  18. 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

  19. Viability study for the implantation of an incineration unit for low level radioactive wastes

    International Nuclear Information System (INIS)

    Andrade, Andre Wagner Oliani

    1995-01-01

    Incineration have been a world-wide accepted volume reduction technique for combustible materials due to its high efficiency and excellent results. This technique is used since the last century as an alternative to reduce cities garbage and during the last four decades for the hazardous wastes. The nuclear industry is also involved in this technique development related to the low level radioactive waste management. There are different types of incineration installations and the definition of the right system is based on a criterious survey of its main characteristics, related to the rad wastes as well technical, economical and burocratic parameters. After the autonomous Brazilian nuclear programme development and the onlook of the future intensive nuclear energy uses, a radwaste generation increase is expected. One of the installations where these radwastes volumes are awaited to be high is the Experimental Center of ARAMAR (CEA). Nuclear reactors for propulsion and power generation have been developed in CEA beyond other nuclear combustible cycle activities. In this panorama it is important to evaluate the incineration role in CEA installations, as a volume reduction technique for an appropriate radioactive wastes management implementation. In this work main aspects related to the low level radwaste incineration systems were up rised. This information are important to a coherent viability study and also to give a clear and impartial about a topic that is still non discussed in the national scenery. (author)

  20. 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)

  1. Encapsulation of mixed radioactive and hazardous waste contaminated incinerator ash in modified sulfur cement

    International Nuclear Information System (INIS)

    Kalb, P.D.; Heiser, J.H. III; Colombo, P.

    1990-01-01

    Some of the process waste streams incinerated at various Department of Energy (DOE) facilities contain traces of both low-level radioactive (LLW) and hazardous constituents, thus yielding ash residues that are classified as mixed waste. Work is currently being performed at Brookhaven National Laboratory (BNL) to develop new and innovative materials for encapsulation of DOE mixed wastes including incinerator ash. One such material under investigation is modified sulfur cement, a thermoplastic developed by the US Bureau of Mines. Monolithic waste forms containing as much as 55 wt % incinerator fly ash from Idaho national Engineering Laboratory (INEL) have been formulated with modified sulfur cement, whereas maximum waste loading for this waste in hydraulic cement is 16 wt %. Compressive strength of these waste forms exceeded 27.6 MPa. Wet chemical and solid phase waste characterization analyses performed on this fly ash revealed high concentrations of soluble metal salts including Pb and Cd, identified by the Environmental Protection Agency (EPA) as toxic metals. Leach testing of the ash according to the EPA Toxicity Characteristic Leaching Procedure (TCLP) resulted in concentrations of Pb and Cd above allowable limits. Encapsulation of INEL fly ash in modified sulfur cement with a small quantity of sodium sulfide added to enhance retention of soluble metal salts reduced TCLP leachate concentrations of Pb and Cd well below EPA concentration criteria for delisting as a toxic hazardous waste. 12 refs., 4 figs., 2 tabs

  2. 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

  3. 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

  4. Method and device for incinerating radioactive wastes and preparing burnable wastes for non-polluting storage

    International Nuclear Information System (INIS)

    Hempelmann, W.

    1975-01-01

    An apparatus for incinerating radioactive wastes includes a furnace which has air inlet conduits and a flue gas outlet conduit and air heaters as well as blowers connected to the air inlets for forcing hot air into the furnace. The apparatus further has a feeding device connected to the charging end of the furnace for introducing liquid or solid wastes thereinto and a device which communicates with the discharge end of the furnace for removing solid reaction products from the furnace. In the flue gas conduit there is connected a plurality of flue gas filters each containing filter candles, a flue gas chamber and a mechanism for removing ashes from the flue gas chamber. The apparatus also includes a mixer section connected with the outlet of each flue gas filter and having a mechanism for mixing cool air with the flue gas filtered by the flue gas filters. Gas blowers connected to the output of the mixer section draw the gas from the apparatus. 18 Claims, 8 Drawing Figures

  5. Two stage, low temperature, catalyzed fluidized bed incineration with in situ neutralization for radioactive mixed wastes

    International Nuclear Information System (INIS)

    Wade, J.F.; Williams, P.M.

    1995-01-01

    A two stage, low temperature, catalyzed fluidized bed incineration process is proving successful at incinerating hazardous wastes containing nuclear material. The process operates at 550 degrees C and 650 degrees C in its two stages. Acid gas neutralization takes place in situ using sodium carbonate as a sorbent in the first stage bed. The feed material to the incinerator is hazardous waste-as defined by the Resource Conservation and Recovery Act-mixed with radioactive materials. The radioactive materials are plutonium, uranium, and americium that are byproducts of nuclear weapons production. Despite its low temperature operation, this system successfully destroyed poly-chlorinated biphenyls at a 99.99992% destruction and removal efficiency. Radionuclides and volatile heavy metals leave the fluidized beds and enter the air pollution control system in minimal amounts. Recently collected modeling and experimental data show the process minimizes dioxin and furan production. The report also discusses air pollution, ash solidification, and other data collected from pilot- and demonstration-scale testing. The testing took place at Rocky Flats Environmental Technology Site, a US Department of Energy facility, in the 1970s, 1980s, and 1990s

  6. Analysis of small cyclones efficiency for primary treatment of incineration gases of radioactive wastes

    International Nuclear Information System (INIS)

    Halasz, M.R.T.; Massarani, G.

    2000-01-01

    The objective of this work is to develop an efficient gas treatment system, especially small diameter cyclones. The high efficiency justifies the interest in the application in radioactive wastes incinerators because it reduces the amount of radioactive ashes of other gas cleaning steps. The first stage of this work is to establish some promising configurations of high efficiency cyclones through modeling (neural networks). After construction of the equipment , the operation conditions of each small diameter cyclone were obtained and the viability of adaptation of a Post-cyclone (PoC) was also evaluated to increase the efficiency. The results show the effectiveness of the small diameter cyclone PoC set. The efficiency in optimized conditions can be higher than 98% for fine materials (D 50 s = 3,5 g/cm 3 ). (author)

  7. De minimis concepts in radioactive waste disposal. Considerations in defining de minimis quantities of solid radioactive waste for uncontrolled disposal by incineration and landfill

    International Nuclear Information System (INIS)

    1983-02-01

    This document deals with recommendations addressed to those national authorities wishing to dispose of low level radioactive waste into the terrestrial environment, on how de minimis levels or quantities can be derived. The only radioactive materials covered here are declared solid radioactive wastes of very low activity which are controlled up to the point where deliberate control is lost, or wastes below a level that requires regulatory control. As regards the disposal sites, these wastes are not intended to be disposed of in fully controlled disposal facilities, such as repositories located in shallow land, rock cavities, etc. On the other hand, it is considered that these materials should not be disposed of in any place, but should be handled like other municipal wastes. Among the different techniques available, only two are considered in this document, namely a sanitary landfill facility, and an urban incineration plant

  8. Incineration as a low-level radioactive waste disposal alternative for the very low level (approx. 200 mCi/yr) institutional waste generator

    International Nuclear Information System (INIS)

    Miller, S.D.

    1982-01-01

    As a result of increased shipping costs and decreased land availability, serious questions have arisen regarding the continued use of shallow land burial for disposal of institutional radioactive wastes. These factors are of special significance to very low-level waste generators such as Arizona State University whose most recent waste shipment averaged approximately 2 mCi per shipped barrel at an effective cost of over $100 per mCi disposed - a total cost of over $14,000. Recent studies have shown incineration to be an attractive waste disposal alternative both in terms of volume reduction of waste, and in its expected insignificant radiological and environmental impact. Arizona State University has purchased an incinerator and has initiated a program to incinerate radioactive wastes. Licensing restrictions involving stack monitoring for a variety of possibly hazardous effluents and 10CFR20 restrictions affecting incineration of certain isotopes could render the change to incineration completely inefficient unless accompanied by a rigorous program of waste segregation designed to ease licensing restrictions. This paper reviews incinerator technology as it applies to radioactive waste management and presents the analysis performed during the licensing phase, along with some of the difficulties inherent in the development process

  9. High-temperature incineration of radioactive waste. Exploitation of the FLK-60 slagging incinerator for the treatment of different waste streams contaminated with plutonium

    International Nuclear Information System (INIS)

    Voorde Van de, N.; Taeymans, A.; Hennart, D.; Vanbrabant, R.; Balleux, W.; Geenen, G.; Gijbels, J.

    1986-01-01

    During the years 1983 and 1984 the FLK-60 high-temperature slagging incinerator at Mol was used for incineration of simulated plutonium waste and BWR power-station waste after extensive technical adaptations. A total of 10 tons of simulated waste containing 15 g of plutonium and 6 tons of simulated waste containing 624 MBq of 60 Co and 393 MBq of cesium isotopes was successfully treated. The average volume reduction factor was 18. Global decontamination factors of 280 000 for 137 Cs and 22 000 000 for 239 Pu were measured. Routine working and interventions for maintenance and repair could be carried out safely in alpha-conditions. The report describes in detail the technical adaptations and the behaviour of the various parts of the installation during the 39 runs carried out in the contract period. It also gives the chemical and radiochemical composition of the granules and secondary waste streams. The plutonium-based leach rate of the granules is in the range of 2 x 10 -5 to 3.5 x 10 -4 g/cm 2 . d. Finally typical mass, energy and radioactivity balances of the installation are given and various options for the final conditioning of the granules are briefly discussed. 6 refs, 6 figs, 29 tables

  10. 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

  11. Corrosion in the off-gas system of a radioactive-waste incinerator

    International Nuclear Information System (INIS)

    Jenkins, C.F.; Peters, J.J.

    1987-01-01

    Corrosion in a low-level radioactive-waste incinerator off-gas system at the Department of Energy's Savannah River Plant is discussed. Severe corrosive attack and failure of an alloy 600 part exposed to high-temperature (>1000 0 C) gases was observed. Rapid attack of carbon steel components, and cracking of austenitic stainless steel parts also occurred at locations where lower gas temperatures and periodic condensate exposure occurred. Investigation showed HCl, SO 2 , SO 3 and phosphorus-oxides were present and contributed to the failures. Mechanisms of high-temperature failure include alloy separation and reactions with phosphorus. Coupons placed in the exhaust stream have provided information for selection of future materials of construction for system components. Several nickel- and iron-base alloys, and a stainless steel with an aluminum-diffusion coating were investigated

  12. 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

  13. Retention and subsequent release of radioactivity from the incineration of wastes containing microspheres

    International Nuclear Information System (INIS)

    Emery, R.J.; Watson, J.E. Jr.

    1990-01-01

    Incineration is the preferred method for disposing of animal carcasses containing radioactive microspheres at the authors University. Routine surveys of ash from successive nonradioactive burns revealed significant contamination from previously incinerated microspheres. Past studies on microsphere incineration quantified the amount of activity retained in ash, but did not address any subsequent releases. This topic was not considered in earlier studies because, in most cases, the carcasses were placed in some type of container to facilitate recovery of ash, preventing contamination of the incinerator refractory. In this study, five sets of controlled burns were performed to quantify the subsequent releases of the microsphere radioisotopes 141 Ce, 113 Sn, 102 Ru, 95 Nb, and 46 Sc. Each set consisted of three successive burns. The first burn of each set incinerated a non-radioactive carcass, the second burn, a radioactive carcass, and the third, a non-radioactive carcass. In all of the burns, the carcasses were placed directly on the incinerator refractory floor, which is the standard procedure during normal operations

  14. Conditioning of alpha and beta-gamma ashes of incinerator, obtained by radioactive wastes incinerating and encapsulation in several matrices

    International Nuclear Information System (INIS)

    Kertesz, C.J.; Chenavas, P.R.; Auffret, L.

    1993-01-01

    In this final report, the work carried out, and the results, obtained on the ash incinerator conditioning study, by means of encapsulation in several matrices, are presented. Three encapsulation matrices were checked: - a ternary cement, containing OPC, blast furnace slag and flying ash, - a two component epoxide system, - an epoxide-cement compound matrix. Three ash categories were employed: - real alpha ash, coming from plutonium bearing wastes, - ash, from inactive combustible waste, obtained by treatment in an incinerator prototype, - ash coming from inactive waste incineration plant. Using three different matrices, the encapsulated form properties were determined: at the laboratory scale, the encapsulating formulation was established, and physico mechanical data were obtained, - on active encapsulated forms, containing a calculated amount of 238 Pu, a radiolysis study was performed in order to measure the composition and volume of the radiolytic gas flow, - at the industrial scale, a pilot plant operating the polyvalent encapsulating process, was designed and put into service. Bench-scale experiments were done, on alpha ash embedded forms using the modified sulphur cement matrix as embedding agent. 4 refs., 30 figs., 27 tabs

  15. Cesium distribution and phases in proxy experiments on the incineration of radioactively contaminated waste from the Fukushima area.

    Science.gov (United States)

    Saffarzadeh, Amirhomayoun; Shimaoka, Takayuki; Kakuta, Yoshitada; Kawano, Takashi

    2014-10-01

    After the March 11, 2011 Tohoku earthquake and Fukushima I Nuclear Power Plant accident, incineration was initially adopted as an effective technique for the treatment of post-disaster wastes. Accordingly, considerable amounts of radioactively contaminated residues were immediately generated through incineration. The level of radioactivity associated with radiocesium in the incineration ash residues (bottom ash and fly ash) became significantly high (several thousand to 100,000 Bq/kg) as a result of this treatment. In order to understand the modes of occurrence of radiocesium, bottom ash products were synthesized through combusting of refuse-derived fuel (RDF) with stable Cs salts in a pilot incinerator. Microscopic and microanalytical (SEM-EDX) techniques were applied and the following Cs categories were identified: low and high concentrations in the matrix glass, low-level partitioning into some newly-formed silicate minerals, partitioning into metal-sulfide compounds, and occurring in newly-formed Cs-rich minerals. These categories that are essentially silicate-bound are the most dominant forms in large and medium size bottom ash particles. It is expected that these achievements provide solutions to the immobilization of radiocesium in the incineration ash products contaminated by Fukushima nuclear accident. Copyright © 2014 Elsevier Ltd. All rights reserved.

  16. 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

  17. Cesium distribution and phases in proxy experiments on the incineration of radioactively contaminated waste from the Fukushima area

    International Nuclear Information System (INIS)

    Saffarzadeh, Amirhomayoun; Shimaoka, Takayuki; Kakuta, Yoshitada; Kawano, Takashi

    2014-01-01

    After the March 11, 2011 Tohoku earthquake and Fukushima I Nuclear Power Plant accident, incineration was initially adopted as an effective technique for the treatment of post-disaster wastes. Accordingly, considerable amounts of radioactively contaminated residues were immediately generated through incineration. The level of radioactivity associated with radiocesium in the incineration ash residues (bottom ash and fly ash) became significantly high (several thousand to 100,000 Bq/kg) as a result of this treatment. In order to understand the modes of occurrence of radiocesium, bottom ash products were synthesized through combusting of refuse-derived fuel (RDF) with stable Cs salts in a pilot incinerator. Microscopic and microanalytical (SEM-EDX) techniques were applied and the following Cs categories were identified: low and high concentrations in the matrix glass, low-level partitioning into some newly-formed silicate minerals, partitioning into metal-sulfide compounds, and occurring in newly-formed Cs-rich minerals. These categories that are essentially silicate-bound are the most dominant forms in large and medium size bottom ash particles. It is expected that these achievements provide solutions to the immobilization of radiocesium in the incineration ash products contaminated by Fukushima nuclear accident. - Highlights: • Behavior of cesium in the waste incineration residues was investigated. • Bottom ash products were synthesized through combusting of stable cesium salts and RDF. • Microscopic and microanalytical techniques were applied. • Cesium distribution and phases were identified in bottom ash products. • Cesium is entrapped in silicate glass, minerals and metal-sulfide phases of bottom ash

  18. Incineration in low-level radioactive waste management at the University of Maryland at Baltimore

    International Nuclear Information System (INIS)

    Cooley, L.R.

    1986-01-01

    The selection of an incinerator by the University of Maryland at Baltimore was carried out under a demonstration grant from the Department of Energy (DOE). The system selected is a 300 lb per hour dual-chambered, controlled air incinerator. The cost of the unit was $130,000, excluding installation. The interior is lined with high temperature brick rather than a castable refractory. The burners in the upper and lower chambers are ''oversized'' to insure responsive temperature control of 2.5 million Btu/h in the upper chamber and 1.3 million Btu/h in the lower. The prescribed operating temperatures are 1900 to 2100 0 F in the upper chamber and 900 to 1200 0 F in the lower chamber. The system has a rated capacity of 300 lbs/h of type IV, pathological waste, but operational experience has limited our feed rate to 150 lbs/h

  19. 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)

  20. Radioactive waste management

    International Nuclear Information System (INIS)

    Kizawa, Hideo

    1982-01-01

    A system of combining a calciner for concentrated radioactive liquid waste and an incinerator for miscellaneous radioactive solid waste is being developed. Both the calciner and the incinerator are operated by fluidized bed method. The system features the following points: (1) Inflammable miscellaneous solids and concentrated liquid can be treated in combination to reduce the volume. (2) Used ion-exchange resin can be incinerated. (3) The system is applicable even if any final waste disposal method is adopted; calcinated and incinerated solids obtained as intermediate products are easy to handle and store. (4) The system is readily compatible with other waste treatment systems to form optimal total system. The following matters are described: the principle of fluidized-bed furnaces, the objects of treatment, system constitution, the features of the calciner and incinerator, and the current status of development. (J.P.N.)

  1. 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...

  2. Radioactive wastes

    International Nuclear Information System (INIS)

    Boegly, W.J.; Alexander, H.J.

    1983-01-01

    A literature review on studies concerning radioactive wastes is presented. Literature on radioactive wastes available from the National Technical Information Service, Washington, DC, was not included in the review. Studies were reviewed that dealt with general programs for radioactive wastes; isolation of radioactive wastes; waste management; waste storage; environmental transport; transportation; risk assessment; and remedial action are reviewed

  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. 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

  5. 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.

  6. 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

  7. 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)

  8. Results of the IAEA CRP on studies of advanced reactor technology options for effective incineration of radioactive waste

    International Nuclear Information System (INIS)

    Maschek, W.; Stanculescu, A.; ); Gopalakrishnan, V.

    2007-01-01

    The IAEA has initiated a Coordinated Research Project (CRP) on 'Studies of Advanced Reactor Technology Options for Effective Incineration of Radioactive Waste'. The overall objective of the CRP, performed within the framework of IAEA's Nuclear Power Technology Development Section's Technical Working Group on Fast Reactors (TWG-FR), is to increase the capability of Member States in developing and applying advanced technologies in the area of long-lived radioactive waste utilization and transmutation. More specifically, the final goal of the CRP is to deepen the understanding of the dynamics of transmutation systems, especially systems with high minor actinide content. Currently, 20 institutions from 15 member states and one international organization are participating in this CRP. The current author list comprises the participants of the last CRP Vienna meeting. The CRP concentrates on the assessment of the transient behaviour of various transmutation systems. For a sound assessment of the transient and accident behaviour, neutron kinetics and dynamics methods and codes have to be qualified, especially as the margins for the safety relevant neutronics parameters are generally becoming small in a transmutation system. Hence, the availability of adequate and qualified methods for the analysis of the various systems is an important point of the exercise. A benchmarking effort between the codes and nuclear data used for the analyses has been performed, which will help specifying the range of validity of methods, and also formulate requirements for future theoretical and experimental research. Should transient experiments become available during the course of the CRP, experimental benchmarking work will also be pursued

  9. Incineration of low level and mixed wastes: 1986

    International Nuclear Information System (INIS)

    Anon.

    1986-01-01

    The University of California at Irvine, in cooperation with the Department of Energy, American Society of Mechanical Engineers, and chapters of the Health Physics Society, coordinated this conference on the Incineration of Low-Level Radioactive and Mixed Wastes, with the guidance of professionals active in the waste management community. The conference was held in April 22-25, 1986 at Sheraton airport hotel Charlotte, North Carolina. Some of the papers' titles were: Protection and safety of different off-gas treatment systems in radioactive waste incineration; performance assessment of refractory samples in the Los Alamos controlled-Air incinerator; incineration systems for low-level and mixed wastes; incineration of low-level radioactive waste in Switzerland-operational experience and future activities

  10. Controlled air incinerator for radioactive waste. Volume II. Engineering design references manual

    International Nuclear Information System (INIS)

    Koenig, R.A.; Draper, W.E.; Newmyer, J.M.; Warner, C.L.

    1982-11-01

    This two-volume report is a detailed design and operating documentation of the Los Alamos National Laboratory Controlled Air Incinerator (CAI) and is an aid to technology transfer to other Department of Energy contractor sites and the commercial sector. Volume I describes the CAI process, equipment, and performance, and it recommends modifications based on Los Alamos experience. It provides the necessary information for conceptual design and feasibility studies. Volume II provides descriptive engineering information such as drawings, specifications, calculations, and costs. It aids duplication of the process at other facilities

  11. Los Alamos Controlled Air Incinerator for radioactive waste. Volume II. Engineering design reference manual

    International Nuclear Information System (INIS)

    Koenig, R.A.; Draper, W.E.; Newmyer, J.M.; Warner, C.L.

    1982-10-01

    This two-volume report is a detailed design and operating documentation of the Los Alamos National Laboratory Controlled Air Incinerator (CAI) and is an aid to technology transfer to other Department of Energy contractor sites and the commercial sector. Volume I describes the CAI process, equipment, and performance, and it recommends modifications based on Los Alamos experience. It provides the necessary information for conceptual design and feasibility studies. Volume II provides descriptive engineering information such as drawings, specifications, calculations, and costs. It aids duplication of the process at other facilities

  12. Los Alamos Controlled Air Incinerator for radioactive waste. Volume I. Rationale, process, equipment, performance, and recommendations

    International Nuclear Information System (INIS)

    Neuls, A.S.; Draper, W.E.; Koenig, R.A.; Newmyer, J.M.; Warner, C.L.

    1982-08-01

    This two-volume report is a detailed design and operating documentation of the Los Alamos National Laboratory Controlled Air Incinerator (CAI) and is an aid to technology transfer to other Department of Energy contractor sites and the commercial sector. Volume I describes the CAI process, equipment, and performance, and it recommends modifications based on Los Alamos experience. It provides the necessary information for conceptual design and feasibility studies. Volume II provides descriptive engineering information such as drawing, specifications, calculations, and costs. It aids duplication of the process at other facilities

  13. Controlled air incinerator for radioactive waste. Volume I. Rationale, process, equipment, performance, and recommendations

    International Nuclear Information System (INIS)

    Neuls, A.S.; Draper, W.E.; Koenig, R.A.; Newmyer, J.M.; Warner, C.L.

    1982-11-01

    This two-volume report is a detailed design and operating documentation of the Los Alamos National Laboratory Controlled Air Incinerator (CAI) and is an aid to technology transfer to other Department of Energy contractor sites and the commercial sector. Volume I describes the CAI process, equipment, and performance, and it recommends modifications based on Los Alamos experience. It provides the necessary information for conceptual design and feasibility studies. Volume II provides descriptive engineering information such as drawings specifications, calculations, and costs. It aids duplication of the process at other facilities

  14. Incineration systems for low level and mixed wastes

    International Nuclear Information System (INIS)

    Vavruska, J.

    1986-01-01

    A variety of technologies has emerged for incineration of combustible radioactive, hazardous, and mixed wastes. Evaluation and selection of an incineration system for a particular application from such a large field of options are often confusing. This paper presents several current incineration technologies applicable to Low Level Waste (LLW), hazardous waste, and mixed waste combustion treatment. The major technologies reviewed include controlled-air, rotary kiln, fluidized bed, and liquid injection. Coupled with any incineration technique is the need to select a compatible offgas effluent cleaning system. This paper also reviews the various methods of treating offgas emissions for acid vapor, particulates, organics, and radioactivity. Such effluent control systems include the two general types - wet and dry scrubbing with a closer look at quenching, inertial systems, fabric filtration, gas absorption, adsorption, and various other filtration techniques. Selection criteria for overall waste incineration systems are discussed as they relate to waste characterization

  15. 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

  16. Theoretical aspects of solid waste incineration

    International Nuclear Information System (INIS)

    Tarbell, J.M.

    1975-01-01

    Theoretical considerations that may be incorporated into the design basis of a prototype incinerator for solid transuranic wastes are described. It is concluded that primary pyrolysis followed by secondary afterburning is a very unattractive incineration strategy unless waste resource recovery is a process goal. The absence of primary combustion air leads to poor waste dispersion with associated diffusion and conduction limitations rendering the process inefficient. Single step oxidative incineration is most attractive when volume reduction is of primary importance. The volume of this type of incinerator (including afterburner) should be relatively much smaller than the pyrolysis type. Afterburning is limited by soot oxidation when preceded by pyrolysis, but limited by turbulent mixing when preceded by direct solid waste oxidation. In either case, afterburner temperatures above 1300 0 K are not warranted. Results based on a nominal solid waste composition and anticipated throughput indicate that NO/sub x/, HF, and SO 2 will not exceed the ambient air quality standards. Control of radioactive particulates, which can be achieved by multiple HEPA filtration, will reduce the conventional particulate emission to the vanishing point. Chemical equilibrium calculations also indicate that chlorine and to a lesser extent fluorine may be precipitated out in the ash as sodium salts if a sufficient flux of sodium is introduced into the incinerator

  17. Radioactivity partitioning of oil sludge undergoing incineration process

    International Nuclear Information System (INIS)

    Muhamat Omar; Suhaimi Hamzah; Muhd Noor Muhd Yunus

    1997-01-01

    Oil sludge waste is a controlled item under the Atomic Energy Act (Act 304) 1984 of which the radioactivity content shall be subjected to analysis. Apart from that the treatment method also shall be approved by Atomic Energy Licensing Board (AELB). Thus, an analysis of the oil sludge for MSE fluidized incinerator was conducted to comply with above requirements using various techniques. Further screening analysis of fly ash as well as bed material were done to study the effect of incinerating the sludge. This paper highlights the analysis techniques and discusses the results with respect to the radioactivity level and the fate of radionuclides subjected to the processing of the waste

  18. 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

  19. Organic waste incineration processes

    International Nuclear Information System (INIS)

    Lemort, F.; Charvillat, J.P.; Nabot, J.P.; Chateauvieux, H.; Thiebaut, C.

    2001-01-01

    Nuclear activities produce organic waste compatible with thermal processes designed to obtain a significant weight and volume reduction as well as to stabilize the inorganic residue in a form suitable for various interim storage or disposal routes. Several processes may be implemented (e.g. excess air, plasma, fluidized bed or rotating furnace) depending on the nature of the waste and the desired objectives. The authors focus on the IRIS rotating-kiln process, which was used for the first time with radioactive materials during the first half of 1999. IRIS is capable of processing highly chlorinated and α-contaminated waste at a rate of several kilograms per hour, while limiting corrosion due to chlorine as well as mechanical entrainment of radioactive particles in the off-gas stream. Although operated industrially, the process is under continual development to improve its performance and adapt it to a wider range of industrial applications. The main focus of attention today is on adapting the pyrolytic processes to waste with highly variable compositions and to enhance the efficiency of the off-gas purification systems. These subjects are of considerable interest for a large number of heat treatment processes (including all off-gas treatment systems) for which extremely durable, high-performance and low-flow electrostatic precipitators are now being developed. (author)

  20. 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

  1. 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.

  2. 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.

  3. 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

  4. 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.

  5. 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.

  6. Incineration/vitrification of radioactive wastes and combustion of pyrolysis gases in thermal plasmas; Incineration/vitrification de dechets radioactifs et combustion de gaz de pyrolyse en plasma d`arc

    Energy Technology Data Exchange (ETDEWEB)

    Girold, Ch. [CEA de la Vallee du Rhone, Departement de Retraitement des Dechets et du Demantelemnet, 30 - Marcoule (France)]|[Limoges Univ., 87 (France)

    1997-03-01

    Two thermal plasma processes used for incineration of radioactive technological wastes (cellulose, plastics, rubber...) have been investigated. First, the different types of radioactive wastes are presented, with a special attention to those which may benefit from a high temperature thermal treatment. The most significant thermal plasma processes, suitable for this goal, are described. Then, the author deals with the post-combustion, in an oxygen plasma jet reactor, of gases from burnable radioactive waste pyrolysis. An experimental planning method as been used to evaluate the combustion performances in the reactor, with a wide range of gas composition and running parameters such as oxygen excess and electrical power. The results of a modeling of kinetics, based on 116 chemicals reactions between 25 species, are compared with experimental values. Finally, an oxygen plasma reactor where the arc is transferred on a basalt melt is experimented. The efficiency of the combustion and the homogeneity of the glass are discussed. The volatility of some glass elements and tracers added to the wastes is also approached in two different ways: by post-trial material balance and by an optical emission spectroscopic method. The author built a diagnostic method that allows the following versus time of the metallic vapours above the melt. (author) 51 refs.

  7. Mixed incineration of RAIW and liquid scintillator waste after storage for decay

    International Nuclear Information System (INIS)

    Naba, K.; Nakazato, K.; Kataoka, K.

    1993-01-01

    Most medical radioactive waste is combustible after radioactive decay. Moreover mixed incineration of LLW with biomedical radioactive waste will lessen radiation exposure to the public. This paper describes the total system flowsheet for the processing of liquid scintillator wastes and radioimmunoassay tube wastes containing iodine 125 (after a two-year storage for decay). The process was tested with a 60 kg/hr capacity incinerator from 1987 to 1991; this has been upgraded to a 150 kg/hr incinerator which is used for nonradioactive biomedical waste incineration as well

  8. 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...

  9. 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...

  10. 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

  11. Regulation of radioactive waste management

    International Nuclear Information System (INIS)

    2002-01-01

    This bulletin contains information about activities of the Nuclear Regulatory Authority of the Slovak Republic (UJD). In this leaflet the regulation of radioactive waste management of the UJD are presented. Radioactive waste (RAW) is the gaseous, liquid or solid material that contains or is contaminated with radionuclides at concentrations or activities greater than clearance levels and for which no use is foreseen. The classification of radioactive waste on the basis of type and activity level is: - transition waste; - short lived low and intermediate level waste (LlLW-SL); - long lived low and intermediate level waste (LlLW-LL); - high level waste. Waste management (in accordance with Act 130/98 Coll.) involves collection, sorting, treatment, conditioning, transport and disposal of radioactive waste originated by nuclear facilities and conditioning, transport to repository and disposal of other radioactive waste (originated during medical, research and industrial use of radioactive sources). The final goal of radioactive waste management is RAW isolation using a system of engineered and natural barriers to protect population and environment. Nuclear Regulatory Authority of the Slovak Republic regulates radioactive waste management in accordance with Act 130/98 Coll. Inspectors regularly inspect and evaluate how the requirements for nuclear safety at nuclear facilities are fulfilled. On the basis of safety documentation evaluation, UJD issued permission for operation of four radioactive waste management facilities. Nuclear facility 'Technologies for treatment and conditioning contains bituminization plants and Bohunice conditioning centre with sorting, fragmentation, evaporation, incineration, supercompaction and cementation. Final product is waste package (Fibre reinforced container with solidified waste) acceptable for near surface repository in Mochovce. Republic repository in Mochovce is built for disposal of short lived low and intermediate level waste. Next

  12. Design considerations for incineration of transuranic-contaminated solid wastes

    International Nuclear Information System (INIS)

    Koenig, R.A.

    1977-01-01

    The Los Alamos Scientific Laboratory has established a development program to evaluate alternate production-level (100-200 lb/hr throughput) volume reduction processes for transuranic-contaminated solid waste. The first process selected for installation and study is based on controlled-air incineration. Design considerations leading to selection of feed preparation, incineration, residue removal, and off-gas cleanup components and their respective radioactive containment provisions will be presented

  13. 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

  14. The solidification of radioactive waste

    International Nuclear Information System (INIS)

    Nagaya, Kiichi; Fujimoto, Yoshio; Hashimoto, Yasuo; Nomura, Ichiro

    1985-01-01

    A previous paper covered the decomposition and vitrification of Na 2 SO 4 (the primary component of the liquid waste from BWR) with silica. Now, in order to establish an integrated treatment system for the radioactive waste from BWR, this paper examines the effects of combining incinerator ash and other incinerator wastes with radioactive waste on the durability of the final vitrified products. A bench scale test plat consisting of a waiped file evaporator/dryer, a Joule-heated glass melter and SO 2 absorber was therefore put into operation and run safety for a period of 3000 hours. The combination of the radioactive waste with incinerator ash and the secondary waste of the incinerator was found to make no difference on the durability of the final vitrified products effecting no increase or decrease. Durability similar to that displayed in the beaker tests was proven, with the final vitrified products exhibiting a leaching rate less than 3 x 10 -4 g/cm 2 /day at 95 deg C. (author)

  15. 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.

  16. 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

  17. Viability study for the implantation of an incineration unit for low level radioactive wastes; Estudo de viabilidade para implantacao de uma unidade de incineracao para rejeitos radioativos de nivel baixo

    Energy Technology Data Exchange (ETDEWEB)

    Andrade, Andre Wagner Oliani

    1995-07-01

    Incineration have been a world-wide accepted volume reduction technique for combustible materials due to its high efficiency and excellent results. This technique is used since the last century as an alternative to reduce cities garbage and during the last four decades for the hazardous wastes. The nuclear industry is also involved in this technique development related to the low level radioactive waste management. There are different types of incineration installations and the definition of the right system is based on a criterious survey of its main characteristics, related to the rad wastes as well technical, economical and burocratic parameters. After the autonomous Brazilian nuclear programme development and the onlook of the future intensive nuclear energy uses, a radwaste generation increase is expected. One of the installations where these radwastes volumes are awaited to be high is the Experimental Center of ARAMAR (CEA). Nuclear reactors for propulsion and power generation have been developed in CEA beyond other nuclear combustible cycle activities. In this panorama it is important to evaluate the incineration role in CEA installations, as a volume reduction technique for an appropriate radioactive wastes management implementation. In this work main aspects related to the low level radwaste incineration systems were up rised. This information are important to a coherent viability study and also to give a clear and impartial about a topic that is still non discussed in the national scenery. (author)

  18. 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

  19. Auditing hazardous waste incineration

    International Nuclear Information System (INIS)

    Jayanty, R.K.M.; Allen, J.M.; Sokol, C.K.; von Lehmden, D.J.

    1990-01-01

    This paper reports that audit standards consisting of volatile and semivoltile organics have been established by the EPA to be provided to federal, state, and local agencies or their contractors for use in performance audits to assess the accuracy of measurement methods used during hazardous waste trial burns. The volatile organic audit standards currently total 29 gaseous organics in 5, 6, 7, 9, and 18-component mixtures at part-per-billion (ppb) levels (1 to 10 000 ppb) in compressed gas cylinders in a balance gas of nitrogen. The semivoltile organic audit standards currently total six organics which are spiked onto XAD-2 cartridges for auditing analysis procedures. Studies of all organic standards have been performed to determine the stability of the compounds and the feasibility of using them as performance audit materials. Results as of July 1987 indicate that all of the selected organic compounds are adequately stabile for use as reliable audit materials. Performance audits have been conducted with the audit materials to assess the accuracy of the measurement methods. To date, 160 performance audits have been initiated with the ppb-level audit gases. The audit results obtained with audit gases during hazardous waste trial burn tests were generally within ±50% of the audit concentrations. A limited number of audit results have been obtained with spiked XAD-2 cartridges, and the results have generally been within ±35% of the audit concentrations

  20. Radioactive waste

    International Nuclear Information System (INIS)

    Berkhout, F.

    1991-01-01

    Focusing on radioactive waste management and disposal policies in the United Kingdom, Sweden and the Federal Republic of Germany, this book gives a detailed historical account of the policy process in these three countries, and draws out the implications for theory and public policy. This comparative approach underlines how profoundly different the policy process has been in different countries. By comparing the evolution of policy in three countries, fundamental questions about the formation and resolution of technical decisions under uncertainty are clarified. The analysis of nuclear strategy, the politics of nuclear power, and the shifting emphasis of government regulation redefines the issue of radwaste management and sets it at the heat of the current debate about power, the environment and society. The combination of up-to-date technological assessment with an account of the social and political implications of radwaste management makes'Radioactive Waste'particularly useful to students of environmental studies, geography and public administration. (author)

  1. 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

  2. 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....

  3. Proceedings of the 1st workshop on radioactive waste treatment technologies, October 28, 1997 Taejon, Korea

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1997-12-31

    This proceedings describes the volume reduction of radioactive waste, the radioactive waste treatment technology, the decontamination and decommissioning, and the incineration and solidification of radioactive waste. Twenty two papers are submitted.

  4. Proceedings of the 1st workshop on radioactive waste treatment technologies, October 28, 1997 Taejon, Korea

    International Nuclear Information System (INIS)

    1997-01-01

    This proceedings describes the volume reduction of radioactive waste, the radioactive waste treatment technology, the decontamination and decommissioning, and the incineration and solidification of radioactive waste. Twenty two papers are submitted

  5. 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...

  6. 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)

  7. Volume Reduction of Decommissioning Radioactive Burnable and Metal Wastes

    International Nuclear Information System (INIS)

    Min, B. Y.; Lee, Y. J.; Yun, G. S.; Lee, K. W.; Moon, J. K.; Choi, Y. K.; Cho, J. H.

    2014-01-01

    A large quantity of radioactive waste was generated during the decommissioning projects. For the purpose of the volume reduction and clearance for decommissioning wastes from decommissioning projects, the incineration and high melting technology has been selected for the decommissioning wastes treatment. 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. Incinerator burns waste at high temperature. Incineration of a mixture of chemically hazardous and radioactive materials, known as 'mixed waste,' has two principal goals: to reduce the volume and total chemical toxicity of the waste. Incineration itself does not destroy the metals or reduce the radioactivity of the waste. A proven melting technology is currently used for low-level waste (LLW) at several facilities worldwide. These facilities use melting as a means of processing LLW for unrestricted release of the metal or for recycling within the nuclear sector. About 16.4 tons of decommissioning combustible waste has been treated using Oxygen Enriched incineration. The incineration facility operated quite smoothly through the analysis major critical parameters of off-gas

  8. 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

  9. 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

  10. Behavior of cesium in municipal solid waste incineration.

    Science.gov (United States)

    Oshita, Kazuyuki; Aoki, Hiroshi; Fukutani, Satoshi; Shiota, Kenji; Fujimori, Takashi; Takaoka, Masaki

    2015-05-01

    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. Copyright © 2015 Elsevier Ltd. All rights reserved.

  11. Radioactive waste treatment apparatus

    International Nuclear Information System (INIS)

    Abrams, R.F.; Chellis, J.G.

    1983-01-01

    Radioactive waste treatment apparatus is disclosed in which the waste is burned in a controlled combustion process, the ash residue from the combustion process is removed and buried, the gaseous effluent is treated in a scrubbing solution the pH of which is maintained constant by adding an alkaline compound to the solution while concurrently extracting a portion of the scrubbing solution, called the blowdown stream. The blowdown stream is fed to the incinerator where it is evaporated and the combustibles in the blowdown stream burned and the gaseous residue sent to the scrubbing solution. Gases left after the scrubbing process are treated to remove iodides and are filtered and passed into the atmosphere

  12. Disposal of radioactive wastes

    International Nuclear Information System (INIS)

    Blomeke, J.O.

    1979-01-01

    Radioactive waste management and disposal requirements options available are discussed. The possibility of beneficial utilization of radioactive wastes is covered. Methods of interim storage of transuranium wastes are listed. Methods of shipment of low-level and high-level radioactive wastes are presented. Various methods of radioactive waste disposal are discussed

  13. Radioactive Waste Management Strategy

    International Nuclear Information System (INIS)

    2002-01-01

    This strategy defines methods and means how collect, transport and bury radioactive waste safely. It includes low level radiation waste and high level radiation waste. In the strategy are foreseen main principles and ways of storage radioactive waste

  14. 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

  15. Chapter 7. Radioactive wastes

    International Nuclear Information System (INIS)

    2000-01-01

    The inspection and assessment activities of Nuclear Regulatory Authority of the Slovak Republic (UJD) focused on minimization of activity and the quantity of produced radioactive waste (RAW), and on increasing safety of waste management. The general scheme of rad-waste management in the Slovak Republic is presented. The radioactive wastes produced during the operation of NPP V-1, NPP V-2 and NPP Mochovce in 1999 are listed.Liquid RAW was treated and conditioned into a solid form at the nuclear facility Technology for treatment and conditioning of RAW. In 1999 combustible solid waste was treated at the nuclear facility Incinerator of VUJE Trnava. Produced liquid and solid RAW are stored at designed equipment at individual nuclear installations (in case of NPP V-1, NPP V-2 Bohunice and NPP Mochovce in compliance with the Regulation No. 67/1987 Coll. law).The status of free capacity of these storages as of 31.121999 is presented. Storage solidified product built the SE-VYZ was fully filled at the end of 1999. In 1999 there was a significant improvement in the process of radioactive waste management by: (A) issuing approval for commissioning the National Repository for RAW, (B) issuing approval for commissioning the Treatment and Conditioning Center for RAW, (C) having the application for approval to transport conditioned RAW to the National repository Mochovce in the final stage of evaluation. At the beginning of 2000 it is realistic to expect that RAW conditioned in the Conditioning center of RAW will start to be disposed at the National repository of RAW in Mochovce

  16. 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

  17. 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

  18. Method for burning radioactive wastes

    International Nuclear Information System (INIS)

    Hattori, Akinori; Tejima, Takaya.

    1987-01-01

    Purpose: To completely process less combustible radioactive wastes with no excess loads on discharge gas processing systems and without causing corrosions to furnace walls. Method: Among combustible radioactive wastes, chlorine-containing less combustible wastes such as chlorine-containing rubbers and vinyl chlorides, and highly heat generating wastes not containing chloride such as polyethylene are selectively packed into packages. While on the other hand, packages of less combustible wastes are charged into a water-cooled jacket type incinerator intermittently while controlling the amount and the interval of charging so that the temperature in the furnace will be kept to lower than 850 deg C for burning treatment. Directly after the completion of the burning, the packed highly heat calorie producing wastes are charged and subjected to combustion treatment. (Yoshihara, H.)

  19. Report: environmental assessment of Darmstadt (Germany) municipal waste incineration plant.

    Science.gov (United States)

    Rimaityte, Ingrida; Denafas, Gintaras; Jager, Johannes

    2007-04-01

    The focus of this study was the emissions from waste incineration plants using Darmstadt (Germany) waste incineration plant as an example. In the study the emissions generated by incineration of the waste were considered using three different approaches. Initially the emissions from the waste incineration plant were assessed as part of the impact of waste management systems on the environment by using a Municipal Solid Waste Management System (MSWMS) assessment tool (also called: LCA-IWM assessment tool). This was followed by a comparison between the optimal waste incineration process and the real situation. Finally a comparison was made between the emissions from the incineration plant and the emissions from a vehicle.

  20. 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....

  1. Materials design considerations and selection for a large rad waste incinerator

    International Nuclear Information System (INIS)

    Vormelker, P.R.; Jenkins, C.F.; Burns, H.H.

    1997-01-01

    A new incinerator has been built to process self-generated, low level radioactive wastes at the Department of Energy's Savannah River Site. Wastes include protective clothing and other solid materials used during the handling of radioactive materials, and liquid chemical wastes resulting from chemical and waste management operations. The basic design and materials of construction selected to solve the anticipated corrosion problems from hot acidic gases are reviewed. Problems surfacing during trial runs prior to radioactive operations are discussed

  2. Radioactive waste in perspective

    National Research Council Canada - National Science Library

    2010-01-01

    ... radioactive. While disposal options for hazardous wastes are generally well established, some types of hazardous waste face issues similar to those for radioactive waste and also require long-term disposal arrangements...

  3. 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

  4. 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)

  5. OVERVIEW OF HAZARDOUS/TOXIC WASTE INCINERATION

    Science.gov (United States)

    Effective hazardous/toxic waste disposal and safe dumpsite cleanup are two of EPA's major missions in the 1980s. Incineration has been recognized as a very efficient process to destroy the hazardous wastes generated by industry or by the dumpsite remediations. The paper provides ...

  6. 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

  7. 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

  8. 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)

  9. 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

  10. Quantifying capital goods for waste incineration.

    Science.gov (United States)

    Brogaard, L K; Riber, C; Christensen, T H

    2013-06-01

    Materials and energy used for the construction of modern waste incineration plants were quantified. The data was collected from five incineration plants (72,000-240,000 tonnes per year) built in Scandinavia (Norway, Finland and Denmark) between 2006 and 2012. Concrete for the buildings was the main material used amounting to 19,000-26,000 tonnes per plant. The quantification further included six main materials, electronic systems, cables and all transportation. The energy used for the actual on-site construction of the incinerators was in the range 4000-5000 MW h. In terms of the environmental burden 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 7-14 kg 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. Copyright © 2013 Elsevier Ltd. All rights reserved.

  11. Radioactive waste management

    International Nuclear Information System (INIS)

    Balek, V.

    1994-01-01

    This booklet is a publication by International Atomic Energy Agency for general awareness of citizens and policy-makers to clarify their concept of nuclear wastes. In a very simple way it tells what is radioactivity, radiations and radioactive wastes. It further hints on various medial and industrial uses of radiations. It discusses about different types of radioactive wastes and radioactive waste management. Status of nuclear power plants in Central and Eastern European countries are also discussed

  12. Radioactive waste management at KANUPP

    International Nuclear Information System (INIS)

    Tahir, Tariq B.; Qamar Ali

    2001-01-01

    This paper describes the existing radioactive waste management scheme of KANUPP. The radioactive wastes generated at KANUPP are in solid, liquid and gaseous forms. The spent fuel of the plant is stored underwater in the Spent Fuel Bay. For long term storage of low and intermediate level solid waste, 3m deep concrete lined trenches have been provided. The non-combustible material is directly stored in these trenches while the combustible material is first burnt in an incinerator and the ash is collected, sealed and also stored in the trenches. The low-level liquid and gaseous effluents are diluted and are discharged into the sea and the atmosphere. The paper also describes a modification carried out in the spent resin collection system in which a locally designed removable tank replaced the old permanent tanks. Presently the low level combustible solid waste is incinerated and stored, but it is planned to replace the present method by using compactor and storing the compacted waste in steel drums underground. (author)

  13. Radioactive hospital wastes. Radiations under control

    International Nuclear Information System (INIS)

    Bondeelle, A.; Delmotte, H.; Gauron, C.

    2006-07-01

    A set of articles proposes an overview of legal and regulatory evolutions regarding radioactive hospital wastes. These legal measures and evolutions are notably present in the Public Health code, in the Labour code. An article outlines the role of the radiation protection expert in the process of elimination of contaminated wastes (four major steps for this elimination are indicated; peculiarities of the hospital are outlined, as well as control procedures and the importance of training and information). An article describes the specific activity of the Creteil incinerator which comprises a unit for the incineration of care activity wastes under a very constraining regulation

  14. Radioactive waste management in Belgium

    International Nuclear Information System (INIS)

    Dejonghe, P.

    1977-01-01

    In 1975 the research association BELGOWASTE was founded in order to prepare a technical and administrative plan for radioactive waste management in Belgium and to take the preliminary steps for establishing an organization which would be responsible for this activity. The association made a survey of all forecasts concerning radioactive waste production by power reactors and the fuel cycle industry based on various schemes of development of the nuclear industry. From the technical point of view, the reference plan for waste management envisages: Purification at the production site of large volumes of low-level effluents; construction of a central facility for the treatment and intermediate storage of process concentrates (slurries, resins, etc.) and medium-level waste; centralization assumes the making of adequate arrangements for transporting waste before final treatment; maximum recovery of plutonium from waste and treatment of resiudal material by incineration at very high temperatures; treatment at the production site of high-level effluents from irradiated fuel reprocessing; construction of an underground long-term storage site for high-level treated waste and plutonium fuel fabrication waste; deep clay formations are at present preferred; disposal of low-level treated waste into the Atlantic ocean. It is intended to entrust the entire responsibility for treatment, disposal and storage of treated waste to a single body with participation by the State, the Nuclear Energy Research Centre (CEN/SCK), the electricity companies and Belgonucleaire. The partners intend to set up their facilities and services in the area of Mol [fr

  15. EIA for a waste incinerator in Denmark

    DEFF Research Database (Denmark)

    Larsen, Sanne Vammen

    2017-01-01

    A planned new waste incinerator will be located in an area which is at risk of flooding – a risk that will increase under climate change. During public hear- ings as part of the project’s EIA, inclusion of climate risks was requested. This led to mitigation measures which will decrease the risk...

  16. 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

  17. Incineration, pyrolysis and gasification of electronic waste

    Directory of Open Access Journals (Sweden)

    Gurgul Agnieszka

    2017-01-01

    Full Text Available Three high temperature processes of the electronic waste processing: smelting/incineration, pyrolysis and gasification were shortly discussed. The most distinctive feature of electronic waste is complexity of components and their integration. This type of waste consists of polymeric materials and has high content of valuable metals that could be recovered. The purpose of thermal treatment of electronic waste is elimination of plastic components (especially epoxy resins while leaving non-volatile mineral and metallic phases in more or less original forms. Additionally, the gaseous product of the process after cleaning may be used for energy recovery or as syngas.

  18. Incineration, pyrolysis and gasification of electronic waste

    Science.gov (United States)

    Gurgul, Agnieszka; Szczepaniak, Włodzimierz; Zabłocka-Malicka, Monika

    2017-11-01

    Three high temperature processes of the electronic waste processing: smelting/incineration, pyrolysis and gasification were shortly discussed. The most distinctive feature of electronic waste is complexity of components and their integration. This type of waste consists of polymeric materials and has high content of valuable metals that could be recovered. The purpose of thermal treatment of electronic waste is elimination of plastic components (especially epoxy resins) while leaving non-volatile mineral and metallic phases in more or less original forms. Additionally, the gaseous product of the process after cleaning may be used for energy recovery or as syngas.

  19. Acid gas control process and apparatus for waste fired incinerators

    International Nuclear Information System (INIS)

    Kubin, P.Z.; Stepan, J.E.

    1992-01-01

    This patent describes a process for reducing noxious emission produced in a waste material incinerator. It comprises incinerating solid waste material in a furnace section of the waste material incinerator; providing an additive to an additive supply storage unit; conveying the additive to an additive injection means that communicates with the furnace section of the waste material incinerator; injecting the additive into a turbulent reaction zone of the furnace section such that acid gas content, acid dewpoint temperature and the level of corrosion in the incinerator are reduced

  20. Clinical waste incinerators in Cameroon--a case study

    DEFF Research Database (Denmark)

    Mochungong, Peter Ikome Kuwoh; Gulis, Gabriel; Sodemann, Morten

    2012-01-01

    Incinerators are widely used to treat clinical waste in Cameroon's Northwest Region. These incinerators cause public apprehension owing to purported risks to operators, communities and the environment. This article aims to summarize findings from an April 2008 case study....

  1. 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.

  2. Radioactive Waste Management Basis

    International Nuclear Information System (INIS)

    Perkins, B.K.

    2009-01-01

    The purpose of this Radioactive Waste Management Basis is to describe the systematic approach for planning, executing, and evaluating the management of radioactive waste at LLNL. The implementation of this document will ensure that waste management activities at LLNL are conducted in compliance with the requirements of DOE Order 435.1, Radioactive Waste Management, and the Implementation Guide for DOE Manual 435.1-1, Radioactive Waste Management Manual. Technical justification is provided where methods for meeting the requirements of DOE Order 435.1 deviate from the DOE Manual 435.1-1 and Implementation Guide.

  3. Objectives for radioactive waste packaging

    International Nuclear Information System (INIS)

    Flowers, R.H.

    1982-04-01

    The report falls under the headings: introduction; the nature of radioactive wastes; how to manage radioactive wastes; packaging of radioactive wastes (supervised storage; disposal); waste form evaluation and test requirements (supervised storage; disposal); conclusions. (U.K.)

  4. Understanding radioactive waste

    Energy Technology Data Exchange (ETDEWEB)

    Murray, R.L.

    1981-12-01

    This document contains information on all aspects of radioactive wastes. Facts are presented about radioactive wastes simply, clearly and in an unbiased manner which makes the information readily accessible to the interested public. The contents are as follows: questions and concerns about wastes; atoms and chemistry; radioactivity; kinds of radiation; biological effects of radiation; radiation standards and protection; fission and fission products; the Manhattan Project; defense and development; uses of isotopes and radiation; classification of wastes; spent fuels from nuclear reactors; storage of spent fuel; reprocessing, recycling, and resources; uranium mill tailings; low-level wastes; transportation; methods of handling high-level nuclear wastes; project salt vault; multiple barrier approach; research on waste isolation; legal requiremnts; the national waste management program; societal aspects of radioactive wastes; perspectives; glossary; appendix A (scientific American articles); appendix B (reference material on wastes). (ATT)

  5. Understanding radioactive waste

    International Nuclear Information System (INIS)

    Murray, R.L.

    1981-12-01

    This document contains information on all aspects of radioactive wastes. Facts are presented about radioactive wastes simply, clearly and in an unbiased manner which makes the information readily accessible to the interested public. The contents are as follows: questions and concerns about wastes; atoms and chemistry; radioactivity; kinds of radiation; biological effects of radiation; radiation standards and protection; fission and fission products; the Manhattan Project; defense and development; uses of isotopes and radiation; classification of wastes; spent fuels from nuclear reactors; storage of spent fuel; reprocessing, recycling, and resources; uranium mill tailings; low-level wastes; transportation; methods of handling high-level nuclear wastes; project salt vault; multiple barrier approach; research on waste isolation; legal requiremnts; the national waste management program; societal aspects of radioactive wastes; perspectives; glossary; appendix A (scientific American articles); appendix B (reference material on wastes)

  6. Radioactive wastes. Management

    International Nuclear Information System (INIS)

    Guillaumont, R.

    2001-01-01

    Many documents (journal articles, book chapters, non-conventional documents..) deal with radioactive wastes but very often this topic is covered in a partial way and sometimes the data presented are contradictory. The aim of this article is to precise the definition of radioactive wastes and the proper terms to describe this topic. It describes the main guidelines of the management of radioactive wastes, in particular in France, and presents the problems raised by this activity: 1 - goal and stakes of the management; 2 - definition of a radioactive waste; 3 - radionuclides encountered; 4 - radio-toxicity and radiation risks; 5 - French actors of waste production and management; 6 - French classification and management principles; 7 - wastes origin and characteristics; 8 - status of radioactive wastes in France per categories; 9 - management practices; 10 - packages conditioning and fabrication; 11 - storage of wastes; 12 - the French law from December 30, 1991 and the opportunities of new ways of management; 13 - international situation. (J.S.)

  7. Radioactive Wastes. Revised.

    Science.gov (United States)

    Fox, Charles H.

    This publication is one of a series of information booklets for the general public published by the United States Atomic Energy Commission. This booklet deals with the handling, processing and disposal of radioactive wastes. Among the topics discussed are: The Nature of Radioactive Wastes; Waste Management; and Research and Development. There are…

  8. Radioactive waste management policy

    International Nuclear Information System (INIS)

    Morrison, R.W.

    1983-06-01

    The speaker discusses the development of government policy regarding radioactive waste disposal in Canada, indicates overall policy objectives, and surveys the actual situation with respect to radioactive wastes in Canada. He also looks at the public perceptions of the waste management situation and how they relate to the views of governmental decision makers

  9. Possibilities of municipal solid waste incinerator fly ash utilisation.

    Science.gov (United States)

    Hartmann, Silvie; Koval, Lukáš; Škrobánková, Hana; Matýsek, Dalibor; Winter, Franz; Purgar, Amon

    2015-08-01

    Properties of the waste treatment residual fly ash generated from municipal solid waste incinerator fly ash were investigated in this study. Six different mortar blends with the addition of the municipal solid waste incinerator fly ash were evaluated. The Portland cement replacement levels of the municipal solid waste incinerator fly ash used were 25%, 30% and 50%. Both, raw and washed municipal solid waste incinerator fly ash samples were examined. According to the mineralogical composition measurements, a 22.6% increase in the pozzolanic/hydraulic properties was observed for the washed municipal solid waste incinerator fly ash sample. The maximum replacement level of 25% for the washed municipal solid waste incinerator fly ash in mortar blends was established in order to preserve the compressive strength properties. Moreover, the leaching characteristics of the crushed mortar blend was analysed in order to examine the immobilisation of its hazardous contents. © The Author(s) 2015.

  10. Handling of radioactive waste

    International Nuclear Information System (INIS)

    Sanhueza Mir, Azucena

    1998-01-01

    Based on characteristics and quantities of different types of radioactive waste produced in the country, achievements in infrastructure and the way to solve problems related with radioactive waste handling and management, are presented in this paper. Objectives of maintaining facilities and capacities for controlling, processing and storing radioactive waste in a conditioned form, are attained, within a great range of legal framework, so defined to contribute with safety to people and environment (au)

  11. Radioactive waste management

    International Nuclear Information System (INIS)

    2003-01-01

    Almost all IAEA Member States use radioactive sources in medicine, industry, agriculture and scientific research, and countries remain responsible for the safe handling and storage of all radioactively contaminated waste that result from such activities. In some cases, waste must be specially treated or conditioned before storage and/or disposal. The Department of Technical Co-operation is sponsoring a programme with the support of the Nuclear Energy Department aimed at establishing appropriate technologies and procedures for managing radioactive wastes. (IAEA)

  12. Waste incineration industry and development policies in China.

    Science.gov (United States)

    Li, Yun; Zhao, Xingang; Li, Yanbin; Li, Xiaoyu

    2015-12-01

    The growing pollution from municipal solid waste due to economic growth and urbanization has brought great challenge to China. The main method of waste disposal has gradually changed from landfill to incineration, because of the enormous land occupation by landfills. The paper presents the results of a study of the development status of the upstream and downstream of the waste incineration industry chain in China, reviews the government policies for the waste incineration power industry, and provides a forecast of the development trend of the waste incineration industry. Copyright © 2015 Elsevier Ltd. All rights reserved.

  13. Danish Emission Inventory for Waste Incineration and Other Waste

    DEFF Research Database (Denmark)

    Hjelgaard, Katja

    2013-01-01

    This report contains detailed methodological issues, activity data, emission factors, uncertainties and references for waste incineration without energy recovery and other waste source categories of the Danish emission inventories 2013. The emissions are calculated for the years 1980-2011 according...

  14. Removal of organics from radioactive waste. V. 2

    International Nuclear Information System (INIS)

    Williams, J.; Kitchin, J.; Burton, W.H.

    1989-05-01

    This report reviews the available literature concerning the removal of organic substances from radioactive waste streams. A substantial portion of low level wastes generated in the various parts of the nuclear fuel cycle, nuclear laboratories and other places where radionuclides are used for research, industrial medical and defense related activities is organic (paper, wood, plastics, rubber etc.) and combustible. These combustible wastes can be processed by incineration. Incineration converts combustible wastes into radioactive ashes and residues that are non-flammable, chemically inert and more homogenous than the initial waste. (author)

  15. Radioactive mixed waste disposal

    International Nuclear Information System (INIS)

    Jasen, W.G.; Erpenbeck, E.G.

    1993-02-01

    Various types of waste have been generated during the 50-year history of the Hanford Site. Regulatory changes in the last 20 years have provided the emphasis for better management of these wastes. Interpretations of the Atomic Energy Act of 1954 (AEA), the Resource Conservation and Recovery Act of 1976 (RCRA), and the Hazardous and Solid Waste Amendments (HSWA) have led to the definition of radioactive mixed wastes (RMW). The radioactive and hazardous properties of these wastes have resulted in the initiation of special projects for the management of these wastes. Other solid wastes at the Hanford Site include low-level wastes, transuranic (TRU), and nonradioactive hazardous wastes. This paper describes a system for the treatment, storage, and disposal (TSD) of solid radioactive waste

  16. Shredder and incinerator technology for volume reduction of commercial transuranic wastes

    International Nuclear Information System (INIS)

    Oma, K.H.

    1986-06-01

    Pacific Northwest Laboratory (PNL) is evaluating alternatives and developing technology for treatment of radioactive wastes generated during commercial nuclear activities. Transuranic wastes that require volume reduction include spent HEPA filters, sample and analytical cell waste, and general process trash. A review of current technologies for volume reduction of these wastes led to the selection and testing of several low-speed shredder systems and three candidate incineration processes. The incinerators tested were the electrically heated control-led-air, gas-heated controlled-air, and rotary kiln. Equipment tests were conducted using simulated commercial transuranic wastes to provide a data base for the comparison of the various technologies. The electrically driven, low-speed shredder process was selected as the preferred method for size reduction of the wastes prior to incineration. All three incinerators effectively reduced the waste volume. Based on a technical and economic evaluation on the incineration processes, the recommended system for the commercial waste application is the gas-heated controlled-air incinerator with a single stage of shredding for feed pretreatment

  17. Radioactive waste management

    International Nuclear Information System (INIS)

    1984-07-01

    The purpose of this document is to set out the Government's current strategy for the long term in the management of radioactive wastes. It takes account of the latest developments, and will be subject to review in the light of future developments and studies. The subject is discussed under the headings: what are radioactive wastes; who is responsible; what monitoring takes place; disposal as the objective; low-level wastes; intermediate-level wastes; discharges from Sellafield; heat generating wastes; how will waste management systems and procedures be assessed; how much more waste is there going to be in future; conclusion. (U.K.)

  18. High temperature slagging incinerator for TRU-waste treatment

    International Nuclear Information System (INIS)

    Van De Voorde, N.; Hennart, D.; Gijbels, J.; Mergan, L.

    1984-01-01

    Since 1974 the Belgian Nuclear Study Center (SCK/CEN) at Mol, with the support of the European Communities, has developed an ''integral'' system for the treatment and the conditioning of radioactive contaminated wastes. The system converts directly, at high temperature (1500 0 C), mixtures of combustibles (paper, plastics, rubber etc.) and non-combustibles (metals, soil, sludge, concrete.) contaminated with transuranium elements as well as beta-gamma emitting isotopes, into a chemically inert and physically stable slag. More than 4000 hours of successful operation, with wide variety of simulated waste composition as well as real waste, have confirmed the safe operability of the high temperature sl'Gging incinerator and the connected installations, such as sorting cells, waste shredder, off-gas purification train, slag extraction system, remoted control, and the alpha-containment building. During the fall of 1983, a final confirmation of the performance of the installation was given by the successful accomplishment of an incineration campaign of 16 to 17 tons of simulated solid plutonium contaminated wastes

  19. Management of Radioactive Wastes

    International Nuclear Information System (INIS)

    Tchokosa, P.

    2010-01-01

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

  20. Significance of waste incineration in Germany; Stellenwert der Abfallverbrennung in Deutschland

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2008-10-15

    The report on the relevance of waste incineration in Germany is covering the following issues: change of the issue waste incineration in the last century, the controversy on waste incineration in the 80ies; environmental relevance of waste incineration; utilization of incineration residues; contribution to environmental protection; possible hazards for human health due are waste incinerator plants; the central challenges of waste incineration today; potential restraints to energy utilization in thermal waste processing; optimization of the energetic utilization of municipal wastes; future of the waste management and the relevance of waste incineration.

  1. 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

  2. Radioactive waste management in Belgium

    International Nuclear Information System (INIS)

    Dejonghe, P.

    1977-01-01

    In 1975 the research association BelgoWaste was founded in order to prepare a technical and administrative plan for radioactive waste management in Belgium and to take the preliminary steps for establishing an organization which would be responsible for this activity. The association made a survey of all forecasts concerning radioactive waste production by power reactors and the fuel cycle industry based on various schemes of development of the nuclear industry. From the technical point of view, the reference plan for waste management envisages: purification at the production site of large volumes of low-level effluents; construction of a central facility for the treatment and intermediate storage of process concentrates (slurries, resins, etc.) and medium-level waste, centralization assuming that adequate arrangements are made for transporting waste before final treatment; maximum recovery of plutonium from waste and treatment of residual material by incineration at very high temperatures; treatment at the production site of high-level effluents from irradiated fuel reprocessing; construction of an underground long-term storage site for high-level treated waste and plutonium fuel fabrication waste (deep clay formations are at present preferred); and disposal of low-level treated waste into the Atlantic Ocean. It is intended to entrust the entire responsibility for treatment, disposal and storage of treated waste to a single body with participation by the State, the Nuclear Energy Research Centre (CEN/SCK), the electricity companies and Belgonucleaire. The partners intend to set up their facilities and services in the area of Mol. (author)

  3. Municipal Solid Waste Incineration For Accra Brewery Limited (Ghana)

    OpenAIRE

    Akoore, Alfred Akelibilna

    2016-01-01

    Waste incineration is a common practice of waste management tool in most developed countries, for the purpose of converting mass and volumes of waste into a very useful energy content. The aim of this study was to compare the costs benefits of waste incineration for Accra Brewery boiler plant and to investigate also the availability of waste and it´s compositions in Accra, as well as to determine the feasibility of using this waste as a source of fuel to the waste incineration plant. T...

  4. Radioactive Waste Management

    International Nuclear Information System (INIS)

    Paulikas, V.

    2006-01-01

    After the Law of the Republic of Lithuania was passed on Radioactive Waste Management on May 20, 1999, much more attention is being given to the disposal of this kind of waste in our country and especially at Ignalina NPP, the facility that generates most of it. The key principle of radioactive waste management is to manage it in such a manner that it would pose no danger to the public and the environment, and would not become an additional burden to future generations. This principle is followed in managing radioactive waste in Lithuania too. (author)

  5. Treatment of radioactive waste - Routine or challenge? Proceedings

    International Nuclear Information System (INIS)

    2003-01-01

    The seminar had the following topics: Proposal for new legislation covering radioactive waste management in the EU, new requirements preparations for the later repository, efficient and cost effective treatment of radioactive waste water, intermediate level waste cementation, incineration of spent ion exchange resins in a triphasic mixture, application of THOR-technology on resins, new development for transportation and storage of reactor vessel parts, and conditioning of nuclear fuel containing wastes. (uke)

  6. Radioactive waste disposal policy

    International Nuclear Information System (INIS)

    Neilson, H.R.

    1982-01-01

    The responsibilities of the Minister of Agriculture, Fisheries and Food and Ministry policy on radioactive waste disposal are described. The disposal of solid radioactive waste at sea is subject to detailed safeguards developed within two international agreements to which the United Kingdom is a contracting party. The agreements are discussed together with a research and monitoring programme to provide scientific data for informed decisions on waste disposal authorisations and dumping licences. (U.K.)

  7. Radioactive mixed waste storage

    International Nuclear Information System (INIS)

    Hennig, J.M.; Jasen, W.G.; Hamilton, W.H.

    1992-08-01

    Various types of waste have been generated during the 50-year history of the Hanford Site. Regulatory changes in the last 20 years have provided the emphasis for better management of these wastes. Interpretations of the Atomic Energy Act of 1954 (AEA) (reference 1) and the Resource Conservation and Recovery Act of 1976 (RCRA) (reference 2) have led to the definition of a group of wastes called radioactive mixed wastes (RMW). As a result of the radioactive and hazardous properties of these wastes, special projects have been initiated for the management of RMW. This paper addresses the storage of solid RMW. The management of bulk liquid RMW will not be described

  8. On site clean up with a hazardous waste incinerator

    International Nuclear Information System (INIS)

    Cross, F.L. Jr.; Tessitore, J.L.

    1987-01-01

    The Army Corps of Engineers and the EPA have determined that on-site incineration for the detoxification of soils, sediments, and sludges is a viable, safe, and economic alternative. This paper discusses an approach to on-site incineration as a method of detoxification of soils/sediments contaminated with organic hazardous wastes. Specifically, this paper describes the procedures used to evaluate on-site incineration at a large Superfund site with extensive PCB contaminated soils and sediments. The paper includes the following: (1) a discussion of site waste quantities and properties, (2) a selection of an incineration technology with a resulting concept and design, (3) a discussion of incinerator permitting requirements, (4) discussion and rationale for an incinerator sub-scale testing approach, and (5) analysis of on-site incineration cost

  9. Encapsulation of radioactive waste

    International Nuclear Information System (INIS)

    Pordes, O.; Plows, J.P.

    1980-01-01

    A method is described for encapsulating a particular radioactive waste which consists of suspending the waste in a viscous liquid encapsulating material, of synthetic resin monomers or prepolymers, and setting the encapsulating material by addition or condensation polymerization to form a solid material in which the waste is dispersed. (author)

  10. Classification of radioactive waste

    International Nuclear Information System (INIS)

    1994-01-01

    Radioactive wastes are generated in a number of different kinds of facilities and arise in a wide range of concentrations of radioactive materials and in a variety of physical and chemical forms. To simplify their management, a number of schemes have evolved for classifying radioactive waste according to the physical, chemical and radiological properties of significance to those facilities managing this waste. These schemes have led to a variety of terminologies, differing from country to country and even between facilities in the same country. This situation makes it difficult for those concerned to communicate with one another regarding waste management practices. This document revises and updates earlier IAEA references on radioactive waste classification systems given in IAEA Technical Reports Series and Safety Series. Guidance regarding exemption of materials from regulatory control is consistent with IAEA Safety Series and the RADWASS documents published under IAEA Safety Series. 11 refs, 2 figs, 2 tab

  11. Radioactive wastes of Nuclear Industry

    International Nuclear Information System (INIS)

    1995-01-01

    This conference studies the radioactive waste of nuclear industry. Nine articles and presentations are exposed here; the action of the direction of nuclear installations safety, the improvement of industrial proceedings to reduce the waste volume, the packaging of radioactive waste, the safety of radioactive waste disposal and environmental impact studies, a presentation of waste coming from nuclear power plants, the new waste management policy, the international panorama of radioactive waste management, the international transport of radioactive waste, finally an economic analysis of the treatment and ultimate storage of radioactive waste. (N.C.)

  12. Radioactive waste disposal

    International Nuclear Information System (INIS)

    Burton, W.R.

    1987-01-01

    Radioactive waste of two different activity levels is buried on the same site. The high level waste e.g. intermediate level waste may be in a trench or cells in a trench bottom, and be surmounted by a layer of concrete surmounted by an intrusion barrier comprising drums containing an aggregate of cement and the lower level activity waste, the whole having a substantially impermeable cap. (author)

  13. Storage of radioactive waste

    International Nuclear Information System (INIS)

    Cohen, B.L.

    1981-01-01

    Several factors are cited which would make the underground storage of radioactive wastes a safe technology: the rock or salt formation containing the waste would require a very long time for dissolution by ground water. Moreover, the backfill material, namely clay, would swell when wet to provide a tight seal, as well as to filter out leaked materials. In addition, casing materials are available which would not dissolve for a million years. A further protection is that the waste itself will be a glass-like material resistant to dissolution. Also, ground water carrying radioactive material would take about 1,000 years to travel 2,000 ft to the surface. Once on the surface, any radioactive leakage can readily be detected. It is concluded that radioactive wastes do not represent a serious problem to health

  14. K. Radioactive waste management

    International Nuclear Information System (INIS)

    1976-01-01

    Radioactive waste management is a controversial and emotive subject. This report discusses radioactivity hazards which arise from each stage of the fuel cycle and then relates these hazards to the New Zealand situation. There are three appendices, two of which are detailed considerations of a paper by Dr. B.L.Cohen

  15. Plasma-thermal processing and incineration of wastes in a shaft incinerator with a combustible filtering material

    Science.gov (United States)

    Kalitko, V. A.; Mossé, A. L.

    2000-09-01

    The authors report the basic technological principles and the special features of a method of combined plasma-thermal processing and incineration of harmful wastes in a shaft incinerator under a layer of the charge of such a well-filtering and well-combustible material as wood sawdust, which absorbs up to 99% of the aerosols of waste gases by fixing and concentrating them in the ash. A calculated-analytical estimate of the filtration properties of wood sawdust is obtained as a function of its dispersity, the thickness of the charge layer, and the filtration rate of the waste gases. Determination is made of the optimum design relations and the parameters of charging of a filtering material under different conditions of processing of wastes, including moistening and impregnation of wood sawdust by an aqueous solution of sorbents to absorb harmful metals. The calculated results are compared and demonstrate consistency with the data on the filtration properties of wood sawdust in other technologies, including thermal processing of radioactive wastes in a similar shaft incinerator.

  16. Method for combustion of radioactive waste

    International Nuclear Information System (INIS)

    Murata, Hiroshi.

    1988-01-01

    Purpose: To conduct stable incineration while maintaining the reactor temperature constant even in a case of burning wastes of high water content. Constitution: Radioactive wastes before placed into an incineration furnace are filled in a vessel of a predetermined volume and the weight thereof is measured to judge the extent of the water content depending on the bulk specific gravity. If the wastes are judged to be of high water content, the amount of combustion air blown to the inside of the furnace is decreased by reducing the opening degree of a control valve for a pressurized air sent from a combustion air blower to the nozzle of the incineration furnace. Further, if the water content of the wastes is judged to be high, signals are also sent to a furnace preheater to actuate it and a combustion gas at high temperature is blown into the furnace. This can keep the fluctuation of the temperature in the furnace as low as possible to conduct stable incineration. (Takahashi, M.)

  17. 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

  18. Numerical modeling of batch formation in waste incineration plants

    Directory of Open Access Journals (Sweden)

    Obroučka Karel

    2015-03-01

    Full Text Available The aim of this paper is a mathematical description of algorithm for controlled assembly of incinerated batch of waste. The basis for formation of batch is selected parameters of incinerated waste as its calorific value or content of pollutants or the combination of both. The numerical model will allow, based on selected criteria, to compile batch of wastes which continuously follows the previous batch, which is a prerequisite for optimized operation of incinerator. The model was prepared as for waste storage in containers, as well as for waste storage in continuously refilled boxes. The mathematical model was developed into the computer program and its functionality was verified either by practical measurements or by numerical simulations. The proposed model can be used in incinerators for hazardous and municipal waste.

  19. Defense waste cyclone incinerator demonstration program: October--March 1979

    International Nuclear Information System (INIS)

    Klinger, L.M.

    1979-01-01

    The cyclone incinerator developed at Mound has proven to be an effective tool for waste volume reduction. During the first half of FY-1979, efforts have been made to increase the versatility of the system. Incinerator development was continued in three areas. Design changes were drafted for the present developmental incinerator to rectify several minor operational deficiencies of the system. Improvements will be limited to redesign unless installation is required to prove design or to permit implementation of other portions of the plan. The applications development portion of the feasibility plan is focused upon expanding the versatility of the incinerator. An improved delivery system was installed for burning various liquids. An improved continuous feed system was installed and will be demonstrated later this year. Late in FY-1979, work will begin on the conceptual design of a production cyclone incinerator which will handle nonrecoverable TRU waste, and which will fully demonstrate the capabilities of the cyclone incinerator system. Data generated in past years and during FY-1979 are being collected to establish cyclone incineration effects on solids, liquids, and gases in the system. Data reflecting equipment life cycles and corrosion have been tabulated. Basic design criteria for a cyclone incinerator system based on developmental work on the incinerator through FY-1979 have been assembled. The portion of the material dealing with batch-type operation of the incinerator will be published later this year

  20. Radioactive waste management

    International Nuclear Information System (INIS)

    Tsoulfanidis, N.

    1991-01-01

    The management of radioactive waste is a very important part of the nuclear industry. The future of the nuclear power industry depends to a large extent on the successful solution of the perceived or real problems associated with the disposal of both low-level waste (LLW) and high-level waste (HLW). All the activities surrounding the management of radioactive waste are reviewed. The federal government and the individual states are working toward the implementation of the Nuclear Waste Policy Act and the Low-Level Waste Policy Act. The two congressional acts are reviewed and progress made as of early 1990 is presented. Spent-fuel storage and transportation are discussed in detail as are the concepts of repositories for HLW. The status of state compacts for LLW is also discussed. Finally, activities related to the decommissioning of nuclear facilities are also described

  1. Radioactive waste disposal in W.A

    International Nuclear Information System (INIS)

    Hartley, B.M.

    1983-01-01

    Radioactive waste in Western Australia arises primarily from medical diagnosis and treatment and from scientific research mainly with a medical orientation. Waste is classified before disposal depending on its level and type of radioactivity and then disposed of either to municipal land fill sites, to the sewerage system or by incineration. The amounts of radioactive materials which may be disposed of to the sewers and air are set by the Radiation Safety Act (1975) Regulations, and the land fill operations are controlled to ensure isolation of the material. Other waste such as unwanted sources used in industrial applications are stored for future disposal. Discussions are being held between officers of the State and Australian Governments aimed at providing suitable disposal methods for sources of this kind

  2. Security of Radioactive Waste

    International Nuclear Information System (INIS)

    Goldammer, W.

    2003-01-01

    Measures to achieve radioactive waste security are discussed. Categorization of waste in order to implement adequate and consistent security measures based on potential consequences is made. The measures include appropriate treatment/storage/disposal of waste to minimize the potential and consequences of malicious acts; management of waste only within an authorised, regulated, legal framework; management of the security of personnel and information; measures to minimize the acquisition of radioactive waste by those with malicious intent. The specific measures are: deter unauthorized access to the waste; detect any such attempt or any loss or theft of waste; delay unauthorized access; provide timely response to counter any attempt to gain unauthorised access; measures to minimize acts of sabotage; efforts to recover any lost or stolen waste; mitigation and emergency plans in case of release of radioactivity. An approach to develop guidance, starting with the categorisation of sources and identification of dangerous sources, is presented. Dosimetric criteria for internal and external irradiation are set. Different exposure scenarios are considered. Waste categories and security categories based on the IAEA INFCIRC/225/Rev.4 are presented

  3. Management on radioactive wastes

    International Nuclear Information System (INIS)

    Balu, K.; Bhatia, S.C.

    1979-01-01

    The basic philosophy governing the radioactive waste management activities in India is to concentrate and contain as much activity as possible and to discharge to the environment only such of these streams that have radioactive content much below the nationally and internationally accepted standards. The concept of ''Zero Release'' is also kept in view. At Tarapur, the effluents are discharged into coastal waters after the radioactivity of the effluents is brought down by a factor 100. The effluents fΩm Rajasthan reactors are discharged into a lake keeping their radioactivity well within permissible limits and a solar evaporation plant is being set up. The plant, when it becomes operational, will be a step towards the concept of ''Zero Release''. At Kalpakkam, the treated wastes are proposed to be diluted by circulating sea water and discharged away from the shore through a long pipe. At Narora, ion exchange followed by chemical precipitation is to be employed to treat effluents and solar evaporation process for total containment. Solid wastes are stored/dispsed in the concrete trenches, underground with the water proofing of external surfaces and the top of the trench is covered with concrete. Highly active wastes are stored/disposed in tile holes which are vaults made of steel-lined, reinforced concrete pipes. Gas cleaning, dilution and dispersion techniques are adopted to treat gaseous radioactive wastes. (M.G.B.)

  4. 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

  5. Fusion reactor radioactive waste management

    International Nuclear Information System (INIS)

    Kaser, J.D.; Postma, A.K.; Bradley, D.J.

    1976-01-01

    Quantities and compositions of non-tritium radioactive waste are estimated for some current conceptual fusion reactor designs, and disposal of large amounts of radioactive waste appears necessary. Although the initial radioactivity of fusion reactor and fission reactor wastes are comparable, the radionuclides in fusion reactor wastes are less hazardous and have shorter half-lives. Areas requiring further research are discussed

  6. Radioactive waste storage issues

    Energy Technology Data Exchange (ETDEWEB)

    Kunz, Daniel E. [Colorado Christian Univ., Lakewood, CO (United States)

    1994-08-15

    In the United States we generate greater than 500 million tons of toxic waste per year which pose a threat to human health and the environment. Some of the most toxic of these wastes are those that are radioactively contaminated. This thesis explores the need for permanent disposal facilities to isolate radioactive waste materials that are being stored temporarily, and therefore potentially unsafely, at generating facilities. Because of current controversies involving the interstate transfer of toxic waste, more states are restricting the flow of wastes into - their borders with the resultant outcome of requiring the management (storage and disposal) of wastes generated solely within a state`s boundary to remain there. The purpose of this project is to study nuclear waste storage issues and public perceptions of this important matter. Temporary storage at generating facilities is a cause for safety concerns and underscores, the need for the opening of permanent disposal sites. Political controversies and public concern are forcing states to look within their own borders to find solutions to this difficult problem. Permanent disposal or retrievable storage for radioactive waste may become a necessity in the near future in Colorado. Suitable areas that could support - a nuclear storage/disposal site need to be explored to make certain the health, safety and environment of our citizens now, and that of future generations, will be protected.

  7. Radioactive waste storage issues

    International Nuclear Information System (INIS)

    Kunz, D.E.

    1994-01-01

    In the United States we generate greater than 500 million tons of toxic waste per year which pose a threat to human health and the environment. Some of the most toxic of these wastes are those that are radioactively contaminated. This thesis explores the need for permanent disposal facilities to isolate radioactive waste materials that are being stored temporarily, and therefore potentially unsafely, at generating facilities. Because of current controversies involving the interstate transfer of toxic waste, more states are restricting the flow of wastes into - their borders with the resultant outcome of requiring the management (storage and disposal) of wastes generated solely within a state's boundary to remain there. The purpose of this project is to study nuclear waste storage issues and public perceptions of this important matter. Temporary storage at generating facilities is a cause for safety concerns and underscores, the need for the opening of permanent disposal sites. Political controversies and public concern are forcing states to look within their own borders to find solutions to this difficult problem. Permanent disposal or retrievable storage for radioactive waste may become a necessity in the near future in Colorado. Suitable areas that could support - a nuclear storage/disposal site need to be explored to make certain the health, safety and environment of our citizens now, and that of future generations, will be protected

  8. 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

  9. 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

  10. Aqueous radioactive waste bituminization

    International Nuclear Information System (INIS)

    Williamson, A.S.

    1980-08-01

    The bituminzation of decontamination and ion exchange resin stripping wastes with four grades of asphalt was investigated to determine the effects of asphalt type on the properties of the final products. All waste forms deformed readily under light loads indicating they would flow if not restrained. It was observed in all cases that product leaching rates increased as the hardness of the asphalt used to treat the waste increased. If bituminization is adopted for any Ontario Hydro aqueous radioactive wastes they should be treated with soft asphalt to obtain optimum leaching resistance and mechanical stability during interim storage should be provided by a corrosion resistant container

  11. Radioactive wastes in Oklo

    International Nuclear Information System (INIS)

    Balcazar, M.; Flores R, J.H.; Pena, P.; Lopez, A.

    2006-01-01

    The acceptance of the Nuclear Energy as electric power supply implies to give answer to the population on the two main challenges to conquer in the public opinion: the nuclear accidents and the radioactive wastes. Several of the questions that are made on the radioactive wastes, its are the mobility migration of them, the geologic stability of the place where its are deposited and the possible migration toward the aquifer mantels. Since the half lives of the radioactive waste of a Nuclear Reactor are of several hundred of thousands of years, the technical explanations to the previous questions little convince to the public in general. In this work summary the results of the radioactive waste generated in a natural reactor, denominated Oklo effect that took place in Gabon, Africa, it makes several thousands of millions of years, a lot before the man appeared in the Earth. The identification of at least 17 reactors in Oklo it was carried out thanks to the difference in the concentrations of Uranium 235 and 238 prospective, and to the analysis of the non-mobility of the radioactive waste in the site. It was able by this way to determine that the reactors with sizes of hardly some decimeter and powers of around 100 kilowatts were operating in intermittent and spontaneous form for space of 150,000 years, with operation cycles of around 30 minutes. Recent studies have contributed information valuable on the natural confinement of the radioactive waste of the Oklo reactors in matrixes of minerals of aluminum phosphate that caught and immobilized them for thousands of millions of years. This extracted information from the nature contributes guides and it allows 'to verify' the validity of the current proposals on the immobilization of radioactive wastes of a nuclear reactor. This work presents in clear and accessible form to the public in general on the secure 'design', operation, 'decommissioning' and 'storage' of the radioactive waste of the reactors that the nature put

  12. Radioactive waste management; Gerencia de rejeitos radioativos

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2013-11-15

    This eighth chapter presents the radioactive wastes and waste disposal; classification of radioactive wastes; basis requests of the radioactive waste management; conditions for a radioactive waste disposal; registers and inventories; transport of radioactive wastes from a facility to another and the radioactive waste management plan.

  13. LCA Comparison of waste incineration in Denmark and Italy

    DEFF Research Database (Denmark)

    Turconi, Roberto; Butera, Stefania; Boldrin, Alessio

    2011-01-01

    Every year around 50 millions Mg solid waste are incinerated in Europe. Large differences exist in different regions, mainly regarding energy recovery, flue gas treatment and management of solid residues. This paper aims to identify and quantify those differences, providing a Life Cycle Assessment...... of two incinerator systems that are representative of conditions in Northern and Southern Europe. The two case studies are Aarhus (Denmark) and Milan (Italy). The results show that waste incineration appears more environmentally friendly in the Danish case than in the Italian one, due to the higher...... energy recovery and to local conditions, e.g. substitution of electricity and heat in the area. Focusing on the incineration process, Milan incinerator performs better than Aarhus, since its upstream impacts (related to the production of chemicals used in flue gas cleaning) are more than compensated...

  14. 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...

  15. 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

  16. 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

  17. 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.

  18. Radioactive waste management

    International Nuclear Information System (INIS)

    Alfredson, P.G.; Levins, D.M.

    1975-08-01

    Present and future methods of managing radioactive wastes in the nuclear industry are reviewed. In the stages from uranium mining to fuel fabrication, the main purpose of waste management is to limit and control dispersal into the environment of uranium and its decay products, particularly radium and radon. Nuclear reactors produce large amounts of radioactivity but release rates from commercial power reactors have been low and well within legal limits. The principal waste from reprocessing is a high activity liquid containing essentially all the fission products along with the transuranium elements. Most high activity wastes are currently stored as liquids in tanks but there is agreement that future wastes must be converted into solids. Processes to solidify wastes have been demonstrated in pilot plant facilities in the United States and Europe. After solidification, wastes may be stored for some time in man-made structures at or near the Earth's surface. The best method for ultimate disposal appears to be placing solid wastes in a suitable geological formation on land. (author)

  19. 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

  20. 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

  1. Radioactive waste management

    International Nuclear Information System (INIS)

    Nosovs'kij, A.V.; Aljeksjejeva, Z.M.; Borozenets', G.P.; Vasilenko, T.M.; Vasil'chenko, V.M.; Pavlenko, A.O.

    2007-01-01

    The main issues of the radioactive waste safe management are covered in the monograph. The international knowledge, as well as the national experience in this field are summarized. The technologies and methods used for the safety objective achievement are described. The main attention is paid to the safety norms and rules, to the descriptions of the radwaste management facilities under operation

  2. Radioactive waste processing field

    International Nuclear Information System (INIS)

    Ito, Minoru.

    1993-01-01

    Storing space for radioactive wastes (storage tunnels) are formed underground of the sea bottom along coast. A plurality of boreholes through which sea water flows are pored vertically in a direction intersecting underground streams of brine in the ground between the tunnels and seaside. Sea water introduction pipes are joined to the upper side walls of the boreholes. The sea water introduction pipes have introduction ports protruded under the sea level of the coastal sea area region. Since sea water flows from the introduction ports to the boreholes passing through the sea water introduction pipes, sea water is always filled in the boreholes. Therefore, brine is sufficiently supplied toward the land by sea water from the boreholes, the underground stream of brine is negligibly small. This can prevent radioactive contamination due to flow of the underground water when radioactive wastes are buried in the underground near coast. (I.N.)

  3. Radioactive waste management in Mexico

    International Nuclear Information System (INIS)

    Paredes, L.; Reyes L, J.; Jimenez D, J.

    2000-01-01

    This paper describes the radioactive waste management in Mexico, particularly the activities that the National Institute of Nuclear Research (NINR) is undertaking in this field. Classification and annual generation of radioactive waste, together with practices and facilities relating to the management of radioactive waste are addressed. The respective national legal framework and policy are outlined. (author)

  4. Radioactive waste processing device

    International Nuclear Information System (INIS)

    Ikeda, Takashi; Funabashi, Kiyomi; Chino, Koichi.

    1992-01-01

    In a waste processing device for solidifying, pellets formed by condensing radioactive liquid wastes generated from a nuclear power plant, by using a solidification agent, sodium chloride, sodium hydroxide or sodium nitrate is mixed upon solidification. In particular, since sodium sulfate in a resin regenerating liquid wastes absorbs water in the cement upon cement solidification, and increases the volume by expansion, there is a worry of breaking the cement solidification products. This reaction can be prevented by the addition of sodium chloride and the like. Accordingly, integrity of the solidification products can be maintained for a long period of time. (T.M.)

  5. Radioactive waste management glossary

    International Nuclear Information System (INIS)

    1988-01-01

    The Waste Management Glossary defines over 300 terms in the English language that have special meanings when they are used in the context of radioactive waste management. The Glossary is intended to provide a consistent reference for these terms for specialists in this field. It also will assist non-specialists who read IAEA reports dealing with waste management. This is the second edition of the Glossary. It is intended to update and replace its predecessor, TECDOC-264, that was issued in 1982. (author)

  6. Radioactive waste management profiles

    International Nuclear Information System (INIS)

    1991-10-01

    In 1989, the International Atomic Energy Agency began development of the Waste Management Data Base (WMDB) to, primarily, establish a mechanism for the collection, integration, storage, and retrieval of information relevant to radioactive waste management in Member States. This report is a summary and compilation of the information contained in the data base. The WMDB contains information and data on several aspects of waste management and offer a ready source of information on such activities as R and D efforts, waste disposal plans and programmes, important programme milestones, waste volume projections, and national and regulatory policies. This report is divided into two parts. Part one describes the Waste Management Data Base system and the type of information it contains. The second part contains data provided by Member States between August 1989 and December 1990 in response to a questionnaire sent by the Agency. However, if a Member State did not respond to the questionnaire, data from IAEA sources, such as technical assistance mission reports, were used - where such data exist. The WMDB system became operational in January 1991. The type of information contained in the data base includes radioactive waste management plans, policies and activities in Member States

  7. Waste incineration and waste prevention: not a contradiction in terms; Abfallverbrennung ist kein Gegner der Abfallvermeidung

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2008-07-15

    The paper provides a detailed analysis of the current situation on waste management in Germany and identifies 10 arguments on the issue that waste incineration and waste prevention are not contradiction in terms. The following topics are discussed within this frame: waste prevention in production and consumption; resource-efficient products; offsetting of efficiency gains by growth of volume; consumer behavior, need of waste management; influence of long-term waste management contracts; product responsibility; highest recovery rates despite incineration of residual waste; precise sorting as a prerequisite for recovery. It is concluded that waste incineration with energy generation and utilization of slag is an environmentally sound option.

  8. Perspectives concerning radioactive waste management

    International Nuclear Information System (INIS)

    Noynaert, L.

    2013-01-01

    The article presents a general overview of the principles of radioactive waste management as established by the International Atomic Energy Agency. Subsequently, research and development related to radioactive waste management at the Belgian Nuclear Research Center SCK·CEN is discussed. Different topical areas are treated including radioactive waste characterisation, decontamination and the long-term management of radioactive waste. The decommissioning of the BR3 reactor and the construction and the exploitation of the underground research laboratory HADES are cited as examples of the pioneering role that SCK·CEN has played in radioactive waste management.

  9. Hazardous waste incineration in context with carbon dioxide.

    Science.gov (United States)

    Reinhardt, Tim; Richers, Ulf; Suchomel, Horst

    2008-02-01

    The Kyoto Protocol of 1997 demands an emission reduction of climate-affecting gases in various industrial sectors. In this context CO2 is one of the relevant gases and waste management is one of the relevant sectors. Referring to the situation in Europe, waste incineration is one of the major sources of CO2 in the waste management sector. The Kyoto Protocol, however, only covers CO2-emissions originating from fossil fuels, whereas the incineration of renewable materials, e.g. wood, is considered to be climate-neutral since it does not make any net contribution to the CO2 inventory of the atmosphere. Unlike the situation with municipal waste, there is little if any information on the CO2-emissions caused by the incineration of hazardous waste in specialized plants, and the renewable fraction in these materials. The present paper focuses on this gap of knowledge. Taking the full-scale hazardous waste incineration plant in Biebesheim, Germany, as an example, a carbon balance was set up for the whole-plant taking into account all other material flows. Afterwards the determination of the proportion of renewable materials in the hazardous waste incinerated by means of the radiocarbon method (14C) is reported. On the basis of the results, optimization potentials are discussed.

  10. 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.

  11. Radioactive waste computerized management

    International Nuclear Information System (INIS)

    Communaux, M.; Lantes, B.

    1993-01-01

    Since December 31, 1990, the management of the nuclear wastes for all the power stations has been computerized, using the DRA module of the Power Generation and Transmission Group's data processing master plan. So now EDF has a software package which centralizes all the data, enabling it to declare the characteristics of the nuclear wastes which are to be stored on the sites operated by the National Radioactive Waste Management Agency (ANDRA). Among other uses, this application makes it possible for EDF, by real time data exchange with ANDRA, to constitute an inventory of validated, shippable packs. It also constitutes a data base for all the wastes produced on the various sites. This application was developed to meet the following requirements: give the producers of radioactive waste a means to fully manage all the characteristics and materials that are necessary to condition their waste correctly; guarantee the traceability and safety of data and automatically assure the transmission of this data in real time between the producers and the ANDRA; give the Central Services of EDF an operation and statistical tool permitting an experienced feed-back based on the complete national production (single, centralized data base); and integrate the application within the products of the processing master plan in order to assure its maintenance and evolution

  12. Radioactive waste management

    International Nuclear Information System (INIS)

    Strohl, P.

    1985-01-01

    The OECD Nuclear Energy Agency (NEA) attaches considerable importance to its cooperation with Japan. It was said in the annual conference in 1977 that the presentation of the acceptable policy regarding radioactive waste management is the largest single factor for gaining public confidence when nuclear power is adopted with assurance. The risk connected with radioactive wastes was often presented as the major obstacle to the development of nuclear energy, however, an overall impression of optimism and confidence prevailed by the technical appraisal of the situation in this field by the committee of the NEA. This evolution can be easily explained by the significant progress achieved in radioactive waste management both at the technical level and with respect to the implementation of special legislation and the establishment of specialized institutions and financing schemes. More research will focus on the optimization of the technical, safety and economic aspects of specific engineering designs at specific sites on the long term isolation of wastes, and the NEA contributes to this general effort. The implementation of disposal programs is also in progress. (Kako, I.)

  13. Categorizing operational radioactive wastes

    International Nuclear Information System (INIS)

    2007-04-01

    The primary objective of this publication is to improve communications among waste management professionals and Member States relative to the properties and status of radioactive waste. This is accomplished by providing a standardized approach to operational waste categorization using accepted industry practices and experience. It is a secondary objective to draw a distinction between operational waste categorization and waste disposal classification. The approach set forth herein is applicable to waste generation by mature (major, advanced) nuclear programmes, small-to-medium sized nuclear programmes, and programmes with waste from other nuclear applications. It can be used for planning, developing or revising categorization methodologies. For existing categorization programmes, the approach set forth in this publication may be used as a validation and evaluation tool for assessing communication effectiveness among affected organizations or nations. This publication is intended for use by waste management professionals responsible for creating, implementing or communicating effective categorization, processing and disposal strategies. For the users of this publication, it is important to remember that waste categorization is a communication tool. As such, the operational waste categories are not suitable for regulatory purposes nor for use in health and safety evaluations. Following Section 1 (Introduction) Section 2 of this publication defines categorization and its relationship to existing waste classification and management standards, regulations and practices. It also describes the benefits of a comprehensive categorization programme and fundamental record considerations. Section 3 provides an overview of the categorization process, including primary categories and sub-categories. Sections 4 and 5 outline the specific methodology for categorizing unconditioned and conditioned wastes. Finally, Section 6 provides a brief summary of critical considerations that

  14. Supercompaction [of radioactive wastes

    International Nuclear Information System (INIS)

    Naughton, M.D.

    1991-01-01

    Public concern over the disposal of radioactive wastes has severely limited the number of disposal sites available and promoted the development of advanced volume reduction technologies. The development of supercompactors is traced with particular reference to the press, hydraulic system and control systems. Experience in the nuclear industry over the past ten years has shown that supercompaction is an effective means of waste volume reduction. Some of the lessons learned and necessary changes in the base process are outlined. The relative merits of central and mobile supercompaction systems are discussed. Supercompactors are not limited to low activity waste although the handling of higher activity waste requires more stringent monitoring and contamination control. Personnel exposure associated with the operation of supercompactors has been low. (UK)

  15. China's status and strategy of radioactive waste management

    International Nuclear Information System (INIS)

    Bi Decai

    2001-01-01

    China has a forty-year history of nuclear industry and nuclear technology application. Safety management of radioactive wastes has been the great concern of related regulatory authorities. After the national policy on regional disposal for low and intermediate level radioactive waste was enacted in 1992, the management of radioactive wastes gradually focused on disposal. Currently, the strategies for radioactive waste management in China are: (a) storing high level radioactive wastes temporarily and launching the study of vitrification and deep geological disposal of high level liquid waste, treating spent fuels from PWR by reprocessing; (b) implementing regional disposal policy for low and intermediate level wastes, implementing cement solidification for low and intermediate level liquid waste before disposal, carrying out bulk casting shallow land disposal technology and hydraulic-fractured cement solidification for deep geological disposal in some special regions under specific conditions, treating low and intermediate level solid radioactive wastes by cement solidification after incineration or by compressing before final disposal; (c) stabilizing the tailing repository by reinforcing embankment, constructing flood dam and overlaying plantation; and (d) developing and formulating laws, regulations, and standards to ensure safe management of radioactive wastes. When establishing standards, other than to follow the generic principles and requirements, emphasis should be placed on the following principles: safety the first, economy, disposal of radioactive wastes as focus, and introduction of international advanced standards as possible. (author)

  16. Radioactive waste management glossary

    International Nuclear Information System (INIS)

    1982-04-01

    Terminology used in documents published by the IAEA is frequently defined in glossaries in the separate documents so that understanding is enhanced, particularly for terms having unique meanings in the field of radioactive waste management. This has been found to be a good practice but frequently a burdensome one, too. In addition, terms in various documents occasionally were used differently. Thus, a common glossary of terms for radioactive waste management documents is believed to have merit. This glossary has been developed for use in IAEA documentation on radioactive waste management topics. The individual items have been compiled by selecting terms and definitions from thirty sources, listed on the next page, and numerous people. An effort has been made to use the definitions in internationally-accepted glossaries (e.g. ICRP, ICRU, ISO), with minimum modification; similarly, definitions in recently published IAEA documents have been respected. Nevertheless, when modifications were believed appropriate, they have been made. The glossary, stored on magnetic tape, is intended to be used as a standard for terminology for IAEA use; it is hoped that some benefits of common international terminology may result from its use in IAEA documentation

  17. Radioactive waste equivalence

    International Nuclear Information System (INIS)

    Orlowski, S.; Schaller, K.H.

    1990-01-01

    The report reviews, for the Member States of the European Community, possible situations in which an equivalence concept for radioactive waste may be used, analyses the various factors involved, and suggests guidelines for the implementation of such a concept. Only safety and technical aspects are covered. Other aspects such as commercial ones are excluded. Situations where the need for an equivalence concept has been identified are processes where impurities are added as a consequence of the treatment and conditioning process, the substitution of wastes from similar waste streams due to the treatment process, and exchange of waste belonging to different waste categories. The analysis of factors involved and possible ways for equivalence evaluation, taking into account in particular the chemical, physical and radiological characteristics of the waste package, and the potential risks of the waste form, shows that no simple all-encompassing equivalence formula may be derived. Consequently, a step-by-step approach is suggested, which avoids complex evaluations in the case of simple exchanges

  18. Argentina's radioactive waste disposal policy

    International Nuclear Information System (INIS)

    Palacios, E.

    1986-01-01

    The Argentina policy for radioactive waste disposal from nuclear facilities is presented. The radioactive wastes are treated and disposed in confinement systems which ensure the isolation of the radionucles for an appropriate period. The safety criteria adopted by Argentina Authorities in case of the release of radioactive materials under normal conditions and in case of accidents are analysed. (M.C.K.) [pt

  19. Treatment technology for organic radioactive waste

    Energy Technology Data Exchange (ETDEWEB)

    Ahn, S. J.; Lee, Y. H.; Shon, J. S. [Korea Atomic Energy Research Institute, Taejon (Korea)

    1999-12-01

    In this report, various alternative technologies to the incineration for the treatment of radioactive organic wastes were described and reviewed, fallen into two groups of low temperature technologies and high temperature technologies. These technologies have the advantages of low volume gaseous emission, few or no dioxin generation, and operation at low enough temperature that radionuclides are not volatilized. Delphi chemical oxidation, mediated electrochemical oxidation, and photolytic ultraviolet oxidation appear to be the most promising low temperature oxidation process and steam reforming and supercritical water oxidation in the high temperature technologies. 52 refs., 39 figs., 2 tabs. (Author)

  20. Sustainable waste management via incineration system: an Islamic ...

    African Journals Online (AJOL)

    This paper would firstly examine solid waste management currently experienced in Malaysia with special concentration given to waste incineration. Its function and benefits entailed from this system shall then be identified. This paper attempts to emphasize this notion within the Islamic perspective, stressing on the needs to ...

  1. EXPERIMENTAL INVESTIGATION OF CRITICAL FUNDAMENTAL ISSUES IN HAZARDOUS WASTE INCINERATION

    Science.gov (United States)

    The report gives results of a laboratory-scale program investigating several fundamental issues involved in hazardous waste incineration. The key experiment for each study was the measurement of waste destruction behavior in a sub-scale turbulent spray flame. (1) Atomization Qual...

  2. 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

  3. Code of practice for the disposal of radioactive waste by the user

    International Nuclear Information System (INIS)

    1985-01-01

    The purpose of the Code is to recommend practices for the Safe disposal of small quantities of radioactive waste so that the exposure of persons to radiation is as low as reasonably achievable and below prescribed limits. The areas covered are: radiological hazard assessments; waste forms; responsibilities of statutory authorities, users and tip and incinerator operators; transport of radioactive waste; mechanisms of disposal, including municipal tips, incineration, sewerage, disposal to the atmosphere and interim storage. Guidelines are given for the packaging and transport of radioactive waste

  4. Volume reduction of low-level radioactive wastes

    International Nuclear Information System (INIS)

    Bryson, H.; Weeter, D.W.; Oakes, T.W.

    1984-01-01

    The Biology Division of Oak Ridge National Laboratory (ORNL), located at the Y-12 site of the Oak Ridge Reservation, produces modest amounts of radioactive mixed (radioactive and hazardous) wastes which present unique disposal problems under current Federal (Dept. of Energy (DOE)), Nuclear Regulatory Commission (NRC) and Environmental Protection Agency (EPA) and State of Tennessee rules and regulations governing the disposal of these types of wastes. These wastes fall into five categories, as generated: (a) liquid (laboratory process) wastes, (b) dry (lab trash) wastes, (c) animal carcases. The liquid waste is considered to contain approx. = 90% of the total radioactivity of the wastes. The most feasible long-term method of dealing with these wastes, consists of four inter-related processes. These are (1) distillation of the liquid wastes to remove a volatile, slightly radioactive organic fraction (to be incinerated); (2) scintillation fluid (''cocktail'') recovery and component separation; (3) incineration (high temperature, high efficiency) of the relatively low activity dry waste, animal bedding, animal carcasses; and the slightly radioactive ( 3 H and 14 C) flammable components from the liquid and scintillation fluid wastes; and (4) cold chemical oxidation and solidification in cement of the aqueous waste fractions from distillation and scintillation fluid separation steps. This alternative provides for the elimination of all hazardous components with the minimum release of radioactivity into the environment. Only a small fraction of the original waste would be landfilled as either immobiled radioactive waste (low activity tritiated water in carbon-14 carbonate and other ''institutional'' radioisotopes or non-hazardous ash

  5. Storage of radioactive wastes

    International Nuclear Information System (INIS)

    1992-07-01

    Even if the best waste minimization measures are undertaken throughout radioisotope production or usage, significant radioactive wastes arise to make management measures essential. For developing countries with low isotope usage and little or no generation of nuclear materials, it may be possible to handle the generated waste by simply practicing decay storage for several half-lives of the radionuclides involved, followed by discharge or disposal without further processing. For those countries with much larger facilities, longer lived isotopes are produced and used. In this situation, storage is used not only for decay storage but also for in-process retention steps and for the key stage of interim storage of conditioned wastes pending final disposal. The report will serve as a technical manual providing reference material and direct step-by-step know-how to staff in radioisotope user establishments and research centres in the developing Member States without nuclear power generation. Considerations are limited to the simpler storage facilities. The restricted quantities and low activity associated with the relevant wastes will generally permit contact-handling and avoid the need for shielding requirements in the storage facilities or equipment used for handling. A small quantity of wastes from some radioisotope production cells and from reactor cooling water treatment may contain sufficient short lived activity from activated corrosion products to require some separate decay storage before contact-handling is suitable. 16 refs, 12 figs, 8 tabs

  6. A COMPARISON: ORGANIC EMISSIONS FROM HAZARDOUS WASTE INCINERATORS VERSUS THE 1990 TOXICS RELEASE INVENTORY AIR RELEASES.

    Science.gov (United States)

    Incineration is often the preferred technology for disposing of hazardous waste, and remediating Superfund sites. The effective implementation of this technology is frequently impeded by strong public opposition `to hazardous waste' incineration HWI). One of the reasons cited for...

  7. Incineration of simulated plutonium-contaminated waste

    International Nuclear Information System (INIS)

    Ford, L.H.; Jenkins, M.J.

    1984-01-01

    Pyrolysis rate data are presented which will enable larger pyrolyser furnaces to be made for processing solid plutonium-contaminated materials at throughputs of up to 20 kg/h using either 1 or 2.5 kg packages as feed. The influence of liquids, such as water, kerosene or oil, on the pyrolysis process has also been assessed. The products of pyrolysis for a range of individual materials and their mixtures have been defined. The oxidation rates for both static and stirred beds of char have been obtained. The implications of both the pyrolysis and char-oxidation processes for plant design are discussed. This work has been commissioned by the Department of the Environment as part of its radioactive waste management programme. The results will be used in the formulation of government policy, but as this stage they do not necessarily represent that policy

  8. Natural radioactivity of wastes

    International Nuclear Information System (INIS)

    Zak, A.; Isajenko, K.; Piotrowska, B.; Kuczbajska, M.; Zabek, A.; Szczygielski, T.

    2010-01-01

    By-products of the combustion of coal (wastes) are often used for various types of construction (dwellings, roads, etc.). The legal regulations (The Ordinance of the Council of Ministers of 2 January 2007 'On the requirements for the content of natural radioactive isotopes of potassium K-40, radium Ra-226 and thorium Th-228 in raws and materials used in buildings for the residence of people and livestock, as well as in the industrial by-products used in the construction, and the control of the content of the aforementioned isotopes' - Law Gazette no. 4/2007 item 29) are in force in Poland. The regulations permit the possibility of utilization of raws and by-products basing upon the level of the natural radioactivity of the examined raws and materials. The article is a survey of the results obtained during the measurements of many types of raws and building materials for almost 30 years by the network of the laboratories in Poland. It is based upon the results stored in the database of the Central Laboratory for Radiological Protection (CLRP), Warsaw. The article tends to outline the radioactivity of the waste materials with respect to other raws and materials used in the construction industry. The article shows the possibilities for the use of by-products originating in the power stations and heat- and power stations (mainly ashes, slag and hinter) in the construction of dwellings and roads. (authors)

  9. Treatment methods for radioactive mixed wastes in commercial low-level wastes: technical considerations

    International Nuclear Information System (INIS)

    MacKenzie, D.R.; Kempf, C.R.

    1986-01-01

    Treatment options for the management of three generic categories of radioactive mixed waste in commercial low-level wastes (LLW) have been identified and evaluated. These wastes were characterized as part of a BNL study in which LLW generators were surveyed for information on potential chemical hazards in their wastes. The general treatment options available for mixed wastes are destruction, immobilization, and reclamation. Solidification, absorption, incineration, acid digestion, wet-air oxidation, distillation, liquid-liquid wastes. Containment, segregation, decontamination, and solidification or containment of residues, have been considered for lead metal wastes which have themselves been contaminated and are not used for purposes of waste disposal shielding, packaging, or containment. For chromium-containing wastes, solidification, incineration, wet-air oxidation, acid digestion, and containment have been considered. For each of these wastes, the management option evaluation has included an assessment of testing appropriate to determine the effect of the option on both the radiological and potential chemical hazards present

  10. Treatment methods for radioactive mixed wastes in commercial low-level wastes: technical considerations

    Energy Technology Data Exchange (ETDEWEB)

    MacKenzie, D.R.; Kempf, C.R.

    1986-01-01

    Treatment options for the management of three generic categories of radioactive mixed waste in commercial low-level wastes (LLW) have been identified and evaluated. These wastes were characterized as part of a BNL study in which LLW generators were surveyed for information on potential chemical hazards in their wastes. The general treatment options available for mixed wastes are destruction, immobilization, and reclamation. Solidification, absorption, incineration, acid digestion, wet-air oxidation, distillation, liquid-liquid wastes. Containment, segregation, decontamination, and solidification or containment of residues, have been considered for lead metal wastes which have themselves been contaminated and are not used for purposes of waste disposal shielding, packaging, or containment. For chromium-containing wastes, solidification, incineration, wet-air oxidation, acid digestion, and containment have been considered. For each of these wastes, the management option evaluation has included an assessment of testing appropriate to determine the effect of the option on both the radiological and potential chemical hazards present.

  11. Radioactive liquid waste filtering device

    International Nuclear Information System (INIS)

    Inami, Ichiro; Tabata, Masayuki; Kubo, Koji.

    1988-01-01

    Purpose: To prevent clogging in filter materials and improve the filtration performance for radioactive liquid wastes without increasing the amount of radioactive wastes. Constitution: In a radioactive waste filtering device, a liquid waste recycling pipe and a liquid recycling pump are disposed for recycling the radioactive liquid wastes in a liquid wastes vessel. In this case, the recycling pipe and the recycling pump are properly selected so as to satisfy the conditions capable of making the radioactive liquid wastes flowing through the pipe to have the Reynolds number of 10 4 - 10 5 . By repeating the transportation of radioactive liquid wastes in the liquid waste vessel through the liquid waste recycling pipe by the liquid waste recycling pump and then returning them to the liquid waste vessel again, particles of fine grain size in the suspended liquids are coagulated with each other upon collision to increase the grain size of the suspended particles. In this way, clogging of the filter materials caused by the particles of fine grain size can be prevented, thereby enabling to prevent the increase in the rising rate of the filtration differential pressure, reduce the frequency for the occurrence of radioactive wastes such as filter sludges and improve the processing performance. (Kamimura, M.)

  12. The transport of radioactive waste

    International Nuclear Information System (INIS)

    Appleton, P.R.; Poulter, D.R.

    1989-01-01

    Regulations have been developed to ensure the safe transport of all radioactive materials by all modes (road, rail, sea and air). There are no features of radioactive waste which set it aside from other radioactive materials for transport, and the same regulations control all radioactive material transport. These regulations and their underlying basis are described in this paper, and their application to waste transport is outlined. (author)

  13. Leaching tests of cemented organic radioactive waste

    International Nuclear Information System (INIS)

    Calabria, Jaqueline A. Almeida; Haucz, Maria Judite A.; Tello, Cledola Cassia O.

    2011-01-01

    The use of radioisotopes in research, medical and industrial activities generates organic liquid radioactive wastes. At Centro de Desenvolvimento da Tecnologia Nuclear (CDTN) are produced organic liquid wastes from different sources, one of these are the solvent extraction activities, whose the waste volume is the largest one. Therefore a research was carried out to treat them. Several techniques to treat organic liquid radioactive wastes have been evaluated, among them incineration, oxidation processes, alkaline hydrolysis, distillation, absorption and cementation. Laboratory experiments were accomplished to establish the most adequate process in order to obtain qualified products for storage and disposal. Absorption followed by cementation was the procedure used in this study, i.e. absorbent substances were added to the organic liquid wastes before mixing with the cement. Initially were defined the absorbers, and evaluated the formulation in relation to the compressive strength of its products. Bentonite from different suppliers (B and G) and vermiculite in two granulometries (M - medium and F - small) were tested. In order to assess the product quality the specimens were submitted to the leaching test according the Standard ISO 6961 and its results were evaluated. Then they were compared with the values established by Standard CNEN NN 6.09 A cceptance criteria for waste products to be disposed , to verify if they meet the requirements for safely storage and disposal. Through this study the best formulations to treat the organic wastes were established. (author)

  14. National inventory of radioactive wastes

    International Nuclear Information System (INIS)

    1997-01-01

    There are in France 1064 sites corresponding to radioactive waste holders that appear in this radioactive waste inventory. We find the eighteen sites of E.D.F. nuclear power plants, The Cogema mine sites, the Cogema reprocessing plants, The Cea storages, the different factories and enterprises of nuclear industry, the sites of non nuclear industry, the Andra centers, decommissioned installations, disposals with low level radioactive wastes, sealed sources distributors, national defence. (N.C.)

  15. Management of radioactive wastes

    International Nuclear Information System (INIS)

    2005-01-01

    The law from December 30, 1991, precisely defines 3 axes of researches for the management of high level and long-lived radioactive wastes: separation/transmutation, surface storage and underground disposal. A global evaluation report about these researches is to be supplied in 2006 by the French government to the Parliament. A first synthesis of the knowledge gained after 14 years of research has led the national commission of the public debate (CNDP) to organize a national debate about the general options of management of high-level and long-lived radioactive wastes before the 2006 date line. The debate comprises 4 public hearings (September 2005: Bar-le-Duc, Saint-Dizier, Pont-du-Gard, Cherbourg), 12 round-tables (October and November 2005: Paris, Joinville, Caen, Nancy, Marseille), a synthesis meeting (December 2005, Dunkerque) and a closing meeting (January 2006, Lyon). This document is the synthesis of the round table debates which took place at Joinville, i.e. in the same area as the Bure underground laboratory of Meuse/Haute-Marne. Therefore, the discussion focuses more on the local impacts of the setting up of a waste disposal facility (environmental aspects, employment, economic development). (J.S.)

  16. Stigma and radioactive waste

    International Nuclear Information System (INIS)

    Mitchell, R.C.

    1988-01-01

    Stigma is a special impact of radioactive waste disposal resulting from the perceptions of risk people have of nuclear waste. In this case, stigma is the devaluing or discrediting of a person, group, or geographical area because of proximity to a nuclear waste disposal site, resulting in negative consequences for the individual and collective (e.g., local economy, community relations, perceived quality of life). As part of a social and economic impact assessment of the proposed HLWR at Hanford Site, WA for Washington State, focus groups were conducted in the Tri-Cities near Hanford to identify stigma effects. Results from the groups showed strong evidence of individual impacts of stigmatization: local residents described prejudice towards them because they live near Hanford which appeared to affect their self-respect, the use of the phrase glowing in the dark by outsiders to symbolize the stigma, and showed concern about the possibility that local products might suffer from reduced demand because of products becoming associated with radioactivity in the public's mind. These results indicate that stigma effects are real and should be studied in research and assessments

  17. Radioactive waste management policy

    International Nuclear Information System (INIS)

    Werthamer, N.R.

    1977-01-01

    The State of New York, some 15 years ago, became a party to an attempt to commercialize the reprocessing and storage of spent nuclear fuels at the West Valley Reprocessing Facility operated by Nuclear Fuel Services, Inc. (NFS). That attempted commercialization, and the State of New York, have fallen victim to changing Federal policies in the United States, leaving an outstanding and unique radioactive waste management problem unresolved. At the beginning of construction in 1963, the AEC assured both NFS and New York State of the acceptability of long-term liquid tank storage for high level wastes, and New York State ERDA therefore agreed to become the responsible long-lived stable institution whose oversight was needed. It was understood that perpetual care and maintenance of the wastes, as liquid, in on-site underground tanks, would provide for safe and secure storage in perpetuity. All that was thought to be required was the replacement of the tanks near the end of their 40-year design life, and the transferring of the contents; for this purpose, a perpetual care trust fund was established. In March of 1972, NFS shut West Valley down for physical expansion, requiring a new construction permit from the AEC. After four years of administrative proceedings, NFS concluded that changes in Federal regulations since the original operating license had been issued would require about 600 million dollars if operations were to resume. In the fall of 1976, NFS informed the NRC, of its intention of closing the reprocessing business. The inventories of wastes left are listed. The premises upon which the original agreements were based are no longer valid. Federal responsibilities for radioactive wastes require Federal ownership of the West Valley site. The views of New York State ERDA are discussed in detail

  18. ALKALINE TREATMENT AND IMMOBILIZATION OF SECONDARY WASTE FROM WASTE INCINERATION

    Directory of Open Access Journals (Sweden)

    Dariusz Mierzwiński

    2017-04-01

    Full Text Available This paper regards the possibility of using geopolymer matrix to immobilize heavy metals present in ash and slag from combustion of waste. In the related research one used the fly ash from coal combustion in one Polish CHP plant and the waste from Polish incineration plants. It was studied if the above-named waste materials are useful in the process of alkali-activation. Therefore, three sets of geopolymer mixtures were prepared containing 60, 50 and 30% of ash and slag from the combustion of waste and fly ash combustion of sewage skudge. The remaining content was fly ash from coal combustion. The alkali-activation was conducted by means of 14M solution of NaOH and sodium water glass. The samples, whose dimensions were in accordance with the PN-EN 206-1 norm, were subjected to 75°C for 24h. According to the results, the geopolymer matrix is able to immobilize heavy metals and retain compressive strength resembling that of concrete.

  19. Incineration of technological waste contaminated with alpha emitters

    International Nuclear Information System (INIS)

    Otter, C.; Moncouyoux, J.P.; Cartier, R.; Durec, J.P.; Afettouche, R.

    1990-01-01

    A large R and D programme is in progress at the CEA on alpha-bearing waste incineration. The program is developed in the laboratory and a pilot plant including the following aspects: physico-chemical characterization of wastes, study of thermal decomposition of wastes, laboratory study of generated gases (first with inactive then with active wastes), development of an industrial pilot plant with inactive wastes, study of corrosion resistance of material (laboratory and pilot plant), study and qualification of nuclear measurements on wastes, ashes and equipment [fr

  20. Experiences with waste incineration for energy production in Denmark

    DEFF Research Database (Denmark)

    Kirkeby, Janus; Grohnheit, Poul Erik; Møller Andersen, Frits

    The Bioenergy Department in SENER have requested assistance with planning for the deployment of bioenergy (Biomass, biogas and waste incineration) in Mexico and information on Danish experiences with developing policy initiatives promoting bioenergy. This introduction to the Danish experiences...... with waste incineration for energy production use is compiled as preparation for SENER’s potential visit to Denmark in 2014. This report was prepared 19 June, 2014 by COWI DTU System Analysis to Danish Energy Agency (DEA) as part of a frame contract agreement....

  1. Radioactive waste management in Korea

    International Nuclear Information System (INIS)

    Lee, Ik Hwan

    1997-01-01

    In order to meet the increasing energy demand in Korea, continuous promotion of nuclear power program will be inevitable in the future. However, the use of nuclear energy eventually requires effective and reliable radioactive waste management. For the safe and economical management of radioactive waste, first of all, volume reduction is essentially required and hence the development of related technologies continuously be pursued. A site for overall radioactive waste management has to be secured in Korea. KEPCO-NETEC will improve public understanding by reinforcing PA and will maintain transparency of radioactive waste management. (author). 1 fig

  2. Radioactive Waste Repositories Administration - SURAO

    International Nuclear Information System (INIS)

    Kucerka, M.

    1998-01-01

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

  3. Leaching from municipal solid waste incineration residues

    Energy Technology Data Exchange (ETDEWEB)

    Hyks, J.

    2008-02-15

    Leaching of pollutants from Municipal Solid Waste Incineration (MSWI) residues has been investigated combining a range of laboratory leaching experiments with geochemical modeling. Special attention was paid to assessing the applicability of laboratory data for subsequent modeling with respect to presumed full-scale conditions; both sample pretreatment and actual influence of leaching conditions on the results of laboratory experiments were considered. It was shown that sample pretreatment may have large impact on leaching test data. In particular, a significant fraction of Pb was shown mobile during the washing of residues with water. In addition, drying of residues (i.e. slow oxidation) prior to leaching experiments increased the leaching of Cr significantly. Significant differences regarding the leaching behavior of individual elements with respect to (non)equilibrium conditions in column percolation experiments were observed in the study. As a result, three groups of elements were identified based on the predominant leaching control and the influence of (non)equilibrium on the results of the laboratory column experiments: I. Predominantly availability-controlled elements (e.g. Na, K, Cl) II. Solubility-controlled elements (e.g. Ca, S, Si, Al, Ba, and Zn) III. Complexation-controlled elements (e.g. Cu and Ni) With respect to the above groups it was suggested that results of laboratory column experiments can, with consideration, be used to estimate full-scale leaching of elements from Group I and II. However, in order to avoid large underestimations in the assessment of leaching from Group III, it is imperative to describe the time-dependent transport of dissolved organic carbon (DOC) in the tested system or to minimize the physical non-equilibrium during laboratory experiments (e.g. bigger column, slower flow velocity). Forward geochemical modeling was applied to simulate long-term release of elements from a MSWI air-pollution-control residue. Leaching of a

  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. Radioactive waste management in Canada

    International Nuclear Information System (INIS)

    Hawley, N.J.

    1979-09-01

    Reports and other Canadian literature on radioactive waste processing and disposal covering the period 1953-1979 are listed. A selected list of international conferences relating to waste management (1959-1979) is attached. (LL)

  6. Radioactive waste engineering and management

    CERN Document Server

    Nakayama, Shinichi

    2015-01-01

    This book describes essential and effective management for reliably ensuring public safety from radioactive wastes in Japan. This is the first book to cover many aspects of wastes from the nuclear fuel cycle to research and medical use, allowing readers to understand the characterization, treatment and final disposal of generated wastes, performance assessment, institutional systems, and social issues such as intergenerational ethics. Exercises at the end of each chapter help to understand radioactive waste management in context.

  7. Controlled-air incineration of alpha-bearing solid wastes

    International Nuclear Information System (INIS)

    Koenig, R.A.; Draper, W.E.; Neuls, A.S.; Newmyer, J.M.

    1980-01-01

    The Los Alamos Scientific Laboratory is completing a study of controlled-air incineration (CAI) as a technique for volume reduction and stabilization of combustible transuranic-contaminated solid wastes. To demonstrate feasibility, a process has been assembled and operated on synthetic and contaminated combustibles. This paper summarizes the CAI project history, process design, provisions for radioactive operation, experimental results to date, and future plans. Achievements include operation at the design feed rate as well as combustion of separate feed compositions including cellulosics, polyethylene, polyvinyl chloride (PVC) and latex rubber. Refractory life has been satisfactory to date, with studies continuing. The offgas cleanup system has proven to be extremely effective; the final high-efficiency filters showing virtually no pressure drop increase. The ability of the system to process high concentrations of PVC has been demonstrated with no chloride-induced degradation detected. Chloride and sulfate removal from the offgas has been excellent with concentrations reaching 8 and 10 ppM maximum, respectively, in the process condensate

  8. Centralized cement solidification technique for low-level radioactive wastes

    International Nuclear Information System (INIS)

    Matsuda, Masami; Nishi, Takashi; Izumida, Tatsuo; Tsuchiya, Hiroyuki.

    1996-01-01

    A centralized cement solidification system has been developed to enable a single facility to solidify such low-level radioactive wastes as liquid waste, spent ion exchange resin, incineration ash, and miscellaneous solid wastes. Since the system uses newly developed high-performance cement, waste loading is raised and deterioration of waste forms after land burial prevented. This paper describes the centralized cement solidification system and the features of the high-performance cement. Results of full-scale pilot plant tests are also shown from the viewpoint of industrial applicability. (author)

  9. Low-level Radioactive waste Management

    International Nuclear Information System (INIS)

    1991-01-01

    This meeting describes low-level radioactive waste management problems and contains 8 papers: 1 Low-level radioactive waste management: exemption concept and criteria used by international organizations. 2 Low-level radioactive waste management: french and foreign regulations 3 Low-level radioactive waste management in EDF nuclear power plants (FRANCE) 4 Low-level radioactive waste management in COGEMA (FRANCE) 5 Importance of low-level radioactive wastes in dismantling strategy in CEA (FRANCE) 6 Low-level radioactive waste management in hospitals 7 Low-level radioactive waste disposal: radiation protection laws 8 Methods of low-level radioactive materials measurements during reactor dismantling or nuclear facilities demolition (FRANCE)

  10. USDOE activities in low-level radioactive waste treatment

    International Nuclear Information System (INIS)

    Vath, J.E.

    1983-01-01

    This paper describes current research, development and demonstration (R, D and D) programs sponsored by the US Department of Energy in the area of low-level radioactive waste treatment. The US Department of Energy Low-Level Radioactive Waste Management Program is directed toward a coordinated program covering the period from low-level radioactive waste generation through the decommissioning of the disposal site. This paper addresses the treatment portion of the program. The development efforts include: mechanical methods for metal and compactible waste volume reduction; incineration of trash or other combustibles through the use of controlled air, cyclone, or molten glass furnaces; ultrafiltration, reverse osmosis, biological or chemical destruction of nitrates; adsorption treatment of low-concentration aqueous waste streams; combustion of organic liquids; and smelting of metal wastes to reduce their volume and conserve our natural resources. (author)

  11. 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

  12. 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

  13. Radioactive waste management for reactors

    International Nuclear Information System (INIS)

    Rodger, W.A.

    1974-01-01

    Radioactive waste management practices at nuclear power plants are summarized. The types of waste produced and methods for treating various types of wastes are described. The waste management systems, including simplified flow diagrams, for typical boiling water reactors and pressurized water reactors are discussed. (U.S.)

  14. 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.

  15. Accelerator driven systems for energy production and waste incineration: Physics, design and related nuclear data

    International Nuclear Information System (INIS)

    Herman, M.; Stanculescu, A.; Paver, N.

    2003-01-01

    This volume contains the notes of lectures given at the workshops 'Hybrid Nuclear Systems for Energy Production, Utilisation of Actinides and Transmutation of Long-lived Radioactive Waste' and 'Nuclear Data for Science and Technology: Accelerator Driven Waste Incineration', held at the Abdus Salam ICTP in September 2001. The subject of the first workshop was focused on the so-called Accelerator Driven Systems, and covered the most important physics and technological aspects of this innovative field. The second workshop was devoted to an exhaustive survey on the acquisition, evaluation, retrieval and validation of the nuclear data relevant to the design of Accelerator Driven Systems

  16. Speciation of Chromium in Bottom Ash Obtained by the Incineration of the Leather Waste Shavings

    OpenAIRE

    k. louhab; H. Assas

    2006-01-01

    The evolution of bottom ash morphology and chromium metals behavior during incineration of a leather waste shavings at different incineration temperature have been studied. The Cr, Ca, Mg, Cl rates in bottom ashes, flay ashes and emitted gases in different incineration temperature of the tannery wastes are also determined. The morphology of the bottom ashes obtained by incineration at different temperature from the leather waste shavings was examined by MEB. The result sho...

  17. Partitioning and transmutation: Radioactive waste management option

    International Nuclear Information System (INIS)

    Stanculescu, A.

    2005-01-01

    Growing world population with increasing energy needs, especially in the developing countries, Threat of global warming due to CO 2 emissions demands non-fossil electricity production. Nuclear will have to be part of a sustainable mix of energy production options Figures show that 350 GWe worldwide capacity is 'nuclear'. Present worldwide spent fuel (containing high Pu inventory) and HLW would need large repositories. In view of the previous facts this lecture deals Partitioning and transmutation as radioactive waste management option. Partitioning and transmutation (P and T) is a complex technology i.e. advanced reprocessing, and demand transuranics fuel fabrication plants, as well as innovative and/or dedicated transmutation reactors. In addition to U, Pu, and 129 I, 'partitioning' extracts from the liquid high level waste the minor actinides (MA) and the long-lived fission products (LLFP) 99-Tc, 93-Zr, 135-Cs, 107-Pd, and 79-Se). 'Transmutation' requires fully new fuel fabrication plants and reactor technologies to be developed and implemented on industrial scale. Present LWRs are not suited for MA and LLFP transmutation (safety consideration, plant operation, poor incineration capability). Only specially licensed LWRs can cope with MOX fuel; for increased Pu loadings (up to 100%), special reactor designs (e.g., ABB80+) are required; a combination of these reactor types could allow Pu inventory stabilization. Long-term waste radiotoxicity can be effectively reduced only if transuranics are 'incinerated' through fission with very hard neutron spectra. New reactor concepts (dedicated fast reactors, Accelerator Driven Systems (ADS), fusion/fission hybrid reactors) have been proposed as transmuters/incinerators. Significant Pu+MAs incineration rates can be achieved in symbiotic scenarios: LWR-MOX and dedicated fast reactors; fast neutron spectrum ADS mainly for MA incineration; very high thermal flux ADS concepts could also provide a significant transuranics

  18. Public debate - radioactive wastes management

    International Nuclear Information System (INIS)

    2005-01-01

    Between September 2005 and January 2006 a national debate has been organized on the radioactive wastes management. This debate aimed to inform the public and to allow him to give his opinion. This document presents, the reasons of this debate, the operating, the synthesis of the results and technical documents to bring information in the domain of radioactive wastes management. (A.L.B.)

  19. Radioactive wastes. Their industrial management

    International Nuclear Information System (INIS)

    Lavie, J.M.

    1982-01-01

    This paper introduces a series that will review the present situation in the field of long-term management of radioactive wastes. Both the meaning and the purposes of an industrial management of radioactive wastes are specified. This short introduction is complemented by outline of data on the French problem [fr

  20. Neutronic measurements of radioactive waste

    International Nuclear Information System (INIS)

    Perot, B.

    1997-01-01

    This document presents the general matters involved in the radioactive waste management and the different non destructive assays of radioactivity. The neutronic measurements used in the characterization of waste drums containing emitters are described with more details, especially the active neutronic interrogation assays with prompt or delayed neutron detection: physical principle, signal processing and evaluation of the detection limit. (author)

  1. 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.

  2. the development of new generation of solid waste refuse incinerators

    African Journals Online (AJOL)

    MATERIALS AND METHODS. These new generation of solid waste refuse incinerators are designed in the round with various locally manufactured special bricks for maximum stability and with minimal use of angle irons except for the doors since they are susceptible to rusting. The four fire boxes apart from allowing the ...

  3. Possibilities for gas turbine and waste incinerator integration

    NARCIS (Netherlands)

    Korobitsyn, M.A.; Jellema, P.; Hirs, Gerard

    1999-01-01

    The aggressive nature of the flue gases in municipal waste incinerators does not allow the temperature of steam in the boiler to rise above 400°C. An increase in steam temperature can be achieved by external superheating in a heat recovery steam generator positioned behind a gas turbine, so that

  4. Management situation and prospect of radioactive waste

    International Nuclear Information System (INIS)

    Han, Pil Jun

    1985-04-01

    This book tell US that management situation and prospect of radioactive waste matter, which includes importance of energy, independence, limitation of fossil fuel energy, density of nuclear energy, strategy of supply of energy resource in Korea, nuclear energy development and radioactive waste matter, summary of management of radioactive waste, statistics of radioactive waste, disposal principle of radioactive waste, management on radioactive waste after using, disposal of Trench, La Marche in French, and Asse salt mine in Germany.

  5. Developing radioactive waste management policy

    International Nuclear Information System (INIS)

    Gichana, Z.

    2012-04-01

    A policy for radioactive waste management with defined goals and requirements is needed as a basis for the preparation of legislation, review or revision of related legislation and to define roles and responsibilities for ensuring the safe management of radioactive waste. A well defined policy and associated strategies are useful in promoting consistency of emphasis and direction within all of the sectors involved in radioactive waste management. The absence of policy and strategy can lead to confusion or lack of coordination and direction. A policy and/or strategy may sometimes be needed to prevent inaction on a particular waste management issue or to resolve an impasse. (author)

  6. 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)

  7. Radioactive waste management at AECL

    International Nuclear Information System (INIS)

    Gadsby, R.D.; Allan, C.J.

    2003-01-01

    AECL has maintained an active program in radioactive waste management since 1945, when the Canadian nuclear program commenced activities at the Chalk River Laboratories (CRL). Waste management activities have included operation of waste management storage and processing facilities at AECL's CRL and Whiteshell Laboratories (WL); operation of the Low Level Radioactive Waste Management Office on behalf of Natural Resources Canada to resolve historic radioactive waste problems (largely associated with radioactive ore recovery, transport and processing operations) that are the responsibility of the Federal Government; development of the concept and related technology for geological disposal of Canada's nuclear fuel waste; development of the Intrusion-Resistant Underground Structure (IRUS) disposal concept for low-level nuclear waste; development of dry storage technology for the interim storage of used fuel; and development and assessment of waste processing technology for application in CANDU nuclear power plants and at CRL and WL. Today these activities are continuing. In addition, AECL is: preparing to decommission the nuclear facilities at WL; carrying out a number of smaller decommissioning projects at CRL; putting in place projects to upgrade the low-level liquid waste processing capabilities of the CRL Waste Treatment Centre, recover and process highly active liquid wastes currently in storage, and recover, condition and improve the storage of selected fuel wastes currently stored in below-ground standpipes in the CRL waste management areas; and assessing options for additional remediation projects to improve the management of other wastes currently in storage and to address environmental contamination from past practices. (author)

  8. Radioactive waste sealing container

    International Nuclear Information System (INIS)

    Tozawa, S.; Kitamura, T.; Sugimoto, S.

    1984-01-01

    A low- to medium-level radioactive waste sealing container is constructed by depositing a foundation coating consisting essentially of zinc, cadmium or a zinc-aluminum alloy over a steel base, then coating an organic synthetic resin paint containing a metal phosphate over the foundation coating, and thereafter coating an acryl resin, epoxy resin, and/or polyurethane paint. The sealing container can consist of a main container body, a lid placed over the main body, and fixing members for clamping and fixing the lid to the main body. Each fixing member may consist of a material obtained by depositing a coating consisting essentially of cadmium or a zinc-aluminum alloy over a steel base

  9. CEA and its radioactive wastes

    International Nuclear Information System (INIS)

    Marano, S.

    1999-01-01

    CEA annually produces about 3500 tons of radioactive wastes in its 43 basic nuclear installations. CEA ranks third behind EDF and Cogema. Low-level wastes (A wastes) are sent to ANDRA (national agency for the management of nuclear wastes)whereas medium-level wastes (B wastes) are stored by CEA itself. CEA has checked off its storing places and has set up an installation Cedra to process and store ancient and new nuclear wastes. 3 other installations are planned to operate within 6 years: Agate (Cadarache) will treat liquid effluents, Stella (Saclay) will process liquid wastes that are beta or gamma emitters, and Atena (Marcoule) will treat and store radioactive sodium coming from Phenix reactor and IPSN laboratories. The use of plasma torch for vitrifying wastes is detailed, the management of all the nuclear wastes produced by CEA laboratories and installations is presented. (A.C.)

  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. Thermal Stability and Material Balance of Nanomaterials in Waste Incineration

    Science.gov (United States)

    Paur, H.-R.; Baumann, W.; Hauser, M.; Lang, I.; Teuscher, N.; Seifert, H.; Stapf, D.

    2017-06-01

    Nanostructured materials are widely used to improve the properties of consumer products such as tires, cosmetics, light weight equipment etc. Due to their complex composition these products are hardly recycled and thermal treatment is preferred. In this study we investigated the thermal stability and material balance of nanostructured metal oxides in flames and in an industrial waste incinerator. We studied the size distribution of nanostructured metal oxides (CeO2, TiO2, SiO2) in a flame reactor and in a heated reaction tube. In the premixed ethylene/air flame, nano-structured CeO2 partly evaporates forming a new particle mode. This is probably due to chemical reactions in the flame. In addition sintering of agglomerates takes place in the flame. In the electrically heated reaction tube however only sintering of the agglomerated nanomaterials is observed. Ceria has a low background in waste incinerators and is therefore a suitable tracer for investigating the fate of nanostructured materials. Low concentrations of Ceria were introduced by a two-phase nozzle into the post-combustion zone of a waste incinerator. By the incineration of coal dust in a burning chamber the Ceria nanoparticles are mainly found in the size range of the fly ash (1 - 10 µm) because of agglomeration. With gas as a fuel less agglomeration was observed and the Ceria nanoparticles were in the particle size range below 1 µm.

  12. Thermal Stability and Material Balance of Nanomaterials in Waste Incineration

    International Nuclear Information System (INIS)

    Paur, H.-R.; Baumann, W.; Hauser, M.; Lang, I.; Teuscher, N.; Seifert, H.; Stapf, D.

    2017-01-01

    Nanostructured materials are widely used to improve the properties of consumer products such as tires, cosmetics, light weight equipment etc. Due to their complex composition these products are hardly recycled and thermal treatment is preferred. In this study we investigated the thermal stability and material balance of nanostructured metal oxides in flames and in an industrial waste incinerator. We studied the size distribution of nanostructured metal oxides (CeO 2 , TiO 2 , SiO 2 ) in a flame reactor and in a heated reaction tube. In the premixed ethylene/air flame, nano-structured CeO 2 partly evaporates forming a new particle mode. This is probably due to chemical reactions in the flame. In addition sintering of agglomerates takes place in the flame. In the electrically heated reaction tube however only sintering of the agglomerated nanomaterials is observed. Ceria has a low background in waste incinerators and is therefore a suitable tracer for investigating the fate of nanostructured materials. Low concentrations of Ceria were introduced by a two-phase nozzle into the post-combustion zone of a waste incinerator. By the incineration of coal dust in a burning chamber the Ceria nanoparticles are mainly found in the size range of the fly ash (1 – 10 µm) because of agglomeration. With gas as a fuel less agglomeration was observed and the Ceria nanoparticles were in the particle size range below 1 µm. (paper)

  13. Waste wood incineration: long-lasting, environment-friendly and CO2-neutral

    International Nuclear Information System (INIS)

    Bouma, J.W.J.

    1993-01-01

    The economic aspects of energy production from waste wood are evaluated. Heating systems based on the incineration of wood have been considerably improved recently. Several aspects of the incineration of waste wood are reviewed: the implications with regard to the greenhouse effect, the calorific value of wood, the incineration process, and the cost price calculation of energy production by waste wood incineration. In conclusion is stated that energy production by waste wood incineration is a valuable economic alternative for heat production by oil products, especially in view of the current anti-pollution taxes in Belgium. (A.S.)

  14. The domestic wastes incinerators; Les incinerateurs d'ordures menegares: quels risques? quelles politiques?

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2004-10-01

    This document presents the opinion of the Committee of Prevention and Precaution (CPP), on the domestic wastes incinerators, in the framework of the global wastes policy. The seven chapters detail and bring advices on the following topics: the elements which are going in and out of the incinerators, the technical processes, the occupational activities and the risks bound to the incinerators use, the transfer modes towards the different environmental areas, the exposure estimation, the risks of people living near the domestic wastes incinerators compared to the other concerning a cancer development, the legislation concerning the domestic wastes and the social acceptability of the incinerators. (A.L.B.)

  15. Vitrification of bottom ash from a municipal solid waste incinerator.

    Science.gov (United States)

    Xiao, Y; Oorsprong, M; Yang, Y; Voncken, J H L

    2008-01-01

    During incineration of municipal solid waste (MSW), various environmentally harmful elements and heavy metals are liberated either into bottom ash, or carried away with the off-gases and subsequently trapped in fly-ash. If these minor but harmful elements are not properly isolated and immobilized, it can lead to secondary environmental pollution to the air, soil and water. The stricter environmental regulations to be implemented in the near future in The Netherlands require a higher immobilization efficiency of the bottom ash treatment. In the present study, MSW incinerator bottom ash was vitrified at higher temperatures and the slag formed and metal recovered were examined. The behaviour of soluble elements that remain in the slag is evaluated by standard leaching test. The results obtained can provide a valuable route to treat the ashes from incinerators, and to make recycling and more efficient utilization of the bottom ash possible.

  16. 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.

  17. Solidification of Simulated Radioactive Incineration Ash by Alkali-activated Slag Composite Cement

    International Nuclear Information System (INIS)

    Li changcheng; Cui Qi; Zhao Yanhong; Pan Sheqi

    2010-01-01

    Simulated radioactive incineration ash (SRIA) was solidified by alkali-activated slag composite cement (AASCC) modified by metakaolin, zeolite, and polymer emulsion powder. The results show that the performance of solidified waste form containing 40% SRIA meets the requirements of GB 14569.1-93. The lowest leaching rate of Cs + on 42nd days reaches 1.32 x 10 -4 cm/d (GB 7023-86,25 degree C), cumulative leach percentage is only 0.041 cm. Also, the lowest 28 days compressive strength of solidified waste form is 45.6 MPa, and later strength growth is still high. The fast setting characteristic of AASCC overcomes effectively the disadvantageous influence caused by some components in SRIA on hydration of cement. The compressive strength of solidified waste is enhanced remarkably, and the ability of immobilizing radionuclide ions is also improved. This is mainly due to synergistic effect between metakaolin and zeolite. Polymer modification also improves the performance of solidified waste form significantly. The three-dimensional polymer network structure formed by emulsion powder in solidified waste form enhances its toughness and impact resistance, and the durability is improved by reducing interconnected pores and optimizing pore structure. However,it also results in reduction in compressive strength. Thus, it is concluded that the suitable dosage percentage is 5%. (authors)

  18. Final disposal of radioactive waste

    Directory of Open Access Journals (Sweden)

    Freiesleben H.

    2013-06-01

    Full Text Available In this paper the origin and properties of radioactive waste as well as its classification scheme (low-level waste – LLW, intermediate-level waste – ILW, high-level waste – HLW are presented. The various options for conditioning of waste of different levels of radioactivity are reviewed. The composition, radiotoxicity and reprocessing of spent fuel and their effect on storage and options for final disposal are discussed. The current situation of final waste disposal in a selected number of countries is mentioned. Also, the role of the International Atomic Energy Agency with regard to the development and monitoring of international safety standards for both spent nuclear fuel and radioactive waste management is described.

  19. Researching radioactive waste disposal

    International Nuclear Information System (INIS)

    Feates, F.; Keen, N.

    1976-01-01

    At present it is planned to use the vitrification process to convert highly radioactive liquid wastes, arising from nuclear power programme, into glass which will be contained in steel cylinders for storage. The UKAEA in collaboration with other European countries is currently assessing the relative suitability of various natural geological structures as final repositories for the vitrified material. The Institute of Geological Sciences has been commissioned to specify the geological criteria that should be met by a rock structure if it is to be used for the construction of a repository though at this stage disposal sites are not being sought. The current research programme aims to obtain basic geological data about the structure of the rocks well below the surface and is expected to continue for at least three years. The results in all the European countries will then be considered so that the United Kingdom can choose a preferred method for isolating their wastes. It is only at that stage that a firm commitment may be made to select a site for a potential repository, when a far more detailed scientific research study will be instituted. Heat transfer problems and chemical effects which may occur within and around repositories are being investigated and a conceptual design study for an underground repository is being prepared. (U.K.)

  20. Solidification of radioactive liquid wastes

    International Nuclear Information System (INIS)

    Hayashi, Tadamasa; Sano, Katsunori.

    1980-01-01

    Purpose: To decrease the amount of surface active agents required for solidifying sodium sulfate-containing concentrated radioactive liquid wastes with asphalts. Method: Water soluble calcium compounds (calcium nitrate, etc.) are added to alkaline radioactive concentrated liquid wastes essentially consisting of sodium sulfate to adjust the pH value of the liquid wastes to 4.5 - 8.5. The addition amount of the water soluble calcium compounds (based on the weight of the calcium ions) is set to about 2 - 5% of the sulfate ions in the liquid wastes. Then, surface active agents are added by 3 - 10 weight % to the solid contents in the liquid wastes. (Ikeda, J.)

  1. Management of radioactive waste: A review

    OpenAIRE

    Luis Paulo Sant'ana; Taynara Cristina Cordeiro

    2016-01-01

    The issue of disposal of radioactive waste around the world is not solved by now and the principal reason is the lack of an efficient technologic system. The fact that radioactive waste decays of radioactivity with time are the main reasons for setting nuclear or radioactive waste apart from the other common hazardous wastes management. Radioactive waste can be classified according to the state of matter and level of radioactivity and this classification can be differently interpreted from co...

  2. Solid waste treatment volume reduction by compaction or incineration

    International Nuclear Information System (INIS)

    Vigreux, B.; Carpentier, S.

    1986-01-01

    A short presentation is made of various techniques available for volume reduction by compaction of solid waste produced during nuclear plant operation. A long industrial experience has been accumulated in France on such compactors. Incineration is the most performing method of volume reduction for combustible waste. The CEA Group and SGN have developed a very reliable, simple and safe incinerator which operates with excess air and at high temperature. Sorting and feeding of the waste, ash discharge and transportation to the conditioning unit, gas treatment, are included in the system. The adding of a programmable controller makes it fully automated. The system is described with some detail and recent performance measurements are given [fr

  3. Solid waste treatment volume reduction by compaction or incineration

    International Nuclear Information System (INIS)

    Vigreux, B.; Carpentier, S.

    1985-01-01

    A short presentation is made of various techniques available for volume reduction by compaction of solid waste produced during nuclear plant operation. A long industrial experience has been accumulated in France on such compactors. Incineration is the most performing method of volume reduction for combustible waste. The CEA Group and SGN have developed a very reliable, simple and safe incinerator which operates with excess air and at high temperature. Sorting and feeding of the waste, ash discharge and transportation to the conditioning unit, gas treatment, are included in the system. The adding of a programmable controller makes it fully automated. The system is described with some detail and recent performance measurements are given [fr

  4. Design of a Pu-238 waste incineration process

    International Nuclear Information System (INIS)

    Charlesworth, D.L.; McCampbell, R.B.

    1985-01-01

    Combustible 238 Pu waste is generated as a result of normal operation and decommissioning activity at the Savannah River Plant and is being retrievably stored at the Plant. As part of the long-term plan to process the stored waste and current waste in preparation for future disposition, a 238 Pu incinceration process is being cold-tested at SRL. The incineration process consists of a continuous-feed preparation system, a two-stage, electrically fired incinerator, and a filtration off-gas system. Process equipment has been designed, fabricated, and installed for nonradioactive testing and cold run-in. Design features to maximize the ability to remotely maintain the equipment were incorporated into the process. Interlock, alarm, and control functions are provided by a programmable controller. Cold testing is scheduled to be completed in 1986

  5. Radioactive waste disposal

    International Nuclear Information System (INIS)

    Petit, J.C.

    1998-04-01

    A deep gap, reflecting a persisting fear, separates the viewpoints of the experts and that of the public on the issue of the disposal of nuclear WASTES. The history of this field is that of the proliferation with time of spokesmen who pretend to speak in the name of the both humans and non humans involved. Three periods can be distinguished: 1940-1970, an era of contestation and confusion when the experts alone represents the interest of all; 1970-1990, an era of contestation and confusion when spokespersons multiply themselves, generating the controversy and the slowing down of most technological projects; 1990-, an era of negotiation, when viewpoints, both technical and non technical, tend to get closer and, let us be optimistic, leading to the overcome of the crisis. We show that, despite major differences, the options and concepts developed by the different actors are base on two categories of resources, namely Nature and Society, and that the consensus is built up through their 'hydridation'. we show in this part that the perception of nuclear power and, in particular of the underground disposal of nuclear wastes, involves a very deep psychological substrate. Trying to change mentalities in the domain by purely scientific and technical arguments is thus in vain. The practically instinctive fear of radioactivity, far from being due only to lack of information (and education), as often postulated by scientists and engineers, is rooted in archetypical structures. These were, without doubt, reactivated in the 40 s by the traumatizing experience of the atomic bomb. In addition, anthropological-linked considerations allow us to conclude that he underground disposal of wastes is seen as a 'rape' and soiling of Mother Earth. This contributes to explaining, beyond any rationality, the refusal of this technical option by some persons. However, it would naturally be simplistic and counter-productive to limit all controversy in this domain to these psychological aspects

  6. Management of radioactive wastes

    International Nuclear Information System (INIS)

    Mawson, C.A.

    1967-01-01

    When I first became concerned with radioactive waste management, in the early 1950's, very little was really known about the subject. There was a general feeling that it was a serious 'problem'. Articles were appearing in the press and talks were being given on the radio suggesting that the wastes generated by the proposed nuclear power reactors might be a serious menace to humanity. The prophets pointed with alarm to the enormous quantities of fission products that would accumulate steadily over the years in tank farms associated with reactor fuel reprocessing plants, and calculations were made of the possible results from rupture of the tanks due to corrosion, earthquakes or enemy attack. Responsible people suggested seriously that the waste disposal problem might be fatal to the development of a nuclear power industry, and this attitude was reinforced by the popular outcry that arose from experience with fallout from nuclear weapons testing. The Canadian nuclear power industry was not critically involved in this controversy because our heavy-water reactors are fuelled with natural uranium, and reprocessing of the fuel is not necessary. The spent fuel contains plutonium, a potential fuel, but the cost of recovering it was such that it was not competitive with natural uranium, which is not in short supply in Canada. Our spent fuel is not dissolved in acid - it is stored. still in its zirconium cladding, under water at the reactor site, or placed in sealed concrete-and-steel pipes below ground. If the price of uranium rises sufficiently it will become profitable to recover the plutonium, and only then shall we have an appreciable amount of waste from this source. However. during the first five or six years of research and development at Chalk River we did investigate fuel processing methods, and like everybody else we grad stainless steel tanks containing high and medium level wastes. These were located quite close to the Ottawa River, and we worried about what

  7. Method of solidifying radioactive waste

    International Nuclear Information System (INIS)

    Hasegawa, Akira; Mihara, Shigeru; Yamashita, Koji; Sauda, Kenzo.

    1988-01-01

    Purpose: To obtain satisfactory plastic solidification products rapidly and more conveniently from radioactive wastes. Method: liquid wastes contain, in addition to sodium sulfate as the main ingredient, nitrates hindering the polymerizing curing reactions and various other unknown ingredients, while spent resins contain residual cationic exchange groups hindering the polymerizing reaction. Generally, as the acid value of unsaturated liquid polyester resins is lower, the number of terminal alkyd resins is small, formation of nitrates is reduced and the polymerizing curing reaction is taken place more smoothly. In view of the above, radioactive wastes obtained by dry powderization or dehydration of radioactive liquid wastes or spent resins are polymerized with unsaturated liquid polyester resins with the acid value of less than 13 to obtain plastic solidification. Thus, if the radioactive wastes contain a great amount of polymerization hindering material such as NaNO 2 , they can be solidified rapidly and conveniently with no requirement for pre-treatment. (Kamimura, Y.)

  8. Gaseous radioactive waste processing system

    International Nuclear Information System (INIS)

    Onizawa, Hideo.

    1976-01-01

    Object: To prevent explosion of hydrogen gas within gaseous radioactive waste by removing the hydrogen gas by means of a hydrogen absorber. Structure: A coolant extracted from a reactor cooling system is sprayed by nozzle into a gaseous phase (hydrogen) portion within a tank, thus causing slipping of radioactive rare gas. The gaseous radioactive waste rich in hydrogen, which is purged in the tank, is forced by a waste gas compressor into a hydrogen occlusion device. The hydrogen occlusion device is filled with hydrogen occluding agents such as Mg, Mg-Ni alloy, V-Nb alloy, La-Ni alloy and so forth, and hydrogen in the waste gas is removed through reaction to produce hydrogen metal. The gaseous radioactive waste, which is deprived of hydrogen and reduced in volume, is stored in an attenuation tank. The hydrogen stored in the hydrogen absorber is released and used again as purge gas. (Horiuchi, T.)

  9. 40 CFR 60.2971 - What are the emission limitations for air curtain incinerators that burn only wood waste, clean...

    Science.gov (United States)

    2010-07-01

    ... air curtain incinerators that burn only wood waste, clean lumber, and yard waste? 60.2971 Section 60... Incinerators That Burn Only Wood Waste, Clean Lumber, and Yard Waste § 60.2971 What are the emission limitations for air curtain incinerators that burn only wood waste, clean lumber, and yard waste? (a) Within...

  10. Krsko NPP radioactive waste characteristics

    International Nuclear Information System (INIS)

    Skanata, D.; Kroselj, V.; Jankovic, M.

    2007-01-01

    In May 2005 Krsko NPP initiated the Radioactive Waste Characterization Project and commissioned its realization to the consulting company Enconet International, Zagreb. The Agency for Radwaste Management was invited to participate on the Project. The Project was successfully closed out in August 2006. The main Project goal consisted of systematization the existing and gathering the missing radiological, chemical, physical, mechanical, thermal and biological information and data on radioactive waste. In a general perspective, the Project may also be considered as a part of broader scope of activities to support state efforts to find a disposal solution for radioactive waste in Slovenia. The operational low and intermediate level radioactive waste has been structured into 6 waste streams that contain evaporator concentrates and tank sludges, spent ion resins, spent filters, compressible and non-compressible waste as well as specific waste. For each of mentioned waste streams, process schemes have been developed including raw waste, treatment and conditioning technologies, waste forms, containers and waste packages. In the paper the main results of the Characterization Project will be briefly described. The results will indicate that there are 17 different types of raw waste that have been processed by applying 9 treatment/conditioning technologies. By this way 18 different waste forms have been produced and stored into 3 types of containers. Within each type of container several combinations should be distinguished. Considering all of this, there are 34 different types of waste packages altogether that are currently stored in the Solid Radwaste Storage Facility at the Krsko NPP site. Because of these findings a new identification system has been recommended and consequently the improvement of the existing database on radioactive waste has been proposed. The potential areas of further in depth characterization are indicated. In the paper a brief description on the

  11. Study of plastic solidification process on solid radioactive waste treatment

    International Nuclear Information System (INIS)

    Jing Weiguan; Zhang Yinsheng; Qian Wenju

    1994-01-01

    Comparisons between the plastic solidification conditions of incinerated ash and waste cation resin by using thermosetting plastic polyvinyl chloride (PVC), polystyrene (PS) and polyethylene (PE), and identified physico-chemical properties and irradiation resistance of solidified products were presented. These solidified products have passed through different tests as compression strength, leachability, durability, stability, permeability and irradiation resistance (10 6 Gy) etc. The result showed that the solidified products possessed stable properties and met the storage requirement. The waste tube of radioimmunoassay, being used as solidification medium to contain incinerated ash, had good mechanical properties and satisfactory volume reduction. This process may develop a new way for disposal solid radioactive waste by means of re-using waste

  12. Strategy for nuclear wastes incineration in hybrid reactors

    International Nuclear Information System (INIS)

    Lelievre, F.

    1998-01-01

    The transmutation of nuclear wastes in accelerator-driven nuclear reactors offers undeniable advantages. But before going into the detailed study of a particular project, we should (i) examine the possible applications of such systems and (ii) compare the different configurations, in order to guide technological decisions. We propose an approach, answering both concerns, based on the complete description of hybrid reactors. It is possible, with only the transmutation objective and a few technological constraints chosen a posteriori, to determine precisely the essential parameters of such reactors: number of reactors, beam current, size of the core, sub-criticality... The approach also clearly pinpoints the strategic decisions, for which the scientist or engineer is not competent. This global scheme is applied to three distinct nuclear cycles: incineration of solid fuel without recycling, incineration of liquid fuel without recycling and incineration of liquid fuel with on-line recycling; and for two spectra, either thermal or fast. We show that the radiotoxicity reduction with a solid fuel is significant only with a fast spectrum, but the incineration times range from 20 to 30 years. The liquid fuel is appropriate only with on-line recycling, at equilibrium. The gain on the radiotoxicity can be considerable and we describe a number of such systems. The potential of ADS for the transmutation of nuclear wastes is confirmed, but we should continue the description of specific systems obtained through this approach. (author)

  13. 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

  14. Radioactive waste management in Tanzania

    International Nuclear Information System (INIS)

    Banzi, F.P.; Bundala, F.M.; Nyanda, A.M.; Msaki, P.

    2002-01-01

    Radioactive waste, like many other hazardous wastes, is of great concern in Tanzania because of its undesirable health effects. The stochastic effects due to prolonged exposure to ionizing radiation produce cancer and hereditary effects. The deterministic effects due to higher doses cause vomiting, skin reddening, leukemia, and death to exposed victims. The aim of this paper is to give an overview of the status of radioactive wastes in Tanzania, how they are generated and managed to protect humans and the environment. As Tanzania develops, it is bound to increase the use of ionizing radiation in research and teaching, industry, health and agriculture. Already there are more than 42 Centers which use one form of radioisotopes or another for these purposes: Teletherapy (Co-60), Brach-therapy (Cs-137, Sr-89), Nuclear Medicine (P-32, Tc-99m, 1-131, 1-125, Ga-67, In-111, Tl-206), Nuclear gauge (Am-241, Cs- 137, Sr-90, Kr-85), Industrial radiography (Am-241, C-137, Co-60, lr-92), Research and Teaching (1-125, Am241/Be, Co-60, Cs-137, H-3 etc). According to IAEA definition, these radioactive sources become radioactive waste if they meet the following criteria: if they have outlived their usefulness, if they have been abandoned, if they have been displaced without authorization, and if they contaminate other substances. Besides the origin of radioactive wastes, special emphasis will also be placed on the existing radiation regulations that guide disposal of radioactive waste, and the radioactive infrastructure Tanzania needs for ultimate radioactive waste management. Specific examples of incidences (theft, loss, abandonment and illegal possession) of radioactive waste that could have led to serious deterministic radiation effects to humans will also be presented. (author)

  15. 40 CFR 60.1445 - What are the emission limits for air curtain incinerators that burn 100 percent yard waste?

    Science.gov (United States)

    2010-07-01

    ... curtain incinerators that burn 100 percent yard waste? 60.1445 Section 60.1445 Protection of Environment... Air Curtain Incinerators That Burn 100 Percent Yard Waste § 60.1445 What are the emission limits for air curtain incinerators that burn 100 percent yard waste? If your air curtain incinerator combusts...

  16. Treatment of Radioactive Gaseous Waste

    International Nuclear Information System (INIS)

    2014-07-01

    Radioactive waste, with widely varying characteristics, is generated from the operation and maintenance of nuclear power plants, nuclear fuel cycle facilities, research laboratories and medical facilities. The waste needs to be treated and conditioned as necessary to provide waste forms acceptable for safe storage and disposal. Although radioactive gaseous radioactive waste does not constitute the main waste flow stream at nuclear fuel cycle and radioactive waste processing facilities, it represents a major source for potential direct environmental impact. Effective control and management of gaseous waste in both normal and accidental conditions is therefore one of the main issues of nuclear fuel cycle and waste processing facility design and operation. One of the duties of an operator is to take measures to avoid or to optimize the generation and management of radioactive waste to minimize the overall environmental impact. This includes ensuring that gaseous and liquid radioactive releases to the environment are within authorized limits, and that doses to the public and the effects on the environment are reduced to levels that are as low as reasonably achievable. Responsibilities of the regulatory body include the removal of radioactive materials within authorized practices from any further regulatory control — known as clearance — and the control of discharges — releases of gaseous radioactive material that originate from regulated nuclear facilities during normal operation to the environment within authorized limits. These issues, and others, are addressed in IAEA Safety Standards Series Nos RS-G-1.7, WS-G-2.3 and NS-G-3.2. Special systems should be designed and constructed to ensure proper isolation of areas within nuclear facilities that contain gaseous radioactive substances. Such systems consist of two basic subsystems. The first subsystem is for the supply of clean air to the facility, and the second subsystem is for the collection, cleanup and

  17. USDOE activities in low-level radioactive waste treatment

    International Nuclear Information System (INIS)

    Vath, J.E.

    1981-01-01

    This paper describes current research, development and demonstration (R, D and D) programs sponsored by the US Department of Energy in the area of low-level radioactive waste treatment. During the twelve month period ending September 30, 1981, 14 prime US Department of Energy contractors were involved with over 40 low-level radioactive waste disposal technology projects. Three specific projects or task areas have been selected for discussion to illustrate new and evolving technologies, and application of technology developed in other waste management areas to low-level waste treatment. The areas to be discussed include a microwave plasma torch incinerator, application of waste vitrification, and decontamination of metal waste by melting

  18. Radioactive Waste Management Objectives

    International Nuclear Information System (INIS)

    2011-01-01

    considered and the specific goals to be achieved at different stages of implementation, all of which are consistent with the Basic Principles. The four Objectives publications include Nuclear General Objectives, Nuclear Power Objectives, Nuclear Fuel Cycle Objectives, and Radioactive Waste Management and Decommissioning Objectives. This publication sets out the objectives that need to be achieved in the area of radioactive waste management, including decommissioning and environmental remediation, to ensure that the Nuclear Energy Basic Principles are satisfied.

  19. 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.)

  20. Radioactive gaseous waste processing device

    International Nuclear Information System (INIS)

    Fukuhara, Yuka.

    1991-01-01

    Radioactive gaseous wastes are introduced to a cooling tower and cooled by cooling water discharged from a cooling water discharging nozzle. Cooled radioactive gaseous wastes are cleaned by cleaning water in the cleaning tower and introduced accompanied with water to a condenser. Water in the gases is condensed in a condenser and gathered in a condensated water receiving tank. Water-removed gases are removed with fine particles by way of filters and then released out of the system by using a blower. Further, water used for cleaning the radioactive gaseous wastes in the cleaning tower is gathered to the liquid wastes receiving tank and sent to a radioactive liquid wastes processing device. On the other hand, condensates collected to the condensates receiving tank are returned to a cooling water discharging nozzle by a pump and re-utilized as cooling water. This can reduce the amount of radioactive liquid wastes, to reduce the processing amount of the radioactive liquid waste processing devices. (I.N.)

  1. The radioactive waste management conference

    International Nuclear Information System (INIS)

    Fareeduddin, S.; Hirling, J.

    1983-01-01

    The international conference on radioactive waste management was held in Seattle, Washington, from 16 to 20 May 1983. The response was gratifying, reflecting world-wide interest: it was attended by 528 participants from 29 Member States of the IAEA and eight international organizations. The conference programme was structured to permit reviews and presentation of up-to-date information on five major topics: - waste management policy and its implementation: national and international approaches; legal, economic, environmental, and social aspects (four sessions with 27 papers from 16 countries and four international organizations); - handling, treatment, and conditioning of wastes from nuclear facilities, nuclear power plants and reprocessing plants, including the handling and treatment of gaseous wastes and wastes of specific types (five sessions with 35 papers); - storage and underground disposal of radioactive wastes: general, national concepts, underground laboratories, and designs of repositories for high-level, and low- and intermediate-level waste disposal (five sessions with 35 papers); - environmental and safety assessment of waste management systems: goals methodologies, assessments for geological repositories, low- and intermediate-level wastes, and mill tailings (four sessions with 26 papers); - radioactive releases to the environment from nuclear operations: status and perspectives, environmental transport processes, and control of radioactive waste disposal into the environment (three sessions with 23 papers)

  2. Radioactive waste management in Belgium

    International Nuclear Information System (INIS)

    Detilleux, E.

    1984-01-01

    The first part of this paper briefly describes the nuclear industry in Belgium and the problem of radioactive wastes with regard to their quality and quantity. The second part emphasizes the recent guidelines regarding the management of the nuclear industry in general and the radioactive wastes in particular. In this respect, important tasks are the reinforcement of administrative structures with regard to the supervision and the control of nuclear activities, the establishment of a mixed company entrusted with the covering of the needs of nuclear plants in the field of nuclear fuels and particularly the setting up of a public autonomous and specialized organization, the 'Public Organization for the Management of Radioactive Waste and Fissile Materials', in short 'O.N.D.R.A.F.'. This organization is in charge of the management of the transport, the conditioning, the storage and the disposal of radioactive wastes. (Auth.)

  3. Radioactive waste processing and disposal

    International Nuclear Information System (INIS)

    1980-01-01

    This compilation contains 4144 citations of foreign and domestic reports, journal articles, patents, conference proceedings, and books pertaining to radioactive waste processing and disposal. Five indexes are provided: Corporate Author, Personal Author, Subject, Contract Number, and Report Number

  4. National radioactive waste management strategy

    International Nuclear Information System (INIS)

    Syed Abd Malik Syed Zain

    1985-01-01

    This article briefs out the strategic management of radioactive wastes in Malaysia. The criteria and methods discussed are those promoted by UTN (Nuclear Energy Unit) which has been given the authority to carry out local research programs in nuclear energy

  5. World ocean and radioactive wastes

    International Nuclear Information System (INIS)

    Kiknadze, O.E.; Sivintsev, Yu.V.

    2000-01-01

    The radioecological situation that took shape in the Arctic, North Atlantic Ocean and Far East regions as a result of radioactive waste marine disposal was assessed. Accurate account of radionuclides formation and decay in submerged water-water reactors of nuclear submarines suggests that total activity of radioactive waste disposed near the Novaya Zemlya amounted to 107 kCi by the end of 1999. Activity of radioactive waste disposed in the North Atlantic currently is not in excess of 430 kCi. It is pointed out that the Far East region heads the list in terms of total activity disposed (529 kCi). Effective individual dose for critical groups of population in the Arctic, North Atlantic and Far East regions was determined. The conclusion was made that there is no detrimental effect of the radioactive waste disposed on radioecological situation in the relevant areas [ru

  6. Method of solidifying radioactive wastes

    International Nuclear Information System (INIS)

    Fukazawa, Tetsuo; Ootsuka, Masaharu; Uetake, Naoto; Ozawa, Yoshihiro.

    1984-01-01

    Purpose: To prepare radioactive solidified wastes excellent in strength, heat resistance, weather-proof, water resistance, dampproof and low-leaching property. Method: A hardening material reactive with alkali silicates to form less soluble salts is used as a hardener for alkali silicates which are solidification filler for the radioactive wastes, and mixed with cement as a water absorbent and water to solidify the radioactive wastes. The hardening agent includes, for example, CaCO 3 , Ca(ClO 4 ) 2 , CaSiF 6 and CaSiO 3 . Further, in order to reduce the water content in the wastes and reduce the gap ratio in the solidification products, the hardener adding rate, cement adding rate and water content are selected adequately. As the result, solidification products can be prepared with no deposition of easily soluble salts to the surface thereof, with extremely low leaching of radioactive nucleides. (Kamimura, M.)

  7. Radioactive waste management in France

    International Nuclear Information System (INIS)

    Pradel, J.

    1975-01-01

    The different stages of radioactive waste production are examined: ore production, reactor operation, reprocessing plants. The treatment and storage methods used and the French realizations relative to these problems are described [fr

  8. Radioactive waste melting furnace

    International Nuclear Information System (INIS)

    Nakayama, Junpei.

    1997-01-01

    The present invention provides a radioactive waste melting furnace excellent in heat insulating property, capable of exchanging only refractory materials with lesser amount of contamination. Namely, an heat insulation layer is disposed on the outer wall of the melting furnace. A refractory layer is disposed on the inner wall being in contact with molten materials in the melting furnace. A metal vessel covering the refractory layer is interposed between the heat insulation layer and the refractory layer. In addition, a metal outer shell covering the heat insulation layer is disposed on the heat insulation layer on the outer wall of the melting furnace. Bricks comprising, for example, alumina, carbon, zircon, magnesia or chromia having a low heat conductivity are used for the outer wall heat insulation layer irrespective of the melting performance. The refractory layer on the inner wall is made of bricks comprising chromia, alumina and zircon as molten materials of low basicity and chromia and magnesia as molten materials of high basicity. The materials of the metal vessel may be ordinary carbon steels, cast irons, or stainless steels. The refractory layer is taken out from the melting furnace together with the metal vessel, and only the refractory layer can be removed. Radiation contamination is eliminated. The metal vessel can be used again. (I.S.)

  9. Radioactive waste problems in Russia

    International Nuclear Information System (INIS)

    Bridges, O.; Bridges, J.W.

    1995-01-01

    The collapse of the former Soviet Union, with the consequent shift to a market driven economy and demilitarisation, has had a profound effect on the nuclear and associated industries. The introduction of tighter legislation to control the disposal of radioactive wastes has been delayed and the power and willingness of the various government bodies responsible for its regulation is in doubt. Previously secret information is becoming more accessible and it is apparent that substantial areas of Russian land and surface waters are contaminated with radioactive material. The main sources of radioactive pollution in Russia are similar to those in many western countries. The existing atomic power stations already face problems in the storage and safe disposal of their wastes. These arise because of limited on site capacity for storage and the paucity of waste processing facilities. Many Russian military nuclear facilities also have had a sequence of problems with their radioactive wastes. Attempts to ameliorate the impacts of discharges to important water sources have had variable success. Some of the procedures used have been technically unsound. The Russian navy has traditionally dealt with virtually all of its radioactive wastes by disposal to sea. Many areas of the Barents, Kola and the Sea of Japan are heavily contaminated. To deal with radioactive wastes 34 large and 257 small disposal sites are available. However, the controls at these sites are often inadequate and illegal dumps of radioactive waste abound. Substantial funding will be required to introduce the necessary technologies to achieve acceptable standards for the storage and disposal of radioactive wastes in Russia. (author)

  10. 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.

  11. Description of the Seibersdorf incineration plant for low level waste

    International Nuclear Information System (INIS)

    Chalupa, G.; Petschnik, G.

    1986-09-01

    After a description of the design and the construction principles of the incinerator building, the furnace and its attached auxilary devices are explained. The incinerator is layed out for low level wastes. It has a vertical furnace, operates with discontinuous feeding for trashes with heat-values between 600 and 10000 kcal/kg waste. The maximum throughput amounts 40 kg/h. The purification of the off-gas is guaranteed by a multistage filter system: 2 stages with ceramic candles, cooling column and a HEPA-filter system. The control of the off-gas cleaning is carried out by a stack instrumentation, consisting of an aerosol-, gas-, Iodine- and Tritium-monitor; the building is surveilled by doserate- and aerosolmonitors. (Author)

  12. Fluidized bed incineration of a slurry waste from caprolactam production

    Energy Technology Data Exchange (ETDEWEB)

    Cammarota, A.; D' Amore, M.; Donsi, G.; Massimilla, L.

    1980-08-01

    Caprolactam tails are a slurry waste produced in the SNIA process for the synthesis of caprolactam. They contain about 65% water, 25% ash and 10% combustible matter. The ashes are low melting, due to the presence of sodium compounds. The incineration of this waste is carried out at temperatures below 600/sup 0/C in beds of silica sand, using a laboratory scale apparatus with a 40 mm ID fluidization column. Variables investigated include sand particle size, slurry flow rate, bed temperature, bed height. The concentrations of CO/sub 2/ and CO are determined continuously in the flue gases. Bed solids are sampled periodically to determine the carbon content. Results of experiments show that the low temperature incineration on a bed of inert solids is a useful technique for the disposal of caprolactam tails. 8 refs.

  13. Simulation of co-incineration of sewage sludge with municipal solid waste in a grate furnace incinerator.

    Science.gov (United States)

    Lin, Hai; Ma, Xiaoqian

    2012-03-01

    Incineration is one of the most important methods in the resource recovery disposal of sewage sludge. The combustion characteristics of sewage sludge and an increasing number of municipal solid waste (MSW) incineration plants provide the possibility of co-incineration of sludge with MSW. Computational fluid dynamics (CFD) analysis was used to verify the feasibility of co-incineration of sludge with MSW, and predict the effect of co-incineration. In this study, wet sludge and semi-dried sludge were separately blended with MSW as mixed fuels, which were at a co-incineration ratios of 5 wt.% (wet basis, the same below), 10 wt.%, 15 wt.%, 20 wt.% and 25 wt.%. The result indicates that co-incineration of 10 wt.% wet sludge with MSW can ensure the furnace temperature, the residence time and other vital items in allowable level, while 20 wt.% of semi-dried sludge can reach the same standards. With lower moisture content and higher low heating value (LHV), semi-dried sludge can be more appropriate in co-incineration with MSW in a grate furnace incinerator. Copyright © 2011 Elsevier Ltd. All rights reserved.

  14. Centralized treatment facility for low level radioactive waste produced in Belgium. The CILVA project

    International Nuclear Information System (INIS)

    Renard, Cl.; Detilleux, M.; Debieve, P.

    1993-01-01

    Due to rather limited amount of waste produced and the small size of the Belgian territory (30 x 10 3 km 2 ), ONDRAF/NIRAS strategy aims at centralizing treatment conditioning and storage of radioactive waste. ONDRAF/NTRAS has decided to set up a new infrastructure: the CILVA unit. The CILVA facility is focused on the supercompaction and the incineration treatment, so that ONDRAF/NIRAS can safely manage all radioactive wastes produced in Belgium. (2 figs.)

  15. Radioactive wastes and their disposal

    International Nuclear Information System (INIS)

    Neumann, L.

    1984-01-01

    The classification of radioactive wastes is given and the achievements evaluated in the disposal of radioactive wastes from nuclear power plants. An experimental pilot unit was installed at the Jaslovske Bohunice nuclear power plant for the bituminization of liquid radioactive wastes. UJV has developed a mobile automated high-output unit for cementation. In 1985 the unit will be tested at the Jaslovske Bohunice and the Dukovany nuclear power plants. A prototype press for processing solid wastes was manufactured which is in operation at the Jaslovske Bohunice plant. A solidification process for atypical wastes from long-term storage of spent fuel elements has been developed to be used for the period of nuclear power plant decommissioning. (E.S.)

  16. High Level Radioactive Waste Management

    International Nuclear Information System (INIS)

    1991-01-01

    The proceedings of the second annual international conference on High Level Radioactive Waste Management, held on April 28--May 3, 1991, Las Vegas, Nevada, provides information on the current technical issue related to international high level radioactive waste management activities and how they relate to society as a whole. Besides discussing such technical topics as the best form of the waste, the integrity of storage containers, design and construction of a repository, the broader social aspects of these issues are explored in papers on such subjects as conformance to regulations, transportation safety, and public education. By providing this wider perspective of high level radioactive waste management, it becomes apparent that the various disciplines involved in this field are interrelated and that they should work to integrate their waste management activities. Individual records are processed separately for the data bases

  17. Overview of radioactive waste management

    International Nuclear Information System (INIS)

    Ritter, G.L.

    1980-01-01

    The question of what to do with radioactive wastes is discussed. The need to resolve this issue promptly is pointed out. Two significant events which have occurred during the Carter administration are discussed. An Interagency Review Group (IRG) on waste management was formed to formulate recommendations leading to the establishment of a National policy for managing radioactive wastes. The technical findings in the IRG report are listed. The author points out some issues not addressed by the report. President Carter issued a national policy statement on Radioactive Waste Management in February 1980. The most significant elements of this statement are summarized. The cancellation of the Waste Isolation Pilot Plant is currently meeting opposition in Congress. This and other items in the National Policy Statement are discussed

  18. Handling and disposing of radioactive waste

    International Nuclear Information System (INIS)

    Trauger, D.B.

    1983-01-01

    Radioactive waste has been separated by definition into six categories. These are: commercial spent fuel; high-level wastes; transuranium waste; low-level wastes; decommissioning and decontamination wastes; and mill tailings and mine wastes. Handling and disposing of these various types of radioactive wastes are discussed briefly

  19. 40 CFR 60.3066 - What are the emission limitations for air curtain incinerators that burn only wood waste, clean...

    Science.gov (United States)

    2010-07-01

    ... Waste Incineration Units That Commenced Construction On or Before December 9, 2004 Model Rule-Air Curtain Incinerators That Burn Only Wood Waste, Clean Lumber, and Yard Waste § 60.3066 What are the... air curtain incinerators that burn only wood waste, clean lumber, and yard waste? 60.3066 Section 60...

  20. Method of processing radioactive laundry wastes

    International Nuclear Information System (INIS)

    Shirai, Takamori; Suzuki, Takeo; Takahara, Toshio.

    1982-01-01

    Purpose: To improve the processing performance of radioactive laundry waste processing device, as well as improve the working life of back osmotic membranes to be secondary wastes. Method: Upon removal of radioactive nucleids in radioactive laundry wastes by separation, radioactive nuclides-containing solids contained in the radioactive laundry wastes are separated and removed in a separation plate type centrifugal cleaner. Then, solid radioactive nuclides and ionized radioactive nuclides remained in the radioactive laundry wastes from which the solids have been removed by separation are separated and removed in a back osmotic membrane processing device. (Aizawa, K.)

  1. Recovery and distribution of incinerated aluminum packaging waste.

    Science.gov (United States)

    Hu, Y; Bakker, M C M; de Heij, P G

    2011-12-01

    A study was performed into relations between physical properties of aluminum packaging waste and the corresponding aluminum scraps in bottom ash from three typical incineration processes. First, Dutch municipal solid waste incineration (MSWI) bottom ash was analyzed for the identifiable beverage can alloy scraps in the +2mm size ranges using chemical detection and X-ray fluorescence. Second, laboratory-scale pot furnace tests were conducted to investigate the relations between aluminum packaging in base household waste and the corresponding metal recovery rates. The representative packaging wastes include beverage cans, foil containers and thin foils. Third, small samples of aluminum packaging waste were incinerated in a high-temperature oven to determine leading factors influencing metal recovery rates. Packaging properties, combustion conditions, presence of magnesium and some specific contaminants commonly found in household waste were investigated independently in the high-temperature oven. In 2007, the bottom ash (+2mm fraction) from the AEB MSWI plant was estimated to be enriched by 0.1 wt.% of aluminum beverage cans scrap. Extrapolating from this number, the recovery potential of all eleven MSWI plants in the Netherlands is estimated at 720 ton of aluminum cans scrap. More than 85 wt.% of this estimate would end up in +6mm size fractions and were amenable for efficient recycling. The pot furnace tests showed that the average recovery rate of metallic aluminum typically decreases from beverage cans (93 wt.%) to foil containers (85 wt.%) to thin foils (77 wt.%). The oven tests showed that in order of decreasing impact the main factors promoting metallic aluminum losses are the packaging type, combustion temperature, residence time and salt contamination. To a lesser degree magnesium as alloying element, smaller packaging size and basic contaminations may also promote losses. Crown Copyright © 2011. Published by Elsevier Ltd. All rights reserved.

  2. Method of disposing radioactive wastes

    International Nuclear Information System (INIS)

    Isozaki, Kei.

    1983-01-01

    Purpose : To enable safety ocean disposal of radioactive wastes by decreasing the leaching rate of radioactive nucleides, improving the quick-curing nature and increasing the durability. Method : A mixture comprising 2 - 20 parts by weight of alkali metal hydroxide and 100 parts by weight of finely powdered aqueous slags from a blast furnace is added to radioactive wastes to solidify them. In the case of medium or low level radioactive wastes, the solidification agent is added by 200 parts by weight to 100 parts by weight of the wastes and, in the case of high level wastes, the solidification agent is added in such an amount that the wastes occupy about 20% by weight in the total of the wastes and the solidification agent. Sodium hydroxide used as the alkali metal hydroxide is partially replaced with sodium carbonate, a water-reducing agent such as lignin sulfonate is added to improve the fluidity and suppress the leaching rate and the wastes are solidified in a drum can. In this way, corrosions of the vessel can be suppressed by the alkaline nature and the compression strength, heat stability and the like of the product also become excellent. (Sekiya, K.)

  3. Radioactive waste management in Canada

    International Nuclear Information System (INIS)

    Hawley, N.J.

    1986-09-01

    This bibliography is an up-date to AECL-6186(Rev 3), 1952-1982, 'Radioactive Waste Management in Canada AECL Publications and Other Literature' compiled by Dianne Wallace. Canadian publications from outside contractors concerning the Canadian Nuclear Fuel Waste Management Program are included in addition to Atomic Energy of Canada Limited reports and papers. 252 refs

  4. 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

  5. The Louisiana State University waste-to-energy incinerator

    International Nuclear Information System (INIS)

    1994-01-01

    This proposed action is for cost-shared construction of an incinerator/steam-generation facility at Louisiana State University under the State Energy Conservation Program (SECP). The SECP, created by the Energy Policy and Conservation Act, calls upon DOE to encourage energy conservation, renewable energy, and energy efficiency by providing Federal technical and financial assistance in developing and implementing comprehensive state energy conservation plans and projects. Currently, LSU runs a campus-wide recycling program in order to reduce the quantity of solid waste requiring disposal. This program has removed recyclable paper from the waste stream; however, a considerable quantity of other non-recyclable combustible wastes are produced on campus. Until recently, these wastes were disposed of in the Devil's Swamp landfill (also known as the East Baton Rouge Parish landfill). When this facility reached its capacity, a new landfill was opened a short distance away, and this new site is now used for disposal of the University's non-recyclable wastes. While this new landfill has enough capacity to last for at least 20 years (from 1994), the University has identified the need for a more efficient and effective manner of waste disposal than landfilling. The University also has non-renderable biological and potentially infectious waste materials from the School of Veterinary Medicine and the Student Health Center, primarily the former, whose wastes include animal carcasses and bedding materials. Renderable animal wastes from the School of Veterinary Medicine are sent to a rendering plant. Non-renderable, non-infectious animal wastes currently are disposed of in an existing on-campus incinerator near the School of Veterinary Medicine building

  6. The Louisiana State University waste-to-energy incinerator

    Energy Technology Data Exchange (ETDEWEB)

    1994-10-26

    This proposed action is for cost-shared construction of an incinerator/steam-generation facility at Louisiana State University under the State Energy Conservation Program (SECP). The SECP, created by the Energy Policy and Conservation Act, calls upon DOE to encourage energy conservation, renewable energy, and energy efficiency by providing Federal technical and financial assistance in developing and implementing comprehensive state energy conservation plans and projects. Currently, LSU runs a campus-wide recycling program in order to reduce the quantity of solid waste requiring disposal. This program has removed recyclable paper from the waste stream; however, a considerable quantity of other non-recyclable combustible wastes are produced on campus. Until recently, these wastes were disposed of in the Devil`s Swamp landfill (also known as the East Baton Rouge Parish landfill). When this facility reached its capacity, a new landfill was opened a short distance away, and this new site is now used for disposal of the University`s non-recyclable wastes. While this new landfill has enough capacity to last for at least 20 years (from 1994), the University has identified the need for a more efficient and effective manner of waste disposal than landfilling. The University also has non-renderable biological and potentially infectious waste materials from the School of Veterinary Medicine and the Student Health Center, primarily the former, whose wastes include animal carcasses and bedding materials. Renderable animal wastes from the School of Veterinary Medicine are sent to a rendering plant. Non-renderable, non-infectious animal wastes currently are disposed of in an existing on-campus incinerator near the School of Veterinary Medicine building.

  7. Radioactive waste below regulatory concern

    International Nuclear Information System (INIS)

    Neuder, S.M.

    1987-01-01

    The U.S. Nuclear Regulatory Commission (NRC) published two notices in the Federal Register concerning radioactive waste below regulatory concern. The first, a Commission Policy Statement and Implementation Plan published August 29, 1986, concerns petition to exempt specific radioactive waste streams from the regulations. The second, an Advanced Notice of Proposed Rulemaking published Decemger 2, 1986, addresses the concept of generic rulemaking by the NRC on radioactive wastes that are below regulatory concern. Radioactive waste determined to be below regulatory concern would not be subject to regulatory control and would not need to go to a licensed low-level radioactive waste disposal site. The Policy Statement and Implementation Plan describe (1) the information a petitioner should file in support of a petition to exempt a specific waste stream, (2) the decision criteria the Commission intends to use for judging the petition, and (3) the internal administrative procedures to use be followed in order to permit the Commission to act upon the petition in an expedited manner

  8. Radioactive waste management in Germany

    International Nuclear Information System (INIS)

    Roesel, H.

    2003-01-01

    The Federal Republic of Germany intends to dispose of all types of radioactive waste in deep geological formations. This waste comprises spent fuel elements, vitrified fission product solution, nuclear power plant operational and decommissioning waste as well as spent sealed radiation sources and miscellaneous waste originating from small waste generators. The Atomic Energy Act gives the responsibility for the disposal of radioactive waste to the Federal Government with the Bundesamt fuer Strahlenschutz (BfS - Federal Office for Radiation Protection) as the legally responsible authority. The Federal Government has made a pronounced change in energy policy since 1998, the most important feature of which is the abandoning or phasing out of nuclear energy. It is intended to irreversibly phase out nuclear energy use for electricity generation. Essential (basic) steps are the agreement which was achieved by the Federal Government and the utilities on June 14, 2000, and signed on June 11, 2001, and the April 2002 amendment of the Atomic Energy Act. (orig.)

  9. Radioactive Waste Management Program Activities in Croatia

    International Nuclear Information System (INIS)

    Matanic, R.

    2000-01-01

    The concept of radioactive waste management in Croatia comprises three major areas: management of low and intermediate level radioactive waste (LILRW), spent fuel management and decommissioning. All the work regarding radioactive waste management program is coordinated by Hazardous Waste Management Agency (APO) and Croatian Power Utility (HEP) in cooperation with other relevant institutions. Since the majority of work has been done in developing low and intermediate level radioactive waste management program, the paper will focus on this part of radioactive waste management, mainly on issues of site selection and characterization, repository design, safety assessment and public acceptance. A short description of national radioactive waste management infrastructure will also be presented. (author)

  10. Low-level radioactive waste in the Midwest: an economic analysis of selected management options

    International Nuclear Information System (INIS)

    1983-06-01

    Possible economic scenarios for disposal of low-level radioactive waste generated in the Midwest are presented. Relative waste disposal site costs are estimated for each state separately, and for 5-state, 13-state, and 16-state regions. Costs for publicly and privately owned and operated sites are estimated as are incineration and transportation costs

  11. Standardization of radioactive waste categories

    International Nuclear Information System (INIS)

    1970-01-01

    A large amount of information about most aspects of radioactive waste management has been accumulated and made available to interested nations in recent years. The efficiency of this service has been somewhat hampered because the terminology used to describe the different types of radioactive waste has varied from country to country and indeed from installation to installation within a given country. This publication is the outcome of a panel meeting on Standardization of Radioactive Waste Categories. It presents a simple standard to be used as a common language between people working in the field of waste management at nuclear installations. The purpose of the standard is only to act as a practical tool for increasing efficiency in communicating, collecting and assessing technical and economical information in the common interest of all nations and the developing countries in particular. 20 refs, 1 fig., 3 tabs

  12. Underground radioactive waste disposal concept

    International Nuclear Information System (INIS)

    Frgic, L.; Tor, K.; Hudec, M.

    2002-01-01

    The paper presents some solutions for radioactive waste disposal. An underground disposal of radioactive waste is proposed in deep boreholes of greater diameter, fitted with containers. In northern part of Croatia, the geological data are available on numerous boreholes. The boreholes were drilled during investigations and prospecting of petroleum and gas fields. The available data may prove useful in defining safe deep layers suitable for waste repositories. The paper describes a Russian disposal design, execution and verification procedure. The aim of the paper is to discuss some earlier proposed solutions, and present a solution that has not yet been considered - lowering of containers with high level radioactive waste (HLW) to at least 500 m under the ground surface.(author)

  13. Plastic solidification of radioactive wastes

    International Nuclear Information System (INIS)

    Moriyama, Noboru

    1981-01-01

    Over 20 years have elapsed after the start of nuclear power development, and the nuclear power generation in Japan now exceeds the level of 10,000 MW. In order to meet the energy demands, the problem of the treatment and disposal of radioactive wastes produced in nuclear power stations must be solved. The purpose of the plastic solidification of such wastes is to immobilize the contained radionuclides, same as other solidification methods, to provide the first barrier against their move into the environment. The following matters are described: the nuclear power generation in Japan, the radioactive wastes from LWR plants, the position of plastic solidification, the status of plastic solidification in overseas countries and in Japan, the solidification process for radioactive wastes with polyethylene, and the properties of solidified products, and the leachability of radionuclides in asphalt solids. (J.P.N.)

  14. Radioactive waste management in Slovenia

    International Nuclear Information System (INIS)

    Fink, K.

    1992-01-01

    The problem of radioactive waste management is both scientifically and technically complex and also deeply emotional issue. In the last twenty years the first two aspects have been mostly resolved up to the point of safe implementation. In the Republic of Slovenia, certain fundamentalist approaches in politics and the use of radioactive waste problem as political marketing tool, make things even more complex. Public involvement in planning and development of radioactive waste management program must be perceived as essential for the success of the program. Education is a precursor to public comprehension and confidence which lead to adequate waste management decisions that will protect the public health, safety and environment without jeopardizing further progress and development. (author) [sl

  15. Method of solidifying radioactive wastes

    International Nuclear Information System (INIS)

    Maeda, Masahiko; Kira, Satoshi; Watanabe, Naotoshi; Nagaoka, Takeshi; Akane, Junta.

    1982-01-01

    Purpose: To obtain solidification products of radioactive wastes having sufficient monoaxial compression strength and excellent in water durability upon ocean disposal of the wastes. Method: Solidification products having sufficient strength and filled with a great amount of radioactive wastes are obtained by filling and solidifying 100 parts by weight of chlorinated polyethylene resin and 100 - 500 parts by weight of particular or powderous spent ion exchange resin as radioactive wastes. The chlorinated polyethylene resin preferably used herein is prepared by chlorinating powderous or particulate polyethylene resin in an aqueous suspending medium or by chlorinating polyethylene resin dissolved in an organic solvent capable of dissolving the polyethylene resin, and it is crystalline or non-crystalline chlorinated polyethylene resin comprising 20 - 50% by weight of chlorine, non-crystalline resin with 25 - 40% by weight of chlorine being particularly preferred. (Horiuchi, T.)

  16. Radioactive liquid waste processing facility

    International Nuclear Information System (INIS)

    Kikuchi, Makoto; Tamada, Shin; Oura, Masato; Sawa, Toshio.

    1991-01-01

    This invention is intended for preventing degradation of an evaporation permeable membrane in a facility for processing radioactive liquid wastes generated in a nuclear power plant, while taking advantages of a film evaporation and concentration system. That is, surface active agents, oils and solids are removed by a pre-filter before sending the radioactive liquid wastes to a liquid wastes processing device (membrane evaporation concentration device) comprising an evaporation permeable membrane. Active carbon or active silica is preferably used for the pre-filter. This can prevent the reduction of surface tension of the radioactive liquid wastes caused by the surface active agents and the destruction of the hydrophobic property of the membrane due to the deposition of the surface active agents to the evaporation permeable membrane in the membrane evaporation and concentration device, that is a back-filter. (T.M.)

  17. GIS analysis in the siting of incinerators as a panacea for solid waste ...

    African Journals Online (AJOL)

    Solid waste represents a key issue that threatens environmental quality in Kaduna metropolis. One of the most viable options to treat such an issue is to incinerate the collected solid waste, which can reduce the cost of solid waste disposal as well as pollution and generate electricity. Despite the significance of incineration, ...

  18. 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

  19. Environmental impacts of residual municipal solid waste incineration: a comparison of 110 French incinerators using a life cycle approach.

    Science.gov (United States)

    Beylot, Antoine; Villeneuve, Jacques

    2013-12-01

    Incineration is the main option for residual Municipal Solid Waste treatment in France. This study compares the environmental performances of 110 French incinerators (i.e., 85% of the total number of plants currently in activity in France) in a Life Cycle Assessment perspective, considering 5 non-toxic impact categories: climate change, photochemical oxidant formation, particulate matter formation, terrestrial acidification and marine eutrophication. Mean, median and lower/upper impact potentials are determined considering the incineration of 1 tonne of French residual Municipal Solid Waste. The results highlight the relatively large variability of the impact potentials as a function of the plant technical performances. In particular, the climate change impact potential of the incineration of 1 tonne of waste ranges from a benefit of -58 kg CO2-eq to a relatively large burden of 408 kg CO2-eq, with 294 kg CO2-eq as the average impact. Two main plant-specific parameters drive the impact potentials regarding the 5 non-toxic impact categories under study: the energy recovery and delivery rate and the NOx process-specific emissions. The variability of the impact potentials as a function of incinerator characteristics therefore calls for the use of site-specific data when required by the LCA goal and scope definition phase, in particular when the study focuses on a specific incinerator or on a local waste management plan, and when these data are available. Copyright © 2013 Elsevier Ltd. All rights reserved.

  20. CEGB's radioactive waste management strategy

    International Nuclear Information System (INIS)

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

    1989-01-01

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

  1. Metallic elements fractionation in municipal solid waste incineration residues

    Science.gov (United States)

    Kowalski, Piotr R.; Kasina, Monika; Michalik, Marek

    2016-04-01

    Municipal solid waste incineration (MSWI) residues are represented by three main materials: bottom ash, fly ash and air pollution control (APC) residues. Among them ˜80 wt% is bottom ash. All of that materials are products of high temperature (>1000° C) treatment of waste. Incineration process allows to obtain significant reduction of waste mass (up to 70%) and volume (up to 90%) what is commonly used in waste management to reduce the amount need to be landfilled or managed in other way. Incineration promote accumulation non-combustible fraction of waste, which part are metallic elements. That type of concentration is object of concerns about the incineration residues impact on the environment and also gives the possibility of attempts to recover them. Metallic elements are not equally distributed among the materials. Several factors influence the process: melting points, volatility and place and forms of metallic occurrence in the incinerated waste. To investigate metallic elements distribution in MSWI residues samples from one of the biggest MSW incineration plant in Poland were collected in 2015. Chemical analysis with emphasis on the metallic elements content were performed using inductively coupled plasma optical emission (ICP-OES) and mass spectrometry (ICP-MS). The bottom ash was a SiO2-CaO-Al2O3-Fe2O3-Na2O rich material, whereas fly ash and APC residues were mostly composed of CaO and SiO2. All of the materials were rich in amorphous phase occurring together with various, mostly silicate crystalline phases. In a mass of bottom ash 11 wt% were metallic elements but also in ashes 8.5 wt% (fly ash) and ˜4.5 wt% (APC residues) of them were present. Among the metallic elements equal distribution between bottom and fly ash was observed for Al (˜3.85 wt%), Mn (770 ppm) and Ni (˜65 ppm). In bottom ash Fe (5.5 wt%), Cr (590 ppm) and Cu (1250 ppm) were concentrated. These values in comparison to fly ash were 5-fold higher for Fe, 3-fold for Cu and 1.5-fold for

  2. Separation of nanoparticles: Filtration and scavenging from waste incineration plants.

    Science.gov (United States)

    Förster, Henning; Thajudeen, Thaseem; Funk, Christine; Peukert, Wolfgang

    2016-06-01

    Increased amounts of nanoparticles are applied in products of everyday life and despite material recycling efforts, at the end of their life cycle they are fed into waste incineration plants. This raises the question on the fate of nanoparticles during incineration. In terms of environmental impact the key question is how well airborne nanoparticles are removed by separation processes on their way to the bag house filters and by the existing filtration process based on pulse-jet cleanable fibrous filter media. Therefore, we investigate the scavenging and the filtration of metal nanoparticles under typical conditions in waste incineration plants. The scavenging process is investigated by a population balance model while the nanoparticle filtration experiments are realized in a filter test rig. The results show that depending on the particle sizes, in some cases nearly 80% of the nanoparticles are scavenged by fly ash particles before they reach the bag house filter. For the filtration step dust cakes with a pressure drop of 500Pa or higher are found to be very effective in preventing nanoparticles from penetrating through the filter. Thus, regeneration of the filter must be undertaken with care in order to guarantee highly efficient collection of particles even in the lower nanometre size regime. Copyright © 2016 Elsevier Ltd. All rights reserved.

  3. 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

  4. Radioactive liquid waste processing system

    International Nuclear Information System (INIS)

    Noda, Tetsuya; Kuramitsu, Kiminori; Ishii, Tomoharu.

    1997-01-01

    The present invention provides a system for processing radioactive liquid wastes containing laundry liquid wastes, shower drains or radioactive liquid wastes containing chemical oxygen demand (COD) ingredients and oil content generated from a nuclear power plant. Namely, a collecting tank collects radioactive liquid wastes. A filtering device is connected to the exit of the collective tank. A sump tank is connected to the exit of the filtering device. A powdery active carbon supplying device is connected to the collecting tank. A chemical fluid tank is connected to the collecting tank and the filtering device by way of chemical fluid injection lines. Backwarding pipelines connect a filtered water flowing exit of the filtering device and the collecting tank. The chemical solution is stored in the chemical solution tank. Then, radioactive materials in radioactive liquid wastes generated from a nuclear power plant are removed by the filtering device. The water quality standard specified in environmental influence reports can be satisfied. In the filtering device, when the filtering flow rate is reduced, the chemical fluid is supplied from the chemical fluid tank to the filtering device to recover the filtering flow rate. (I.S.)

  5. 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.

  6. Radioactive waste repository study

    International Nuclear Information System (INIS)

    1978-11-01

    This is the second part of a report of a preliminary study for AECL. It considers the requirements for an underground waste repository for the disposal of wastes produced by the Canadian Nuclear Fuel Program. The following topics are discussed with reference to the repository: 1) geotechnical assessment, 2) hydrogeology and waste containment, 3) thermal loading and 4) rock mechanics. (author)

  7. 40 CFR 62.14815 - What are the emission limitations for air curtain incinerators that burn 100 percent wood wastes...

    Science.gov (United States)

    2010-07-01

    ... air curtain incinerators that burn 100 percent wood wastes, clean lumber and/or yard waste? 62.14815... Before November 30, 1999 Air Curtain Incinerators That Burn 100 Percent Wood Wastes, Clean Lumber And/or Yard Waste § 62.14815 What are the emission limitations for air curtain incinerators that burn 100...

  8. Report on radioactive waste disposal

    International Nuclear Information System (INIS)

    1993-01-01

    The safe management of radioactive wastes constitutes an essential part of the IAEA programme. A large number of reports and conference proceedings covering various aspects of the subject have been issued. The Technical Review Committee on Underground Disposal (February 1988) recommended that the Secretariat issue a report on the state of the art of underground disposal of radioactive wastes. The Committee recommended the need for a report that provided an overview of the present knowledge in the field. This report covers the basic principles associated with the state of the art of near surface and deep geological radioactive waste disposal, including examples of prudent practice, and basic information on performance assessment methods. It does not include a comprehensive description of the waste management programmes in different countries nor provide a textbook on waste disposal. Such books are available elsewhere. Reviewing all the concepts and practices of safe radioactive waste disposal in a document of reasonable size is not possible; therefore, the scope of this report has been limited to cover essential parts of the subject. Exotic disposal techniques and techniques for disposing of uranium mill tailings are not covered, and only brief coverage is provided for disposal at sea and in the sea-bed. The present report provides a list of references to more specialized reports on disposal published by the IAEA as well as by other bodies, which may be consulted if additional information is sought. 108 refs, 22 figs, 2 tabs

  9. Radioactive waste gas processing systems

    International Nuclear Information System (INIS)

    Kita, Kaoru; Minemoto, Masaki; Takezawa, Kazuaki.

    1981-01-01

    Purpose: To effectively separate and remove only hydrogen from hydrogen gas-containing radioactive waste gases produced from nuclear power plants without using large scaled facilities. Constitution: From hydrogen gas-enriched waste gases which contain radioactive rare gases (Kr, Xe) sent from the volume control tank of a chemical volume control system, only the hydrogen is separated in a hydrogen separator using palladium alloy membrane and rare gases are concentrated, volume-decreased and then stored. In this case, an activated carbon adsorption device is connected at its inlet to the radioactive gas outlet of the hydrogen separator and opened at its outlet to external atmosphere. In this system, while only the hydrogen gas permeates through the palladium alloy membrane, other gases are introduced, without permeation, into the activated carbon adsorption device. Then, the radioactive rare gases are decayed by the adsorption on the activated carbon and then released to the external atmosphere. (Furukawa, Y.)

  10. Classification of solid wastes as non-radioactive wastes

    International Nuclear Information System (INIS)

    Suzuki, Masahiro; Tomioka, Hideo; Kamike, Kozo; Komatu, Junji

    1995-01-01

    The radioactive wastes generally include nuclear fuels, materials contaminated with radioactive contaminants or neutron activation to be discarded. The solid wastes arising from the radiation control area in nuclear facilities are used to treat and stored as radioactive solid wastes at the operation of nuclear facilities in Japan. However, these wastes include many non-radioactive wastes. Especially, a large amount of wastes is expected to generate at the decommissioning of nuclear facilities in the near future. It is important to classify these wastes into non-radioactive and radioactive wastes. The exemption or recycling criteria of radioactive solid wastes is under discussion and not decided yet in Japan. Under these circumstances, the Nuclear Safety Committee recently decided the concept on the category of non-radioactive waste for the wastes arising from decommissioning of nuclear facilities. The concept is based on the separation and removal of the radioactively contaminated parts from radioactive solid wastes. The residual parts of these solid wastes will be treated as non-radioactive waste if no significant difference in radioactivity between the similar natural materials and materials removed the radioactive contaminants. The paper describes the procedures of classification of solid wastes as non-radioactive wastes. (author)

  11. Radioactive liquid waste processing device

    International Nuclear Information System (INIS)

    Mukai, Osamu; Kitamura, Masahiro.

    1992-01-01

    In a radioactive liquid waste processing device comprising a freeze-drying vessel for freezing and then vacuum drying acidic liquid wastes containing radioactive materials and a cold trap condensing steams evaporated in the freeze-drying vessel, a dust collecting electrode of an electric dust collector is disposed in the freeze-drying vessel for capturing fine solid particles and inorganic salts in steams. With such a constitution, upon sublimation of the water content contained in a freezing product of an acidic solution, since fine solid particles and inorganic salts entrained by steams are collected by the dust collecting electrode, radioactive materials entrained by recovered steams are almost eliminated, decontamination efficiency of the liquid waste processing device can be increased. Further, heat for the sublimation can be supplied to the solution-freezing product by a radiation heat caused by electric discharge of the dust collecting electrode, thereby enabling to eliminate the heater which was unnecessary so far. (T.M.)

  12. Public debate on radioactive wastes

    International Nuclear Information System (INIS)

    2005-01-01

    The definition and implementation of safe and perennial solutions for the management of radioactive wastes is a necessity from the point of view of both the nuclear industrialists and the public authorities, but also of the overall French citizens. For the low- or medium-level or short living radioactive wastes, some solutions have been defined are are already implemented. On the other hand, no decision has been taken so far for the long living medium to high-level radioactive wastes. Researches are in progress in this domain according to 3 ways of research defined by the law from December 30, 1991: separation-transmutation, disposal in deep underground, and long duration surface or sub-surface storage. This paper presents in a digest way, the principle, the results obtained so far, and the perspectives of each of the three solutions under study. (J.S.)

  13. [Mercury Distribution Characteristics and Atmospheric Mercury Emission Factors of Typical Waste Incineration Plants in Chongqing].

    Science.gov (United States)

    Duan, Zhen-ya; Su, Hai-tao; Wang, Feng-yang; Zhang, Lei; Wang, Shu-xiao; Yu, Bin

    2016-02-15

    Waste incineration is one of the important atmospheric mercury emission sources. The aim of this article is to explore the atmospheric mercury pollution level of waste incineration industry from Chongqing. This study investigated the mercury emissions from a municipal solid waste incineration plant and a medical waste incineration plant in Chongqing. The exhaust gas samples in these two incineration plants were obtained using USA EPA 30B method. The mercury concentrations in the fly ash and bottom ash samples were analyzed. The results indicated that the mercury concentrations of the municipal solid waste and medical waste incineration plant in Chongqing were (26.4 +/- 22.7) microg x m(-3) and (3.1 +/- 0.8) microg x m(-3) in exhaust gas respectively, (5279.2 +/- 798.0) microg x kg(-1) and (11,709.5 +/- 460.5) microg x kg(-1) in fly ash respectively. Besides, the distribution proportions of the mercury content from municipal solid waste and medical waste in exhaust gas, fly ash, and bottom ash were 34.0%, 65.3%, 0.7% and 32.3%, 67.5%, 0.2% respectively; The mercury removal efficiencies of municipal solid waste and medical waste incineration plants were 66.0% and 67.7% respectively. The atmospheric mercury emission factors of municipal solid waste and medical waste incineration plants were (126.7 +/- 109.0) microg x kg(-1) and (46.5 +/- 12.0) microg x kg(-1) respectively. Compared with domestic municipal solid waste incineration plants in the Pearl River Delta region, the atmospheric mercury emission factor of municipal solid waste incineration plant in Chongqing was lower.

  14. Management of Radioactive Wastes in Developing Countries

    International Nuclear Information System (INIS)

    Abdel Ghani, A.H.

    1999-01-01

    The management of radioactive wastes is one area of increasing interest especially in developing countries having more and more activities in the application of radioisotopes in medicine, research and industry. For a better understanding of radioactive waste management in developing countries this work will discuss the following items:Classification of countries with respect to waste management programs. Principal Radionuclides used in medicine, biological research and others and the range of radioactivity commonly used. Estimation of radioactive waste volumes and activities. Management of liquid wastes Collection. Treatment. Management of small volumes of organic liquid waste. Collection Treatment. Packaging and storage of radioactive wastes

  15. Environmental impacts of residual Municipal Solid Waste incineration: A comparison of 110 French incinerators using a life cycle approach

    Energy Technology Data Exchange (ETDEWEB)

    Beylot, Antoine, E-mail: a.beylot@brgm.fr; Villeneuve, Jacques

    2013-12-15

    Highlights: • 110 French incinerators are compared with LCA based on plant-specific data. • Environmental impacts vary as a function of plants energy recovery and NO{sub x} emissions. • E.g. climate change impact ranges from −58 to 408 kg CO{sub 2}-eq/tonne of residual MSW. • Implications for LCA of waste management in a decision-making process are detailed. - Abstract: Incineration is the main option for residual Municipal Solid Waste treatment in France. This study compares the environmental performances of 110 French incinerators (i.e. 85% of the total number of plants currently in activity in France) in a Life Cycle Assessment perspective, considering 5 non-toxic impact categories: climate change, photochemical oxidant formation, particulate matter formation, terrestrial acidification and marine eutrophication. Mean, median and lower/upper impact potentials are determined considering the incineration of 1 tonne of French residual Municipal Solid Waste. The results highlight the relatively large variability of the impact potentials as a function of the plant technical performances. In particular, the climate change impact potential of the incineration of 1 tonne of waste ranges from a benefit of −58 kg CO{sub 2}-eq to a relatively large burden of 408 kg CO{sub 2}-eq, with 294 kg CO{sub 2}-eq as the average impact. Two main plant-specific parameters drive the impact potentials regarding the 5 non-toxic impact categories under study: the energy recovery and delivery rate and the NO{sub x} process-specific emissions. The variability of the impact potentials as a function of incinerator characteristics therefore calls for the use of site-specific data when required by the LCA goal and scope definition phase, in particular when the study focuses on a specific incinerator or on a local waste management plan, and when these data are available.

  16. Radioactive waste repository study

    International Nuclear Information System (INIS)

    1978-11-01

    This is the first part of a report of a preliminary study for Atomic Energy of Canada Limited. It considers the requirements for an underground waste repository for the disposal of wastes produced by the Canadian Nuclear Fuel Program. The following topics are discussed with reference to the repository: 1) underground layout, 2) cost estimates, 3) waste handling, 4) retrievability, decommissioning, sealing and monitoring, and 5) research and design engineering requirements. (author)

  17. Radioactive waste integrated management system

    International Nuclear Information System (INIS)

    Song, D. Y.; Choi, S. S.; Han, B. S.

    2003-01-01

    In this paper, we present an integrated management system for radioactive waste, which can keep watch on the whole transporting process of each drum from nuclear power plant temporary storage house to radioactive waste storage house remotely. Our approach use RFID(Radio Frequency Identification) system, which can recognize the data information without touch, GSP system, which can calculate the current position precisely using the accurate time and distance measured from satellites, and the spread spectrum technology CDMA, which is widely used in the area of mobile communication

  18. 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

  19. Radioactive waste removing device

    International Nuclear Information System (INIS)

    Sakai, Takuhiko.

    1982-01-01

    Purpose: To cleanup primary coolants for LMFBR type reactors by magnetically generating a high speed rotational flow in the flow of liquid metal, and adsorbing radioactive corrosion products and fission products onto capturing material of a complicated shape. Constitution: Three-phase AC coils for generating a rotational magnetic field are provided to the outside of a container through which liquid sodium is passed to thereby generate a high speed rotational stream in the liquid sodium flowing into the container. A radioactive substance capturing material made of a metal plate such as of nickel and stainless steel in the corrugated shape with shape edges is secured within a flow channel. Magnetic field at a great slope is generated in the flow channel by the capturing material to adsorb radioactive corrosion products and fission products present in the liquid sodium onto the capturing material and removing therefrom. This enables to capture the ferri-magnetic impurities by adsorption. (Moriyama, K.)

  20. Exergy analysis of aluminum recovery from municipal solid waste incineration

    DEFF Research Database (Denmark)

    Vyzinkarova, Dana; Allegrini, Elisa; Laner, D.

    Two main challenges, associated with the recovery of aluminum from state-of-the-art municipal solid waste (MSW) incineration plants, are yield as well as quality losses of metallic aluminum due to particle surface oxidation and presence of impurities. Yet, in the framework of life cycle assessment...... (LCA) a direct measure for expressing the quality of primary and secondary resources is missing. In view of a possible solution, exergy has been proposed as a concept to evaluate the quality of resources. In this paper, LCA and exergy analyses for two waste treatment approaches are conducted...... in parallel to each other, with a goal to evaluate the added value of exergy for LCA studies in the resource recovery context. The functional unit is the treatment of 1 ton MSW. Two alternative approaches for recovering aluminum from MSW directed to a waste-to-energy plant are considered. A) MSW is treated...

  1. A Comparison of Organic Emissions from Hazardous Waste Incinerators Versus the 1990 Toxics Release Inventory Air Releases

    Science.gov (United States)

    Incineration is often the preferred technology for disposing of hazardous waste and remediating Superfund sites. The effective implementation of this technology is frequently impeded by strong public opposition to hazardous waste incineration (HWI). One of the reasons cited for t...

  2. Bioprocessing of low-level radioactive and mixed hazard wastes

    International Nuclear Information System (INIS)

    Stoner, D.L.

    1990-01-01

    Biologically-based treatment technologies are currently being developed at the Idaho National Engineering Laboratory (INEL) to aid in volume reduction and/or reclassification of low-level radioactive and mixed hazardous wastes prior to processing for disposal. The approaches taken to treat low-level radioactive and mixed wastes will reflect the physical (e.g., liquid, solid, slurry) and chemical (inorganic and/or organic) nature of the waste material being processed. Bioprocessing utilizes the diverse metabolic and biochemical characteristics of microorganisms. The application of bioadsorption and bioflocculation to reduce the volume of low-level radioactive waste are strategies comparable to the use of ion-exchange resins and coagulants that are currently used in waste reduction processes. Mixed hazardous waste would require organic as well as radionuclide treatment processes. Biodegradation of organic wastes or bioemulsification could be used in conjunction with radioisotope bioadsorption methods to treat mixed hazardous radioactive wastes. The degradation of the organic constituents of mixed wastes can be considered an alternative to incineration, while the use of bioemulsification may simply be used as a means to separate inorganic and organics to enable reclassification of wastes. The proposed technology base for the biological treatment of low-level radioactive and mixed hazardous waste has been established. Biodegradation of a variety of organic compounds that are typically found in mixed hazardous wastes has been demonstrated, degradative pathways determined and the nutritional requirements of the microorganisms are understood. Accumulation, adsorption and concentration of heavy and transition metal species and transuranics by microorganisms is widely recognized. Work at the INEL focuses on the application of demonstrated microbial transformations to process development

  3. Radioactive waste management alternatives

    International Nuclear Information System (INIS)

    Baranowski, F.P.

    1976-01-01

    The information in the US ERDA ''Technical Alternatives Document'' is summarized. The first two points show that waste treatment, interim storage and transportation technologies for all wastes are currently available. Third, an assessment of integrated waste management systems is needed. One such assessment will be provided in our expanded waste management environmental statement currently planned for release in about one year. Fourth, geologies expected to be suitable for final geologic storage are known. Fifth, repository system assessment methods, that is a means to determine and assess the acceptability of a terminal storage facility for nonretrievable storage, must and will be prepared. Sixth, alternatives to geologic storage are not now available. Seventh, waste quantities and characteristics are sensitive to technologies and fuel-cycle modes, and therefore an assessment of these technologies and modes is important. Eighth, and most important, it is felt that the LWR fuel cycle can be closed with current technologies

  4. Radioactive Waste management - v. 1

    International Nuclear Information System (INIS)

    1987-01-01

    The state of the art for each stage and activities correlated to the nuclear fuel cycle, describing the activities of main countries of the world in this area, is presented. In this volume, the principles which described the several sources of radioactive wastes from nuclear industry, the standardization of waste categories, the strategies adopted for treatment and disposal, the repository types and the practices and proposals of several countries in this field, are presented. (M.C.K.) [pt

  5. Disposal of radioactive waste material

    International Nuclear Information System (INIS)

    Cairns, W.J.; Burton, W.R.

    1984-01-01

    A method of disposal of radioactive waste consists in disposing the waste in trenches dredged in the sea bed beneath shallow coastal waters. Advantageously selection of the sites for the trenches is governed by the ability of the trenches naturally to fill with silt after disposal. Furthermore, this natural filling can be supplemented by physical filling of the trenches with a blend of absorber for radionuclides and natural boulders. (author)

  6. The limitation of radioactive wastes from hospitals

    International Nuclear Information System (INIS)

    Schuurman, B.; IJtsma, D.; Zwigt, A.

    1987-01-01

    Interviews were made with radiation experts working at hospitals about the treatment and limiting of radioactive wastes. The authors conclude that with the aid of hospital personnel a decrease of the volume of radioactive waste is possible. 25 refs

  7. Environmental impact assessment of the incineration of municipal solid waste with auxiliary coal in China

    DEFF Research Database (Denmark)

    Zhao, Yan; Xing, Wei; Lu, Wenjing

    2012-01-01

    The environmental impacts of waste incineration with auxiliary coal were investigated using the life-cycle-based software, EASEWASTE, based on the municipal solid waste (MSW) management system in Shuozhou City. In the current system, MSW is collected, transported, and incinerated with 250kg of co...... political reduction targets. Results indicate that heavy metal and acidic gas emissions should be given more attention in waste incineration. This study provides scientific support for the management of MSW systems dominated by incineration with auxiliary coal in China.......The environmental impacts of waste incineration with auxiliary coal were investigated using the life-cycle-based software, EASEWASTE, based on the municipal solid waste (MSW) management system in Shuozhou City. In the current system, MSW is collected, transported, and incinerated with 250kg of coal...... per ton of waste. Based on observed environmental impacts of incineration, fossil CO2 and heavy metals were primary contributors to global warming and ecotoxicity in soil, respectively. Compared with incinerators using excess coal, incineration with adequate coal presents significant benefits...

  8. Monitoring of radioactive nuclides in incinerator fly ash and adsorption of Cs in simulated and actual eluate of the fly ash onto clay and soil

    International Nuclear Information System (INIS)

    Iwahana, Yuki; Koike, Yuya; Nakamura, Toshihiro

    2014-01-01

    Radioactive nuclides in the incinerator fly ash of municipal solid waste was determined and monitored. For leaching radioactive Cs from incinerating fly ash in reclaimed land, a modified No. 13 elution test and adsorption with stable Cs onto andosol were performed. The activity concentration of radioactive nuclides in incinerator fly ash was constant within the range of the activity concentration before the accident at Fukushima Daiichi Nuclear Power Station. The 134 Cs/ 137 Cs activity concentration ratio was almost equal to 1, corresponding to 137 Cs existing in environment before the accident. 40% of 137 Cs in incinerator fly ash eluted with the modified No. 13 elution test, and adsorption ratio of Cs + onto the andosol showed 90% as being the primary concentration was equal to or more than 5000 μg L −1 . In addition, the desorption results used for 5 types of solvent showed that desorption ratio of adsorbed Cs + from the soil was 3.6% at the maximum. Hence, it is anticipated that using a soil that is similar in composition to the andosol suppresses the leaching out of radioactive Cs from reclaimed land. (author)

  9. Geomechanical problems in study of radioactive wastes disposal

    International Nuclear Information System (INIS)

    Feng Yixing

    1987-01-01

    Methods for both low-intermediate level radioactive wastes disposal and high level radioactive waste disposal were introduced briefly. Geomechanical problems in radioactive wastes disposal were discussed. Some suggestions were proposed for the radioactive wastes disposal in China

  10. Dukovany radioactive waste disposal facility

    International Nuclear Information System (INIS)

    Horyna, J.

    1998-01-01

    The most significant source of radioactive wastes in the Czech Republic is the operation of nuclear power plant. The original NPP design included only storage of concentrates and unsorted solid wastes in the nuclear power plant. Our concept of waste management from nuclear power plant operation has been gradually developed and it consists of solidification of radioactive concentrates, volume reduction of solid wastes by compressing and disposal of conditioned wastes in surface concrete vaults. The most significant part of the arising waste was assumed to be evaporator concentrates. in the design of the NPP it has been assumed that up to 1% of fuel element cladding may fail. With a sufficient number of natural and man-made barriers, the release of radioactive material will be limited and delayed, its migration retarded and its concentration sufficiently diluted to assure that the impact will remain in prescribed levels. Initial site selection studies started in the later seventies taking into account social, economic conditions and requirements for the protection of nature. After performed area surveys, the site near the constructed NPP Dukovany has been chosen. Safety assessment of Dukovany repository has been based on 3 critical scenarios: -groundwater transport to the nearest water supply, -Intrusion after end of institutional control, -dwelling on the site after end of institutional control. Compartment models based on the scenarios described above were formulated to estimate committed effective equivalent dose due to different exposure ways. (author)

  11. Nuclear power and radioactive waste

    International Nuclear Information System (INIS)

    Grimston, M.

    1991-03-01

    The gap between the relative perceptions in the area of nuclear waste is wide. The broad view of the industry is that the disposal of nuclear waste is not a serious technical problem, and that solutions are already available to provide safe disposal of all our waste. The broad view of those who oppose the industry is that radioactive waste is so unpleasant, and will remain lethal for so long, that no acceptable policy will ever be developed, and so production of such waste (except, oddly, the significant amounts arising from uses of radioactive materials in medicine, agriculture, industrial safety research, etc) should stop immediately. This booklet will not attempt to describe in great detail the technicalities of the United Kingdom nuclear industry's current approach to radioactive waste: such issues are described in detail in other publications, especially those by Nirex. It is our intention to outline some of the main issues involved, and to associate these issues with the divergence in perceptions of various parties. (author)

  12. Long term plant biomonitoring in the vicinity of waste incinerators in The Netherlands

    NARCIS (Netherlands)

    Dijk, van C.J.; Doorn, van W.; Alfen, van A.J.

    2015-01-01

    Since the mid-nineties new waste incineration plants have come into operation in the Netherlands. Burning of waste can result in the emission of potentially toxic compounds. Although the incineration plants must comply with strict conditions concerning emission control, public concern on the

  13. Characterization of deposits and their influence on corrosion in waste incineration plants in Denmark

    DEFF Research Database (Denmark)

    Montgomery, Melanie; Larsen, OH

    2001-01-01

    A program has been initiated in Denmark to investigate the aggressive environment in various waste incineration plants. The results described are the preliminary results from one waste incineration plant. Deposits and corrosion products have been removed from various locations in the boiler...

  14. Management of hospital radioactive wastes

    International Nuclear Information System (INIS)

    Houy, J.C.; Rimbert, J.C.; Bouvet, C.; Laugle, S.

    1997-01-01

    The hospital radioactive wastes are of three types: solid, liquid and gaseous. Prior to final evacuation all these wastes are checked by a detector the threshold of which is lower than the standard. This system allows detecting activities very low under the daily recommended threshold of 37 kBq (1μ Ci), for the group II. In metabolic radiotherapy the unsealed sources of iodine 131 will form mainly the wastes arising from the rooms contaminated by the patient himself. In this service anything touching the patient's room most by systematically checked. All the rooms are provided with toilette with two compartments, one connected traditionally to the sewerage system for faeces and the other coupled to tanks for urine storing. The filled reservoirs waits around 10 month span prior to being emptied, after checking, into the sewerage system. The volume activity most be lower than 7 Bq per liter (standard). For the hot labs, injection room and in-vitro lab, the liquid waste retrieved from dedicated stainless sinks are stored in storage tanks and will waits for 2 years before evacuation. The undies coming from the metabolic radiotherapy service are possible contaminated by the patient sheets, pillow cases, etc. These undies freshly contaminated may be contaminating if the contamination is non fixated. All the undies coming from this service are checked like all the wastes by means of the fixed detector. For the solid wastes two evacuation channels are possible: the urban garbage repository for household wastes and the Brest waste repository for hospital wastes. For the liquid waste arising for urines, used washing water, etc, the evacuation will be done towards city sewerage system after storing or dilution. Concerning the liquid wastes presenting chemical risks, they will be evacuated in cans by NETRA. Concerning the gaseous wastes, trapped on active carbon filters, they will be handled like solid wastes and will be directed to the waste repository of Brest. The other

  15. Radioactive waste management regulatory framework in Mexico

    International Nuclear Information System (INIS)

    Barcenas, M.; Mejia, M.

    2001-01-01

    The purpose of this paper is to present an overview of the current regulatory framework concerning the radioactive waste management in Mexico. It is intended to show regulatory historical antecedents, the legal responsibilities assigned to institutions involved in the radioactive waste management, the sources of radioactive waste, and the development and preparation of national standards for fulfilling the legal framework for low level radioactive waste. It is at present the most important matter to be resolved. (author)

  16. State planning council on radioactive waste management

    International Nuclear Information System (INIS)

    Anon.

    1981-01-01

    This report contains the findings and policy resolutions resulting from the Council's meeting. The texts of policy resolutions on radioactive waste transport, spent fuel storage, and high-level radioactive waste disposal test facilities are included. A draft legislation statement is presented in support of the establishment of a clear national policy for high-level radioactive waste disposal and management. A status report containing a summary of regional activities in the field of low-level radioactive wastes is presented

  17. Comparison of slagging pyrolysis and molten salt incinerators for treating TRU waste at the INEL

    International Nuclear Information System (INIS)

    1977-11-01

    For the comparison, it is assumed that the waste product is required to meet the acceptance criteria of the Waste Isolation Pilot Plant, i.e., low leachability. Slagging pyrolysis incinerates combustible waste and melts noncombustible waste; the resulting slag forms a glass of low leachability. In the molten salt incinerator, combustion occurs at low temperatures with no accumulation of explosive gases, but the waste must have been previously sorted into combustibles and noncombustibles and then shredded. The economics, safety, and technical features are compared. Advantages, disadvantages, and areas of technical uncertainty of the two systems are listed. Development costs and schedules for the two types of incinerators are discussed

  18. Cementation of liquid radioactive waste

    International Nuclear Information System (INIS)

    Efremenkov, V.

    2004-01-01

    The cementation methods for immobilisation of radioactive wastes are discussed in terms of methodology, chemistry and properties of the different types of cements as well as the worldwide experience in this field. Two facilities for cementation - DEWA and MOWA - are described in details

  19. High-level radioactive wastes

    International Nuclear Information System (INIS)

    Grissom, M.C.

    1982-10-01

    This bibliography contains 812 citations on high-level radioactive wastes included in the Department of Energy's Energy Data Base from January 1981 through July 1982. These citations are to research reports, journal articles, books, patents, theses, and conference papers from worldwide sources. Five indexes are provided: Corporate Author, Personal Author, Subject, Contract Number, and Report Number

  20. Chemical decontamination of radioactive waste

    International Nuclear Information System (INIS)

    Mohamed, H.I.

    2006-01-01

    Radioactive wastes are generated in a number of different kinds of facilities and arise in a wide range of concentrations of radioactive materials and in a variety of physical and chemical forms. There is also a variety of alternatives for treatment and conditioning of the wastes prior disposal. The importance of treatment of radioactive waste for protection of human and environment has long been recognized and considerable experience has gained in this field. Generally, the methods used for treatment of radioactive wastes can be classified into three type's biological, physical and chemical treatment this physical treatment it gives good result than biological treatment. Chemical treatment is fewer hazards and gives good result compared with biological and physical treatments. Chemical treatment is fewer hazards and gives good result compared with biological and physical treatments. In chemical treatment there are different procedures, solvent extraction, ion exchange, electro dialysis but solvent extraction is best one because high purity can be optioned on the other hand the disadvantage that it is expensive. Beside the solvent extraction technique one can be used is ion exchange which gives reasonable result, but requires pretreatment that to avoid in closing of column by colloidal and large species. Electro dialysis technique gives quite result but less than solvent extraction and ion exchange technique the advantage is a cheep.(Author)

  1. Safe disposal of radioactive wastes

    International Nuclear Information System (INIS)

    Hooker, P.; Metcalfe, R.; Milodowski, T.; Holliday, D.

    1997-01-01

    A high degree of international cooperation has characterized the two studies reported here which aim to address whether radioactive waste can be disposed of safely. Using hydrogeochemical and mineralogical surveying techniques earth scientists from the British Geological Survey have sought to identify and characterise suitable disposal sites. Aspects of the studies are explored emphasising their cooperative nature. (UK)

  2. Experience in radioactive waste management of research centre-CIAE

    International Nuclear Information System (INIS)

    Luo Shanggeng

    2001-01-01

    China Institute of Atomic Energy (CIAE) is the birthplace of China nuclear science and technology and the important base for nuclear science and technology implementing pioneering, basic and comprehensive studies. The major tasks and activities of CIAE are: (1) Fundamental research of nuclear science and technology; (2) Research and development of advanced nuclear energy; and (3) Application of nuclear technology. CIAE is equipped with three research reactors (15MW heavy water reactor, 3.5MW light water swimming pool reactor, 27kW neutron source reactor), four zero-power facilities, eleven accelerators, hot cells and a lot of glove boxes which produce various kinds of radioactive wastes. CIAE pays great attention to the safe management of radioactive waste. Many measurements were and are adopted. CIAE carries out the national policy of radioactive waste management and the international fundamental principles of radioactive waste management. To protect human body and environment both now and future generation minimizes the releasing amounts and activity, minimizes the solidified wastes to be disposed of. The principles of 'controlled generation, categorized collection, volume-reduction immobilization, reliable package, in-situ storage, safe transportation and disposal' are followed in managing LLW and ILW. The liquid wastes are separately treated by precipitation, evaporation, ion exchange or adsorption by organic or inorganic materials. The spent organic solvents are treated by incineration at a special incinerator. The low level radioactive gases and liquids can be discharged into the environment only when they are clean-up and permissible level is achieved. Such discharge is controlled by two factors: total discharge amount and specific activity. The solid wastes are separately collected in site according to their physical properties and specific activity. The storage waste is retrievable designed. The spent/sealed radiation sources are collected and stored with

  3. Enviromental impact of a hospital waste incineration plant in Krakow (Poland).

    Science.gov (United States)

    Gielar, Agnieszka; Helios-Rybicka, Edeltrauda

    2013-07-01

    The environmental impact of a hospital waste incineration plant in Krakow was investigated. The objective of this study was to assess the degree of environmental effect of the secondary solid waste generated during the incineration process of medical waste. The analysis of pollution of the air emissions and leaching test of ashes and slag were carried out. The obtained results allowed us to conclude that (i) the hospital waste incineration plant significantly solves the problems of medical waste treatment in Krakow; (ii) the detected contaminant concentrations were generally lower than the permissible values; (iii) the generated ashes and slag contained considerable concentrations of heavy metals, mainly zinc, and chloride and sulfate anions. Ashes and slag constituted 10-15% of the mass of incinerated wastes; they are more harmful for the environment when compared with untreated waste, and after solidification they can be deposited in the hazardous waste disposal.

  4. Energy potential of municipal solid waste incineration in urban areas of China.

    NARCIS (Netherlands)

    Zheng, Ling

    2006-01-01

    This study aims to evaluate the energy potential of municipal solid waste (MSW) incineration in Chinese cities from 1996 to 2020. In China, with improving the standard of living recently, the extreme increase of the municipal solid waste generation (MSWG)

  5. Coal combustion ashes: A radioactive Waste?

    International Nuclear Information System (INIS)

    Michetti, F.P.; Tocci, M.

    1992-01-01

    The radioactive substances naturally hold in fossil fuels, such as Uranium and Thorium, after the combustion, are subjected to an increase of concentration in the residual combustion products as flying ashes or as firebox ashes. A significant percentage of the waste should be classified as radioactive waste, while the political strategies seems to be setted to declassify it as non-radioactive waste. (Author)

  6. National Syrian Program for Radioactive Waste Management

    International Nuclear Information System (INIS)

    Othman, I.; Takriti, S.

    2009-06-01

    A national plan for radioactive waste management has been presented. It includes identifying, transport, recording, classifying, processing and disposal. It is an important reference for radioactive waste management for those dealing with radioactive waste, and presents a complete protection to environemnt and people. (author)

  7. Radioactive waste disposal in Greece

    International Nuclear Information System (INIS)

    Radioactive waste is any material which contains or is contaminated by radionuclides and for which no use is foreseen. According to this definition, a large number of sources, solid, liquid and gaseous, within the Greek territory can be - and, actually, is - declared as waste. The types of such solid sources are presented. It is estimated that these solid sources represent above 90% of all disused sources in Greece. The medical sources of Co-60 and Cs-137 were used in Teletherapy units, while the Ra-226 ones are in the form of needles or tubes used in Brachytherapy. All the industrial sources had been used for measuring moisture, density, thickness, elementary composition, etc. The small sources used by research labs are mainly in the form of discs. The above sources had been imported a long time ago (even 3 decades ago), had been used, and then stored as useless inside the user's premises. Since 1990 all the users of radioactive sources are obliged to return them back to the suppliers when they are no longer in use. In fact, no source is imported unless there is a written declaration of acceptance by its producer. A project concerning the export of all disused sealed sources is in progress. For every source a certificate will be issued, proper container will be purchased and all the necessary documents will be prepared so that it can be transported for final disposal or reuse in a foreign repository facility. Apart from this 'old generated' waste, unsealed radionuclides have always been used in nuclear medicine producing waste. The above radionuclides are used either in vivo (injected or ingested by patients) or in vitro (labeling of blood and other cells). Both uses leave some radioactive waste inside the needles, the tubes, or other material. Since 1991, Greece has a well-established regulatory system for controlling waste from nuclear medicine labs, so that disposing such solid or liquid waste does no harm to the environment. A revision of these regulations has

  8. 40 CFR 60.1920 - What are the emission limits for air curtain incinerators that burn 100 percent yard waste?

    Science.gov (United States)

    2010-07-01

    ... curtain incinerators that burn 100 percent yard waste? 60.1920 Section 60.1920 Protection of Environment... or Before August 30, 1999 Model Rule-Air Curtain Incinerators That Burn 100 Percent Yard Waste § 60.1920 What are the emission limits for air curtain incinerators that burn 100 percent yard waste? If...

  9. 40 CFR 60.1925 - How must I monitor opacity for air curtain incinerators that burn 100 percent yard waste?

    Science.gov (United States)

    2010-07-01

    ... curtain incinerators that burn 100 percent yard waste? 60.1925 Section 60.1925 Protection of Environment... or Before August 30, 1999 Model Rule-Air Curtain Incinerators That Burn 100 Percent Yard Waste § 60.1925 How must I monitor opacity for air curtain incinerators that burn 100 percent yard waste? (a) Use...

  10. 40 CFR 60.1450 - How must I monitor opacity for air curtain incinerators that burn 100 percent yard waste?

    Science.gov (United States)

    2010-07-01

    ... curtain incinerators that burn 100 percent yard waste? 60.1450 Section 60.1450 Protection of Environment... Air Curtain Incinerators That Burn 100 Percent Yard Waste § 60.1450 How must I monitor opacity for air curtain incinerators that burn 100 percent yard waste? (a) Use EPA Reference Method 9 in appendix A of...

  11. Apparatus for fixing radioactive waste

    International Nuclear Information System (INIS)

    Murphy, J.D.; Pirro, J. Jr.; Lawrence, M.; Wisla, S.F.

    1975-01-01

    Fixing radioactive waste is disclosed in which the waste is collected as a slurry in aqueous media in a metering tank located within the nuclear facilities. Collection of waste is continued from time to time until a sufficient quantity of material to make up a full shipment to a burial ground has been collected. The slurry is then cast in shipping containers for shipment to a burial ground or the like by metering through a mixer into which fixing materials are simultaneously metered at a rate to yield the desired proportions of materials. (U.S.)

  12. Design of municipal solid waste incinerator for use in semi-arid regions

    Directory of Open Access Journals (Sweden)

    M. B. Oumarou

    2012-08-01

    Full Text Available The paper treats the design of a municipal solid waste incinerator suited to the semiarid regions with northern Nigeria and Niger Republic in West Africa as the study area. Proximate and ultimate analyses results from the solid waste were used as basis for calculations, using standard formulas and correlations. The calorific value of the solid waste samples in the study area is not high enough to sustain an incineration process and it ranges from 5.024 MJ/kg to 5.867 MJ/kg. For these types of low calorific value fuels, the parallel flow concept was found to be the appropriate type of incinerator. The solid waste to be fed in the incinerator needs to be mixed with 50% of supplementary fuel in the form of readily available bagasse to make it up to the required lower calorific value. Major characteristics of the designed municipal solid waste incinerator were: total volume of incinerator chamber: 82.5 m3, length of the incinerator bed: 11m; width of the incinerator bed: 3m and height of the incinerator chamber: 2.5 m, while the suitable adiabatic flame temperature was found to be 1,587 K.

  13. Radioactive waste management: Spanish experiences

    International Nuclear Information System (INIS)

    Beceiro, A. R.

    1996-01-01

    Radioactive waste generation began in Spain during the 1950's, in association with the first applications of radioactive isotopes in industry, medicine and research. Spain's first nuclear power plant began its operations in 1968. At present, there are in operation some one thousand installations possessing the administrative authorization required to use radioactive isotopes (small producers), nine nuclear groups and a tenth is now entering the dismantling phase. There are also activities and installations pertaining to the front end of the nuclear fuel cycle (mining, milling and the manufacturing of fuel elements). Until 1985, the research center Junta de Energia Nuclear (now CIEMAT) rendered radioactive waste removal, and subsequent conditioning and temporary storage services to the small producers. Since the beginning of their operations the nuclear power plants and fuel cycle facilities have had the capacity to condition and temporarily store their own radioactive wastes. ENRESA (Empresa Nacional de Residuos Radiactivos, S. A.) began its operations in the second half of 1985. It is a state-owned company created by the Government in accordance with a previous parliamentary resolution and commissioned to establish a system for management of such wastes throughout Spain, being in charge also of the dismantling of nuclear power plants and other major installations at the end of their operating lifetimes. Possibly the most outstanding characteristic of ENRESA's evolution over these last seven years has been the need to bring about a compromise between solving the most immediate and pressing day-to-day problems of operation (the first wastes were removed at the beginning of 1986) and establishing the basic organization, resources, technology and installations required for ENRESA to operate efficiently in the long term. (author)

  14. Optimized Metal Recovery from Fly Ash from Municipal Solid Waste Incineration

    OpenAIRE

    Weibel, Gisela

    2017-01-01

    Switzerland plays a pioneering role in sustainable waste management with a long tradition of waste incineration and the prohibition to landfill unburnt municipal solid waste since 2000. In recent years, the focus has been laid on further reduction of pollutants from incineration residues because the revised Swiss Waste Ordinance prescribes the recovery of metals from fly ash starting in 2021. Fly ash collected in the heat recovery section and the electrostatic precipitator contains high conce...

  15. Radioactive wastes: underground laboratories implantation

    International Nuclear Information System (INIS)

    Bataille, Ch.

    1997-01-01

    This article studies the situation of radioactive waste management, more especially the possible storage in deep laboratories. In front of the reaction of public opinion relative to the nuclear waste question, it was essential to begin by a study on the notions of liability, transparence and democracy. At the beginning, it was a matter of underground researches with a view to doing an eventual storage of high level radioactive wastes. The Parliament had to define, through the law, a behaviour able to come to the fore for anybody. A behaviour which won recognition from authorities, from scientists, from industrial people, which guarantees the rights of populations confronted to a problem whom they were not informed, on which they received only few explanations. (N.C.)

  16. Ultimate disposal of radioactive wastes

    International Nuclear Information System (INIS)

    Roethemeyer, H.

    1991-01-01

    The activities developed by the Federal Institution of Physical Engineering PTB and by the Federal Office for Radiation Protection (BfS) concentrated, among others, on work to implement ultimate storage facilities for radioactive wastes. The book illuminates this development from site designation to the preliminary evaluation of the Gorleben salt dome, to the preparation of planning documents proving that the Konrad ore mine is suitable for a repository. The paper shows the legal provisions involved; research and development tasks; collection of radioactive wastes ready for ultimate disposal; safety analysis in the commissioning and post-operational stages, and product control. The historical development of waste management in the Federal Republic of Germany and international cooperation in this area are outlined. (DG) [de

  17. The persistent pollutants emission from medical waste incineration in China

    International Nuclear Information System (INIS)

    Yan, Mi; Li, Xiao-Dong; Lu, Sheng-Yong; Yan, Jian-Hua

    2010-01-01

    The huge amount of medical waste (MW) has caused a tough challenge to environment protection, for its serious infectious feature. At present, the incineration is the priority and main technology option for MW disposal in China. However, the medical waste incineration (MWI) is considered the major source of persistent organic pollutants (POPs), especially PCDD/Fs. In order to get an overall information of pollutants emission from MWI, a series study were conducted, involved in the generation and the components content of MW in China, the fingerprint of PCDD/Fs emission from MWI, POPs (PCDD/Fs, PCBs and HxCBz) concentration in residue ash. It is estimated that the generation of MW was 897,034 tons in 2008, plastic and rubber accounted for 24.5% of the MW weight. PCDD/Fs emission could be divided into two main groups according the fingerprint, and the ratio of PCDFs to PCDDs was mostly over 1.5. The TEQ of PCDD/Fs was over 30 times than WHO-TEQ of PCBs, and the TEQ of PCDD/Fs accounted for about 65% of the total output of PCDD/Fs in line with the UNEP default emission factors for MWI (Class 3, 63.7%). (author)

  18. Treatment and conditioning of historical radioactive waste

    International Nuclear Information System (INIS)

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

    2009-01-01

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

  19. The management of radioactive wastes in Canada

    International Nuclear Information System (INIS)

    1979-01-01

    Ten papers are presented, dealing with the management and environmental impact of radioactive wastes, environmental considerations related to uranium mining and milling, the management of uranium refining wastes, reactor waste management, proposals for the disposal of low- and intermediate-level wastes, disposal of nuclear fuel wastes, federal government policy on radioactive waste management, licensing requirements, environmental assessment, and internatioal cooperation in wast management. (LL)

  20. Radioactive Waste Management BasisApril 2006

    Energy Technology Data Exchange (ETDEWEB)

    Perkins, B K

    2011-08-31

    This Radioactive Waste Management Basis (RWMB) documents radioactive waste management practices adopted at Lawrence Livermore National Laboratory (LLNL) pursuant to Department of Energy (DOE) Order 435.1, Radioactive Waste Management. The purpose of this Radioactive Waste Management Basis is to describe the systematic approach for planning, executing, and evaluating the management of radioactive waste at LLNL. The implementation of this document will ensure that waste management activities at LLNL are conducted in compliance with the requirements of DOE Order 435.1, Radioactive Waste Management, and the Implementation Guide for DOE Manual 435.1-1, Radioactive Waste Management Manual. Technical justification is provided where methods for meeting the requirements of DOE Order 435.1 deviate from the DOE Manual 435.1-1 and Implementation Guide.

  1. Croatian radioactive waste management program: Current status

    International Nuclear Information System (INIS)

    Matanic, R.; Lebegner, J.

    2001-01-01

    Croatia has a responsibility to develop a radioactive waste management program partly due to co-ownership of Krsko nuclear power plant (Slovenia) and partly because of its own medical and industrial radioactive waste. The total amount of generated radioactive waste in Croatia is stored in temporary storages located at two national research institutes, while radioactive waste from Krsko remains in temporary storage on site. National power utility Hrvatska Elektroprivreda (HEP) and Hazardous Waste Management Agency (APO) coordinate the work regarding decommissioning, spent fuel management and low and intermediate level radioactive waste (LILRW) management in Croatia. Since the majority of work has been done in developing the LILRW management program, the paper focuses on this part of radioactive waste management. Issues of site selection, repository design, safety assessment and public acceptance are being discussed. A short description of the national radioactive waste management infrastructure has also been presented. (author)

  2. Operational testing of an electrically fired Pu-238 waste incineration process

    International Nuclear Information System (INIS)

    Holmes, H.; Charlesworth, D.L.

    1987-01-01

    Combustible 238 Pu waste is generated from normal operation and decommissioning activity at the Savannah River Plant and is being retrievably stored at the Plant. An electrically fired, two-stage incineration process is being developed to use incineration to process and recovery plutonium from the waste. A prototype incinerator is being tested to assess its capability to be remotely operated and maintained. Technical development is focusing on continuous feeding, vacuum control, remote operability and mechanical integrity of the system, ash burnout, and life of the belt in the primary incinerator chamber. 6 figs., 5 tabs

  3. Glass phase in municipal and industrial waste incineration bottom ashes

    Science.gov (United States)

    Rafał Kowalski, Piotr; Michalik, Marek

    2015-04-01

    Waste incineration bottom ash is a material with rising significance in waste streams in numerous countries. Even if some part of them is now used as raw materials the great amount is still landfilled. High temperature of thermal processes (>1000°C) together with fast cooling results in high content of glass in bottom ash. Its chemical composition is influenced by various factors like composition of raw wastes and used incineration technique. Most of bottom ash grains are composed of glass with large amount of mineral phases and also metallic constituents embedded into it. Glass susceptibility for alteration processes together with the characteristics of glass-based grains can bring environmental risk in time of improper or long term storage on landfill site. In this study bottom ashes from thermal treatment of municipal and industrial (including hazardous and medical) wastes were studied to determine glass content, its chemical composition with emphasis on metal content (especially potentially hazardous) and its relations to metallic components of grains. Samples were collected from two thermal treatment plants in Poland. Qualitative and quantitative X-ray diffraction (XRD) analyses were used for determination of mineral composition of studied samples. Rietveld method and addition of internal standard for determination of amorphous phase content were used. Scanning electron microscopy fitted with energy dispersive spectrometry (SEM-EDS) were used for detailed analysis of glass and glass associated phases. Waste incineration bottom ash is a multi-components material rich in amorphous phase. It dominant part is represented by Si-rich glass. It is a main component of bottom ash grains but it contains minerals present in large quantities and also various forms of metallic elements. Glass within grains is often porous and cracked. In bottom ashes from thermal treatment of municipal wastes ~ 45-55 wt % of amorphous phase were present, mostly in form of glass with high

  4. 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.

  5. Radioactive waste repository study

    International Nuclear Information System (INIS)

    1978-11-01

    This is the third part of a report of a preliminary study for AECL. It summarizes the topics considered in reports AECL-6188-1 and AECL-6188-2 as requirements for an undergpound repository for disposal of wastes produced by the Canadian Nuclear Fuel Program. (author)

  6. CO2 emission factors for waste incineration: Influence from source separation of recyclable materials

    DEFF Research Database (Denmark)

    Larsen, Anna Warberg; Astrup, Thomas

    2011-01-01

    CO2-loads from combustible waste are important inputs for national CO2 inventories and life-cycle assessments (LCA). CO2 emissions from waste incinerators are often expressed by emission factors in kg fossil CO2 emitted per GJ energy content of the waste. Various studies have shown considerable...... variations between emission factors for different incinerators, but the background for these variations has not been thoroughly examined. One important reason may be variations in collection of recyclable materials as source separation alters the composition of the residual waste incinerated. The objective...... of this study was to quantify the importance of source separation for determination of emission factors for incineration of residual household waste. This was done by mimicking various source separation scenarios and based on waste composition data calculating resulting emission factors for residual waste...

  7. The management of radioactive waste

    International Nuclear Information System (INIS)

    1991-08-01

    One of the key questions asked about nuclear power production is whether the industry can manage its waste safely and economically. Management must take account of long term safety, since some radioisotopes take a very long time to decay. This long term decay, which can take millions of years, focused attention for the first time on the need for some wastes to be managed for a very long time beyond the lifetime of those who generated the waste. This paper reviews what the different types of waste are, what the technical consensus is on the requirements for their safe management, and how the present state of knowledge developed. It describes how radioactive waste management is practised and planned within the fuel cycle and indicates the moderate scale of the costs in relation to the total cost of producing electricity. Country annexes give more information about what is being done in a selection of countries, in order to indicate how radioactive waste management is carried out in practice. (Author)

  8. Innocuous management of radioactive wastes

    International Nuclear Information System (INIS)

    Vargas, C.

    1997-01-01

    The relations between peaceful uses and bellicose uses of the nuclear energy are complexes in relation to international establishment of norms to control the destiny of the radioactive materials, above all in the context of the existing international legislation of respect to the autonomy of the countries, and in the determination of the institution or institutions upon the ones that would fall on. The nuclear safeguards of materials and the possibilities of performing their function. Important efforts have been done to unify, to help and to impose international measures on the behalf of an environmentally harmless processing of the radioactive wastes [es

  9. Geologic disposal of radioactive waste

    International Nuclear Information System (INIS)

    Tassoni, E.; Giulianelli, G.; Testa, L.; Bocola, W.; Girolimetti, G.; Giacani, G.

    1983-01-01

    The heat dissipation arising from the radioactive decay constitutes an important problem of the geological disposal of high level radioactive waste. A heating experiment was carried out in a clay quarry near Monterotondo (Rome), at 6.4 M in depth by means of a heater whose thermal power ranged from 250 to 500 watt. The experimental results fit well the theoretical values and show that the clay is a homogeneous and isotropic medium. The clay thermal conductivity, which was deducted by means of the ''curve fitting'' method, ranges from 0.015 to 0.017 watt/C

  10. Low level radioactive waste disposal/treatment technology overview: Savannah River site

    International Nuclear Information System (INIS)

    Sturm, H.F. Jr.

    1987-01-01

    The Savannah River Site will begin operation of several low-level waste disposal/treatment facilities during the next five years, including a new low-level solid waste disposal facility, a low-level liquid effluent treatment facility, and a low-level liquid waste solidification process. Closure of a radioactive hazardous waste burial ground will also be completed. Technical efforts directed toward waste volume reduction include compaction, incineration, waste avoidance, and clean waste segregation. This paper summarizes new technology being developed and implemented. 11 refs., 1 fig

  11. Development of new treatment process for low level radioactive waste at Tokai reprocessing plant

    International Nuclear Information System (INIS)

    Horiguchi, Kenichi; Sugaya, Atsushi; Saito, Yasuo; Tanaka, Kenji; Akutsu, Shigeru; Hirata, Toshiaki

    2009-01-01

    The Low-level radioactive Waste Treatment Facility (LWTF) was constructed at the Tokai Reprocessing Plant (TRP) and cold testing has been carried out since 2006. The waste which will be treated in the LWTF is combustible/incombustible solid waste and liquid waste. In the LWTF, the combustible/incombustible solid waste will be incinerated. The liquid waste will be treated by a radio-nuclides removal process and subsequently solidified in cement. This report describes the essential technologies of the LWTF and results of R and D work for the nitrate-ion decomposition technology for the liquid waste. (author)

  12. UK: Technical data for waste incineration background for modelling of product-specific emissions in a life cycle assessment context

    DEFF Research Database (Denmark)

    Hauschild, Michael Zwicky

    with the disposal of a product through waste incineration. Based on knowledge of the material composition of the product and the technology applied in the waste incineration plant, the model estimates input of energy and auxiliary materials required for the incineration of the product and generation of energy...... and output of emissions to the environment caused by the incineration. The work has been performed as part of the EUREKA project EUROENVIRON 1296: LCAGAPS, sponsored by the Danish Agency for Industry and Trade. This report presents a compilation of technical data on waste incineration that serve...... as background for a model of incineration processes to be used in the inventory analysis of LCA....

  13. Next generation of high-efficient waste incinerators. Final report

    Energy Technology Data Exchange (ETDEWEB)

    Jappe Frandsen, F.

    2010-11-15

    Modern society produces increasing amounts of combustible waste which may be utilized for heat and power production, at a lower emission of CO{sub 2}, e.g. by substituting a certain fraction of energy from fossil fuel-fired power stations. In 2007, 20.4 % of the district heating and 4.5 % of the power produced in Denmark came from thermal conversion of waste, and waste is a very important part of a future sustainable, and independent, Danish energy supply [Frandsen et al., 2009; Groen Energi, 2010]. In Denmark, approx 3.3 Mtons of waste was produced in 2005, an amount predicted to increase to 4.4 Mtons by the year 2030. According to Affald Danmark, 25 % of the current WtE plant capacity in Denmark is older than 20 years, which is usually considered as the technical and economical lifetime of WtE plants. Thus, there is a need for installation of a significant fraction of new waste incineration capacity, preferentially with an increased electrical efficiency, within the next few years. Compared to fossil fuels, waste is difficult to handle in terms of pre-treatment, combustion, and generation of reusable solid residues. In particular, the content of inorganic species (S, Cl, K, Na, etc.) is problematic, due to enhanced deposition and corrosion - especially at higher temperatures. This puts severe constraints on the electrical efficiency of grate-fired units utilizing waste, which seldom exceeds 26-27%, campared to 46-48 % for coal combustion in suspension. The key parameters when targeting higher electrical efficiency are the pressure and temperature in the steam cycle, which are limited by high-temperature corrosion, boiler- and combustion-technology. This report reviews some of the means that can be applied in order to increase the electrical efficiency in plants firing waste on a grate. (Author)

  14. Classification of Radioactive Waste. General Safety Guide

    International Nuclear Information System (INIS)

    2009-01-01

    This publication is a revision of an earlier Safety Guide of the same title issued in 1994. It recommends revised waste management strategies that reflect changes in practices and approaches since then. It sets out a classification system for the management of waste prior to disposal and for disposal, driven by long term safety considerations. It includes a number of schemes for classifying radioactive waste that can be used to assist with planning overall national approaches to radioactive waste management and to assist with operational management at facilities. Contents: 1. Introduction; 2. The radioactive waste classification scheme; Appendix: The classification of radioactive waste; Annex I: Evolution of IAEA standards on radioactive waste classification; Annex II: Methods of classification; Annex III: Origin and types of radioactive waste

  15. Vitrification of hazardous and radioactive wastes

    International Nuclear Information System (INIS)

    Bickford, D.F.; Schumacher, R.

    1995-01-01

    Vitrification offers many attractive waste stabilization options. Versatility of waste compositions, as well as the inherent durability of a glass waste form, have made vitrification the treatment of choice for high-level radioactive wastes. Adapting the technology to other hazardous and radioactive waste streams will provide an environmentally acceptable solution to many of the waste challenges that face the public today. This document reviews various types and technologies involved in vitrification

  16. Flaring versus thermal incineration of waste gases in the oil and gas industry

    International Nuclear Information System (INIS)

    Smolarski, G.M.

    1999-01-01

    The efficient combustion of waste gases at oil processing plants, battery or well sites is discussed. Several problem situations are examined, field test results are reviewed, and custom design systems are explained including modifications to systems to conserve fuel. It is shown that combustion of waste gases in fuel efficient thermal incinerators is a practical means of disposal, particularly for sour or toxic gas of low heating value. These gases contain noxious compounds that may cause odours or adverse health effects. Results of a field tests of a portable in-situ incinerator show that compared to flaring (to oxide waste gas), incineration is a more efficient form of waste management. Emission tests also prove the superior performance of incineration. The feasibility of incinerating oil storage tank vapours was also demonstrated. Tests were also conducted with a fuel-efficient Glycol Still Off-Gas Incinerator which was developed to control toxic waste emissions. Glycol dehydration removes water vapour from natural gas. The key compounds that are removed by glycol are aromatic hydrocarbons or BTEX compounds (benzene, toluene, ethylbenzene and xylene), and sulphur compounds. The main design considerations for any incinerator are temperature, turbulence and residence time. An incinerator exit temperature of 760 degrees C is generally needed to reduce sulphur compounds. 2 refs., 8 tabs., 7 figs

  17. 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.

  18. 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.

  19. Immobilization of hazardous and radioactive waste into glass structures

    International Nuclear Information System (INIS)

    Wicks, G.G.

    1997-01-01

    As a result of more than three decades of international research, glass has emerged as the material of choice for immobilization of a wide range of potentially hazardous radioactive and non-radioactive materials. The ability of glass structures to incorporate and then immobilize many different elements into durable, high integrity, waste glass products is a direct function of the unique random network structure of the glassy state. Every major country involved with long-term management of high-level radioactive waste (HLW) has either selected or is considering glass as the matrix of choice for immobilizing and ultimately, disposing of the potentially hazardous, high-level radioactive material. There are many reasons why glass is preferred. Among the most important considerations are the ability of glass structures to accommodate and immobilize the many different types of radionuclides present in HLW, and to produce a product that not only has excellent technical properties, but also possesses good processing features. Good processability allows the glass to be fabricated with relative ease even under difficult remote-handling conditions necessary for vitrification of highly radioactive material. The single most important property of the waste glass produced is its ability to retain hazardous species within the glass structure and this is reflected by its excellent chemical durability and corrosion resistance to a wide range of environmental conditions. In addition to immobilization of HLW glass matrices are also being considered for isolation of many other types of hazardous materials, both radioactive as well as nonradioactive. This includes vitrification of various actinides resulting from clean-up operations and the legacy of the cold war, as well as possible immobilization of weapons grade plutonium resulting from disarmament activities. Other types of wastes being considered for immobilization into glasses include transuranic wastes, mixed wastes, contaminated

  20. Radioactive waste management in Canada

    International Nuclear Information System (INIS)

    1990-11-01

    This bibliography is a review of the Canadian literature on radioactive waste management from 1953 to the present. It incorporates the references from the previous AECL--6186 revisions, and adds the current data and some of the references that had been omitted. Publications from outside organizations of concern to the Canadian Nuclear Fuel Waste Program are included in addition to AECL Research reports and papers. This report is intended as an aid in the preparation of the Concept Assessment Document and is complementary to AECL Research's internal document-ready references on the MASS-11 word processing systems

  1. Chemical treatment of radioactive wastes

    International Nuclear Information System (INIS)

    Pottier, P.E.

    1968-01-01

    This is the third manual of three commissioned by the IAEA on the three principal techniques used in concentrating radioactive liquid wastes, namely chemical precipitation, evaporation and ion exchange. The present manual deals with chemical precipitation by coagulation-flocculation and sedimentation, commonly called ''chemical treatment'' of low-activity wastes. Topics discussed in the manual are: (i) principles of coagulation on flocculation and sedimentation and associated processes; (ii) process and equipment; (iii) conditioning and disposal of flocculation sludge; (iv) sampling and the equipment required for experiments; and (v) factors governing the selection of processes. 99 refs, 17 figs, 4 tabs

  2. Radioactive waste and public acceptance

    International Nuclear Information System (INIS)

    Perkins, B.

    1977-01-01

    Radioactive waste just happens to be the major issue in the public eye now--it could be replaced by another issue later. A survey is quoted to prove that wastes are not really one of the burning national issues of the day. The people opposing the nuclear program cannot be said to represent the public. The taste of the press for the melodramatic is pointed out. The issue needs to be presented with the proper perspective, in the context of the benefits and risks of nuclear power

  3. Low-level radioactive waste

    International Nuclear Information System (INIS)

    McLaren, L.H.

    1983-03-01

    This bibliography contains information on low-level radioactive waste included in the Department of Energy's Energy Data Base for January through December 1982. The abstracts are grouped by subject category as shown in the table of contents. Entries in the subject index also facilitate access by subject, e.g., Low-Level Radioactive Wastes/Transport. Within each category the arrangement is by report number for reports, followed by nonreports in reverse chronological order. These citations are to research reports, journal articles, books, patents, theses, and conference papers from worldwide sources. Five indexes, each proceded by a brief description, are provided: Corporate Author, Personal Author, Subject, Contract Number, and Report Number. 492 references

  4. Shallow disposal of radioactive waste

    International Nuclear Information System (INIS)

    1985-02-01

    A review and evaluation of computer codes capable of simulating the various processes that are instrumental in determining the dose rate to individuals resulting from the shallow disposal of radioactive waste was conducted. Possible pathways of contamination, as well as the mechanisms controlling radionuclide movement along these pathways have been identified. Potential transport pathways include the unsaturated and saturated ground water systems, surface water bodies, atmospheric transport and movement (and accumulation) in the food chain. Contributions to dose may occur as a result of ingestion of contaminated water and food, inhalation of contaminated air and immersion in contaminated air/water. Specific recommendations were developed regarding the selection and modification of a model to meet the needs associated with the prediction of dose rates to individuals as a consequence of shallow radioactive waste disposal. Specific technical requirements with regards to risk, sensitivity and uncertainty analyses have been addressed

  5. Standard guide for characterization of radioactive and/or hazardous wastes for thermal treatment

    CERN Document Server

    American Society for Testing and Materials. Philadelphia

    2003-01-01

    1.1 This guide identifies methods to determine the physical and chemical characteristics of radioactive and/or hazardous wastes before a waste is processed at high temperatures, for example, vitrification into a homogeneous glass ,glass-ceramic, or ceramic waste form. This includes waste forms produced by ex-situ vitrification (ESV), in-situ vitrification (ISV), slagging, plasma-arc, hot-isostatic pressing (HIP) and/or cold-pressing and sintering technologies. Note that this guide does not specifically address high temperature waste treatment by incineration but several of the analyses described in this guide may be useful diagnostic methods to determine incinerator off-gas composition and concentrations. The characterization of the waste(s) recommended in this guide can be used to (1) choose and develop the appropriate thermal treatment methodology, (2) determine if waste pretreatment is needed prior to thermal treatment, (3) aid in development of thermal treatment process control, (4) develop surrogate wa...

  6. Radioactive waste solidifying material

    International Nuclear Information System (INIS)

    Ono, Keiichi; Sakai, Etsuro.

    1989-01-01

    The solidifying material according to this invention comprises cement material, superfine powder, highly water reducing agent, Al-containing rapid curing material and coagulation controller. As the cement material, various kinds of quickly hardening, super quickly hardening and white portland cement, etc. are usually used. As the superfine powder, those having average grain size smaller by one order than that of the cement material are desirable and silica dusts, etc. by-produced upon preparing silicon, etc. are used. As the highly water reducing agent, surface active agents of high decomposing performance and comprising naphthalene sulfonate, etc. as the main ingredient are used. As the Al-containing rapidly curing material, calcium aluminate, etc. is used in an amount of less than 10 parts by weight based on 100 parts by weight of the powdery body. As the coagulation controller, boric acid etc. usually employed as a retarder is used. This can prevent dissolution or collaption of pellets and reduce the leaching of radioactive material. (T.M.)

  7. Storage container for radioactive wastes

    International Nuclear Information System (INIS)

    Phlix, P.; Credoz, J.P.

    1989-01-01

    A container for transport and storage of solidified low and medium level radioactive waste is characterized by fast and safe closure with a plug that can be tested. The container is made of concrete and inside of composite allowing dimension variations with time and thermal insulation. The plug made of precasted concrete comprises a metal part that can be, for instance, welded to a ring of the container [fr

  8. Radioactive waste inventories and projections

    International Nuclear Information System (INIS)

    McLaren, L.H.

    1982-11-01

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

  9. Public Education and Radioactive Waste

    International Nuclear Information System (INIS)

    Sarten, S.

    2009-01-01

    Throughout the country the mention of anything nuclear or the word radiation ignites fear in the minds of many Americans. Political hype, news stories and the lack of basic understanding about nuclear power and radiation causes many people to reject what they do not understand. Often little, if any, thought may have been given to nearby nuclear weapons facilities where family members and neighbors were gainfully employed at these sites. As older nuclear facilities are closed being a result of the end of the Cold War, with indications that radioactive materials might be transported to other parts of the country, the public in expressing concern. It is important that the public have an understanding of how these materials are handled to insure public safety. It becomes important that both the companies handling these materials and the U.S. Department of Energy create an environment that will involve community participation in developing strategies that will promote and support an understanding of how radioactive wastes will be packaged, transported, and disposed. This is being performed in Oak Ridge, TN. through the efforts of the Oak Ridge Site Specific Advisory Board (ORSSAB). The ORSSAB is a DOE sponsored board of private citizens from all walks of life and professionalism's. The objective of this paper is to offer suggestions as to how public confidence, through education about nuclear, radioactive and associated and wastes are effectively handle the problems related to waste disposal, removal or on-site storage. It is essential that the public fully understand and become involved in the need for the reduction of the waste stream volumes and the technical problems being faced in reaching this goal. The effort of gaining public understanding and support of this important task cannot be limited to just those within close proximity to the facility presently housing these materials, but must extend to those outlying areas and along any potential route that might be

  10. What to do with radioactive wastes?

    International Nuclear Information System (INIS)

    2006-01-01

    This power point presentation (82 slides) gives information on what is a radioactive waste, radioactivity and historical review of radioactivity, radioactive period, natural radioactivity (with examples of data), the three main radiation types (α, β, γ), the origin of radioactive wastes (nuclear power, research, defense, other), the proportion of radioactive wastes in the total of industrial wastes in France, the classification of nuclear wastes according to their activity and period, the quantities and their storage means, the 1991 december 30 law (France) related to the radioactive waste management, the situation in other countries (Germany, Belgium, Canada, USA, Finland, Japan, Netherlands, Sweden, Switzerland), volume figures and previsions for the various waste types in 2004, 2010 and 2020, the storage perspectives, the French national debate on radioactive waste management and the objective of perpetuated solutions, the enhancement of the public information, the 15 June 2006 law on a sustainable management of radioactive materials and wastes with three main axis (deep separation and transmutation, deep storage, waste conditioning and long term surface storage), and the development of a nuclear safety and waste culture that could be extended to other types of industry

  11. Discarding system for radioactive waste

    International Nuclear Information System (INIS)

    Shinbori, Kuniaki; Komura, Shiro.

    1992-01-01

    Radiation contamination dose on the surface and permeation extent of contamination are measured relative to the surfaces to be measured, such as of floors, walls, ceilings of concrete building structures in an administration area after removing equipments and pipelines disposed so far in a nuclear power facility. Then, it is judged as to whether they are radioactive or not. If the surfaces to be measured are judged radioactive, it is further judged if radioactive contamination is present only on the surfaces or it permeates from the surfaces to the inner side, or it intrudes into cracks present on the surfaces. Then, decontamination methods are applied depending on the states of respective modes of contamination, to decontaminate each of the portions. Decontamination liquid wastes are classified depending on the level of the radioactivity contained therein, and then packed in containers. A confirmation measurement is conducted again to the surfaces to be measured from which the contaminated portions were removed. With such procedures, the operation time is shortened, as well as it can remarkably contribute to the reduction of the radiation dose and greatly reduce the waste processing cost. (T.M.)

  12. 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

  13. Solidification agent for radioactive waste

    International Nuclear Information System (INIS)

    Sakai, Etsuro; Shibayama, Yukio.

    1986-01-01

    Purpose: In low and medium level radioactive waste processing, to obtain superior solidified blocks by mixing cement, super-fine dusts and high-performance water-reducing agent and water to radioactive waste materials for solidification. Constitution: The various types of portland cements available are used for solidification. Silica dust is used as the super-fine dust and has an average article size of one order smaller than that of the cement used for solidification. Napthalene, sulfonic acid formalydehyde condensation salts etc. are used as the water-reducing agents. For example, for hundred units, by weight, of cement and super-fine dust 10 units (by solid content) are added. Furthermore, smaller quantities of water are desirable. By mixing the radioactive wastes with cement, super-fine dust, water-reducing agents, and water, the solidified material shows superior chemical resistance and durability. The processing capacity is also increased. Furthermore, a more leach resistant solid can be obtained for storage. (Takahashi, M.)

  14. Media analysis of radioactive wastes

    International Nuclear Information System (INIS)

    Janowski, M.J.

    1989-01-01

    The radioactive waste cleanup community has not effectively utilized its most powerful communications tool to inform the general public; the print and broadcast media. Environmental interest groups have known of the value of accessing the media for their message for years and have used it effectively. The radioactive waste cleanup community's efforts to date have not been focused on education of the media so that they in turn can inform the public of our cleanup mission. Their focus must be to learn of the importance of the media, develop training programs that train technical people in how to know and respond to the media's needs for information, and then incorporate that training into a comprehensive program of public information in which access to the media is a key communications tool. This paper discusses how media education and access is a cost-effective means of accomplishing community relations goals of public information and public participation in radioactive waste cleanup and has been effectively utilized at the Weldon Spring Site Remedial Action Project

  15. Stress and radioactive waste management

    International Nuclear Information System (INIS)

    Williams, R.G.; Olshansky, S.J.

    1987-01-01

    In the Supreme Court case ''People Against Nuclear Energy (PANE) vs Metropolitan Edison,'' one of the conclusions was that the Nuclear Regulatory Commission did not have to consider psychological distress, community cohesiveness and sense of well-being in the supplement to the Environmental Impact Statement (EIS) covering the restart of Three Mile Island (TMI). This decision was based on the assumption that the intention of the National Environmental Policy Act (NEPA) is to focus on the physical environment, and the casual chain between psychological distress and adverse health effects is tenuous. In this paper the authors summarize the literature on the relationship between environmentally-induced stress and its effects on health. They present the results of a new survey research project in which levels of stress were evaluated in West Chicago, Illinois, a community in which radioactive wastes have been present for many years. Explanatory social variables are brought into the evaluation in which stress is evaluated as a function of proximity to the radioactive waste site. In addition, stress is discussed in the context of attitudes on nuclear power, environmental group participation, and knowledge about the health effects associated with radioactive waste. The paper ends with a discussion of the portion of the Supreme Court decision in which psychological distress, community stability, cohesiveness and sense of well being are excluded as variables to address in EISs

  16. Final storage of radioactive waste

    International Nuclear Information System (INIS)

    Ziehm, Cornelia

    2015-01-01

    As explained in the present article, operators of nuclear power plants are responsible for the safe final disposal of the radioactive wastes they produce on the strength of the polluter pays principle. To shift the burden of responsibility for safe disposal to society as a whole would violate this principle and is therefore not possible. The polluter pays principle follows from more general principles of the fair distribution of benefits and burdens. Instances of its implementation are to be found in the national Atomic Energy Law as well as in the European Radioactive Waste and Spent Fuel Management Directive. The polluters in this case are in particular responsible for financing the installation and operation of final disposal sites. The reserves accumulated so far for the decommissioning and dismantling of nuclear power plants and disposal of radioactive wastes, including the installation and operation of final disposal sites, should be transferred to a public-law fund. This fund should be supplemented by the polluters to cover further foreseeable costs not covered by the reserves accumulated so far, including a realistic cost increase factor, appropriate risk reserves as well as the costs of the site selection procedure and a share in the costs for the safe closure of the final disposal sites of Morsleben and Asse II. This would merely be implementing in the sphere of atomic law that has long been standard practice in other areas of environmental law involving environmental hazards.

  17. Tracing source and migration of Pb during waste incineration using stable Pb isotopes

    International Nuclear Information System (INIS)

    Li, Yang; Zhang, Hua; Shao, Li-Ming; He, Pin-Jing

    2017-01-01

    Highlights: • The migration of Pb during waste incineration was investigated using Pb isotopes. • Source tracing of Pb during incineration by isotopic technology was feasible. • Contributions of MSW components were measured to trace Pb sources quantitatively. • Isotopic technology helps understand the migration of Pb during thermal treatment. - Abstract: Emission of Pb is a significant environmental concern during solid waste incineration. To target Pb emission control strategies effectively, the major sources of Pb in the waste incineration byproducts must be traced and quantified. However, identifying the migration of Pb in each waste component is difficult because of the heterogeneity of the waste. This study used a laboratory-scale incinerator to simulate the incineration of municipal solid waste (MSW). The Pb isotope ratios of the major waste components ( 207 Pb/ 206 Pb = 0.8550–0.8627 and 208 Pb/ 206 Pb = 2.0957–2.1131) and their incineration byproducts were measured to trace sources and quantify the Pb contribution of each component to incineration byproducts. As the proportions of food waste (FW), newspaper (NP), and polyethylene bag (PE) in the artificial MSW changed, the contribution ratios of FW and PE to Pb in fly ash changed accordingly, ranging from 31.2% to 50.6% and from 35.0% to 41.8%, respectively. The replacement of PE by PVC significantly increased the partitioning and migration ratio of Pb. The use of Pb isotope ratios as a quantitative tool for tracing Pb from raw waste to incineration byproducts is a feasible means for improving Pb pollution control.

  18. Tracing source and migration of Pb during waste incineration using stable Pb isotopes

    Energy Technology Data Exchange (ETDEWEB)

    Li, Yang [State Key Laboratory of Pollution Control and Resources Reuse, Tongji University, 1239 Siping Road, Shanghai 200092 (China); Institute of Waste Treatment and Reclamation, Tongji University, 1239 Siping Road, Shanghai 200092 (China); Zhang, Hua, E-mail: zhanghua_tj@tongji.edu.cn [State Key Laboratory of Pollution Control and Resources Reuse, Tongji University, 1239 Siping Road, Shanghai 200092 (China); Institute of Waste Treatment and Reclamation, Tongji University, 1239 Siping Road, Shanghai 200092 (China); Shao, Li-Ming; He, Pin-Jing [Institute of Waste Treatment and Reclamation, Tongji University, 1239 Siping Road, Shanghai 200092 (China); Research and Training Center on Rural Waste Management, Ministry of Housing and Urban-Rural Development of P.R. China, 1239 Siping Road, Shanghai 200092 (China)

    2017-04-05

    Highlights: • The migration of Pb during waste incineration was investigated using Pb isotopes. • Source tracing of Pb during incineration by isotopic technology was feasible. • Contributions of MSW components were measured to trace Pb sources quantitatively. • Isotopic technology helps understand the migration of Pb during thermal treatment. - Abstract: Emission of Pb is a significant environmental concern during solid waste incineration. To target Pb emission control strategies effectively, the major sources of Pb in the waste incineration byproducts must be traced and quantified. However, identifying the migration of Pb in each waste component is difficult because of the heterogeneity of the waste. This study used a laboratory-scale incinerator to simulate the incineration of municipal solid waste (MSW). The Pb isotope ratios of the major waste components ({sup 207}Pb/{sup 206}Pb = 0.8550–0.8627 and {sup 208}Pb/{sup 206}Pb = 2.0957–2.1131) and their incineration byproducts were measured to trace sources and quantify the Pb contribution of each component to incineration byproducts. As the proportions of food waste (FW), newspaper (NP), and polyethylene bag (PE) in the artificial MSW changed, the contribution ratios of FW and PE to Pb in fly ash changed accordingly, ranging from 31.2% to 50.6% and from 35.0% to 41.8%, respectively. The replacement of PE by PVC significantly increased the partitioning and migration ratio of Pb. The use of Pb isotope ratios as a quantitative tool for tracing Pb from raw waste to incineration byproducts is a feasible means for improving Pb pollution control.

  19. Radioactive Waste and Clean-up Division

    International Nuclear Information System (INIS)

    Collard, G.

    2001-01-01

    The main objectives of the Radioactive Waste and Clean-up division of SCK-CEN are outlined. The division's programme consists of research, development and demonstration projects and aims to contribute to the objectives of Agenda 21 on sustainable development in the field of radioactive waste and rehabilitation of radioactively contaminated sites

  20. Radioactive Waste and Clean-up: Introduction

    International Nuclear Information System (INIS)

    Collard, G.

    2000-01-01

    SCK-CEN's Radioactive Waste and Clean-up Division performs studies and develops strategies, techniques and technologies in the area of radioactive waste management, the decontamination and decommissioning of nuclear installations and the remediation of radioactive-contaminated sites. These activities are performed in the context of our responsibility towards the safety of present and future generations and contribute to achieve intrageneration equity

  1. Radioactive waste storage and disposal: the challenge

    International Nuclear Information System (INIS)

    Prince, A.T.

    1978-03-01

    Solutions to waste management problems are available. After radium is removed, tailings from uranium ores can be disposed of safely in well-designed retention areas. Work is being done on the processing of non-fuel reactor wastes through incineration, reverse osmosis, and evaporation. Spent fuels have been stored safely for years in pools; dry storage in concrete cannisters is being investigated. Ultimate disposal of high-level wastes will be in deep, stable geologic formations. (LL)

  2. 40 CFR 62.15375 - What are the emission limits for air curtain incinerators that burn 100 percent yard waste?

    Science.gov (United States)

    2010-07-01

    ... curtain incinerators that burn 100 percent yard waste? 62.15375 Section 62.15375 Protection of Environment... Combustion Units Constructed on or Before August 30, 1999 Air Curtain Incinerators That Burn 100 Percent Yard Waste § 62.15375 What are the emission limits for air curtain incinerators that burn 100 percent yard...

  3. 40 CFR 62.15380 - How must I monitor opacity for air curtain incinerators that burn 100 percent yard waste?

    Science.gov (United States)

    2010-07-01

    ... curtain incinerators that burn 100 percent yard waste? 62.15380 Section 62.15380 Protection of Environment... Combustion Units Constructed on or Before August 30, 1999 Air Curtain Incinerators That Burn 100 Percent Yard Waste § 62.15380 How must I monitor opacity for air curtain incinerators that burn 100 percent yard...

  4. Radioactive Waste Management BasisSept 2001

    International Nuclear Information System (INIS)

    Goodwin, S.S.

    2011-01-01

    This Radioactive Waste Management Basis (RWMB) documents radioactive waste management practices adopted at Lawrence Livermore National Laboratory (LLNL) pursuant to Department of Energy (DOE) Order 435.1, Radioactive Waste Management. The purpose of this RWMB is to describe the systematic approach for planning, executing, and evaluating the management of radioactive waste at LLNL. The implementation of this document will ensure that waste management activities at LLNL are conducted in compliance with the requirements of DOE Order 435.1, Radioactive Waste Management, and the Implementation Guide for DOE manual 435.1-1, Radioactive Waste Management Manual. Technical justification is provided where methods for meeeting the requirements of DOE Order 435.1 deviate from the DOE Manual 435.1-1 and Implementation Guide.

  5. Design of an experimental incinerator for alpha waste

    International Nuclear Information System (INIS)

    Warren, J.H.

    1979-08-01

    An electrically heated controlled-air two-stage incinerator has been designed for burning small volumes (5 kg/h) of solid wastes. Distinguishing features of the design are compactness, relatively lightweight, and ease of assembly made possible by using prefabricated ceramic components to form two combustion chambers surrounded by packed fiber insulation within a steel case. Electric girdle heaters around the two combustion chambers provide 600 to 1000 0 C. These temperatures combined with controlled air give minimum ash entrainment and long combustion gas residence times to yield approx. 10 9 off-gas decontamination factors with conventional off-gas cleaning equipment. After decommissioning, the design allows for ease of disassembly and convenient disposal of the ceramic components. 24 figures, 1 table

  6. Chapter No.6. Radioactive waste (RAW)

    International Nuclear Information System (INIS)

    2002-01-01

    UJD SR supervises all phases of radioactive waste management at nuclear installations and final phases of institutional radioactive waste management. Total concentrates generation and minimisation trends during recent period (for NPP V1, NPP V2 Bohunice and NPP Mochovce) as well as increasing of their conditioning are presented. So nearly 8000 m3 of concentrates were stored at the end of year 2001, representing 75.5% of storage capacity at Bohunice site. Total amount of solid waste stored at VVER NPPs reached 3500 m3 at December 2001. The solid waste storage capacity of NPP V1 Bohunice is spent. NPP A1 Bohunice with a heterogeneous reactor using natural uranium, moderated by heavy water and cooled by CO 2 had been in operation for 4 years. It was finally shut down in February 1977 after an accident (INES level 4). Main activities in 2001 were focused on an increasing of radwaste management safety by the waste solidification or storage improvement, especially in the case of inorganic spent fuel coolant. The total solid radwaste inventory in 2001 (including filters) represents cca 700 m3 of soft and pre-pressed not sorted waste, 700 m3 of sorted waste, more then 1 000 t of scrap and next 260 m3 of scrap in drums. The total volume of contaminated soils and concrete is more than 7200 m3. The volume of solid radwaste depends on the extent of dismantling works and following treatment, conditioning and disposal. The total volume is also increased by products of bituminization and cementation facilities in drums stored before conditioning at NPP A1 Bohunice site. The facilities focused only on treatment of radwaste from NPP A1 decommissioning are operated by the same operator as a part of this decommissioned nuclear installation. Experimental and research treatment plants are operated by VUJE. A facility for the treatment and conditioning of operational liquid radwaste from NPP Mochovce is under preparation and a start of construction is foreseen in 2004. The nuclear

  7. Radioactive liquid wastes processing device

    International Nuclear Information System (INIS)

    Sauda, Kenzo; Koshiba, Yukihiko; Yagi, Takuro; Yamazaki, Hideki.

    1985-01-01

    Purpose: To carry out optimum photooxidizing procession following after the fluctuation in the density of organic materials in radioactive liquid wastes to thereby realize automatic remote procession. Constitution: A reaction tank is equipped with an ultraviolet lamp and an ozone dispersing means for the oxidizing treatment of organic materials in liquid wastes under the irradiation of UV rays. There are also provided organic material density measuring devices to the inlet and outlet of the reaction tank, and a control device for controlling the UV lamp power adjusting depending on the measured density. The output of the UV lamp is most conveniently adjusted by changing the applied voltage. The liquid wastes in which the radioactivity dose is reduced to a predetermined level are returned to the reaction tank by the operation of a switching valve for reprocession. The amount of the liquid wastes at the inlet is controlled depending on the measured ozone density by the adjusting valve. In this way, the amount of organic materials to be subjected to photolysis can be kept within a certain limit. (Kamimura, M.)

  8. Law on the management of radioactive waste

    International Nuclear Information System (INIS)

    1999-01-01

    This law regulate the relations of legal persons, enterprises without the rights of legal persons, and natural persons in the management of radioactive waste in Lithuania and establish the legal grounds for the management of radioactive waste. Thirty one article of the law deals with the following subjects: principles of radioactive waste management, competence of the Government, State Nuclear Power Safety Inspectorate, Ministry of Economy, Ministry of Environment and Radiation Protection Center in the sphere of regulation of the radioactive waste management, activities subject to licensing, issue of licences and authorisations, duties and responsibilities of the waste producer, founding of the radioactive waste management agency, its basic status and principles of the activities, functions of the agency, management of the agency, transfer of the radioactive waste to the agency, assessment of the existing waste management facilities and their past practices, siting, design and construction, safety assessment, commissioning and operation of the radioactive waste management facilities, radiation protection, quality assurance, emergency preparedness, decommissioning of radioactive waste storage and other facilities, post-closure surveillance of the repository, disused sealed sources, transportation, export and transit of radioactive waste

  9. 40 CFR 63.1219 - What are the replacement standards for hazardous waste incinerators?

    Science.gov (United States)

    2010-07-01

    ... organic hazardous constituent (POHC). (i) You must treat each POHC in the waste feed that you specify... concentration or mass in the hazardous waste feed, considering the results of hazardous waste analyses or other... hazardous waste incinerators? 63.1219 Section 63.1219 Protection of Environment ENVIRONMENTAL PROTECTION...

  10. Incinerator performance: effects of changes in waste input and furnace operation on air emissions and residues

    DEFF Research Database (Denmark)

    Astrup, Thomas; Riber, Christian; Pedersen, Anne Juul

    2011-01-01

    and residue composition at a full-scale incinerator were affected by known additions of specific waste materials to the normal municipal solid waste (MSW) input. Six individual experiments were carried out (% ww of total waste input): NaCl (0.5%), shoes (1.6%), automobile shredder waste (14%), batteries (0...

  11. Radioactive waste management in France

    International Nuclear Information System (INIS)

    Faussat, A.

    1988-01-01

    Solutions for radioactive waste management are already in existence and applied on an industrial scale for short-lived wastes. France has acquired an aknowledged expertise on the international level and several foreign contemporaries are interested in the relevant techniques developed. An intensive international cooperation has allowed to define bases for an underground deep repository for long-lived wastes. It is therefore important to choose a site which meets the expected storage conditions. This development work has been started in several countries in a similar way and which should be completed by the beginning of the next century. An 'open channel' with the public about this emotional topic can smooth the way for solutions by which mankind can master its technological challenges

  12. Volume reduction options for the management of low-level radioactive wastes

    International Nuclear Information System (INIS)

    Clark, D.E.; Lerch, R.E.

    1977-01-01

    This paper examines volume reduction options that are now or soon will be available for low-level wastes. These wastes generally are in the form of combustible solids, noncombustible solids, and wet wastes (solid/liquid). Initially, the wastes are collected and stored onsite. Preconditioning may be required, e.g., sorting, shredding, and classifying the solids into combustible and noncombustible fractions. The volume of combustible solids can be reduced by compaction, incineration/pyrolysis, acid digestion, or molten salt combustion. Options for reducing the volume of noncombustible solids include compaction, size reduction and decontamination, meltdown-casting, dissolution and electropolishing. Burnable wet wastes (e.g., organic wastes) can be evaporated or combusted; nonburnable wet wastes can be treated by various evaporative or nonevaporative processes. All radioactive waste processing operations result in some equipment contamination and the production of additional radioactively contaminated wastes (secondary wastes). 23 figures

  13. 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

  14. Thermal treatment of organic radioactive waste

    International Nuclear Information System (INIS)

    Chrubasik, A.; Stich, W.

    1993-01-01

    The organic radioactive waste which is generated in nuclear and isotope facilities (power plants, research centers and other) must be treated in order to achieve a waste form suitable for long term storage and disposal. Therefore the resulting waste treatment products should be stable under influence of temperature, time, radioactivity, chemical and biological activity. Another reason for the treatment of organic waste is the volume reduction with respect to the storage costs. For different kinds of waste, different treatment technologies have been developed and some are now used in industrial scale. The paper gives process descriptions for the treatment of solid organic radioactive waste of low beta/gamma activity and alpha-contaminated solid organic radioactive waste, and the pyrolysis of organic radioactive waste

  15. Innovative use of recovered municipal solid waste incineration bottom ash as a component in growing media.

    Science.gov (United States)

    Sormunen, Annika; Teo, Kanniainen; Tapio, Salo; Riina, Rantsi

    2016-07-01

    The utilisation of municipal solid waste incineration bottom ash has been extensively studied, for example, in the unbound layers of roads and the products of cement and concrete industry. On the other hand, less attention has been given to other innovative utilisation possibilities, such as using the municipal solid waste incineration bottom ash as a component in growing media of plants. The municipal solid waste incineration bottom ash contains useful substances, such as calcium, that can influence plant growth in a positive manner. Therefore, the utilisation of this waste-derived material in the growing media may substitute the use of commercial fertilisers. Since the municipal solid waste incineration bottom ash also contains hazardous substances that can be toxic to plants, the main aim of this study was to add different amounts of recovered municipal solid waste incineration bottom ash in the growing media and to evaluate the effect of this material on plant growth. Based on the obtained results, the concentration of, for example copper and zinc, increased in test plants; ryegrass and barley, when recovered municipal solid waste incineration bottom ash was added in their growing media. On the other hand, this did not have a significant effect on plant growth, if compared with the growth of plants in commercially produced growing medium. Furthermore, the replacement of natural sand with municipal solid waste incineration bottom ash had a positive liming effect in the growing media. Overall, these findings suggest that the utilisation of recovered municipal solid waste incineration bottom ash as a component in growing media is possible and, thus, may allow more widespread and innovative use of this waste-derived material. © The Author(s) 2016.

  16. Determination of the optimal area of waste incineration in a rotary kiln using a simulation model.

    Science.gov (United States)

    Bujak, J

    2015-08-01

    The article presents a mathematical model to determine the flux of incinerated waste in terms of its calorific values. The model is applicable in waste incineration systems equipped with rotary kilns. It is based on the known and proven energy flux balances and equations that describe the specific losses of energy flux while considering the specificity of waste incineration systems. The model is universal as it can be used both for the analysis and testing of systems burning different types of waste (municipal, medical, animal, etc.) and for allowing the use of any kind of additional fuel. Types of waste incinerated and additional fuel are identified by a determination of their elemental composition. The computational model has been verified in three existing industrial-scale plants. Each system incinerated a different type of waste. Each waste type was selected in terms of a different calorific value. This allowed the full verification of the model. Therefore the model can be used to optimize the operation of waste incineration system both at the design stage and during its lifetime. Copyright © 2015 Elsevier Ltd. All rights reserved.

  17. 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 ...

  18. Instructive for radioactive solid waste management

    International Nuclear Information System (INIS)

    Mora Rodriguez, Patricia

    2014-01-01

    An instructive is established for the management system of radioactive solid residues waste of the Universidad de Costa Rica, ensuring the collection, segregation, storage and disposal of waste. The radioactive solid waste have been segregated and transferred according to features and provisions of the Universidad de Costa Rica and CICANUM [es

  19. United Kingdom government policy towards radioactive waste

    International Nuclear Information System (INIS)

    Pritchard, G.

    1986-01-01

    There are three areas of radioactive waste management which exemplify, beyond any reasonable doubt, that the United Kingdom has in the past (and intends in the future), to pursue a policy of dispersal and disposal of radioactive wastes: These are: (I) dumping of low-level waste in the deep ocean and, on a parallel, seabed emplacement of highly active waste; (II) the liquid discharges from Windscale into the Irish Sea; and (III) land dumping of low- and intermediate-level waste

  20. Current Methods to Detoxify Fly Ash from Waste Incineration

    Energy Technology Data Exchange (ETDEWEB)

    Hallgren, Christine; Stroemberg, Birgitta [TPS Termiska Processer AB, Nykoeping (Sweden)

    2004-07-01

    Fly ash from waste incineration contains large amounts of heavy metals and dioxins, which will cause a significant disposal problem within the coming years. The amount of fly ash produced in Sweden is currently approximately 60,000 tons/y. New technological options for the decontamination and/or inertization of incinerator fly ash are being developed with the objective of rendering a product that can be reused or, at least, be deposited at standard landfill sites with no risk. Many of these technologies have been tested at industrial scale or in pilot projects. The proposed alternatives include: Thermal treatments; Immobilization/stabilization by cement based techniques; Wet chemical treatments (extractions, immobilizations); Microbiological treatments. Of these, thermal treatments are the most promising solution. Depending on the temperature thermal treatments are classified in two main types: 1) low temperature (below 600 deg C) thermal treatments and 2) high temperature (above 1200 deg C) thermal treatments (vitrification). Most dioxins can be successfully destroyed at temperatures up to 400 deg C under oxygen deficient conditions and at temperatures up to 600 deg C under oxidising conditions. However most heavy metals remain in the fly ash after low temperature treatment. At a temperature of 900 deg C most heavy metals can also be removed in a 10% HCl atmosphere by forming volatile metal chlorides (CT-Fluapur process). During vitrification processes the fly ash melts and forms an inert glassy slag. The product does not leach any significant amount of heavy metals and is free from dioxin. The volume of the fly ash is significantly reduced. The product can be land filled at low costs or used as construction material. The properties of the product depend on the cooling process and on additives such as sand, limestone or waste glass. A series of vitrification methods at industrial size or in pilot scale using different furnaces are studied. Among these, plasma

  1. STORAGE AND RECOVERY OF SECONDARY WASTE COMING FROM MUNICIPAL WASTE INCINERATION PLANTS IN UNDERGROUND MINE

    Directory of Open Access Journals (Sweden)

    Waldemar Korzeniowski

    2016-09-01

    Full Text Available Regarding current and planned development of municipal waste incineration plants in Poland there is an important problem of the generated secondary waste management. The experience of West European countries in mining shows that waste can be stored successfully in the underground mines, but especially in salt mines. In Poland there is a possibility to set up the underground storage facility in the Salt Mine “Kłodawa”. The mine today is capable to locate over 3 million cubic meters and in the future it can increase significantly. Two techniques are proposed: 1 – storage of packaged waste, 2 – waste recovery as selfsolidifying paste with mining technology for rooms backfilling. Assuming the processing capacity of the storage facility as 100 000 Mg of waste per year, “Kłodawa” mine will be able to accept around 25 % of currently generated waste coming from the municipal waste incineration plants and the current volume of the storage space is sufficient for more than 20 years. Underground storage and waste recovery in mining techniques are beneficial for the economy and environment.

  2. Environmental impact assessment of the incineration of municipal solid waste with auxiliary coal in China.

    Science.gov (United States)

    Zhao, Yan; Xing, Wei; Lu, Wenjing; Zhang, Xu; Christensen, Thomas H

    2012-10-01

    The environmental impacts of waste incineration with auxiliary coal were investigated using the life-cycle-based software, EASEWASTE, based on the municipal solid waste (MSW) management system in Shuozhou City. In the current system, MSW is collected, transported, and incinerated with 250 kg of coal per ton of waste. Based on observed environmental impacts of incineration, fossil CO(2) and heavy metals were primary contributors to global warming and ecotoxicity in soil, respectively. Compared with incinerators using excess coal, incineration with adequate coal presents significant benefits in mitigating global warming, whereas incineration with a mass of coal can avoid more impacts to acidification, photochemical ozone and nutrient enrichment because of increased electricity substitution and reduced emission from coal power plants. The "Emission standard of air pollutants for thermal power plants (GB13223-2011)" implemented in 2012 introduced stricter policies on controlling SO(2) and NO(x) emissions from coal power plants. Thus, increased use of auxiliary coal during incineration yields fewer avoided impacts on acidification and nutrient enrichment. When two-thirds of ash is source-separated and landfilled, the incineration of rest-waste presents better results on global warming, acidification, nutrient enrichment, and even ecotoxicity in soil. This process is considered a promising solution for MSW management in Shuozhou City. Weighted normalized environmental impacts were assessed based on Chinese political reduction targets. Results indicate that heavy metal and acidic gas emissions should be given more attention in waste incineration. This study provides scientific support for the management of MSW systems dominated by incineration with auxiliary coal in China. Copyright © 2012 Elsevier Ltd. All rights reserved.

  3. Technical data for waste incineration - background for modelling of product-specific emissions in a life cycle assessment context

    DEFF Research Database (Denmark)

    Erichsen, Hanne; Hauschild, Michael Zwicky

    with the disposal of a product through waste incineration. Based on knowledge of the material composition of the product and the technology applied in the waste incineration plant, the model estimates input of energy and auxiliary materials required for the incineration of the product and generation of energy...... and output of emissions to the environment caused by the incineration. The work has been performed as part of the EUREKA project EUROENVIRON 1296: LCAGAPS, sponsored by the Danish Agency for Industry and Trade....

  4. Sponsored research on radioactive waste management

    International Nuclear Information System (INIS)

    1983-01-01

    The report is in chapters entitled: introduction (background, responsibilities, options, structure of the programme); strategy development; disposal of accumulations; disposal of radioactive waste arisings; quality assurance for waste conditioning quality assurance related to radioactive waste disposal (effectiveness of different rock types as natural barriers to the movement of radioactivity, and non-site specific factors in the design of repositories; radiological assessment; environmental studies; research and development to meet requirements specific to UKAEA wastes; long term research (processes for the solidification of highly active liquid wastes); plutonium contamination waste minimisation. (U.K.)

  5. The Radioactive Waste Management at Studsvik

    Energy Technology Data Exchange (ETDEWEB)

    Hedlund, R.; Lindskog, A.

    1966-04-15

    The report was originally prepared as a contribution to the discussions in an IAEA panel on economics of radioactive waste management held in Vienna from 13 - 17 December 1965. It contains the answers and comments to the questions of a questionnaire for the panel concerning the various operations associated with the management (collection, transport, treatment, discharge, storage, and operational monitoring) of: - radioactive liquid wastes, except high-level effluents from reactor fuel recovering operations; - solid wastes, except those produced from treatment of high level wastes; - gaseous wastes produced from treatment of the foregoing liquid and solid wastes; - equipment decontamination facilities and radioactive laundries.

  6. 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

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

    Science.gov (United States)

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

    2016-01-01

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

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

    Directory of Open Access Journals (Sweden)

    M. Adama

    2016-01-01

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

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

    Science.gov (United States)

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

    2016-01-01

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

  10. 40 CFR 60.3067 - How must I monitor opacity for air curtain incinerators that burn only wood waste, clean lumber...

    Science.gov (United States)

    2010-07-01

    ... curtain incinerators that burn only wood waste, clean lumber, and yard waste? 60.3067 Section 60.3067... Incinerators That Burn Only Wood Waste, Clean Lumber, and Yard Waste § 60.3067 How must I monitor opacity for air curtain incinerators that burn only wood waste, clean lumber, and yard waste? (a) Use Method 9 of...

  11. 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

  12. 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. 

  13. Radioactive waste management in Germany

    International Nuclear Information System (INIS)

    Brammer, K.J.

    2011-01-01

    The responsibility for the disposal of radioactive waste is regulated in the Federal Republic of Germany in the Atomic Energy Act. Basically, it is the responsibility of the waste producers to carry out all necessary processing steps up to the delivery to a repository. The Federal Republic reserves the right to select, explore and operate the repository (§ 9a, para. 3 AtG). The costs of all necessary expenditures of this task are borne by the waste producers in accordance with § 21 AtG regulation. The waste quantity forecasts have shown that by the year 2080 a total volume of about 300,000 m3 of low- and intermediate-level (non-heat-generating) waste will be generated in research, industry, medicine and in the production of electricity in nuclear power plants. This waste is to be transported to the ‘Konrad repository’ which is under construction. The Federal Office for Radiation Protection (BfS), which is responsible for the construction and operation, intends to commission the repository at 2019. As a repository for heat-generating wastes, i. Approximately 10.000 tSM spent fuel (BE) 7,500 molds (HAW and MAW, corresponding to about 6000 tSM) returned Waste from reprocessing, the Gorleben salt dome has been explored since 1979. The works were resumed on 01.10.2010 after a 10-year break. Federal Environment Minister Röttgen has made it clear that the Federal Government has proposed a transparent procedure and a dialogue and participation procedure for open-ended exploration. (roessner)

  14. Radioactive wastes management: what is the situation?

    International Nuclear Information System (INIS)

    2002-01-01

    This presentation takes stock on the situation of the radioactive wastes management in France. It gives information on the deep underground disposal, the public information, the management of the radioactive wastes in France, the researches in the framework of the law of the 30 december 1991, the underground laboratory of Meuse/Haute-Marne, the national agency for the radioactive wastes management (ANDRA) and its sites. (A.L.B.)

  15. Natural radioactivity at CBPP waste pile

    International Nuclear Information System (INIS)

    Kovac, Jadranka; Marovic, Gordana

    2008-01-01

    Electrical power requirements will necessitate doubling the present generating capacity in Croatia in the future. As a result, environmental discharges associated with the coal power industry will considerably increase. Burning of coal is one source of enhanced radiation exposure to naturally occurring elements, particularly members of uranium and thorium decay chains. By coal burning (in CBPP at about 1700 C degrees) the activity originating from uranium and thorium is redistributed from underground (where the impact on humanity is nil) and liberated into the environment. Most of the radioactive substances are concentrated in the ash and slag, which are heavy and drop to the bottom of a furnace, lately transported to deposit pile, from where some activity may leach into aquifer, or be dispersed by wind. Lighter fly ash, however, is carried up the chimney and into the atmosphere and irradiates people and contaminates food crops. Also, 222 Rn escapes into the atmosphere during incineration, while the non-gaseous members of the uranium decay series remain in the ash and slag. Extensive investigations have been performed in the coal burning power plant (CBPP) Plomin in Croatia and at deposit pile. A network of radon escalation measurements, in-situ gamma-spectrometric measurements and monitoring of waste pile were organized. The results of the measurements confirm that the ash/slag deposite site are well monitored and involve all the necessary protective measures. All obtained data can be used as a valuable database for future estimations and modeling of the impact of radioactive pollution to the marine environment. (author)

  16. AECL experience with low-level radioactive waste technologies

    International Nuclear Information System (INIS)

    Buckley, L.P.; Charlesworth, D.H.

    1988-08-01

    Atomic Energy of Canada Limited (AECL), as the Canadian government agency responsible for research and development of peaceful uses of nuclear energy, has had experience in handling a wide variety of radioactive wastes for over 40 years. Low-level radioactive waste (LLRW) is generated in Canada from nuclear fuel manufacturers and nuclear power facilities, from medical and industrial uses of radioisotopes and from research facilities. The technologies with which AECL has strength lie in the areas of processing, storage, disposal and safety assessment of LLRW. While compaction and incineration are the predominant methods practised for solid wastes, purification techniques and volume reduction methods are used for liquid wastes. The methods for processing continue to be developed to improve and increase the efficiency of operation and to accommodate the transition from storage of the waste to disposal. Site-specific studies and planning for a LLRW disposal repository to replace current storage facilities are well underway with in-service operation to begin in 1991. The waste will be disposed of in an intrusion-resistant underground structure designed to have a service life of over 500 years. Beyond this period of time the radioactivity in the waste will have decayed to innocuous levels. Safety assessments of LLRW disposal are performed with the aid of a series of interconnected mathematical models developed at Chalk River specifically to predict the movement of radionuclides through and away from the repository after its closure and the subsequent health effects of the released radionuclides on the public. The various technologies for dealing with radioactive wastes from their creation to disposal will be discussed. 14 refs

  17. Management of radioactive wastes produced by users of radioactive materials

    International Nuclear Information System (INIS)

    1985-01-01

    This report is intended as a document to provide guidance for regulatory, administrative and technical authorities who are responsible for, or are involved in, planning, approving, executing and reviewing national waste management programmes related to the safe use of radioactive materials in hospitals, research laboratories, industrial and agricultural premises and the subsequent disposal of the radioactive wastes produced. It provides information and guidance for waste management including treatment techniques that may be available to establishments and individual users

  18. Applicability Flowchart for Hospital/Medical/Infectious Waste Incinerators (HIMWI) Amended October 6, 2009

    Science.gov (United States)

    This October 2009 document contains a diagram that that are intended to assist you in determining whether you own or operate any equipment that is subject to the Hospital/Medical/Infectious Waste Incinerators (HIMWI) regulations.

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

    National Research Council Canada - National Science Library

    Arunajatesan, S

    1997-01-01

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

  20. Volume reduction and solidification of liquid and solid low-level radioactive waste

    International Nuclear Information System (INIS)

    May, J.R.

    1979-01-01

    This paper presents a brief background of the development of a method of radioactive waste volume reduction using a unique fluidized bed calciner/incinerator. The volume reduction system is capable of processing a variety of liquid chemical wastes, spent ion exchange resin beads, filter treatment sludges, contaminated lubricating oils, and miscellaneous combustible solids such as paper, rags, protective clothing, wood, etc. All of these wastes are processed in one chemical reaction vessel. Detailed process data is presented that shows the system is capable of reducing the total volume of disposable radioactive waste generated by light water reactors by a factor of 10. Equally important to reducing the volume of power reactor radwaste is the final form of the stored or disposable radwaste. This paper also presents process data related to a new radwaste solidification system, presently being developed, that is particularly suited for immobilizing the granular solids and ashes resulting from volume reduction by calcination and/or incineration