A study on the safety of radioactive waste incineration facilities

Energy Technology Data Exchange (ETDEWEB)

Seo, Y C [Yonsei Univ., Seoul (Korea, Republic of); Park, W J; Lee, B S; Lee, S H [Korea Institute of Nuclear Safety, Taejon (Korea, Republic of)

1994-12-15

The main scope of the project is the selection of some considerable items in design criteria of radioactive waste incineration facilities not only for the protection of workers and residents during operation but also for the safe disposal of ashes after incineration. The technological and regulational status on incineration technologies in domestic and foreign is surveyed and analyzed for providing such basic items which must be contained in the guideline for safe and appropriate design, construction and operation of the facilities. The contents of the project are summarized as follows; surveying the status on incineration technologies for both radioactive and non-radioactive wastes in domestic and foreign, surveying and analysing same related technical standards and regulations in domestic and foreign, picking out main considerable items and proposing a direction of further research.

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

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)

Operation of controlled-air incinerators and design considerations for controlled-air incinerators treating hazardous and radioactive wastes

International Nuclear Information System (INIS)

McRee, R.E.

1986-01-01

This paper reviews the basic theory and design philosophies of the so-called controlled-air incinerator and examines the features of this equipment that make it ideally suited to the application of low-level radioactive waste disposal. Special equipment design considerations for controlled air incinerators treating hazardous and radioactive wastes are presented. 9 figures

Non-radioactive verification test of ZRF25 radioactive combustible solid waste incinerator

International Nuclear Information System (INIS)

Wang Peiyi; Li Xiaohai; Yang Liguo

2013-01-01

This paper mainly introduces the construction and test run of ZRF25 radioactive combustible solid waste incinerator, by a series of simulating waste tests, such as 24 h test, 72 h test, 168 h test, making a conclusion that the incinerator runs reliably. In addition, all of the indexes (such as treatment capacity, volume reduction coefficient, clinker ignition loss of incineration ash) meet the requirements of contract and pollution discharging standards. (authors)

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.)

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

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.)

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

Some notes about radioactive wastes incineration

International Nuclear Information System (INIS)

Martin Martin, L.

1984-01-01

A general review about the most significant techniques in order to incinerate radioactive wastes by controlled air, acid digestion, fluidized bed, etc., is presented. These features are briefly exposed in the article through feed preparation, combustion effectiveness, etc. (author)

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

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)

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

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

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

Characterization on incineration residue of radioactive solid wastes

International Nuclear Information System (INIS)

Katoh, Kiyoshi; Hirayama, Katsuyoshi; Kato, Akira.

1989-01-01

Characterization was carried out on incineration residue discharged from the radioactive solid waste incineration unit (capacity, 100 kg/h) in use at the Tokai Research Establishment of Japan Atomic Energy Research Institute (JAERI) to obtain basic data for investigating solidification methods of the residue. The characterized residue was taken from furnace and a primary ceramic filter of the incineration unit which incinerates combustible solid wastes generated at JAERI and the outside organizations. Items of characterization involve a particle size distribution, misplaced materials content, ignition loss, chemical composition and radioactivity of nuclides in the ash. As the results, the size of ash sampled from the furnace distributed a wide range, with about 35∼60 % of ash smaller than 5 mm and about 10∼25 % of massive one larger than 30 mm (max. size: ∼130 mm). The ignition loss was 2∼3 %. The chemical compositions of the ash were mainly SiO 2 , Fe 2 O 3 , CaO and Al 2 O 3 . The specific activities of the ash were about 0.4∼4 x 10 3 Bq/g, and principal contaminants were 60 Co and 137 Cs. (author)

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

Incineration of radioactive wastes containing only C-14 and H-3

International Nuclear Information System (INIS)

Garcia, Corazon M.

1992-01-01

C-14 and H-3 arc popularly used in chemical and biological research institutions in the Philippines. Most of the solid radioactive wastes generated by these institutions consist of combustible materials such as paper and accumulated environmental samples. Liquid wastes usually contain organic substances. The method proposed for managing C-14 and H-3 wastes is incineration which is expected to provide an acceptable means of disposal for C-14 and H-3 and their hazardous organic constituent. In the incineration process) the radioactively contaminated waste will be mixed with non-radioactive combustible wastes to lower the activity concentration and to improve the efficiency of combustion which will be carried out in a locally fabricated drum incinerator. The calculations presented determines the concentration limit for the incinerable wastes and the restriction on specific activity of the particles of the incinerable wastes containing C-14 or H-3 on the basis of the accepted air concentration and on the annual dose limit for an average radiation worker in the country. In the calculations for C-14, considerations were taken on the exposure received from the deposition of radioactive particles in the lungs containing unoxidized carbon. Calculations for H-3, however, is based on the assumption that the concentration of the radionuclide in the body water is the same as that in the environment. (author)

Incineration of radioactive waste

International Nuclear Information System (INIS)

Caramelle, D.; Florestan, J.; Waldura, C.

1990-01-01

This paper reports that one of the methods used to reduce the volume of radioactive wastes is incineration. Incineration also allows combustible organic wastes to be transformed into inert matter that is stable from the physico-chemical viewpoint and ready to be conditioned for long-term stockage. The quality of the ashes obtained (low carbon content) depends on the efficiency of combustion. A good level of efficiency requires a combustion yield higher than 99% at the furnace door. Removal efficiency is defined as the relation between the CO 2 /CO + CO 2 concentrations multiplied by 100. This implies a CO concentration of the order of a few vpm. However, the gases produced by an incineration facility can represent a danger for the environment especially if toxic or corrosive gases (HCL,NO x ,SO 2 , hydrocarbons...) are given off. The gaseous effluents must therefore be checked after purification before they are released into the atmosphere. The CO and CO 2 measurement gives us the removal efficiency value. This value can also be measured in situ at the door of the combustion chamber. Infrared spectrometry is used for the various measurements: Fourier transform infrared spectrometry for the off-gases, and diode laser spectrometry for combustion

A new incinerator for burning radioactive waste

International Nuclear Information System (INIS)

Mallek, H.; Laser, M.

1978-01-01

A new two stage incinerator for burning radioactive waste consisting of a pyrolysis chamber and an oxidation chamber is described. The fly ash is retained in the oxidation chamber by high temperature filter mats. The capacity of the installed equipment is about 100 kg/h. Waste with different composition and different calorific value were successfully burnt. The operation of the incinerator can easily be controlled by addition of a primary air stream to the pyrolysis chamber and a secondary air stream to the oxidation chamber. During continuous operation the CO and C (organic) content is below 100 ppm and 50 ppm, respectively. The burn-out of the ash is very good. After minor changes the incinerator may be suitable for burning of α-bearing waste

Conventional incinerator redesign for the incineration of low level radioactive solid wastes.; Rediseno de un incinerador convencional para la incineracion de desechos radiactivos de bajo nivel.

Energy Technology Data Exchange (ETDEWEB)

Lara Z, L E.C.

1997-04-01

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).

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)

Treatment of solid radioactive waste: The incineration of low level radioactive waste

International Nuclear Information System (INIS)

Dirks, F.; Hempelmann, W.

1982-01-01

Nuclear facilities produce large quantities of burnable solid radioactive waste which incineration can reduce in volume and change into a form capable of ultimate storage. Experiments over many years were carried out at the Karlsruhe Nuclear Research Center to determine the boundary conditions for the design and construction of incineration plants for radioactive waste. On the basis of those experiments a test facility was started up in 1971. This operating facility consists of a shaft furnace lined with ceramics with a downstream series of ceramic flue gas filters. In 1976 the plant was exchanged by the installation of a pilot facility for burning organic solvents and of a flue gas scrubber. The plant has so far been in operation for more than 28000 hours and has processed in excess of 1500 to of solid and some 300 m 3 of liquid low level radioactive wastes. Various repairs and interventions were carried out without greatly impairing availability, which was 81 % on the average. The plant design is being used by various licensees in Japan and Europe; three plants are either in operation or completed, three more are under construction or in the planning stage. On the basis of the available process an incineration plant for alpha contaminated waste will be built at the Karlsruhe Nuclear Research Center in the next few years. (orig.)

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

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.

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)

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

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.)

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

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

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)

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

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

Feasibility study of cyclone incineration treatment for radioactive solid waste

International Nuclear Information System (INIS)

Zhou Lianquan; Wang Peiyi; Ma Mingxie; Yang Liguo; Li Xiaohai; Qiu Mingcai; Zhang Xiaobin; Dong Jingling; Lu Xiaowu; Li Chuanlian; Yang Baomin

2002-01-01

Feasibility study of cyclone incineration treatment for radioactive solid waste is introduced. The structure of cyclone incineration furnace is defined according to test results. The results show: under given conditions of technology: i.e., inlet flowrate ≥30 m/s, total volume ≥210 Nm 3 /h, the mixed solid material with more than 40% of plastics and rubber can completely be incinerated after suitable smash and mixing. The advantages of the furnace are: simple structure, high strength of volume heat, no preheating and combustion-supporting of assistant fuel, bridging and melt leak can be avoided in the stuff. The pretreatment of solid waste is simple, and a little amount of non-combustible substance in the waste can be allowed

Accumulative behavior of radioactive cesium during the incineration of municipal solid waste

International Nuclear Information System (INIS)

Mizuhara, Shinji; Kawamoto, Katsuya; Maeseto, Tomoharu; Kuramochi, Hidetoshi; Osako, Masahiro

2015-01-01

Understanding the long-term accumulation behavior of radioactive cesium (r- Cs) in municipal solid waste (MSW) incineration plants is important for safety management of them. In this study, first, not only air dose rate but also r-Cs activity in wall adhesion dust at different point in the inside of a MSW incineration plant were measured. The results showed that higher amounts of the Cs were observed in the surface layer of refractory and that higher air dose ratios were obtained in the upstream region in incineration process. However, the Cs content of adhered dust onto the surface material of incineration equipment was higher in downstream than upstream because of the decrease of flue gas temperature. (author)

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

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

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

International Nuclear Information System (INIS)

Sauer, R.E.; Jessop, D.

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

Incineration of radioactive wastes at the Nuclear Research Center Karlsruhe

Energy Technology Data Exchange (ETDEWEB)

Baehr, W; Hempelmann, W; Krause, H

1976-06-01

In 1971 a large incineration plant started operation in the Nuclear Research Center Karlsruhe. This plant is serving for routine incineration of up to 100 kg of combustible radioactive solids or 40 l of contaminated organic liquids and oils per hour. A dry off-gas cleaning system has been developed for this installation in which the fumes are cleaned by ceramic filter candles. After passing the filtering system and cooling, the off-gas is discharged directly through a stack. The activity concentration in the off-gas is measured by a continuous monitoring system. The ashes arising from the incineration are mixed with cement grout and filled into 200 l-drums. By this way approximately one drum of fixed ashes results from 100 drums of combustible wastes. During the first four years of operation, more than 4,000 m/sup 3/ of combustible solids and about 60 m/sup 3/ organic solvents have been incinerated in the plant. The operating experiences are presented.

The incineration of solid radioactive waste: a centralized solution

International Nuclear Information System (INIS)

Hernborg, G.; Broden, K.; Oehrn, G.

1985-01-01

Almost all the combustible low-level β- and γ-radioactive waste from Sweden, and even some waste from German nuclear power plants, is treated in an incineration plant at Studsvik. To date most of the ash has been put into 100-litre drums, which in turn have been put in 200-litre drums with concrete in between. Recently, methods have been developed and equipment installed for homogeneous solidification of the ash into concrete. Over the years since the start-up of the plant in 1976 the incinerator has worked with a high availability factor. Personnel doses and activity releases to the environment are well below limits set by regulatory authorities. (orig.)

Feasibility study of incineration treatment of radioactive waste oil

International Nuclear Information System (INIS)

Wang Peiyi; Zhou Lianquan; Ma Mingxie; Yang Liguo; Li Xiaohai; Qiu Mingcai; Zhang Xiaobin; Dong Jingling; Yang Baomin

2001-01-01

The author describes the combustion experiment of radioactive waste oil, including determination of the basic properties of the waste oils, pretreatment and incineration experiment. As for low flash point oil possibly mixed with gasoline, it is recommended to add kerosine to lower the viscosity. Spray incineration experiment shows that for waste oil with viscosity less than 30 mPa·s, it can be completely burnt even if the heat strength in the stove is less than 1.6 x 10 6 kJ/(m 3 ·h). Within a broad range of extra-air coefficient, CO concentration in flue gas is below 0.1%

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

Nuclear waste incineration technology status

Energy Technology Data Exchange (ETDEWEB)

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

1981-07-15

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.

Radioactivity decontamination efficiency of ceramic filter in an incineration volume reduction system of radioactive waste

International Nuclear Information System (INIS)

Kanbe, Hiromi; Mayuzumi, Masami; Yoshiki, Sinya; Sema, Toru; Koyama, Hiroaki; Ono, Tetsuo; Nagae, Madoka; Takaoku, Yoshinobu; Hozumi, Masahiro.

1987-01-01

The small pilot facility of a cyclone type suspension incineration system of radioactive waste was set up in order to evaluate the decontamination efficiency of a high efficiency ceramic filter. The evaluation was made by use of 54 Mn, 59 Fe, 60 Co, 65 Zn and 137 Cs. 1. The decontamination factor by one line of ceramic filter for every species were over 10 5 . 2. The decontamination factor increased by one oder when water vapor exists in off-gas. The same tendency was also observed when iron dioxide existed at the incineration of cation exchange resin. (author)

A commercial regional incinerator facility for treatment of low-level radioactive waste

International Nuclear Information System (INIS)

Sauer, R.E.; Jessop, D.T.

1986-01-01

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 fro 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

Incineration plant for radioactive waste at the Nuclear Research Center Karlsruhe

International Nuclear Information System (INIS)

Baehr, W.; Hempelmann, W.; Krause, H.

1977-02-01

In 1971 a large incineration plant started operation in the Nuclear Research Center Karlsruhe. This plant is serving for routine incineration of up to 100 kg of combustible radioactive solids or 40 l of contaminated organic liquids and oils per hour. A dry off-gas cleaning system has been developed for this installation in which the flue gases are cleaned by ceramic filter candles. After passing the filtering system and cooling the off-gas is discharged directly through a stack. The activity concentration in the off-gas is measured by a continuous monitoring system. The ashes arising from the incineration are mixed with cement grout and filled into 200 ldrums. By this way approximately one drum of fixed ashes results from 100 drums of combustible wastes. During the first four years of operation, more than 4,000 m 3 of combustible solids and about 60 m 3 organic solvents have been incinerated in the plant. The operating experiences are presented. (orig.) [de

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

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

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

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

Experimental study on pyrolysis incineration process for radioactive wastes

International Nuclear Information System (INIS)

Ma Mingxie; Qiu Mingcai; Wang Peiyi; Zhou Lianquan; Liu Xiaoqin

1993-01-01

In order to treat combustible radioactive wastes containing plastics and rubber in a considerable amount, a pyrolysis incineration process has been developed. Laboratory study and pilot test for the technology were performed. The results obtained in pilot test show that the waste containing a larger amount of plastics and rubber can be burnt perfectly in given technologic conditions, with a high volume-reduction factor obtained, and the process is easy to control

Technology for removing radioactive Cs from incineration fly ash

International Nuclear Information System (INIS)

Ichikawa, Seigo; Nishizaki, Yoshihiko; Takano, Takehiko; Kumagai, Naokazu

2016-01-01

Radioactive cesium contained in incineration fly ash is highly soluble in water. We took advantage of this fact to develop a method for first using water cleaning to transfer cesium to water and then using adsorbent to recover this cesium in high concentrations. Since the adsorbent becomes radioactive waste, inorganic minerals such as zeolite are desirable from the point of view of long-term storage stability; however, zeolite is not suitable for cleaning water containing materials that inhibit cesium adsorption such as K+ and Na+. The feature of the new technology is that it provides a method for effective recovery of cesium from contaminated cleaning water using insoluble ferro-cyanide which is synthesized in situ, and for heat treatment of this cesium adsorbed from the ferro-cyanide to zeolite, thereby achieving reduction of radioactive waste and improvement of stability for long-term storage. (author)

Decontamination factors of ceramic filter in radioactive waste incineration system

International Nuclear Information System (INIS)

Kanbe, Hiromi; Mayuzumi, Masami; Ono, Tetsuo; Yoshiki, Shinya; Kouyama, Hiroaki; Nagae, Madoka; Sekiguchi, Ryosaku; Takaoku, Yoshinobu; Hozumi, Masahiro.

1987-01-01

A suspension-firing type radioactive waste incineration system is developed and cold demonstration testing of ceramic filters for the system are carried out. The incineration system, which is useful for a wide variety of waste materials, can serve to simplify the facilities and to reduce the costs for waste disposal. The incineration system can be used for drying-processing of concentrated waste liquids and disposal of flame resistant materials including ion exchange resins and rubber, as well as for ordinary combustible solid materials. An on-line backwash system is adopted to allow the ceramic filters to operate stably for a long period of time. For one-step filtering using the ceramic filter, the decontamination factor is greater than 10 5 for the processing of various wastes. In a practical situation, there exist vapor produced by the spray drier and the cladding in used ion exchange resin, which act to increase the decontamination performance of the ceramic filters to ensure safe operation. For the waste incineration system equipped with a waste gas processing apparatus consisting of a ceramic filter and HEPA filter, the overall decontamination factor is expected to be greater than 10 6 at portions down to the outlet of the ceramic filter and greater than 10 8 at portions down to the outlet of the HEPA filter. (Nogami, K.)

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

Monitoring program for evaluating radionuclide emissions from incineration of low-level radioactive waste

International Nuclear Information System (INIS)

Wittmer, S.C.; Solomon, H.F.

1984-01-01

The implementation of an incineration program for low-level radioactive waste is a complex task, especially in the area of obtaining environmental permits. To provide assurance to the appropriate regulatory agencies involved with environmental permitting and others that an incineration program is properly conducted, emissions monitoring to identify radionuclides and their fate may be needed. An electronic spreadsheet software program Lotus 1-2-3 (Lotus Development Corporation) on an IBM Personal Computer has been used to perform data reduction for test results from such a monitoring program and to present them graphically to facilitate interpretation. The sampling technique includes: (1) the use of an EPA Method 5 stack sampling train modified to exclude the dry-catch filtration assembly with ethanolamine used to scrub incinerator gas at depressed temperatures and (2) a continuous composite liquid sampler for incinerator wet scrubber discharge to the sanitary sewer. Radionuclides in the samples are assayed using scintillation spectrometry

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

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

Protection and safety functions of different off-gas treatment systems in radioactive waste incineration

International Nuclear Information System (INIS)

Caramelle, D.; Chevalier, G.; Chevalier, G.

1986-01-01

Gaseous effluent cleaning installations are designed to protect workmen and environment and must be efficient enough to guarantee that the amounts of gases and dusts emitted by a furnace operating normally or accidentally are at an acceptable level in the atmosphere on the incinerator site. The process equipments necessary to operations and the monitoring devices must be reliable. The main risk in normal operation is occupational exposure close to the radioactive products accumulation points. The accidental risks are mainly related to an outage of the off-gas cleaning or a tightness failure with radioactive products dissemination resulting from either internal perturbation (filter tear, exhauster failure, ...) or external incident (electricity cut-off, furnace disarrangements, fire or explosion inside the incinerator). In view of these risks, it is interesting to examine the safety and protection functions of different components of off-gas treatment systems

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)

Setting up experimental incineration system for low-level radioactive samples and combustion experiments

International Nuclear Information System (INIS)

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

1997-01-01

An incineration system was constructed which were composed of a combustion furnace (AP-150R), a cyclone dust collector, radioisotope trapping and measurement apparatus and a radioisotope storage room built in the first basement of the Radioisotope Center. Low level radioactive samples (LLRS) used for the combustion experiment were composed of combustible material or semi-combustible material containing 500 kBq of 99m TcO 4 or 23.25 kBq of 131 INa. The distribution of radioisotopes both in the inside and outside of combustion furnace were estimated. We measured radioactivity of a smoke duct gas in terminal exit of the exhaust port. In case of combustion of LLRS containing 99m TcO 4 or 131 INa, concentration of radioisotopes at the exhaust port showed less than legal concentration limit of these radioisotopes. In cases of combustion of LLRS containing 99m TcO 4 or 131 INa, decontamination factors of the incineration system were 120 and 1.1, respectively. (author)

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

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

High temperature materials for radioactive waste incineration and vitrification. Revision 1

International Nuclear Information System (INIS)

Bickford, D.F.; Ondrejcin, R.S.; Salley, L.

1986-01-01

Incineration or vitrification of radioactive waste subjects equipment to alkaline or acidic fluxing, oxidation, sulfidation, carburization, and thermal shock. It is necessary to select appropriate materials of construction and control operating conditions to avoid rapid equipment failure. Nickel- and cobalt-based alloys with high chromium or aluminum content and aluminum oxide/chromium oxide refractories with high chromium oxide content have provided the best service in pilot-scale melter tests. Inconel 690 and Monofrax K-3 are being used for waste vitrification. Haynes 188 and high alumina refractory are undergoing pilot scale tests for incineration equipment. Laboratory tests indicate that alloys and refractories containing still higher concentrations of chromium or chromium oxide, such as Inconel 671 and Monofrax E, may provide superior resistance to attack in glass melter environments

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

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

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.

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

An incinerator for combustable radwastes

International Nuclear Information System (INIS)

Li Jingquan; Jiang Yun; Zhang Yinsheng; Chen Boling; Zhang Shihang

1989-01-01

An incinerator has been built up in Shanghai. In this paper, the devices of the incinerator, main parameters of the process, and the results of non-radioactive waste and simulated radwaste combustion tests were contributed. That provides reference information for radwaste treatment with incineration process

Performance evaluation of air cleaning devices of an operating low level radioactive solid waste incinerator

International Nuclear Information System (INIS)

Subramanian, V.; Surya Narayana, D.S.; Sundararajan, A.R.; Satyasai, P.M.; Ahmed, Jaleel

1997-01-01

Particle removal efficiencies of a cyclone separator, baghouse filters and a high efficiency particulate activity (HEPA) filter bank of an incinerator have been determined during the incineration of combustible low level solid radioactive wastes with surface dose of 20 - 50 gy/h. Experimental runs have been carried out to collect the particulates in various aerodynamic size ranges using an eight stage Andersen sampler and a low pressure impactor (LPI) while the incinerator is in operation. The collection efficiencies of the cyclone, baghouse and HEPA filters have been found to be 100 per cent for particles of size greater than 4.7, 2.1 and 1.1 μm respectively. The results of our investigations indicate that the air cleaning devices of the incinerator are working according to their design criteria. The data will be useful in the design and operation of air cleaning devices for toxic gaseous effluents. (author). 3 refs., 2 figs., 1 tab

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

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

The Studsvik incinerator

International Nuclear Information System (INIS)

Hetzler, F.

1988-01-01

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

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

Feasibility study of a granular bed prefilter for purifying combustion gases from a solid radioactive waste incinerator

International Nuclear Information System (INIS)

Girod, M.

1993-01-01

The purpose of incineration is to minimize the volumes of radioactive waste to be stored. Cleaning combustion gases from these incinerators requires prefilters to protect the very high efficiency filters (known by the French acronym THE). These prefilters should make it possible to recover products such as plutonium while at the same time presenting a very limited source of secondary waste. This document sets out the feasibility study for a granular bed prefilter. This bed should be made of a material which is itself combustible so that it can be recycled in the incinerator to minimize production of secondary waste. During an initial stage, a design study of a demonstration device was carried out using a calculation code constructed on the basis of existing physical models, and which makes it possible to forecast the performance of the support. This theoretical approach has been correlated against experimental results from the validation test. During a second stage, the study dealt with the selection of the material from which the bed was made as well as quantification of the release of radiation during incineration of the plutonium contamined material. In this way, the very low transfer of radioactivity into the gaseous phase was demonstrated. Finally, during a third stage, a study of the change in efficiency and the loss of charge of a granular bed filter was carried out during industrial operation using an incinerator. In conclusion, it was demonstrated that the granular bed represents a viable solution for prefiltering at 200 deg C. Research might develop along a different path and involve using the granular bed as a high temperature filter at 500 to 600 deg C

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

Loading device for incinerator

International Nuclear Information System (INIS)

Hempelmann, W.

1983-01-01

An incinerator for radioactive waste is described. Heat radiation from the incinerator into the loading device is reduced by the design of the slider with a ceramic plate and the conical widening of the pot, and also by fixing a metal plate between the pot and the floor. (PW) [de

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)

Improvement of the IRIS Process for Incineration of Various Radioactive Waste Compositions

International Nuclear Information System (INIS)

Lemort, F.; Charvillat, J. P.

2003-01-01

Incineration represents a promising weight and volume reduction technique for alpha-contaminated organic waste. Following several years of laboratory research initiated in 1983 on a nonradioactive prototype unit at the CEA's Rhone Valley (Marcoule) Research Center, an innovative process, IRIS, has been developed to meet the need for processing nuclear glove box waste containing large amounts of chlorine. In March 1999, the first highly chlorinated alpha-contaminated waste was incinerated in the industrial facility based on the IRIS process at the CEA's Valduc Center. The nonradioactive prototype at Marcoule and the radioactive facility at Valduc demonstrated that the process is highly effective with a continuously fed rotating tubular kiln and with a very effective control of corrosion by pyrolytic decomposition of the waste initially at 550 C. The ash quality meets specification requirements (< 1% carbon, < 1% chlorine) and the volume and weight reduction factors are sufficient (around 30). The offgas treatment system exhibits very high operating efficiency complying with gaseous emission standards

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

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.

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.

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

Incineration plant for thermal destruction of radioactive liquid wastes

International Nuclear Information System (INIS)

Bartoli, B.; Lisbonne, P.

1988-01-01

Incineration was selected to destroy organic liquids contaminated by radioelements. This treatment offers the advantage of reducing the volume of wastes considerably. Therefore an incineration plant has been built within the nuclear research center of Cadarache. After an experimental work with inactive organic liquids from June 1980 to March 1981, the incineration plant was approved by safety authorities for the incineration of contaminated organic liquids. The capacity ranges from 20l/hr to 50l/hr. On the basis of 6 years of operation and a volume of 200 m3 the incineration plant has shown reliable operating conditions in the destruction of various contaminated organic liquids

High temperature incineration. Densification of granules from high temperature incineration

International Nuclear Information System (INIS)

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

1982-01-01

The incineration system of radioactive waste discussed in this report, is an ''integral'' system, which directly transforms a definite mixture of burnable and unburnable radioactive waste in a final product with a sufficient insolubility to be safely disposed of. At the same time, a significant volume reduction occurs by this treatment. The essential part of the system is a high temperature incinerator. The construction of this oven started in 1974, and while different tests with simulated inactive or very low-level active waste were carried out, the whole system was progressively and continuously extended and adapted, ending finally in an installation with completely remote control, enclosed in an alpha-tight room. In this report, a whole description of the plant and of its auxiliary installations will be given; then the already gained experimental results will be summarized. Finally, the planning for industrial operation will be briefly outlined. An extended test with radioactive waste, which was carried out in March 1981, will be discussed in the appendix

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

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

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

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

Improvement of incineration efficiency of spent ion exchange resins on the incinerator at nuclear power plants. Manufacturing the solids of the resins mixed with paraffin wax and their incinerating test results on actual incinerator

International Nuclear Information System (INIS)

Izumi, Takeshi; Ohtsu, Takashi; Inagawa, Hirofumi; Kawakami, Takashi; Hagiwara, Masahiro; Ino, Takao; Ishiyama, Yuji

2011-01-01

In nuclear power plants, ion exchange resins are used at water purification systems such as condensate demineralizers. After usage, used ion exchange resins are stored at plants as low level radioactive wastes. Ion exchange resins contain water and so, those are flame resistant materials. At present, ion exchange resins are incinerated with other inflammable materials at incinerators. Furthermore, ion exchange resins are fine particle beads and are easy to be scattered in all directions, so operators must pay attentions for treatment. Then, we have developed the new solidification system of ion exchange resins with paraffin wax. Ion exchange resins are mixed and extruded with paraffin wax and these solids are enabled to incinerate at existing incinerators. In order to demonstrate this new method, we made the large amount of solids and incinerated them at actual incinerator. From these results, we have estimated to be able to incinerate the solids only at actual incinerator. (author)

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)

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

R and D for an off-gas treatment system for a slagging pyrolysis radioactive waste incinerator. Final report for Phase I

International Nuclear Information System (INIS)

Christian, J.D.; Kirstein, B.E.; Pence, D.T.

1978-01-01

Preliminary evaluations were made of off-gas treatment needs for a slagging pyrolysis incinerator (SPI) of Andco--Torrax design for the treatment of radioactive waste at the INEL. Approximate decontamination factors (DFs) for particulates of 10 7 and for volatilized radionuclides of 10 3 will be required across the off-gas system. If lead is present in the waste at concentrations greater than 25-to-120 g/metric ton, volatilized lead will result in formation of substantial deposits in the off-gas system and regenerative towers. A review was made of radioactive incinerator development. Particulate and volatile component removal mechanisms and devices were reviewed. Three off-gas treatment systems were proposed for the SPI which will provide DFs for particulates of 10 8 . 9 figures, 7 tables

Incineration of spent ion exchange resin

International Nuclear Information System (INIS)

Hasegawa, Chiaki

1990-01-01

It is a pressing need to reduce radioactive waste which is generated from the maintenance and operation of a nuclear power plant. Incineration of low level combustible solid waste such as polyethylene seats, paper and others have been successfully performed since 1984 at the Shimane Nuclear Power Station. Furthermore, for extending incineration treatment to spent ion exchange resin, the incineration test was carried out in 1989. However, as the cation exchange resin contains sulfur and then incineration generates SOx gases, so the components of this facility will be in a corrosive environment. We surveyed incineration conditions to improve the corrosive environment at the exhaust gas treatment system. This paper includes these test results and improved method to incinerate spent ion exchange resin. (author)

Incineration process fire and explosion protection

International Nuclear Information System (INIS)

Ziegler, D.L.

1975-01-01

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

Recent research in incinerator radioactive smoke filtration and improvements in a TRU waste incinerator plant

International Nuclear Information System (INIS)

Carpernier, S.; de Tassigny, C.; Hashimoto, Y.; Inove, A.

1989-01-01

In the area concerned, when incineration is carried out, it is always accompanied by the production of combustion gases which entrain fly ash, which is generally hazardous and/or a carrier of radioactivity, and which must be collected before the gasses are releases to the atmosphere. The fly ash concerned consists of secondary solid effluents which, with the consumable filters designed to stop them, tend to lower and quality of the waste volume and weight reduction factors, sometimes significantly. Hence it is an excellent idea to burn the organic part of the fly ash and also to stop thoroughly the inorganic parts by prefilters and final filters, carefully designed and selected for their performance and their longest possible service life, in order to minimize the process waste built up with time. This paper discusses the testing of ceramic and fiber candles for their refractive qualities, thermal shock behavior, commercial cost and efficiency for a given grain size distribution

Contamination of incinerator at Tokai Reprocessing Plant

International Nuclear Information System (INIS)

Takahashi, Mutsuo

1994-01-01

Originally, at Tokai Reprocessing Plant an incinerator was provided in the auxiliary active facility(waste treatment building). This incinerator had treated low level solid wastes generated every facilities in the Tokai Reprocessing Plant since 1974 and stopped the operation in March 1992 because of degeneration. The radioactivity inventory and distribution was evaluated to break up incinerator, auxiliary apparatuses(bag filter, air scrubbing tower, etc.), connecting pipes and off-gas ducts. This report deals with the results of contamination survey of incinerator and auxiliary apparatuses. (author)

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

Incineration plant for low active waste at Inshass, LAWI

International Nuclear Information System (INIS)

Krug, W.; Thoene, L.; Schmitz, H.J.; Abdelrazek, I.D.

1993-10-01

The LAWI (Low Active Waste Incinerator) prototype incinerating plant was devised and constructed according to the principle of the Juelich thermoprocess and installed at the Egyptian research centre Inshass. In parallel, AEA Cairo devised and constructed their own operations building for this plant with all the features, infrastructural installations and rooms required for operating the plant and handling and treating low-level radioactive wastes. The dimensions of this incinerator were selected so as to be sufficient for the disposal of solid, weakly radioactive combustible wastes from the Inshass Research Centre and the environment (e.g. Cairo hospitals). (orig./DG) [de

Incinerator for power reactor low-level radioactive waste

International Nuclear Information System (INIS)

Drolet, T.S.; Sovka, J.A.

1976-01-01

The technique chosen for volume reduction of combustible waste is incineration by a propane-fired unit. Noncombustible material will be compacted into 200 liter drums. A program of segregation of wastes at the producing nuclear stations was instituted. The design and operation of the incinerator, dose limits to the public, and derived release limits for airborne effluents are discussed

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)

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

Recommendations for continuous emissions monitoring of mixed waste incinerators

International Nuclear Information System (INIS)

Quigley, G.P.

1992-01-01

Considerable quantities of incinerable mixed waste are being stored in and generated by the DOE complex. Mixed waste is defined as containing a hazardous component and a radioactive component. At the present time, there is only one incinerator in the complex which has the proper TSCA and RCRA permits to handle mixed waste. This report describes monitoring techniques needed for the incinerator

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

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

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

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.

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.)

Requirements for permitting a mixed waste incinerator

International Nuclear Information System (INIS)

Trichon, M.; Feldman, J.; Serne, J.C.

1990-01-01

The consideration, design, selection and operation of any incinerator depends primarily on characteristic quality (ultimate and proximate analyses) and quantity to the waste to be incinerated. In the case of burning any combination of mixed hazardous, biomedical and radioactive low level waste, specific federal and generic state environmental regulatory requirements are outlined. Combustion chamber temperature and waste residence time requirements will provide the rest of the envelope for consideration. Performance requirements must be balanced between the effects of time and temperature on destruction of the organic waste and the vaporization and possible emission of the inorganic waste components (e.g., toxic metals, radioactive inorganics) as operating conditions and emission levels will be set in state and federal regulatory permits. To this end the complete characterization of the subject waste stream must be determined if an accurate assessment of incineration effectiveness and impact are to be performed

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

Review of the incineration of 500 tonnes of radio-active residues

International Nuclear Information System (INIS)

Rodier, J.; Seyfried, P.; Charbonneaux, M.

1969-01-01

During its first five years operation, the incinerator at the Marcoule Centre has burnt almost 500 tonnes of radio-active residues. Improvements in some of the details of the process have been made during this period; they concern the nature of the materials involved. The technical and radiological results for the installation are very favorable, and have made it possible to maintain a high charge factor.Although the overall economic results are not advantageous in the case of ungraded solid residues this method represents nevertheless the best available for eliminating oils, solvents, wood and dead animals. It can also be of use furthermore each time that a dilution in the atmosphere can advantageously be used as a method of disposing of certain radio elements such as tritium or carbon 14 in the form of gases or vapours. (author) [fr

Fluidized bed incineration of transuranic contaminated waste

International Nuclear Information System (INIS)

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

1978-01-01

A 9 kg/hr pilot scale fluidized bed incinerator is now being used for burning various types of radioactive waste at Rocky Flats Plant. General solid combustible waste containing halogenated materials is burned in a fluidized bed of sodium carbonate for in situ neutralization of thermally generated acidic gases. A variety of other production related materials has been burned in the incinerator, including ion exchange resin, tributyl phosphate solutions, and air filters. Successful operation of the pilot plant incinerator has led to the design and construction of a production site unit to burn 82 kg/hr of plant generated waste. Residues from incinerator operations will be processed into glass buttons utilizing a vitrification plant now under development

Incinerator for radioactive wastes

International Nuclear Information System (INIS)

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

1981-01-01

A two-stage incinerator is provided which includes a primary combustion chamber and an afterburn chamber for off-gases. The latter is formed by vertical tubes in combination with associated manifolds which connect the tubes together to form a continuous tortuous path. Electrically-controlled heaters surround the tubes while electrically-controlled plate heaters heat the manifolds. A gravity-type ash removal system is located at the bottom of the first afterburner tube while an air mixer is disposed in that same tube just above the outlet from the primary chamber. A ram injector in combination with rotary a magazine feeds waste to a horizontal tube forming the primary combustion chamber. (author)

Incineration/vitrification of radioactive wastes and combustion of pyrolysis gases in thermal plasmas

International Nuclear Information System (INIS)

Girold, Ch.

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)

High temperature slagging incineration of hazardous waste

International Nuclear Information System (INIS)

Vanbrabant, R.; Van de Voorde, N.

1987-01-01

The SCK/CEN, as the treatment center for the low level radioactive waste in Belgium, develops appropriate treatment systems for different kinds of wastes. The technical concept of the high temperature slagging incineration system has been developed and improved. The construction of the first demonstration plant was initiated in 1974. Since then the system has been operated regularly and further developed with the view to industrial operations. Now it handles about 5 tons of waste in a week. The waste which is treated consists of low level beta/gamma and alpha-contaminated radioactive waste. Because of the special characteristics the system is thought to be an excellent incineration system for industrial hazardous waste as well. Recently the SCK/CEN has received the authorization to treat industrial hazardous waste in the same installation. Preliminary tests have been executed on special waste products, such as PCB-contaminated liquids, with excellent incineration results. Incineration efficiency up to 99.9999% could be obtained. The paper presents the state of the art of this original The SCK/CEN-technology and gives the results of the tests done with special hazard

Volume Reduction of Decommissioning Radioactive Burnable and Metal Wastes

Energy Technology Data Exchange (ETDEWEB)

Min, B. Y.; Lee, Y. J.; Yun, G. S.; Lee, K. W.; Moon, J. K. [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of); Choi, Y. K.; Cho, J. H. [SunKwang Atomic Energy Safety Co., Seoul (Korea, Republic of)

2014-10-15

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.

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

Savannah River Plant incinerator demonstration

International Nuclear Information System (INIS)

Lewandowski, K.E.

1983-01-01

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

Radioactive waste incineration system cold demonstration test

Energy Technology Data Exchange (ETDEWEB)

Hozumi, Masahiro; Takaoku, Yoshinobu; Koyama, Shigeru; Nagae, Madoka; Seike, Yasuhiko; Yamanaka, Yasuhiro; Shibata, Kenji; Manabe, Kyoichi

1984-12-01

To demonstrate Waste Incineration System (WIS) which our company has been licensed by Combustion Engineering Inc., USA we installed a demonstration test plant in our Hiratsuka Research Laboratory and started the demonstration test on January 1984. One of the characteristics of this system is to be able to process many kinds of wastes with only one system, and to get high volume reduction factors. In our test plant, we processed paper, cloth, wood, polyethylene sheets as the samples of solid combustible wastes and spent ion exchange resins with incineration and processed condensed liquid wastes with spray drying. We have got good performances and enough Decontamination Factor (DF) data for the dust control equipment. In this paper, we introduce this demonstration test plant and report the test results up to date. (author).

Commercial incineration demonstration

International Nuclear Information System (INIS)

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

1981-01-01

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

Advice concerning the advantages of a reference incinerator for low-level and intermediate-level radioactive waste processing

International Nuclear Information System (INIS)

Luyten, G.B.

1985-05-01

In this report, an inventory is presented of new incinerators and flue gas filters used in low and intermediate-level radioactive waste combustion. It is argued that a 'reference equipment' for the combustion of solid and liquid low- and intermediate-level wastes best meets existing Dutch radiation protection standards. A cost-benefit analysis of such an equipment is given including annual costs of investment, capital and exploration. A separate combustion process of organic liquids and carrions is considered finally. (G.J.P.)

System of the incineration for the liquid scintillation garbage

International Nuclear Information System (INIS)

Naba, Katsumi

1981-12-01

In Japan from 1980 the incineration of the used scintillation liquid has been permitted according to the safety guide regulation of Japan Scientific Technology Agency. This incineration method would disperse the radioactivity in local site and destroy the chemicals at the same time. This system are consist of three parts. (1) Filtration and pH. adjustment of liquid garbage. (2) Bubbling vaporization in closed cycle. The temperature of the solution inside vessel is kept from 65 0 C to 85 0 C and the solution is bubbled with nealy 4 0 C circulated air. After the end of distillation, water layer is separated from the organic chemical layer and put it down the drain according to the regulation. (3) The residue is mixed with only the distilled organic chemicals according to the next classification, thereafter incineration is carried out. (a) For under the radioactive concentration of 1 x 10 -3 μCi/ml, the mixed scintillation liquid are burned up in specially designed incinerator. (b) For over the level of 1 x 10 -3 μCi/ml, only the distilled organic chemicals are burned up and the residue will be sent to the Waste Disposal Site. (c) For under the water content of 5% these liquid garbage can be directly are burned up without distillation The residue seemed to be suitable for the combustion of the dried carcased animals as the auxiliary fuels. This incinerator will be able to use as room heater or water heater for the bath without radioactive contamination inside of install room. (author)

Incineration of spent ion exchange resins in a triphasic mixture at Belgoprocess

International Nuclear Information System (INIS)

Deckers, J.; Luycx, P.

2003-01-01

Up to 1998, spent ion exchange resins have been fed to the incinerator in combination with various other solid combustible wastes at Belgoprocess. However, thanks to sustained efforts to reduce radioactive waste production in all nuclear facilities in Belgium, the annual production of solid combustible waste is now much too small to allow this practice to be continued. Since the incinerator at Belgoprocess is not capable of treating spent ion exchange resins as such, it was decided to adopt the use of foam as a carrier to feed the resins to the incinerator. The mixture is a pseudohomogeneous charged foam, ensuring easy handling and allowing incineration in the existing furance, while a number of additives may be included, such as oil to increase the calorific value of the mixture and accelerate combustion. The first incineration campaign of spent ion exchange resins in a triphasic foam mixture, in conjunction with other liquid and solid combustible wastes, will be started in January 2000. The foam, comprising 70% by weight of resins, 29% by weight of water and 1% by weight of surfactant will be pulverized in the incinerator through an injection lance, at a feed rate of 40 to 100 kg/h. The incinerator and associated off-gas treatment system can be operated at standard conditions. Belgoprocess is the subsidiary of the Belgian national agency for the management of radioactive waste, known by its Dutch and French acronyms, NIRAS and ONDRAF respectively. The company ensures the treatment, conditioning and interim storage of nearly all radioactive waste produced in Belgium. (orig.)

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

Development of Mitsui/Juelich Incineration System and hydro-thermal ash solidification

International Nuclear Information System (INIS)

Suzuki, S.; Kamada, S.; Nakamori, Y.; Katakura, M.; Yamazaki, N.

1988-01-01

This paper summarizes the developing program for Mitsui/Juelich Incinerated System combined with Hydrothermal ash solidification. The system is an integrated one and capable for volume reduction of various kind of radioactive waste and safe disposal of residual incinerator ash. The system also has an advantage of reducing construction and operation cost. An outline of the incineration plant is also presented in this paper

Problems of safety and protection posed during overpressures in radioactive waste incinerator combustion chambers

International Nuclear Information System (INIS)

Chevalier, G.; Caramelle, D.

1987-01-01

The incineration of radioactive spent fuel is a method of preserving these wastes offering a substantial reduction in volume (from 20 to 50), and the solid residue (ash, etc.) can be packaged and stored more safely than the initial wastes. However, these advantages should not be acquired to the detriment of safety and protection of personnel and of the environment during and after operation. Our recommendations are aimed to define the conditions to be satisfied so that the equipment to be constructed, as well as their method of use: - ensure the correct operation of the installation under the stipulated conditions - limit the consequences of an incident with respect to the installations, the personnel and the environment

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

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

Oxygen incineration process for treatment of alpha-contaminated wastes

Energy Technology Data Exchange (ETDEWEB)

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.

The Valduc waste incineration facility starts operations (iris process)

International Nuclear Information System (INIS)

Chateauvieux, H.; Guiberteuau, P.; Longuet, T.; Lannaud, J.; Lorich, M.

1998-01-01

In the operation of its facilities the Valduc Research Center produces alpha-contaminated solid waste and thus decided to build an incineration facility to treat the most contaminated combustible waste. The process selected for waste incineration is the IRIS process developed by the CEA at the Marcoule Nuclear Research Center. The Valduc Center asked SGN to build the incineration facility. The facility was commissioned in late 1996, and inactive waste incineration campaigns were run in 1997. The operator conducted tests with calibrated radioactive sources to qualify the systems for measuring holdup of active material from outside the equipment. Chlorinated waste incineration test runs were performed using the phosphatizing process developed by the Marcoule Research Center. Inspections performed after these incineration runs revealed the complete absence of corrosion in the equipment. Active commissioning of the facility is scheduled for mid-1998. The Valduc incinerator is the first industrial application of the IRIS process. (author)

CIF---Design basis for an integrated incineration facility

International Nuclear Information System (INIS)

Bennett, G.F.

1991-01-01

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

Incineration facility for radioactively contaminated polychlorinated biphenyls and other wastes

International Nuclear Information System (INIS)

1982-06-01

The statement assesses the environmental impacts associated with the construction of an incineration facility and related support facilities for the disposal of hazardous organic waste materials (including PCBs) which are contaminated with trace quantities of low-assay enriched uranium. The proposed action includes the incineration facility at Oak Ridge, Tennessee and storage, packaging, and shipping facilities at the Gaseous Diffusion Plants in Paducah, KY, and Portsmouth, OH; hazardous organic wastes from these plants and from the Y-12 Plant and Oak Ridge National Laboratories would be shipped to the proposed incineration facility. Impacts assessed include the effects of the project on air and water quality, on socioeconomic conditions, on public and occupational health and safety, and on ecology. Additionally, the statement presents an assessment of the potential impacts from accidents at the incineration facility or during transportation of the waste materials to the facility. The major impact identified was the potential for short-term occupational exposure to high concentrations of PCBs in smoke during the worst credible accident; mitigation of this impact will be addressed during the final design of the proposed facility. Alternatives which were assessed include no action, chemical destruction processes, and alternative transportation routes; all would have greater adverse impact or would increase the risk of an accident with the potential for adverse impact. The alternatives of commercial disposal, alternative sites, multiple incinerators, and alternative modes were eliminated from detailed analysis either because they are not feasible or because preliminary analysis showed that they would have clearly more adverse impact upon the environment than the proposed action

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

Control system for high-temperature slagging incinerator plant

International Nuclear Information System (INIS)

Matsuzaki, Yuji

1986-01-01

Low-level radioactive wastes generated in the nuclear generating plants are increasing year by year and to dispose them safely constitutes a big problem for the society. A few years ago, as the means of reducing them to as little volume as possible by incinerating and fusing the wastes, a high-temperature slagging incinerating method was developed, and this method is highly assessed. JGC Corp. has introduced that system technology and in order to prove the capacity of disposal and salubrity of the plant, and have constructed a full-sized pilot plant, then obtained the operational record and performance as they had planned. This report introduces the general processing of the wastes from their incineration and fusion as well as process control technology characteristic to high-temperature slagging incinerator furnaces and sensor technology. (author)

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

Incineration in the nuclear field. The SGN experience

International Nuclear Information System (INIS)

Carpentier, S.

1993-01-01

The operation of power reactors, like that of fuel fabrication and nuclear fuel reprocessing plants, generated substantial quantities of waste. A large share of this waste is low- and medium-level waste, which is also combustible. Similarly, a number of institutes, laboratories, and hospitals, in the course of their activities, generated waste which a portion is radioactive and combustible. The chief advantage of incineration is to minimize the volume of burnable waste treated, and to produce a residue termed 'ash'. SGN has built up 25 years of experience in this field. The incinerators have been designed and the incineration processes are specially studied by SGN

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

Fluidized bed incineration of radioactive waste

International Nuclear Information System (INIS)

Ziegler, D.L.

1976-01-01

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

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)

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

The radioactive organic wastewater treatment of INER

International Nuclear Information System (INIS)

Shen Chinchang; Chen Chaorui; Chung Jenchren

2014-01-01

The treatment strategy of radioactive organic wastewater was to separate it at first, then to treat it step by step by the characteristics of liquid layer. The waste liquid has separated into three layers, the organic layer, aqueous layer and the bottom gel mastic by natural sedimentation. The organic layer has occupied 23% of the total volume, the intermediate aqueous layer occupied 75% of the total volume, the bottom mastic was about 2% of the total. The aqueous layer of organic waste was with Total Organic Carbon (TOC) 20,000ppm. The combustion test shows good treatment performance and all samples can be decomposed completely by incineration. The experiment of incineration has passed the test more than 200 batches and 3000L low-level radioactive organic aqueous solution. The process goes smoothly and gas emission values far below the regulatory limit. Each kilogram of polymer absorber can absorb 45 kg aqueous solution to form a solid combustible material and can be decomposed by incineration. Organic waste solvents were diesel miscible and similar calorific value and small viscosity. It can be used as an incinerator auxiliary fuel of radioactive incinerator. The method testing has begun in this year. It has expected to save diesel fuel consumption of incineration, and well solved such kind waste liquid. (author)

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

Review of the incineration of 500 tonnes of radio-active residues; Bilan de l'incineration de 500 tonnes de residus radioactifs

Energy Technology Data Exchange (ETDEWEB)

Rodier, J; Seyfried, P; Charbonneaux, M [Commissariat a l' Energie Atomique, Chusclan (France). Centre de Production de Plutonium de Marcoule

1969-07-01

During its first five years operation, the incinerator at the Marcoule Centre has burnt almost 500 tonnes of radio-active residues. Improvements in some of the details of the process have been made during this period; they concern the nature of the materials involved. The technical and radiological results for the installation are very favorable, and have made it possible to maintain a high charge factor.Although the overall economic results are not advantageous in the case of ungraded solid residues this method represents nevertheless the best available for eliminating oils, solvents, wood and dead animals. It can also be of use furthermore each time that a dilution in the atmosphere can advantageously be used as a method of disposing of certain radio elements such as tritium or carbon 14 in the form of gases or vapours. (author) [French] L'incinerateur du Centre de Marcoule a brule, durant les 5 premieres annees de fonctionnement, pres de 500 tonnes de residus radioactifs. Les ameliorations de detail realisees au cours de cette periode ont porte sur la nature des materiaux employes. Les bilans techniques et radiologiques de l'installation sont tres favorables et ont permis de maintenir un facteur de charge eleve. Si le bilan economique n'est pas favorable a l'incineration des residus solides 'tout venant' cette methode constitue cependant la solution ideale pour l'elimination des huiles, des solvants, du bois et des cadavres d'animaux. En outre, elle peut etre interessante chaque fois que la dilution dans l'atmosphere peut etre avantageusement mise a profit pour rejeter certains radioelements tels que le tritium ou le carbone 14 sous forme de gaz ou de vapeurs. (auteur)

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

Controlled air pyrolysis incinerator

International Nuclear Information System (INIS)

Dufrane, K.H.; Wilke, M.

1982-01-01

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

Alpha waste incinerator at the Cea Valduc

International Nuclear Information System (INIS)

Anon.

2000-01-01

The Cea/Valduc has brought into operation an incinerator for alpha waste. The incineration is in two steps. The first one is a pyrolysis under reduction atmosphere in a furnace at 550 celsius degrees and the second one is a calcination under oxidizing atmosphere of the pyrolysis residue in a furnace at 900 celsius degrees. The ashes have less than 1% of carbon. The gas coming from incineration become oxidized at 1100 Celsius degrees, then are cooled, filtered to eliminate any track of radioactivity. Then, they are cleaned with a neutralisation process. The facility reduces the volume of waste in a factor 20. The capacity of treatment is 7 kg/h. The annual capacity is 30 m 3 . The investment represents 70 millions of francs and the cost of functioning is 2 M F by year. (N.C.)

Decommissioning Combustible Waste Treatment using Oxygen-Enriched Incinerator

Energy Technology Data Exchange (ETDEWEB)

Min, Byungyoun; Lee, Yoonji; Yun, Gyoungsu; Lee, Kiwon; Moon, Jeikwon [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

2014-05-15

The aim of the paper is current status of treatment for the decommissioning combustible waste in KAERI and for the purpose of the volume reduction and clearance for decommissioning combustible wastes generated by the decommissioning projects. The incineration technology has been selected for the treatment of combustible wastes. About 34 tons of decommissioning combustible waste has been treated using Oxygen Enriched incineration. Temperature, pressure of major components, stack gas concentration, i. e., SOx, NOx, CO, CO{sub 2} and HCl, and the residual oxygen were measured. Measured major parameters during normal operation were sustained on a stable status within a criteria operation condition. Oxygen enriched air, 22vol. % (dry basis) was used for stable incineration. The volume reduction ratio has achieved about 1/117. The incineration with decommissioning radioactive combustible waste is possible with moderate oxygen enrichment of 22 vol.% (dry basis) into the supply air. The incineration facility operated quite smoothly through the analysis major critical parameters of off-gas. The pressure, off-gas flow and temperature of major components remained constant within the range specified. The measures gases and particulate materials in stack were considerably below the regulatory limits. The achieved volume reduction ratio through incineration is about 1/117.

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.

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)

Controlled air incineration of hazardous chemical waste at the Los Alamos National Laboratory

International Nuclear Information System (INIS)

Stretz, L.A.; Borduin, L.C.; Draper, W.E.; Koenig, R.A.; Vavruska, J.S.

1982-01-01

An incineration system, originally demonstrated as a transuranic (TRU) waste volume-reduction process, is described. The production-scale controlled air incinerator using commercially available equipment and technology was modified for solid radioactive waste service. The same incinerator and offgas treatment system has been modified further for use in evaluating the destruction of hazardous liquid wastes such as polychlorinated biphenyls (PCBs) and hazardous solid wastes such as pentachlorophenol (PCP)-treated wood. Results of a PCP-treated wood incineration test show a PCP destruction efficiency of greater than 99.99% in the primary chamber for the operating conditions investigated. Conditions and results for this test are described

The Controlled-Air Incinerator at Los Alamos

Energy Technology Data Exchange (ETDEWEB)

Newmyer, J.N.

1994-04-01

The Controlled-Air Incinerator (CAI) at Los Alamos is being modified and upgraded to begin routine operations treating low-level mixed waste (LLMW), radioactively contaminated polychlorinated biphenyl (PCB) wastes, low-level liquid wastes, and possibly transuranic (TRU) wastes. This paper describes those modifications. Routine waste operations should begin in late FY95.

Incineration of low level waste

International Nuclear Information System (INIS)

Gussmann, H.; Klemann, D.; Mallek, H.

1986-01-01

At present, various incinerators for radioactive waste are operated with more or less good results worldwide. Both, plant manufacturers and plant owners have repeatedly brought about plant modifications and improvements over the last 10 years, and this is true for the combustion process and also for the waste gas treatment systems. This paper attempts to summarize requirements, in general, by owner/operators for the plants which are designed and erected today

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

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

Evaluation of physicochemical properties of radioactive cesium in municipal solid waste incineration fly ash by particle size classification and leaching tests.

Science.gov (United States)

Fujii, Kengo; Ochi, Kotaro; Ohbuchi, Atsushi; Koike, Yuya

2018-07-01

After the Fukushima Daiichi-Nuclear Power Plant accident, environmental recovery was a major issue because a considerable amount of municipal solid waste incineration (MSWI) fly ash was highly contaminated with radioactive cesium. To the best of our knowledge, only a few studies have evaluated the detailed physicochemical properties of radioactive cesium in MSWI fly ash to propose an effective method for the solidification and reuse of MSWI fly ash. In this study, MSWI fly ash was sampled in Fukushima Prefecture. The physicochemical properties of radioactive cesium in MSWI fly ash were evaluated by particle size classification (less than 25, 25-45, 45-100, 100-300, 300-500, and greater than 500 μm) and the Japanese leaching test No. 13 called "JLT-13". These results obtained from the classification of fly ash indicated that the activity concentration of radioactive cesium and the content of the coexisting matter (i.e., chloride and potassium) temporarily change in response to the particle size of fly ash. X-ray diffraction results indicated that water-soluble radioactive cesium exists as CsCl because of the cooling process and that insoluble cesium is bound to the inner sphere of amorphous matter. These results indicated that the distribution of radioactive cesium depends on the characteristics of MSWI fly ash. Copyright © 2018 Elsevier Ltd. All rights reserved.

Rocky Flats Plant fluidized-bed incinerator

International Nuclear Information System (INIS)

Meile, L.J.; Meyer, F.G.; Johnson, A.J.; Ziegler, D.L.

1982-01-01

Laboratory and pilot-scale testing of a fluidized-bed incineration process for radioactive wastes led to the installation of an 82-kg/hr demonstration unit at Rocky Flats Plant in 1978. Design philosophy and criteria were formulated to fulfill the needs and objectives of an improved radwaste-incineration system. Unique process concepts include low-temperature (550 0 C), flameless, fluidized-bed combustion and catalytic afterburning; in-situ neutralization of acid gases; and dry off-gas cleanup. Detailed descriptions of the process and equipment are presented along with a summary of the equipment and process performance during a 2-1/2 year operational-testing period. Equipment modifications made during the test period are described. Operating personnel requirements for solid-waste burning are shown to be greater than those required for liquid-waste incineration; differences are discussed. Process-utility and raw-materials consumption rates for full-capacity operation are presented and explained. Improvements in equipment and operating procedures are recommended for any future installations. Process flow diagrams, an area floor plan, a process-control-system schematic, and equipment sketches are included

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

Feasibility and conceptual design for a mobile incineration system for combustible LLW

International Nuclear Information System (INIS)

1982-09-01

Since volume reduction by incineration, with subsequent solidification before shipping, can result in typical overall reductions between 40 to 1 and 60 to 1 (depending on density), there are strong economic incentives for small generators to incinerate their low-level radioactive wastes, and minimize the volumes for which they must pay to ship and bury. Because of these factors, the concept of a Mobile Incineration System (MIS) appears to be a viable alternative for small generators. This report covers the conceptual design of a MIS consisting of a controlled-air incinerator with the required off-gas treatment system mounted on two semi-trailers which can be brought to the site of the small generator. It also covers the regulatory and licensing aspects, as well as the economics related to the design. 17 tables

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.

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

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

What it took to get an NRC license for centralized incineration

International Nuclear Information System (INIS)

DiSalvo, R.; Zielenbach, W.

1987-01-01

In 1982, Battelle joined five other commercial generators of low level radioactive waste in conducting a study of the technical and economic feasibility and the licensability of a central facility for incinerating LLW. The project generated a license application to the USNRC and supporting documentation related to the safety and environmental impacts of the facility. After thorough review, the NRC has issued a Finding of No Significant Impact and the associated license authorization, which is the first of its kind for an incineration facility

Siting a low-level radioactive waste incinerator in North Carolina: the impacts of public opposition

International Nuclear Information System (INIS)

Miller, E.M.

1987-01-01

Establishing low-level radioactive waste (LLRW) facilities has become increasingly difficult due to public opposition to siting proposals. Widespread opposition to siting new waste management facilities of all types has focused sharp attention on the technical, political, and socioeconomic problems associated with siting controversial, but necessary facilities. This paper reviews a recent private sector initiative to site a LLRW incinerator in Bladen County, NC. Public reactions to the proposed facility are documents, as well as reasons for public opposition to the facility. The impacts of public opposition on the siting process, regulatory agencies, the media, industry, the general public, and elected officials are examined. The paper points out how public opposition to proposed waste management facilities may have both positive and negative impacts on the long-term management of LLRW. In doing so, the paper addresses policy questions, processes, and perceptions that will shape the debate over the development and location of new treatment and disposal facilities for managing LLRW. 14 references

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)

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

Development of low level radioactive waste incineration plant

International Nuclear Information System (INIS)

Shaharum bin Ramli; Azmir bin Hanafiah

1994-01-01

A laboratory scale liquid waste incineration plant has been constructed. Preliminary tests were conducted by burning kerosene as the waste. The temperature reached 1200 deg.C. The exhaust gas was analysed for CO and CO sub 2 content. The hydrocarbon content was not measured without the proper analyser. Thus, parameters such as the optimum air:kerosene ratio and the maximum kerosene injection rate could not be determined. Complete tests will be carried out with the newly received hydrocarbon, NO sub x, CO, CO sub 2 and O sub 2 gas analyser

Incineration of contaminated oil from Sellafield - 16246

International Nuclear Information System (INIS)

Broadbent, Craig; Cassidy, Helen; Stenmark, Anders

2009-01-01

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

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)

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

On-line, real-time measurements of decontamination factors for a low-level waste incinerator

International Nuclear Information System (INIS)

Close, D.A.; Draper, W.E.

1982-01-01

A method is described to monitor the distribution of radioactive isotopes through the off-gas treatment system of an incinerator. Simulated commercial waste spiked with known amounts of five fission products, 131 I, 106 Ru, 137 Cs, 59 Fe, 60 Co, were incinerated. High resolution photon detectors were installed on the off-gas handling system of the controlled air incinerator at the Los Alamos National Laboratory to determine relative decontamination factors, which ranged from a low of 40 for 137 Cs to a high of 50O0 for 131 I. Background measurements were made to determine the residual activity in the incinerator. Due to the constant purging of the system to maintain a negative pressure with respect to the surrounding environment, the residual activity decays more rapidly than dictated by its half-life. (orig.)

A chemical basis for the partitioning of radionuclides in incinerator operation

International Nuclear Information System (INIS)

Burger, L.L.

1995-01-01

Incineration as a method of treating radioactive or mixed waste is attractive because of volume reduction, but may result in high concentrations of some hazardous components. For safety reasons during operation, and because of the environmental impact of the plant, it is important to know how these materials partition between the furnace slay, the fly ash, and the stack emission. The chemistry of about 50 elements is discussed and through consideration of high temperature thermodynamic equilibria, an attempt is made to provide a basis for predicting how various radionuclides and heavy metals behave in a typical incinerator. The chemistry of the individual elements is first considered and a prediction of the most stable chemical species in the typical incinerator atmosphere is made. The treatment emphasizes volatility and the parameters considered are temperature, acidity, oxygen, sulfur, and halogen content, and the presence of several other key non-radioactive elements. A computer model is used to calculate equilibrium concentrations of many species in several systems at temperatures ranging from 500 to 1600 degrees K. It is suggested that deliberate addition of various feed chemicals can have a major impact on the fate of many radionuclides and heavy metals. Several problems concerning limitations and application of the data are considered

Operational readiness review for the TSCA incinerator start-up at the Oak Ridge K-25 site

International Nuclear Information System (INIS)

Jordan, Elizabeth A.; Murray, Alexander P.; Kiang, Peter M.

1992-01-01

The Department of Energy (DOE) Toxic Substances Control Act (TSCA) incinerator at Oak Ridge K-25 Site was designed in the early 1980's as a treatment alternative for the increasing quantities of radioactive mixed waste accumulating from gaseous diffusion plant (GDP) operations. The waste feed principally contains low assay uranium and PCBs, although listed solvents and heavy metal containing sludges have also be incinerated. Construction was completed in 1986 and the unit underwent an extensive series of tests and trial burns, because of the following unique characteristics: the incinerator treats radioactive mixed wastes; increased size of the incinerator for greater waste throughout and treatment capacity; expansion of the waste acceptance criteria to include materials and radionuclides from non-GDP operations, such as ORNL and Y-12; modifications and improvement to the Air Pollution Control (APC) system; treatment of large quantities and concentrations of PCB containing materials; projected longevity of operation (40 years); humid, Eastern location with a high, annual precipitation. The incinerator was initially fired in July, 1986. The full performance testing (with the APC) and DOE acceptance of the facility occurred a year later. The trial burn period lasted from 1988 through 1990. Numerous equipment problems were initially encountered, including excessive draft fan wear and failure. These problems have been overcome, the facility is fully permitted, DOE provided authorization for full operations in 1991, and, to date, over two million pounds of mixed waste have been incinerated, with an average volume reduction factor of approximately nine. This paper discusses the Office of Environmental Restoration and Waste Management Readiness Review for the incinerator. (author)

The application of probabilistic risk assessment to a LLW incinerator

International Nuclear Information System (INIS)

Li, K.K.; Huang, F.T.

1993-01-01

The 100 Kg/hr low-level radioactive waste (LLW) incinerator and the 1,500 ton supercompactor are two main vehicles in the Taiwan Power Company's Volume Reduction Center. Since the hot test of the incinerator in mid 1990, various problems associated with the original design and operating procedures were encountered. During the early stages of putting an incinerator in service, the modification and fine-tuning of the system would help future reliable operations. The probabilistic risk assessment (PRA) method was introduced to evaluate the interaction between potential system failure and its environmental impact and further help diagnose the system defects initially. The draft Level 1 system analysis was completed and the event and fault trees were constructed. Qualitatively, this approach is useful for preventing the system failure from occurring. However, Levels 2 and 3 analysis can only be done when sufficient data become available in the future

Long lived nuclear waste transmutation: context and trends; L`incineration des dechets nucleaires a vie longue, contexte et perspectives

Energy Technology Data Exchange (ETDEWEB)

Prunier, C; Pacton, L

1994-12-31

After a recall of the actual strategy, in France, for the radioactive wastes, we give an overview of the programs CAPRA and SPIN (Separation-Incineration) for separate the minors actinides (Am,Np,..) and then to reduce the radiological risk create by these products by incineration in a LMFBR. 13 figs, 1 annexe.

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

CO-incineration

International Nuclear Information System (INIS)

Boehmer, S.; Rumplmayr, A.

2001-01-01

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

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 ...

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

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.

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

Incineration of toluene and chlorobenzene in a laboratory incinerator

International Nuclear Information System (INIS)

Mao, Z.; Mcintosh, M.J.; Demirgian, J.C.

1992-01-01

This paper reports experimental results on the incineration of toluene and chlorobenzene in a small laboratory incinerator. Temperature of the incinerator, excess air ratio and mean residence time were varied to simulate both complete and incomplete combustion conditions. The flue gas was monitored on line using Fourier transform infrared (FTIR) spectroscopy coupling with a heated long path cell (LPC). Methane, toluene, benzene, chlorobenzene, hydrogen chloride and carbon monoxide in the flue gas were simultaneously analyzed. Experimental results indicate that benzene is a major product of incomplete combustion (PIC) besides carbon monoxide in the incineration of toluene and chlorobenzene, and is very sensitive to combustion conditions. This suggests that benzene is a target analyle to be monitored in full-scale incinerators

INEL RCRA [Resource Conservation and Recovery Act] permit for incineration of hazardous waste: Status report

International Nuclear Information System (INIS)

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

1987-01-01

The Waste Experimental Reduction Facility (WERF) was constructed to reduce the volume of low-level radioactive waste at the Idaho National Engineering Laboratory (INEL). To address the problem of radioactively contaminated ignitable hazardous waste resulting from INEL activities, a development program was carried out to evaluate WERF's ability to meet the regulated criteria for incinerating liquid and solid ignitable waste. Concurrently, INEL submitted its hazardous waste Part B application under the Resource Conservation and Recovery Act (RCRA). As required, and as a major step in the permitting process, the WERF incinerator portion of the permit application included a proposed trial burn, which is a demonstration test of the incinerator's ability to destroy hazardous materials. The trial burn plan was designed to demonstrate the system performance for liquid and solid ignitable wastes at three operating conditions, using a prepared mix of materials representative of waste to be processed. EPA Region X reviewed and commented on the plan prior to the trial burn. Results of the liquid feed trial burn showed a greater than 97% probability of meeting the RCRA-dictated DRE value for chlorinated solvents and a greater than 99% probability for nonchlorinated solvents. Nonchlorinated solid waste results were calculated at a 93% probability of meeting the required DRE, with a 75% probability for chlorinated solid wastes. In addition, the incinerator DRE continued to improve long after the assumed pre-test equilibrium period had ended. The trial burn demonstrates that the WERF incinerator can safely and adequately destroy ignitable hazardous and mixed waste and provides a significant enhancement of the INEL's waste management system

Joule-heated glass-furnace system for the incineration of low-level radioactive wastes

International Nuclear Information System (INIS)

Armstrong, K.M.; Klingler, L.M.; Doty, J.W.; Kramer, D.P.

1982-01-01

For the past 1-1/2 years, Mound has been preparing and evaluating a commercially available joule-heated glass furnace unit, coupled with a wet scrubbing system. The purpose of the glass furnace evaluation is to advance and document incinerator technology for such combustibles as solids, resins, and sludges, and to develop a stable waste form for subsequent disposal. Four (4) waste nonradioactive types were selected to determine the combustion efficiency of the furnace unit: (1) dry solid waste composed of paper, plastics, rubber, and cloth, (2) ion exchange resin of both the anionic and cationic type, (3) filter sludge composed of diatomaceous earth, organic cellulosic filter aid, and powdered ion exchange resin, and (4) cartridge filters having glass and plastic filter surfaces and nonmetallic cores. When completed, the combustion efficiency experiments for the proposed nonradioactive waste-types revealed the ability of the furnace to easily incinerate waste at feedrates of up to 150 lb/hr. During the course of the experiments, combustibles in the offgas remained consistently low, suggesting excellent combustion efficiency. Furthermore, ash produced by the combustion process was effectively incorporated into the melt by convective currents in the glass. Future work on the glass furnace incinerator will include spiking the waste to determine radioisotope behavior in the furnace

Treatment of Decommissioning Combustible Wastes with Incineration Technology

Energy Technology Data Exchange (ETDEWEB)

Min, B. Y. Min; Yang, D. S.; Yun, G. S.; Lee, K. W.; Moon, J. K. [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

2015-05-15

The aim of the paper is current status of management for the decommissioning radioactive combustible and metal waste in KAERI. In Korea, two decommissioning projects were carried out for nuclear research facilities (KRR-1 and KRR-2) and a uranium conversion plant (UCP). Through the two decommissioning projects, lots of decommissioning wastes were generated. Decommissioning waste can be divided into radioactive waste and releasable waste. The negative pressure of the incineration chamber remained constant within the specified range. Off-gas flow and temperature were maintained constant or within the desired range. The measures gases and particulate materials in the stack were considerably below the regulatory limits. The achieved average volume reduction ratio during facility operation is about 1/65.

Environmental safety of the disposal system for radioactive substance-contaminated wastes

International Nuclear Information System (INIS)

Oosako, Masahiro

2012-01-01

In accordance with the full-scale enforcement of 'The Act on Special Measures concerning the Handling of Radioactive Pollution' in 2012, the collective efforts of entire Japan for dealing with radioactive pollutants began. The most important item for dealing with radioactive pollution is to control radioactive substances that polluted the global environment and establish a contaminated waste treatment system for risk reduction. On the incineration system and landfill disposal system of radioactive waste, this paper arranges the scientific information up to now, and discusses the safety of the treatment / disposal systems of contaminated waste. As for 'The Act on Special Measures concerning the Handling of Radioactive Pollution,' this paper discusses the points of the Act and basic policy, roadmap for the installation of interim storage facilities, and enforcement regulations (Ordinance of the Ministry of the Environment). About the safety of waste treatment system, it discusses the safety level of technical standards at waste treatment facilities, safety of incineration facilities, and safety of landfill disposal sites. (O.A.)

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

International Nuclear Information System (INIS)

Conley, D.; Corrigan, S.

1996-01-01

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

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

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

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)

Radioactive-site-remediation technologies seminar. Speaker slide copies

International Nuclear Information System (INIS)

1992-06-01

The contents of this report include the following: approaches to sampling radioactive heterogeneous waste; soil characterization methodology for determining application of soil washing; vorce (volume reduction/chemical extraction) program; treatment of radioactive compounds in water; polymer solidification of low-level radioactive, hazardous, and mixed waste; in situ vitrification of soils contaminated with radioactive and mixed wastes; decontamination of contaminated buildings; incineration of radioactive waste; in situ stabilization/solidification with cement-based grouts; environmental restoration and waste management; removal of contaminants from soils by electrokinetics; and treatment, compaction, and disposal of residual radioactive waste

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.

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

Low and intermediate radioactive waste management at OPG's western waste management facility

International Nuclear Information System (INIS)

Ellsworth, M.

2006-01-01

'Full text:' This paper will discuss low and intermediate level radioactive waste operations at Ontario Power Generation's Western Waste Management Facility. The facility has been in operation since 1974 and receives about 5000 - 7000 m 3 of low and intermediate level radioactive waste per year from Ontario's nuclear power plants. Low-level radioactive waste is received at the Waste Volume Reduction Building for possible volume reduction before it is placed into storage. Waste may be volume reduced by one of two methods at the WWMF, through either compaction or incineration. The Compactor is capable of reducing the volume of waste by a factor up to 5:1 for most waste. The Radioactive Incinerator is capable of volume reducing incinerable material by a factor up to 70:1. After processing, low-level waste is stored in above ground concrete warehouse-like structures called Low Level Storage Buildings. Low-level waste that cannot be volume reduced is placed into steel containers and stored in the Low Level Storage Buildings. Intermediate level waste is stored mainly in steel lined concrete storage structures. WWMF has both above ground and in-ground storage structures for intermediate level waste. Intermediate level waste consists primarily of resin and filters used to keep reactor water systems clean, and some used reactor core components. All low and intermediate level waste storage at the WWMF is considered interim storage and the material can be retrieved for future disposal or permanent storage. Current improvement initiatives include the installation of a new radioactive incinerator and a shredder/bagger. The new incinerator is a continuous feed system that is expected to achieve volume reduction rates up to 70:1, while incinerating higher volumes of waste than its predecessor. The shredder will break down large/bulky items into a form, which can be processed for further volume reduction. A Refurbishment Waste Storage Project is underway in anticipation of the

The Savannah River Plant Consolidated Incineration Facility

International Nuclear Information System (INIS)

Weber, D.A.

1987-01-01

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

Comparison of high temperature gas particulate collectors for low level radwaste incinerator volume reduction systems

International Nuclear Information System (INIS)

Moscardini, R.L.; Johnston, J.R.; Waters, R.M.; Zievers, J.F.

1983-01-01

Incinerator system off-gases must be treated to prevent the release of particulates, noxious gases and radioactive elements to the environment. Fabric filters, venturi scrubbers, cyclone separators, an ceramic or metal filter candles have been used for particulate removal. Dry high temperature particulate collectors have the advantage of not creating additional liquid wastes. This paper presents a graphical comparison of different methods for filtering particles from high temperature incineration system off-gases. Eight methods of off-gas handling are compared. A much larger group may be present, but some judicious selection of different, but related systems was done for this paper based on experience with the Combustion Engineering Waste Incineration System (CE/WIS) Prototype. The eight types are: Inertial Devices, Electrostatic Precipitators (ESP), Standard Fabric Bags, Woven Ceramic Bags, Granular Beds, Sintered Metal Tubes, Felted Ceramic Bags and Ceramic Filter Candles. For high temperature LLRW particulate collection in incinerator off-gas systems, ceramic filter candles are the best overall choice

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

Los Alamos controlled air incinerator upgrade for TRU/mixed waste operations

International Nuclear Information System (INIS)

Vavruska, J.S.; Borduin, L.C.; Hutchins, D.A.; Warner, C.L.; Thompson, T.K.

1989-01-01

The Los Alamos Controlled Air Incinerator (CAI) is undergoing a major process upgrade to accept Laboratory-generated transuranic (TRU) and TRU mixed wastes on a production basis. In the interim,prior to the scheduled 1992 operation of a new on-site LLW/mixed waste incinerator, the CAI will also be accepting solid and liquid low-level mixed wastes. This paper describes major modifications that have been made to the process to enhance safety and ensure reliability for long-term, routine waste incineration operations. The regulatory requirements leading to operational status of the system are also briefly described. The CAI was developed in the mid-1970s as a demonstration system for volume reduction of TRU combustible solid wastes. It continues as a successful R and D system well into the 1980s during which incineration tests on a wide variety of radioactive and chemical waste forms were performed. In 1985, a DOE directive required Los Alamos to reduce the volume of its TRU waste prior to ultimate placement in the geological repository at the Waste Isolation Pilot Project (WIPP). With only minor modifications to the original process flowsheet, the Los Alamos CAI was judged capable of conversion to a TRU waste operations mode. 9 refs., 1 fig

The existing state of sewage sludge containing radioactive substances

International Nuclear Information System (INIS)

Shirasaki, Makoto; Hisaoka, Natsuki

2012-01-01

Radioactive substances were discharged over a wide range from the accident of the Fukushima Daiichi Nuclear Station of Tokyo Electric Power Company. As a result, in sewer system, especially in the combined sewer system that jointly collects rainwater and sewage, radioactive substances accumulated on the surface of urban areas were transferred together with rainwater to sewage plants and accumulated there. In the process of further treatment, radioactive substances were transferred to and concentrated in sewage sludge, and a high concentration of radioactive substances were detected in incineration ash. For this reason, some sewage plants still continuously store dewatered sludge, incinerator ash, etc. This paper introduces the current state of waste treatment from the published data from each local government in Tohoku and Kanto districts. As for the sewer, which is essential as a lifeline, the Ministry of Land, Infrastructure, Transport and Tourism, together with the Japan Sewage Works Association, established 'Investigative Commission on Radioactive Substance Countermeasures in Sewerage System.' This group grasped the damage situation due to radioactive substances, and summarized the measures to be taken by sewage managers, such as the storage method for sewage sludge containing radioactive substances as well as the method for the volume reduction of sewage sludge. (O.A.)

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

Destruction of nuclear graphite using closed chamber incineration

International Nuclear Information System (INIS)

Senor, D.J.; Hollenberg, G.W.; Morgan, W.C.; Marianowski, L.G.

1994-01-01

Closed chamber incineration (CCI) is a novel technique by which irradiated nuclear graphite may be destroyed without the risk of radioactive cation release into the environment. The process utilizes an enclosed combustion chamber coupled with molten carbonate fuel cells (MCFCs). The transport of cations is intrinsically suppressed by the MCFCs, such that only the combustion gases are conducted through for release to the environment. An example CCI design was developed which had as its goal the destruction of graphite fuel elements from the Fort St. Vrain reactor (FSVR). By employing CCI, the volume of high level waste from the FSVR will be reduced by approximately 87 percent. Additionally, the incineration process will convert the SiC coating on the FSVR fuel particles to SiO 2 , thus creating a form potentially suitable for direct incorporation in a vitrification process stream. The design is compact, efficient, and makes use of currently available technology

High Solids Consolidated Incinerator Facility (CIF) Wastes Stabilization with Ceramicrete and Super Cement

International Nuclear Information System (INIS)

Walker, B.W.

1999-01-01

High Solids ash and scrubber solution waste streams were generated at the incinerator facility at SRS by burning radioactive diatomaceous filter rolls which contained small amounts of uranium, and listed solvents (F and U). This report details solidification activities using selected Mixed Waste Focus Area (MWFA) technologies with the High Solids waste streams

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)

Design Of Fluidized-bed Incinerator

International Nuclear Information System (INIS)

Lee, Bong Hun

1992-04-01

This book tells of design of fluidized-bed incinerator, which includes outline of fluidized-bed incinerator such as definition, characteristic, structure of principle of incineration and summary of the system, facilities of incinerator with classification of incinerator apparatus of supply of air, combustion characteristic, burnup control and point of design of incinerator, preconditioning facilities on purpose, types and characteristic of that system, a crusher, point of design of preconditioning facilities, rapid progress equipment, ventilation equipment, chimney facilities, flue gas cooling facilities boiler equipment, and removal facility of HCI/SOX and NOX.

RADIOACTIVE MATERIALS IN BIOSOLIDS: DOSE MODELING

Science.gov (United States)

The Interagency Steering Committee on Radiation Standards (ISCORS) has recently completed a study of the occurrence within the United States of radioactive materials in sewage sludge and sewage incineration ash. One component of that effort was an examination of the possible tra...

Testing cleanable/reuseable HEPA prefilters for mixed waste incinerator air pollution control systems

Energy Technology Data Exchange (ETDEWEB)

Burns, D.B.; Wong, A.; Walker, B.W.; Paul, J.D. [Westinghouse Savannah River Co., Aiken, SC (United States)

1997-08-01

The Consolidated Incineration Facility (CIF) at the US DOE Savannah River Site is undergoing preoperational testing. The CIF is designed to treat solid and liquid RCRA hazardous and mixed wastes from site operations and clean-up activities. The technologies selected for use in the air pollution control system (APCS) were based on reviews of existing incinerators, air pollution control experience, and recommendations from consultants. This approach resulted in a facility design using experience from other operating hazardous/radioactive incinerators. In order to study the CIF APCS prior to operation, a 1/10 scale pilot facility, the Offgas Components Test Facility (OCTF), was constructed and has been in operation since late 1994. Its mission is to demonstrate the design integrity of the CIF APCS and optimize equipment/instrument performance of the full scale production facility. Operation of the pilot facility has provided long-term performance data of integrated systems and critical facility components. This has reduced facility startup problems and helped ensure compliance with facility performance requirements. Technical support programs assist in assuring all stakeholders the CIF can properly treat combustible hazardous, mixed, and low-level radioactive wastes. High Efficiency Particulate Air (HEPA) filters are used to remove hazardous and radioactive particulates from the exhaust gas strewn before being released into the atmosphere. The HEPA filter change-out frequency has been a potential issue and was the first technical issue to be studied at the OCTF. Tests were conducted to evaluate the performance of HEPA filters under different operating conditions. These tests included evaluating the impact on HEPA life of scrubber operating parameters and the type of HEPA prefilter used. This pilot-scale testing demonstrated satisfactory HEPA filter life when using cleanable metal prefilters and high flows of steam and water in the offgas scrubber. 8 figs., 2 tabs.

75 FR 74107 - Request for a License To Import Radioactive Waste

Science.gov (United States)

2010-11-30

... NUCLEAR REGULATORY COMMISSION Request for a License To Import Radioactive Waste Pursuant to 10 CFR 110.70(b) ``Public Notice of Receipt of an Application,'' please take notice that the Nuclear.... EnergySolutions, August 27, Radioactive waste 1,000 tons Incineration for Germany. 2010, November 3, 2010...

Evaluation of IAEA Clearance Concept for Low-level Radioactive Waste from a Radioisotope Research Institute.

Science.gov (United States)

Yumoto, Yasuhiro; Okada, Shigeru; Kinno, Ikuo; Nagamatsu, Tomohiro; Nouso, Kazuhiro; Nakayama, Eiichi

2016-05-01

The clearance of solid low-level radioactive laboratory waste (LLRW) after decay-in-storage (DIS) obtained from a research institute and thoroughly separated using the separation and classification protocols presented in this study was evaluated. The radioisotope (RI) content of incinerated LLRW from the specified RI research group (group A); the RI content of LLRW obtained in fiscal year 2000, which contained radionuclides with half-lives of less than 164 d (LLRW2); and the RI content of the LLRW reported in group A's disposal records were compared. The LLRW2 and LLRW of group A were incinerated after 2 y of decay-in-storage and immediately after storage, respectively. The highest ratio of the RI of incinerated LLRW to the value in the disposal records was 2.52 for ⁵¹Cr. The radioactivities of radionuclides in both the LLRW2 and LLRW for ³⁵S, ⁴⁵Ca, ⁵¹Cr, ¹²⁵I, ³²P, ³³P, and ⁹⁹mTc and the incinerated ash after 1 y later of decay-in-storage were below the clearance level defined by the RS-G-1.7 of the International Basic Safety Standard without contamination by ³H and ¹⁴C. These remains contained very small amounts of some long-half-life radionuclides of natural origin after 7 y of decay-in-storage. This LLRW separation protocol was effective for the separation of ³H and ¹⁴C. LLRW2 after 2 years of DIS and its incinerated ash after one year later of DIS were below the clearance level for radioactivity and radioactivity concentration.

Design and construction of engineering test device of a multi-purpose radwaste incineration system

International Nuclear Information System (INIS)

Wang Peiyi; Zhou Lianquan; Ma Mingxie; Qiu Mingcai; Yang Liguo; Li Xiaohai; Zhang Xiaobin; Lu Xiaowu; Dong Jingling; Wang Xujin; Li Chuanlian; Yang Baomin

2002-01-01

The author describes designs of main un-standard devices, monitoring system and safety system, as well as construction of the engineering system devices for a multi-purpose radwaste incineration system. Un-standard devices include waste crusher, pyrolysis furnace, incinerator furnace, cool stream dilution device and bag filter, etc. The monitoring system mainly includes industrial controlled computer, supported by conventional electrical equipment and instruments. Designs of system safety takes account of containment of radioactive materials fire-prevention, explosion prevention, anti-corrosion, redundance and reservation, emergency system, controlling and electric safety system, etc. Results show that main technological system remains good airtight with leakage ratio at 0.67%

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

Radioactive caesium contamination due to Fukushima Daiichi Nuclear Power Plants accident in Osaka city. Evaluation of accumulation and decontamination of radioactive materials via reverse logistics function of a city

International Nuclear Information System (INIS)

Nishio, Takayuki; Kitano, Masaaki; Sakai, Mamoru; Takakura, Akito; Katahira, Kenshi; Nishitani, Takashi

2015-01-01

We surveyed background level of radioactive contamination in city area of Osaka before combusting the wide area disposal of disastrous debris at a municipal waste incineration plant of Osaka city. The debris was caused by Tohoku district great earthquake disaster and suspected to be contaminated with radionuclides released from the Fukushima Daiichi Nuclear Power Plants. We also investigated radioactivity in incineration ash of municipal waste incineration plants and of sewage treatment plants, as well as in water clarifier sludge of potable water treatment plants, and evaluated the accumulation and cleansing of radioactive materials via the reverse logistic function of the city. Radioactive caesium deposited in Osaka city area was estimated to be approximately 4.3 GBq from the concentrations observed in the monthly fallout, whereas that collected as municipal wastes and sewage was estimated to be approximately 0.9 GBq a year in 2011. Even two years after the accident, "1"3"4Cs, which is the evidence of the Fukushima Daiichi Nuclear Power Plant accident, had been detected in the municipal wastes at a level comparable to the activities found just after the accident, however, the radioactive caesium concentration in fallout measured in the Osaka city area had decreased below a detection limit after May 2012. Introduction of materials contaminated with radioactive caesium from outside the city area was suspected because the observed contamination level was inexplicable by that of observed in the environmental wastes such as pruned branches which are contaminated by with the fallout in city area of Osaka. (author)

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

40 CFR 761.70 - Incineration.

Science.gov (United States)

2010-07-01

... 40 Protection of Environment 30 2010-07-01 2010-07-01 false Incineration. 761.70 Section 761.70... and Disposal § 761.70 Incineration. This section applies to facilities used to incinerate PCBs... regular intervals of no longer than 15 minutes. (4) The temperatures of the incineration process shall be...

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

Phytotoxicology section investigation in the vicinity of the Bruce Nuclear Power Development, the Pickering Nuclear Generating Station and the Darlington Nuclear Generating Station, in October, 1989

International Nuclear Information System (INIS)

1991-02-01

The Phytotoxicology Section, Air Resources Branch is a participant in the Pickering and Bruce Nuclear Contingency Plans. The Phytotoxicology Emergency Response Team is responsible for collecting vegetation samples in the event of a nuclear emergency at any of the nuclear generating stations in the province. As part of its responsibility the Phytotoxicology Section collects samples around the nuclear generating stations for comparison purposes in the event of an emergency. Because of the limited frequency of sampling, the data from the surveys are not intended to be used as part of a regulatory monitoring program. These data represent an effort by the MOE to begin to establish a data base of tritium concentrations in vegetation. The Phytotoxicology Section has carried out seven surveys in the vicinity of Ontario Hydro nuclear generating stations since 1981. Surveys were conducted for tritium in snow in the vicinity of Bruce Nuclear Power Development (BNPD), February, 1981; tritium in cell-free water of white ash in the vicinity of BNPD, September, 1981; tritium in snow in the vicinity of BNPD, March, 1982; tritium in tree sap in the vicinity of BNPD, April, 1982; tritium in tree sap in the vicinity of BNPD, April, 1984, tritium in the cell-free water of white ash in the vicinity of BNPD, September, 1985; and, tritium in cell-free water of grass in the vicinity of Pickering Nuclear Generation Station (PNGS), October 1986. In all cases a pattern of decreasing tritium levels with increasing distance from the stations was observed. In October, 1989, assessment surveys were conducted around Bruce Nuclear Power Development, the Pickering Nuclear Generating Station and the new Darlington Nuclear Generating Station (DNGS). The purpose of these surveys was to provide baseline data for tritium in cell-free water of grass at all three locations at the same time of year. As none of the reactor units at DNGS had been brought on line at the time of the survey, this data was to be

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

Controlled air incineration

International Nuclear Information System (INIS)

Seitz, K.A.

1991-01-01

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

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

A novel device for processing radioactive combustibles

International Nuclear Information System (INIS)

Phelan, P.F.; Thompson, T.K.

1991-01-01

Los Alamos National Laboratory is assisting EG ampersand G Rocky Flats, Colorado, with the development of a special incinerator for wastes contaminated with plutonium, a radioactive element. This paper describes one conceptual design that was developed by T.K. Thompson, Inc., under contract to Los Alamos National Laboratory. The design is a tentative proposal that tries to address the many constraints that are peculiar to this project. It has not been endorsed or accepted by EG ampersand G Rocky Flats, and it is subject to revision. Nevertheless, it is noteworthy because of the novel concepts it embodies. Before examining the design itself, it is instructive to understand the constraints imposed by safety and operational concerns. There are three main requirements related to safety: There may be no emissions of radioactive material either to the atmosphere or into the building that houses the incinerator. The outer surfaces of the combustion chamber must be kept below 140oF so that the lead-lined rubber gloves will not melt if the operator reaches inside the glovebox while the incinerator is hot. The combustion chambers and other locations where plutonium-containing ash could accumulate must be designed in such a way that it would be impossible for a critically accident to occur. 3 figs

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)

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

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.

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

Spray drying of liquid radioactive wastes

International Nuclear Information System (INIS)

Abrams, R.F.; Monat, J.P.

1984-01-01

Full scale performance tests of a Koch spray dryer were conducted on simulated liquid radioactive waste streams. The liquid feeds simulated the solutions that result from radwaste incineration of DAW an ion exchange resins, as well as evaporator bottoms. The integration of the spray dryer into a complete system is discussed

Electrochemical incineration of C-14-containing liquid wastes. First results and outlook; Behandlung C-14-haltiger fluessiger Abfaelle mittels elektrochemischer Totaloxidation. Erste Ergebnisse und Ausblick

Energy Technology Data Exchange (ETDEWEB)

Friedrich, Hans-Juergen [Fraunhofer-Institut fuer Keramische Technologien und Systeme (IKTS), Dresden (Germany). Aussenstelle Rossendorf; Knappik, Reinhard; Zschornack, Daniel [Verein fuer Kernverfahrenstechnik und Analytik Rossendorf e.V. (VKTA), Dresden (Germany). Fachbereich Analytik und Monitoring; Mueller, Wolfgang [IUT GmbH, Berlin (Germany)

2014-06-15

Liquid radioactive wastes containing carbon-14 are not acceptable for radioactive waste repository. At present incineration is the only approved way of treatment in Germany. But capacities are limited and incineration by itself is known to be a technically complex and rather expansive process. Therefore within an experimental proof of concept it should be examined whether an electrochemical incineration process is also applicable for this purpose. The R and D activities mainly comprised the gathering of informations about the chemical nature and constitution of such liquid wastes from enterprises, research laboratories and a number of the state owned collecting facilities, numerous electrochemical examinations with typical organic substances and finally electrolysis tests with original carbon-14 waste solution at lab-scale. We were able to demonstrate that electrochemical oxidation permits almost quantitative mineralization of the organic waste substances. The carbon dioxide released during electrolysis was completely fixed as solid calcium carbonate which is acceptable for final repository. An estimate shows that in comparison to conventional incineration a substantial decrease in the costs of treatment and repository can be expected. With regard to technical application further steps of development are necessary. (orig.)

Incineration of dry burnable waste from reprocessing plants with the Juelich incineration process

International Nuclear Information System (INIS)

Dietrich, H.; Gomoll, H.; Lins, H.

1987-01-01

The Juelich incineration process is a two stage controlled air incineration process which has been developed for efficient volume reduction of dry burnable waste of various kinds arising at nuclear facilities. It has also been applied to non nuclear industrial and hospital waste incineration and has recently been selected for the new German Fuel Reprocessing Plant under construction in Wackersdorf, Bavaria, in a modified design

Behavior of radioactive metal surrogates under various waste combustion conditions

International Nuclear Information System (INIS)

Yang, Hee Chul; Lee, Jae Hee; Kim, Jung Guk; Yoo, Jae Hyung; Kim, Joon Hyung

2002-01-01

A laboratory investigation of the behavior of radioactive metals under the various waste combustion atmospheres was conducted to predict the parameters that influence their partitioning behavior during waste incineration. Neodymium, samarium, cerium, gadolinium, cesium and cobalt were used as non-radioactive surrogate metals that are representative of uranium, plutonium, americium, curium, radioactive cesium, and radioactive cobalt, respectively. Except for cesium, all of the investigated surrogate metal compounds converted into each of their stable oxides at medium temperatures from 400 to 900 .deg. C, under oxygen-deficient and oxygen-sufficient atmospheres (0.001-atm and 0.21-atm O 2 ). At high temperatures above 1,400 .deg. C, cerium, neodymium and samarium in the form of their oxides started to vaporize but the vaporization rates were very slow up to 1500 .deg. C. Inorganic chlorine (NaCl) as well as organic chlorine (PVC) did not impact the volatility of investigated Nd 2 O 3 , CoO and Cs 2 O. The results of laboratory investigations suggested that the combustion chamber operating parameters affecting the entrainment of particulate and filtration equipment operating parameters affecting particle collection efficiency be the governing parameters of alpha radionuclides partitioning during waste incineration

SRL incinerator components test facility

International Nuclear Information System (INIS)

Freed, E.J.

1982-08-01

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

Expansion control for cementation of incinerated ash

International Nuclear Information System (INIS)

Nakayama, T.; Suzuki, S.; Hanada, K.; Tomioka, O.; Sato, J.; Irisawa, K.; Kato, J.; Kawato, Y.; Meguro, Y.

2015-01-01

A method, in which incinerated ash is solidified with a cement material, has been developed to dispose of radioactive incinerated ash waste. A small amount of metallic Al, which was not oxidized in the incineration, existed in the ash. When such ash was mixed with a cement material and water, alkaline components in the ash and the cement were dissolved in the mixing water and then metallic Al reaction with the alkaline compounds resulted in generation of H 2 . Because the H 2 generation began immediately just after the mixing, H 2 bubbles pushed up the mixed grout material and an expanded solidified form was obtained. The expansion leads to lowering the strength of the solidified form and making harmful void. In this study, we tried to control H 2 generation from the reaction of metallic Al in the cementation by means of following two methods, one was a method to let metallic Al react prior to the cementation and the other was a method to add an expansion inhibitor that made an oxide film on the surface of metallic Al. In the pre-treatment, the ash was soaked in water in order to let metallic Al react with it, and then the ash with the immersion solution was dried at 105 Celsius degrees. The pre-treated ash was mixed with an ordinary portland cement and water. The inhibitor of lithium nitrite, sodium nitrite, phosphoric acid, or potassium dihydrogen phosphate was added at the mixing process. The solidified forms prepared using the pre-treated ash and lithium nitrite were not expanded. Phosphoric acid and sodium nitrite were effective for expansion control, but potassium dihydrogen phosphate did not work. (authors)

Radioactive contamination of sewage sludge

International Nuclear Information System (INIS)

Soeder, C.J.; Zanders, E.; Raphael, T.

1986-01-01

Because of the radioactivity released through the explosion of the nuclear reactor near Chernobyl radionuclides have been accumulated to a significant extent in sewage sludge in the Federal Republic of Germany. This is demonstrated for samples from four activated sludge plants according to a recent recommendation of the German Commission for Radiation Protection, there is until now no reason to deviate from the common practices of sludge disposal or incineration. The degree of radioactive contamination of plant materials produced on farm lands on which sewage sludge is being spread cannot be estimated with sufficient certainty yet. Additional information is required. (orig.) [de

Method of processing radioactive wastes

International Nuclear Information System (INIS)

Nomura, Ichiro; Hashimoto, Yasuo.

1984-01-01

Purpose: To improve the volume-reduction effect, as well as enable simultaneous procession for the wastes such as burnable solid wastes, resin wastes or sludges, and further convert the processed materials into glass-solidified products which are much less burnable and stable chemically and thermally. Method: Auxiliaries mainly composed of SiO 2 such as clays, and wastes such as burnable solid wastes, waste resins and sludges are charged through a waste hopper into an incinerating melting furnace comprising an incinerating and a melting furnace, while radioactive concentrated liquid wastes are sprayed from a spray nozzle. The wastes are burnt by the heat from the melting furnace and combustion air, and the sprayed concentrated wastes are dried by the hot air after the combustion into solid components. The solid matters from the concentrated liquid wastes and the incinerating ashes of the wastes are melted together with the auxiliaries in the melting furnace and converted into glass-like matters. The glass-like matters thus formed are caused to flow into a vessel and gradually cooled to solidify. (Horiuchi, T.)

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

International Nuclear Information System (INIS)

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

2009-01-01

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

Incineration with energy recovery

Energy Technology Data Exchange (ETDEWEB)

Mahoney, T.G.

1986-02-01

Motherwell Bridge Tacol Ltd. operate a 'Licence Agreement' with Deutsche Babcock Anlagen of Krefeld, West Germany, for the construction of Municipal Refuse Incineration plant and Industrial Waste plant with or without the incorporation of waste heat recovery equipment. The construction in the UK of a number of large incineration plants incorporating the roller grate incinerator unit is discussed. The historical background, combustion process, capacity, grate details, refuse analysis and use as fuel, heat recovery and costs are outlined.

Research and development of improved type radioactive waste volume reduction system

International Nuclear Information System (INIS)

Okamoto, Masahiro; Watanabe, Yoshifumi; Yamaoka, Katsuaki; Masaki, Tetsuo; Akagawa, Yoshihiro; Murakami, Tadashi; Miyake, Takashi.

1985-01-01

Development and research had been conducted since 1978 on an improved type radioactive waste volume reduction system incorporating calcining and incinerating fluidized bed type furnaces. This system can dispose of concentrated liquid wastes, combustible solid wastes, spent ion exchange resins and so forth by calcination or incineration to turn them into reduced-volume products. Recently a pilot test facility has constructed and tests has been conducted to demonstrate actual performance. Representative results of pilot tests are reported in this paper. (author)

Waste incineration, Part I: Technology.

Science.gov (United States)

1990-02-01

Based upon an overview of the technology of incineration and the nature of hospital waste, HHMM offers the following suggestions: Old retort or other excess air incinerators should be replaced regardless of age. Even if emissions control equipment and monitoring devices can be retrofitted, excess-air incinerators are no longer cost-effective in terms of capacity, fuel consumption, and heat recovery. Audit (or have a specialist audit) your waste stream thoroughly. Consult a qualified engineering company experienced in hospital installations to get a system specified as exactly as possible to your individual conditions and needs. Make sure that the capacity of your incinerator will meet projections for future use. Anticipate the cost of emissions control and monitoring devices whether your state currently requires them or not. Make sure that your incinerator installation is engineered to accept required equipment in the future. Develop a strong community relations program well in advance of committing to incinerator installation. Take a proactive position by inviting your neighbors in during the planning stages. Be sure the contract governing incinerator purchase and installation has a cancellation clause, preferably without penalties, in case community action or a change in state regulations makes installation and operation impractical. The technology is available to enable hospitals to burn waste effectively, efficiently, and safely. HHMM echoes the concerns of Frank Cross--that healthcare facilities, as well as regional incinerators and municipalities, show the same concern for environmental protection as for their bottom lines. When emissions are under control and heat is recovered, both the environment and the bottom line are healthier.

Thermal behavior of hazardous and radioactive metals under incineration conditions

International Nuclear Information System (INIS)

Seo, Y.C.; Kang, K.H.; Yang, H.C.; Park, H.H.

1993-01-01

The behavior of heavy metals and their effects on air pollution at temperatures up to 900 C under incineration conditions were observed. Pure metals and their oxide compounds, except arsenic, were very stable in the tested range of temperatures. However, the chlorides of some metals were evaporated or decomposed to result in gas emission to the environment at lower temperatures, while other chloride compounds were converted into their stable oxide forms. Evaporation of such compounds were analyzed using an equation of maximum evaporation flux based on the kinetic theory with a fitted parameter, α, the fraction of impinging gas molecules to the condensing surface. Values of α, were obtained in the range of 10 -6 to 10 -9 . Such volatile metal compounds and arsenic must be carefully controlled

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

Practices and developments in the management of low and intermediate level radioactive waste in Sweden

International Nuclear Information System (INIS)

Hultgren, Aa.

1983-06-01

In the Swedish nuclear power program ten reactors are in operation and two more under construction. About 100000 m 3 of low and intermediate level radioactive waste will be produced from the operation of these reactors until the year 2010 and about 150000 m 3 from their decommissioning. All burnable radioactive wastes are sent to the Studsvik incineration plant for incineration. Spent resins are incorporated into cement or bitumen. The volume of non-combustible solid waste is reduced by compaction where possible. At the Studsvik research centre a substantial program for improved management of accumulated and future radioactive waste is at the beginning of its implementation. This includes advanced treatment and intermediate storage in a rock cavity. An R and D program on volume reduction of spent resins has reached the point of process verification and equipment design. All low and intermediate radioactive waste will be disposed in a rock cavity planned for commissioning by 1988. The paper reviews actual management experience and development efforts for low and intermediate level radioactive waste in Sweden. Contribution to the Seminar on the Management of Radioactive Waste, Taipei, Taiwan, 25-26 June, 1983. (Author)

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...

INCINERATION TREATMENT OF ARSENIC-CONTAMINATED SOIL

Science.gov (United States)

An incineration test program was conducted at the U.S. Environmental Protection Agency's Incineration Research Facility to evaluate the potential of incineration as a treatment option for contaminated soils at the Baird and McGuire Superfund site in Holbrook, Massachusetts. The p...

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

Mound cyclone incinerator. Volume I. Description and performance

International Nuclear Information System (INIS)

Klingler, L.M.

1981-01-01

The Mound cyclone incinerator was developed to fill a need for a simple, relaible incinerator for volume reduction of dry solid waste contaminated with plutonium-238. Although the basic design of the incinerator is for batch burning of solid combustible waste, the incinerator has also been adapted to volume reduction of other waste forms. Specialized waste feeding equipment enables continuous burning of both solid and liquid waste, including full scintillation vials. Modifications to the incinerator offgas system enable burning of waste contaminated with isotopes other than plutonium-238. This document presents the design and performance characteristics of the Mound Cyclone Incinerator for incineration of both solid and liquid waste. Suggestions are included for adaptation of the incinerator to specialized waste materials

Oxygen enrichment incineration

International Nuclear Information System (INIS)

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

2000-10-01

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

Oxygen enrichment incineration

Energy Technology Data Exchange (ETDEWEB)

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

2000-10-01

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

Current and perspective on the radioactive waste management at territory of the Kola Peninsula

International Nuclear Information System (INIS)

Amazova, Ludmila

1999-01-01

According to this presentation, 25 thousand cubic metres of solid radioactive waste of one million Ci activity has accumulated in the Murmansk Region because of previous civilian and military activities and more will come as a result of the coming decommissioning of nuclear submarines and nuclear power plants. Only a part of the solid radioactive waste is reprocessed at the Kola nuclear power plant and at the repairing and technological enterprise Atomflot. Compaction and incineration are used to decrease the volume of waste. An incineration facility at Atomflot fails to satisfy new requirements and even releases more radioactivity to the atmosphere than what used to come from the Kola nuclear power plant operation. Solid radioactive waste is stored non-reprocessed Spetscombinat special plant Radon. This plant collects and stores radioactive waste produced by the civil industry and at the bases of the Northern Fleet. It is emphasised, however, that during the observation period there were no cases of dangerous increase in radioactivity in the atmosphere. Soil and vegetation contamination by long-lived radionuclides was at the background level. The establishment of a common reprocessing and regional storage facility for long-term storage has been proposed by the Ministry for Atomic Energy

ORGDP RCRA/PCB incinerator facility

International Nuclear Information System (INIS)

Rogers, T.

1987-01-01

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

Chemical and sewage sludge co-incineration in a full-scale MSW incinerator: toxic trace element mass balance.

Science.gov (United States)

Biganzoli, Laura; Grosso, Mario; Giugliano, Michele; Campolunghi, Manuel

2012-10-01

Co-incineration of sludges with MSW is a quite common practice in Europe. This paper illustrates a case of co-incineration of both sewage sludges and chemical sludges, the latter obtained from drinking water production, in a waste-to-energy (WTE) plant located in northern Italy and equipped with a grate furnace, and compares the toxic trace elements mass balance with and without the co-incineration of sludges. The results show that co-incineration of sewage and chemical sludges does not result in an increase of toxic trace elements the total release in environment, with the exception of arsenic, whose total release increases from 1 mg t(fuel) (-1) during standard operation to 3 mg t(fuel) (-1) when sludges are co-incinerated. The increase of arsenic release is, however, attributable to the sole bottom ashes, where its concentration is five times higher during sludge co-incineration. No variation is observed for arsenic release at the stack. This fact is a further guarantee that the co-incineration of sludges, when performed in a state-of-the-art WTE plant, does not have negative effects on the atmospheric environment.

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

A novel hydrothermal method to convert incineration ash into pollucite for the immobilization of a simulant radioactive cesium

Energy Technology Data Exchange (ETDEWEB)

Jing, Zhenzi, E-mail: zzjing@tongji.edu.cn [Key Laboratory of Advanced Civil Engineering Materials, Ministry of Education, Tongji University, 4800 Cao’an Road, Shanghai 201804 (China); Hao, Wenbo; He, Xiaojun; Fan, Junjie; Zhang, Yi; Miao, Jiajun [Key Laboratory of Advanced Civil Engineering Materials, Ministry of Education, Tongji University, 4800 Cao’an Road, Shanghai 201804 (China); Jin, Fangming [School of Environmental Science and Engineering, Shanghai Jiao Tong University, 800 Dongchuan Road, Shanghai 200240 (China)

2016-04-05

Highlights: • Incineration ash could be converted hydrothermally to pollucite to immobilize Cs. • Pollucite could be synthesized readily with a wide range of Cs/Si ratios. • With Ca(OH){sub 2} added, a tough pollucite could be used to solidify Cs-polluted RHA. • Leaching results showed that the amount of Cs leached from specimen was very low. - Abstract: The Fukushima nuclear accident in Japan on March 11, 2011 produced huge amounts of Cs-polluted incineration ashes; conventional solidification methods seem unsuitable for the treatment of large amounts of Cs-polluted ashes. A novel hydrothermal method was developed to directly convert Cs-polluted incineration ash (rice husk ash) into pollucite to immobilize Cs in its crystal structure in situ. Results revealed that pollucite could be synthesized readily over a wide range of added Cs (Cs/Si = 0.2–0.6); the addition of more Cs (Cs/Si ≥ 0.5) caused the formation of a small amount of cesium aluminosilicate (CsAlSiO{sub 4}), which exhibits poor immobilization behavior for Cs. Pollucite could be formed even for a short curing time (1 h) or at a low curing temperature (150 °C). However, a high curing temperature or a long curing time favored the formation of a pure pollucite. With the added calcium hydroxide, a tough specimen with a flexural strength of approximately 22 MPa could be obtained, which suggested that this technology may be applied directly to the solidification of Cs-polluted incineration ashes. Hydrogarnet and tobermorite formations enhanced the strength of the solidified specimens, and meanwhile the formed pollucite was present in a matrix steadily. Leaching test demonstrated that the amount of Cs that leached from the synthesized specimens was very low (0.49 × 10{sup −5}–2.31 × 10{sup −5}) and even lower than that from the reference hollandite-rich synroc (2.0 × 10{sup −2}), although a higher content of Cs was found in the synthesized pollucite specimens (6.0–31.7%) than in the

Controlled air incinerator conceptual design study

International Nuclear Information System (INIS)

1982-01-01

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

Incineration: efficient, economical and environmental

International Nuclear Information System (INIS)

Mascarenhas, A.

2003-01-01

Significant improvements in incinerator design and technology resulting in optimal performance, increased reliability and reduced capital and operating costs are discussed. The objective of the discussion is to draw attention to incineration as a cost effective and environmentally responsible means of disposing of the waste products generated by the oil and gas industry, while improving air quality and reduce greenhouse gas emissions at the same time. The main point put forward is that because the global warming potential of methane is 21 times greater than that of carbon dioxide, the complete combustion potential of incineration, combined with the fact that incineration requires significantly less fuel gas to combust low heat content streams, offers significantly reduced greenhouse gas emissions and improved air quality

Recycling ampersand incineration: Evaluating the choices

International Nuclear Information System (INIS)

Denison, R.A.; Ruston, J.

1993-01-01

Conflicts between proponents of municipal solid waste incineration and advocates of recycling have escalated with efforts to reduce the volume of waste that ends up in landfills. Central to this debate is competition for materials that are both combustible and recyclable. Environmental and economic concerns also play a major role. This book, produced by the Environmental Defense Fund, compares recycling and incineration. It is intended for 'citizens, government officials, and business people who want to help resolve the solid-waste crisis.' The book is divided into three parts: recycling and incineration; health and environmental risk of incineration; and planning, public participation, and environmental review requirements. The book does an excellent job of discussing the benefits of recycling and the pitfalls of incineration. It provides helpful information for identifying questions that should be raised about incineration, but it does not raise similar queries about recycling. There is much worthwhile information here, but the book would be more useful if it identified critical issues for all waste reduction and management options

Incineration conference 1990

International Nuclear Information System (INIS)

Anon.

1990-01-01

This book contains the proceedings of the 1990 incineration conference. The proceedings are organized under the following headings: Regulations- international comparison, Current trends in facility design, Oxygen enhancement, Metals, Off-gas treatment, Operating experience: transportable, Materials, Operating experience: R/A and mixed, Incineration of specific wastes, Medical waste management, Ash qualification, Ash solidification/ immobilization, Innovative technologies, Operating experience : medical waste, Instrumentation and monitoring, process control and modeling, Risk assessment/management, Operating considerations

Radioactive contamination of sewage sludge. Preliminary data

Energy Technology Data Exchange (ETDEWEB)

Soeder, C J; Zanders, E; Raphael, T

1986-01-01

Because of the radioactivity released through the explosion of the nuclear reactor near Chernobyl radionuclides have been accumulated to a significant extent in sewage sludge in the Federal Republic of Germany. This is demonstrated for samples from four activated sludge plants according to a recent recommendation of the German Commission for Radiation Protection, there is until now no reason to deviate from the common practices of sludge disposal or incineration. The degree of radioactive contamination of plant materials produced on farm lands on which sewage sludge is being spread cannot be estimated with sufficient certainty yet. Additional information is required.

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

Incineration experiences at the Tsuruga P.S. and outline of the advanced type incineration system at the Tokai No. 2 P.S

International Nuclear Information System (INIS)

Yui, K.; Kurihara, Y.; Inoue, S.; Takamori, H.; Karita, Y.

1987-01-01

In 1978, the first radwaste incineration plant among Japanese nuclear power stations started its operation at Tsuruga P.S., and the first advanced radwaste incineration plant has been constructed and accomplished the test operation in September 1986. This paper describes the outline of Tsuruga incineration plant and its operation achievements, and the outline of advanced incineration technology, Tokai No. 2 incineration plant and its test operation results

Field testing of particulate matter continuous emission monitors at the DOE Oak Ridge TSCA incinerator. Toxic Substances Control Act.

Science.gov (United States)

Dunn, James E; Davis, Wayne T; Calcagno, James A; Allen, Marshall W

2002-01-01

A field study to evaluate the performance of three commercially available particulate matter (PM) continuous emission monitors (CEMs) was conducted in 1999-2000 at the US Department of Energy (DOE) Toxic Substances Control Act (TSCA) Incinerator. This study offers unique features that are believed to enhance the collective US experience with PM CEMs. The TSCA Incinerator is permitted to treat PCB-contaminated RCRA hazardous low-level radioactive wastes. The air pollution control system utilizes MACT control technology and is comprised of a rapid quench, venturi scrubber, packed bed scrubber, and two ionizing wet scrubbers in series, which create a saturated flue gas that must be conditioned by the CEMs prior to measurement. The incinerator routinely treats a wide variety of wastes including high and low BTU organic liquids, aqueous, and solid wastes. The various possible combinations for treating liquid and solid wastes may present a challenge in establishing a single, acceptable correlation relationship for individual CEMs. The effect of low-level radioactive material present in the waste is a unique site-specific factor not evaluated in previous tests. The three systems chosen for evaluation were two beta gauge devices and a light scattering device. The performance of the CEMs was evaluated using the requirements in draft Environmental Protection Agency (EPA) Performance Specification 11 (PS11) and Procedure 2. The results of Reference Method 5i stack tests for establishing statistical correlations between the reference method data and the CEMs responses are discussed.

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)

Incineration and flue gas treatment technologies

International Nuclear Information System (INIS)

1997-01-01

The proceedings are presented of an international symposium on Incineration and Flue Gas Treatment Technologies, held at Sheffield University in July 1997. Papers from each of the six sessions cover the behaviour of particles in incinerator clean-up systems, pollution control technologies, the environmental performance of furnaces and incinerators, controlling nitrogen oxide emissions, separation processes during flue gas treatment and regulatory issues relating to these industrial processes. (UK)

ISCORS ASSESSMENT OF RADIOACTIVITY IN SEWAGE SLUDGE: MODELING TO ASSESS RADIATION DOSES

Science.gov (United States)

The Interagency Steering Committee on Radiation Standards (ISCORS) has recently completed a study of the occurrence within the United States of radioactive materials in sewage sludge and sewage incineration ash. One component of that effort was an examination of the possible tran...

Leaching of solidified TRU-contaminated incinerator ash

International Nuclear Information System (INIS)

Fuhrmann, M.; Colombo, P.

1984-01-01

Leach rate and cumulative fractional releases of plutonium were determined for a series of laboratory-scale waste forms containing transuranic (TRU) contaminated incinerator ash. The solidification agents from which these waste forms were produced are commercially available materials for radioactive waste disposal. The leachants simulate groundwaters with chemical compositions that are indiginous to different geological media proposed for repositories. In this study TRU-contaminated ash was incorporated into waste forms fabricated with portland type I cement, urea-formaldehyde, polyester-styrene or Pioneer 221 bitumen. The ash was generated at the dual-chamber incinerator at the Rocky Flats Plant. These waste forms contained between 1.25 x 10 -2 and 4.4 x 10 -2 Ci (depending on the solidification agent) of mixed TRU isotopes comprised primarily of 239 Pu and 240 Pu. Five leachant solutions were prepared consisting of: (1) demineralized water, (2) simulated brine, (3) simplified sodium-dominated groundwater (30 meq NaCl/liter), (4) simplified calcium-dominated groundwater (30 meq CaCl 2 /liter), and (5) simplified bicarbonate-dominated groundwater (30 meq NaHCO 3 /liter). Cumulative fractional releases were found to vary significantly with different leachants and solidification agents. In all cases waste forms leached in brine gave the lowest leach rates. Urea-formaldehyde had the greatest release of radionuclides while polyester-styrene and portland cement had approximately equivalent fractional releases. Cement cured for 210 days retained radionuclides three times more effectively than cement cured only 30 days

Screening calculations for radioactive waste releases from non-nuclear facilities

International Nuclear Information System (INIS)

Xu, Shulan; Soederman, Ann-Louis

2009-02-01

A series of screening calculations have been performed to assess the potential radiological consequences of discharges of radioactive substances to the environment arising from waste from non-nuclear practices. Solid waste, as well as liquids that are not poured to the sewer, are incinerated and ashes from incineration and sludge from waste water treatment plants are disposed or reused at municipal disposal facilities. Airborne discharges refer to releases from an incineration facility and liquid discharges refer both to releases from hospitals and laboratories to the sewage system, as well as leakage from waste disposal facilities. The external exposure of workers is estimated both in the waste water treatment plant and at the disposal facility. The calculations follow the philosophy of the IAEA's safety guidance starting with a simple assessment based on very conservative assumptions which may be iteratively refined using progressively more complex models, with more realistic assumptions, as necessary. In the assessments of these types of disposal, with cautious assumptions, carried out in this report we conclude that the radiological impacts on representative individuals in the public are negligible in that they are small with respect to the target dose of 10 μSv/a. A Gaussian plume model was used to estimate the doses from airborne discharges from the incinerator and left a significant safety margin in the results considering the conservative assumptions in the calculations. For the sewage plant workers the realistic approach included a reduction in working hours and the shorter exposure time resulted in maximum doses around 10 μSv/a. The calculations for the waste disposal facility show that the doses are higher or in the range of the target dose. The excess for public exposure is mainly caused by H-3 and C-14. The assumption used in the calculation is that all of the radioactive substances sent to the incineration facility and waste water treatment plant

Screening calculations for radioactive waste releases from non-nuclear facilities

Energy Technology Data Exchange (ETDEWEB)

Shulan Xu; Soederman, Ann-Louis

2009-02-15

A series of screening calculations have been performed to assess the potential radiological consequences of discharges of radioactive substances to the environment arising from waste from non-nuclear practices. Solid waste, as well as liquids that are not poured to the sewer, are incinerated and ashes from incineration and sludge from waste water treatment plants are disposed or reused at municipal disposal facilities. Airborne discharges refer to releases from an incineration facility and liquid discharges refer both to releases from hospitals and laboratories to the sewage system, as well as leakage from waste disposal facilities. The external exposure of workers is estimated both in the waste water treatment plant and at the disposal facility. The calculations follow the philosophy of the IAEA's safety guidance starting with a simple assessment based on very conservative assumptions which may be iteratively refined using progressively more complex models, with more realistic assumptions, as necessary. In the assessments of these types of disposal, with cautious assumptions, carried out in this report we conclude that the radiological impacts on representative individuals in the public are negligible in that they are small with respect to the target dose of 10 muSv/a. A Gaussian plume model was used to estimate the doses from airborne discharges from the incinerator and left a significant safety margin in the results considering the conservative assumptions in the calculations. For the sewage plant workers the realistic approach included a reduction in working hours and the shorter exposure time resulted in maximum doses around 10 muSv/a. The calculations for the waste disposal facility show that the doses are higher or in the range of the target dose. The excess for public exposure is mainly caused by H-3 and C-14. The assumption used in the calculation is that all of the radioactive substances sent to the incineration facility and waste water treatment

Quantifying capital goods for waste incineration

International Nuclear Information System (INIS)

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

2013-01-01

Highlights: • Materials and energy used for the construction of waste incinerators were quantified. • The data was collected from five incineration plants in Scandinavia. • Included were six main materials, electronic systems, cables and all transportation. • The capital goods contributed 2–3% compared to the direct emissions impact on GW. - Abstract: 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 CO 2 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 CO 2 per tonne of waste combusted

Seventy years of incineration

Energy Technology Data Exchange (ETDEWEB)

Dumbleton, Brian

1995-06-08

A third waste incineration plant, which will conform to new United Kingdom emission standards is currently under construction at Tyseley in Birmingham. The plant will generate 25MW of electricity for 25,000 households by burning 350,000 t of municipal wastes per year. The site has been used for such energy from waste schemes since 1926. The new plant includes the latest air pollution abatement equipment designed to absorb mercury vapour and dioxins together with fabric filters. Other improvements at the Tyseley site include a new purpose built public waste disposal facility, clinical waste and animal carcass incineration and the recovery of 16,000t of ferrous metals per year for recycling. Because these waste products are incinerated it also therefore reduce`s Birmingham`s need for landfill sites. (UK)

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

Commercial Cyclone Incinerator Demonstration Program: April-September 1979

International Nuclear Information System (INIS)

Alexander, B.M.

1979-01-01

The commercial cyclone incinerator program was designed to study the effects of burning low-level waste contaminated with beta and gamma emitters in a cyclone system. The ultimate program goal is the demonstration of a cyclone incinerator at a nuclear power plant. During the past six months, the first program objective, NRC review of the Feasibility Plan, was achieved, and work began on the second objective, Complete Incinerator Feasibility Plan. Potential applications for the cyclone incinerator have been investigated. The feasibility plan for the incinerator system was reviewed with the Nuclear Regulatory Commission (NRC). Following a series of cold checkout burns, implementation of the feasibility plan was begun with the start of laboratory-scale experiments. Inconel 601 is being investigated as a material of construction for the incinerator burn chamber

Risks of municipal solid waste incineration: an environmental perspective.

Science.gov (United States)

Denison, R A; Silbergeld, E K

1988-09-01

The central focus of the debate over incineration of municipal solid waste (MSW) has shifted from its apparent management advantages to unresolved risk issues. This shift is a result of the lack of comprehensive consideration of risks associated with incineration. We discuss the need to expand incinerator risk assessment beyond the limited view of incinerators as stationary air pollution sources to encompass the following: other products of incineration, ash in particular, and pollutants other than dioxins, metals in particular; routes of exposure in addition to direct inhalation; health effects in addition to cancer; and the cumulative nature of exposure and health effects induced by many incinerator-associated pollutants. Rational MSW management planning requires that the limitations as well as advantages of incineration be recognized. Incineration is a waste-processing--not a waste disposal--technology, and its products pose substantial management and disposal problems of their own. Consideration of the nature of these products suggests that incineration is ill-suited to manage the municipal wastestream in its entirety. In particular, incineration greatly enhances the mobility and bioavailability of toxic metals present in MSW. These factors suggest that incineration must be viewed as only one component in an integrated MSW management system. The potential for source reduction, separation, and recycling to increase the safety and efficiency of incineration should be counted among their many benefits. Risk considerations dictate that alternatives to the use of toxic metals at the production stage also be examined in designing an effective, long-term MSW management strategy.

Clean burn: Incinerators get more efficient

International Nuclear Information System (INIS)

Budd, G.

2003-01-01

Combustion efficiency and accuracy of today's new breed of incinerators is discussed. The latest of these units are capable of delivering 99.99 per cent combustion efficiency with no visible flame, black smoke or detectable odour. Near-complete combustion is achieved with incineration because of the very high temperatures reached in the enclosed combustion chamber as a combination of temperature, time for burning, and a good mix of gases and oxygen. Controlling these inputs is the key to efficient incineration, as is high quality fibre refractory lining; control means control of the stack top temperature, which will affect what comes out of the top water and how well the combustion byproducts are dispersed. Until recently, incinerators have not been highly regarded by the oil industry. However, with the growing concerns about greenhouse gases, carcinogens and in response to increasing regulations aimed at reducing venting and flaring, incinerators are coming into their own. Today they are seen more and more frequently in well testing, coalbed methane testing, at battery sites and at gas plants

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)

State-of-the-art report on low-level radioactive waste treatment

International Nuclear Information System (INIS)

Kibbey, A.H.; Godbee, H.W.

1980-09-01

An attempt is made to identify the main sources of low-level radioactive wastes that are generated in the United States. To place the waste problem in perspective, rough estimates are given of the annual amounts of each generic type of waste that is generated. Most of the wet solid wastes arise from the cleanup of gaseous and liquid radioactive streams prior to discharge or recycle. The treatment of the process streams and the secondary wet solid wastes thus generated is described for each type of government or fuel cycle installation. Similarly, the institutional wet wastes are also described. The dry wastes from all sources have smilar physical and chemical characteristics in that they can be classified as compactible, noncompactible, combustible, noncombustible, or combinations thereof. The various treatment options for concentrated or solid wet wastes and for dry wastes are discussed. Among the dry-waste treatment methods are compaction, baling, and incineration, as well as chopping, cutting, and shredding. Organic materials can usually be incinerated or, in some cases, biodegraded. The filter sludges, spent resins, incinerator ashes, and concentrated liquids are usually solidified in cement, urea-formaldehyde, or unsaturated polyester resins prior to burial. Asphalt has not yet been used as a solidificaton agent in the United States, but it probably will be used in the near future. The treatment of radioactive medical and bioresearch wastes is described, but the waste from radiochenmical, pharmaceutical, and other industries is not well defined at the present time. Recovery of waste metals and treatment of hazardous contaminated wastes are discussed briefly. Some areas appearing to need more research, development, and demonstration are specifically pointed out

State-of-the-art report on low-level radioactive waste treatment

Energy Technology Data Exchange (ETDEWEB)

Kibbey, A.H.; Godbee, H.W.

1980-09-01

An attempt is made to identify the main sources of low-level radioactive wastes that are generated in the United States. To place the waste problem in perspective, rough estimates are given of the annual amounts of each generic type of waste that is generated. Most of the wet solid wastes arise from the cleanup of gaseous and liquid radioactive streams prior to discharge or recycle. The treatment of the process streams and the secondary wet solid wastes thus generated is described for each type of government or fuel cycle installation. Similarly, the institutional wet wastes are also described. The dry wastes from all sources have smilar physical and chemical characteristics in that they can be classified as compactible, noncompactible, combustible, noncombustible, or combinations thereof. The various treatment options for concentrated or solid wet wastes and for dry wastes are discussed. Among the dry-waste treatment methods are compaction, baling, and incineration, as well as chopping, cutting, and shredding. Organic materials can usually be incinerated or, in some cases, biodegraded. The filter sludges, spent resins, incinerator ashes, and concentrated liquids are usually solidified in cement, urea-formaldehyde, or unsaturated polyester resins prior to burial. Asphalt has not yet been used as a solidificaton agent in the United States, but it probably will be used in the near future. The treatment of radioactive medical and bioresearch wastes is described, but the waste from radiochenmical, pharmaceutical, and other industries is not well defined at the present time. Recovery of waste metals and treatment of hazardous contaminated wastes are discussed briefly. Some areas appearing to need more research, development, and demonstration are specifically pointed out.

The IRIS Incinerator at Cea-Valduc assessment after more than one ton and a half of active waste incineration

International Nuclear Information System (INIS)

Chateauvieux, H.; Guiberteau, P.; Longuet, T.; Lemort, F.; Lannaud, J.; Lorich, M.; Medzadourian, M.

2000-01-01

During the operation of its facilities, the Valduc Research Center produces alpha-contaminated solid waste. An incineration facility has been built to treat the most contaminated combustible waste. The process selected for waste incineration is the IRIS process, which was developed by the CEA at the Marcoule Nuclear Research Center. The Valduc Center asked SGN to build the incineration facility. The facility was commissioned in late 1996, and inactive waste incineration campaigns were run during more than 2,500 hours in 1997-1998. Active commissioning of the facility was performed in March 1999. Since then five campaigns with active waste and a complete plutonium cleaning session have been carried out, the results of which are given in the paper. The Valduc incinerator is the first industrial active application of the IRIS process. (authors)

Incineration of ion-exchange resins

International Nuclear Information System (INIS)

Valkiainen, M.; Nykyri, M.

1985-01-01

Incineration of ion-exchange resins in a fluidized bed was studied on a pilot plant scale at the Technical Research Centre of Finland. Both granular and powdered resins were incinerated in dry and slurry form. Different bed materials were used in order to trap as much cesium and cobalt (inactive tracers) as possible in the bed. Also the sintering of the bed materials was studied in the presence of sodium. When immobilized with cement the volume of ash-concrete is 4 to 22% of the concrete of equal compressive strength acquired by direct solidification. Two examples of multi-purpose equipment capable of incinerating ion-exchange resins are presented. (orig.)

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

Low-level and mixed waste incinerator survey report

International Nuclear Information System (INIS)

Garcia, E.C.

1988-10-01

The Low-Level and Mixed Waste Survey Task was initiated to investigate and document current and planned incinerator facilities in the Department of Energy Defense Programs (DOE-DP) system. A survey was mailed to the DOE field offices requesting information regarding existing or planned incinerator facilities located under their jurisdiction. The information requested included type, capacities, uses, costs, and mechanical description of the incinerators. The results of this survey are documented in this report. Nine sites responded to the survey, with eight sites listing nine incineration units in several stages of operations. The Idaho National Engineering Laboratory listed two operational facilities. There are four incinerators that are planned for start-up in 1991. Of the existing incinerators, three are used mostly for low-level wastes, while the planned units will be used for low-level, mixed, and hazardous wastes. This report documents the current state of the incineration facilities in the DOE-DP system and provides a preliminary strategy for management of low-level wastes and a basis for implementing this strategy. 5 refs., 4 figs., 14 tabs

Oak Ridge Toxic Substances Control Act (TSCA) Incinerator test bed for continuous emissions monitoring systems (CEMS)

International Nuclear Information System (INIS)

Gibson, L.V. Jr.

1997-01-01

The Toxic Substances Control Act (TSCA) Incinerator, located on the K-25 Site at Oak Ridge, Tennessee, continues to be the only operational incinerator in the country that can process hazardous and radioactively contaminated polychlorinated biphenyl (PCB) waste. During 1996, the US Department of Energy (DOE) Environmental Management Office of Science and Technology (EM-50) and Lockheed Martin Energy Systems established a continuous emissions monitoring systems (CEMS) test bed and began conducting evaluations of CEMS under development to measure contaminants from waste combustion and thermal treatment stacks. The program was envisioned to promote CEMS technologies meeting requirements of the recently issued Proposed Standards for Hazardous Waste Combustors as well as monitoring technologies that will allay public concerns about mixed waste thermal treatment and accelerate the development of innovative treatment technologies. Fully developed CEMS, as well as innovative continuous or semi-continuous sampling systems not yet interfaced with a pollutant analyzer, were considered as candidates for testing and evaluation. Complementary to other Environmental Protection Agency and DOE sponsored CEMS testing and within compliant operating conditions of the TSCA Incinerator, prioritization was given to multiple metals monitors also having potential to measure radionuclides associated with particulate emissions. In August 1996, developers of two multiple metals monitors participated in field activities at the incinerator and a commercially available radionuclide particulate monitor was acquired for modification and testing planned in 1997. This paper describes the CEMS test bed infrastructure and summarizes completed and planned activities

40 CFR 60.2886 - What is a new incineration unit?

Science.gov (United States)

2010-07-01

... 40 Protection of Environment 6 2010-07-01 2010-07-01 false What is a new incineration unit? 60... Waste Incineration Units for Which Construction is Commenced After December 9, 2004, or for Which... incineration unit? (a) A new incineration unit is an incineration unit subject to this subpart that meets...

Incineration of Sludge in a Fluidized-Bed Combustor

OpenAIRE

Chien-Song Chyang; Yu-Chi Wang

2017-01-01

For sludge disposal, incineration is considered to be better than direct burial because of regulations and space limitations in Taiwan. Additionally, burial after incineration can effectively prolong the lifespan of a landfill. Therefore, it is the most satisfactory method for treating sludge at present. Of the various incineration technologies, the fluidized bed incinerator is a suitable choice due to its fuel flexibility. In this work, sludge generated from industrial plants was treated in ...

40 CFR 60.2015 - What is a new incineration unit?

Science.gov (United States)

2010-07-01

... 40 Protection of Environment 6 2010-07-01 2010-07-01 false What is a new incineration unit? 60... Industrial Solid Waste Incineration Units for Which Construction Is Commenced After November 30, 1999 or for... is a new incineration unit? (a) A new incineration unit is an incineration unit that meets either of...

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

Performance history of the WERF incinerator

International Nuclear Information System (INIS)

Dalton, J.D.; Bohrer, H.A.; Smolik, G.R.

1988-01-01

As society's environmental conscience grows, diverse political economical, and social contentions cloud the issue of proper waste management. However, experience at the Waste Experimental Reduction Facility (WERF) at the Idaho National Engineering Laboratory (INEL) demonstrates clearly that incineration is an effective component in responsible, long-term waste management. Using a simple but safe design, the WERF incinerator has successfully reduced the volume of low-level beta/gamma waste. This paper discusses some of the achievements and problems experienced during operation of the WERF incinerator

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.

Radioactive waste management at Institute for Nuclear Research (ICN) - Pitesti

International Nuclear Information System (INIS)

Bujoreanu, C.

2004-01-01

The amounts of liquid and solid wastes accumulated at the Radioactive Wastes Treatment Plant are given. The technologies used for the treatment and conditioning of radioactive wastes are presented. The final product is metallic drum-concrete-radioactive wastes (type A package) for the final disposal at the National Repository Baita, Bihor. The facilities for radioactive waste management at ICN Pitesti are: Plant for treatment, with uranium recovery of liquid radioactive waste resulting from the fabrication of CANDU type nuclear fuel; Plant for treatment of low-active liquid wastes; Plant for conditioning in concrete of the radioactive concentrate obtained during the evaporation treatment of liquid radioactive waste; Plant for incineration of solid radioactive waste contaminated with natural uranium; Plant for treatment and conditioning of organic liquid radioactive waste with tritium content. This wastes are generated by Cernavoda-NPP operation; Plant for conditioning into bitumen of spent ion exchangers at TRIGA reactor. The existing Facility is Baita repository - with two rock cavities of an uranium mine and the total capacity of 21000 containers (200 l drums)

Conceptual process description of M division incinerator project

Energy Technology Data Exchange (ETDEWEB)

Thompson, T.K.

1989-04-13

This interoffice memorandum describes an incineration system to be used for incinerating wood. The system is comprised of a shredder and an incinerator. The entire process is described in detail. A brief study of particulates, carbon monoxide, carbon dioxide, and nitrogen oxides emission is presented.

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

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

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

Energy Technology Data Exchange (ETDEWEB)

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.

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

Permeability of Consolidated Incinerator Facility Wastes Stabilized with Portland Cement

International Nuclear Information System (INIS)

Walker, B.W.

1999-01-01

The Consolidated Incinerator Facility (CIF) at the Savannah River Site (SRS) burns low-level radioactive wastes and mixed wastes as method of treatment and volume reduction. The CIF generates secondary waste, which consists of ash and off-gas scrubber solution. Currently the ash is stabilized/solidified in the Ashcrete process. The scrubber solution (blowdown) is sent to the SRS Effluent Treatment Facility (ETF) for treatment as waste water. In the past, the scrubber solution was also stabilized/solidified in the Ashcrete process as blowcrete and will continue to be treated this way for listed waste burns and scrubber solution that do not meet the Effluent Treatment Facility (ETF) Waste Acceptance Criteria (WAC)

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

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.)

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.

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

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.)

The Texas approach to the management of low-level radioactive waste after 1992

International Nuclear Information System (INIS)

Jacobi, L.R.

1992-01-01

By 1993, Texas licensees will be producing 52000 ft 3 of low level radioactive waste (LLRW) containing 11000 Ci of Radioactivity. The three operating pressurized water reactors will produce 63% of the waste volume and greater than 90% of the radioactivity. While the majority of the waste is solid LLRW, some of it, such as liquid scintillation vials and bulk liquids from hospitals, universities, and research facilities, is mixed waste. Most of this waste can be shipped out of state and incinerated, but 60 ft 3 of lead contaminated waste from nuclear power plants and other industrial plants requires land disposal

Process modeling study of the CIF incinerator

International Nuclear Information System (INIS)

Hang, T.

1995-01-01

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

CO2 laser-aided waste incineration

International Nuclear Information System (INIS)

Costes, J.R.; Guiberteau, P.; Caminat, P.; Bournot, P.

1994-01-01

Lasers are widely employed in laboratories and in certain industrial applications, notably for welding, cutting and surface treatments. This paper describes a new application, incineration, which appears warranted when the following features are required: high-temperature incineration (> 1500 deg C) with close-tolerance temperature control in an oxidizing medium while ensuring containment of toxic waste. These criteria correspond to the application presented here. Following a brief theoretical introduction concerning the laser/surface interaction, the paper describes the incineration of graphite waste contaminated with alpha-emitting radionuclides. Process feasibility has been demonstrated on a nonradioactive prototype capable of incinerating 10 kg -h-1 using a 7 kW CO 2 laser. An industrial facility with the same capacity, designed to operate within the constraints of an alpha-tight glove box environment, is now at the project stage. Other types of applications with similar requirements may be considered. (authors). 3 refs., 7 figs

Quantifying capital goods for waste incineration

DEFF Research Database (Denmark)

Brogaard, Line Kai-Sørensen; Riber, C.; Christensen, Thomas Højlund

2013-01-01

material used amounting to 19,000–26,000tonnes 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 4000–5000MWh. In terms of the environmental burden...... 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.......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...

Air curtain incinerator equipment performance evaluation report

Energy Technology Data Exchange (ETDEWEB)

1987-01-01

About 50 tonnes of oil-contaminated debris and related wood products were successfully incinerated in a 10-h performance evaluation of a mobile air curtain incinerator. The test was conducted to evaluate the incinerator's ability to combust oil-contaminated trash and debris obtained from oil spill sites. The operating principle of the apparatus involves a diesel engine driving an air blower to deliver ca 20,000 scfm of air into a 5-m long manifold angled at a 30{degree} slope into an incineration tank. A bottomhole aerator is lowered to the bottom of the tank and compressed air is injected into the aerator to control burn efficiency. The blower is engaged once the debris in the tank is burning sufficiently after starting a fire in the debris. The air curtain effect created by the air deflecting off the opposite wall from the blower manifold and bouncing off the bottom and up the side of the incineration tank results in repeated combustion of the gases, thereby significantly reducing the degree of visible smoke emission. The unit is capable of incinerating ca 5 tonnes/h and of generating ca 16 m{sup 3}/h of hot water which can be used for flushing spill sites and cleaning shorelines. 12 figs.

Dioxin formation from waste incineration.

Science.gov (United States)

Shibamoto, Takayuki; Yasuhara, Akio; Katami, Takeo

2007-01-01

There has been great concern about dioxins-polychlorinated dibenzo dioxins (PCDDs), polychlorinated dibenzo furans (PCDFs), and polychlorinated biphenyls (PCBs)-causing contamination in the environment because the adverse effects of these chemicals on human health have been known for many years. Possible dioxin-contamination has received much attention recently not only by environmental scientists but also by the public, because dioxins are known to be formed during the combustion of industrial and domestic wastes and to escape into the environment via exhaust gases from incinerators. Consequently, there is a pressing need to investigate the formation mechanisms or reaction pathways of these chlorinated chemicals to be able to devise ways to reduce their environmental contamination. A well-controlled small-scale incinerator was used for the experiments in the core references of this review. These articles report the investigation of dioxin formation from the combustion of various waste-simulated samples, including different kinds of paper, various kinds of wood, fallen leaves, food samples, polyethylene (PE), polystyrene (PS), polyvinyl chloride (PVC), polyvinylidene chloride, polyethylene tetraphthalate (PET), and various kinds of plastic products. These samples were also incinerated with inorganic chlorides (NaCl, KCl, CuCI2, MgCl2, MnCl2, FeCl2, CoCl2, fly ash, and seawater) or organic chlorides (PVC, chlordane, and pentachlorophenol) to investigate the role of chlorine content and/or the presence of different metals in dioxin formation. Some samples, such as newspapers, were burned after they were impregnated with NaCl or PVC, as well as being cocombusted with chlorides. The roles of incineration conditions, including chamber temperatures, O2 concentrations, and CO concentrations, in dioxin formation were also investigated. Dioxins (PCDDs, PCDFs, and coplanar-PCBs) formed in the exhaust gases from a controlled small-scale incinerator, where experimental waste

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.

Technological process of a multi-purpose radwaste incineration system

International Nuclear Information System (INIS)

Wang Peiyi; Zhou Lianquan; Ma Mingxie; Qiu Mingcai; Yang Liguo; Li Xiaohai; Zhang Xiaobin; Lu Xiaowu; Dong Jingling; Wang Xujin; Li Chuanlian; Yang Baomin

2002-01-01

The author introduces the technological process of a multi-purpose radwaste incineration system. It is composed of three parts: pretreatment, incinerating and clean up of off-gas. The waste that may be treated include combustible solid waste, spent resins and oils. Technological routes of the system is pyrolysis incinerating for solid waste, spray incinerating for spent oils, combination of dry-dust removing and wet adsorption for cleaning up off-gas

Operational experience with Seibersdorf low-level incinerator

International Nuclear Information System (INIS)

Chalupa, G.

1987-01-01

This report contains information about an excess air incinerator which burned low level β and γ wastes (also α up to determined limits). The incinerator was started up in 1980 and it is clear that in a technical plant of such magnitude, some changes and alterations will be needed to be overcome according to the experiences of operation. This paper - after a short description of the incinerator plant itself - gives a summary of some of the operation and the changes which are made in the plant according to these facts. A partial redesign of the incinerator plant in the first half of 1985 resulted in a very satisfying new design, which proved its superiority during the runs in 1985 and 1986

Activated carbon for incinerator uses

International Nuclear Information System (INIS)

Che Seman Mahmood; Norhayati Alias; Mohd Puad Abu

2002-01-01

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

Los Alamos controlled-air incineration studies

International Nuclear Information System (INIS)

Koenig, R.A.; Warner, C.L.

1983-01-01

Current regulations of the Environmental Protection Agency (EPA) require that PCBs in concentrations greater than 500 ppM be disposed of in EPA-permitted incinerators. Four commercial incineration systems in the United States have EPA operating permits for receiving and disposing of concentrated PCBs, but none can accept PCBs contaminated with nuclear materials. The first section of this report presents an overview of an EPA-sponsored program for studying PCB destruction in the large-scale Los Alamos controlled-air incinerator. A second major FY 1983 program, sponsored by the Naval Weapons Support Center, Crane, Indiana, is designed to determine operating conditions that will destroy marker smoke compounds without also forming polycyclic aromatic hydrocarbons (PAHs), some of which are known or suspected to be carcinogenic. We discuss the results of preliminary trial burns in which various equipment and feed formulations were tested. We present qualitative analyses for PAHs in the incinerator offgas as a result of these tests

Evaluation of low-level solid radioactive waste generated by a large hospital and disposed of with ordinary refuse

International Nuclear Information System (INIS)

Conte, L.; Pedroli, G.; Monciardini, M.; Bianchi, L.; Novario, R.; Beretta, A.

1996-01-01

In the Lombardy region some hospitals have recently been reported to the local authorities because of the presence of radioactivity in hospital refuse sent to the municipal tips for incineration. On various occasions the refuse collectors coming from the hospitals had to return with their refuse as traces of radioactivity were detected at the entrance to the tips equipped with monitoring systems. Hospitals administering radioactive substances for diagnostic or therapeutic purposes produce radioactive waste mainly in solid and liquid form. This waste is principally present in patient excreta and in contaminated materials. Radioactive waste present in patient excreta is normally disposed of through the sewage system provided that the concentration limits and annual activity stipulated by law are respected. The contaminated materials coming from the departments that carry out radioisotopic investigations and therapy with unsealed sources can be collected separately and sent to a tip after a period of storage to permit radioactive decay. However, part of the radioactive waste escapes all checks and inevitably mixes with normal refuse or with special hospital refuse that is not considered radioactive. This occurs in the case of: 1. excreta from patients who are not hospitalised after a radioisotopic investigation and materials contaminated by the excreta; 2. excreta from hospitalised patients which are eliminated outside the nuclear medicine and radiotherapy departments; 3. contaminated materials produced with unsealed sources in hospital departments other than those of nuclear medicine and radiotherapy; The waste indicated in point 1 is probably the main problem in ecological terms as the patients who are not hospitalised eliminate radioactive excreta into domestic sewage systems and can also contaminate materials that are disposed of with normal household refuse. In this case any solution to the problem would seriously affect diagnostic activities carried out in the

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.

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.

40 CFR 60.2992 - What is an existing incineration unit?

Science.gov (United States)

2010-07-01

... 40 Protection of Environment 6 2010-07-01 2010-07-01 false What is an existing incineration unit... Times for Other Solid Waste Incineration Units That Commenced Construction On or Before December 9, 2004 Applicability of State Plans § 60.2992 What is an existing incineration unit? An existing incineration unit is...

Development of Mitsubishi--Lurgi fluidized bd incinerator with pre-drying hearths

Energy Technology Data Exchange (ETDEWEB)

Hori, Y; Senshu, A; Mishima, K; Sato, T; Honda, H

1979-02-01

For a better disposal of a steadily increasing volume of sludges with energy conservation it is essential to develop an effective and energy-saving incinerator. The fluidized bed incinerator now widely used for the disposal of sludges has many superior features as compared with the conventional vertical multiple-hearth incinerator, but, on the other hand, has a defect, that is, a large fuel consumption. This is due to the fact that the fluidized bed incinerator has generally low drying efficiency notwithstanding its excellent burning characteristics with minimum excess air. The feasibility of fuel saving by installing sludge pre-drying hearths and an exhaust gas recirculation system additionally on the conventional fluidized bed incinerator and conducted incineration tests on various kinds of sludges, using a 1500 kg/h pilot plant equipped with the incinerator is examined. As the result, the Mitsubishi--Lurgi fluidized bed incinerator with high efficiency multiple pre-drying hearths which consumes less fuel was developed. Part of the incineration test results are presented.

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.

National Plan for the management of radioactive materials and wastes 2013-2015

International Nuclear Information System (INIS)

2013-02-01

This new release of the National Plan for the management of radioactive materials and wastes (PNGMDR) first addresses the principles and objectives of this management: presentation of radioactive materials and wastes, principles to be taken into account to define the different management ways, legal and institutional framework for waste management, societal dimension and memory safeguarding, waste management cost and financing. It proposes an assessment and draws perspectives for the existing management practices: management of historical situations, management of residues of mine processing and mine tailings, management of radioactive wastes, waste management with respect to radioactive decay, valorization of radioactive wastes, incineration of radioactive wastes, storage of very-low-activity wastes, of storage of low- and medium-activity and short-life wastes, management of reinforced natural radioactivity wastes. The third part gives an overview of needs and perspectives for management methods: wastes requiring a specific processing, low-activity long-life wastes, and high-activity and medium-activity long-life wastes

Reduction of radioactive waste by improvement of conditioning facilities

Energy Technology Data Exchange (ETDEWEB)

Radde, E.

2014-07-01

The NES (Nuclear Engineering Seibersdorf) is the only radioactive waste conditions and storage facility in Austria. It manages waste originating from research, industry and medicine. Its main goal is, not only to treat and store waste safety, but also to optimize processes to further reduce the waste volume. To achieve this goal, the New Handling Facility was built. In this paper we will show how the waste volume can be easily reduced by optimizing the conditioning and waste stream process. The NES owns a water treatment plant for cleaning of active waste water, an incineration plant that is used to burn radioactive waste. (Author)

An overview of a nuclear waste incinerator's erection and commissioning

International Nuclear Information System (INIS)

Li Xiaohai; Zhou Lianquan; Wang Peiyi; Yang Liguo; Zhang Xiaobin; Wang Xujin; Li Chuanlian; Dong Jingling; Zheng Bowen; Qiu Mingcai

2004-01-01

An incinerator for combustible nuclear waste, with spent oil and graphite included, was established. The processes are briefly described, which combines pyrolysis-incineration of solid, spray-incineration of oils and fixed bed incineration of graphite, followed by off-gas treatment employing both dry and wet means. The results from non-active and active trial run are also reported

Development and testing of a mobile incinerator

International Nuclear Information System (INIS)

Eggett, D.R.

1986-01-01

The development and testing of a mobile incinerator for processing of combustible dry active waste (DAW) and contaminated oil generated at Nuclear Power Plants is presented. Topics of discussion include initial thoughts on incineration as applied to nuclear waste; DOE's Aerojet's, and CECo's role in the Project; design engineering concepts; site engineering support; licensability; generation of test data; required reports of the NRC and Illinois and California EPA's; present project schedule for incinerating DAW at Dresden and other CECo Stations; and lessons learned from the project

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

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

40 CFR 63.988 - Incinerators, boilers, and process heaters.

Science.gov (United States)

2010-07-01

... 40 Protection of Environment 10 2010-07-01 2010-07-01 false Incinerators, boilers, and process... Routing to a Fuel Gas System or a Process § 63.988 Incinerators, boilers, and process heaters. (a) Equipment and operating requirements. (1) Owners or operators using incinerators, boilers, or process...

Determination of the radioactive nature of a waste. Situation and practices in various EU member states. Final report + synthesis

International Nuclear Information System (INIS)

Strasser, F.; Huclier, S.; Mokili, M.; Chardon, P.; Landesman, C.

2005-12-01

Security in waste treatment sites is apprehended in different ways in the four states of the European Union that have been compared for the purpose of this study. France and Germany are the field of two opposed situations: in France all waste treatment sites are equipped with radioactivity detection portals, whereas Germany considers that waste containing radioactive traces is managed in a specific way and cannot infiltrated normal waste flows due to extensive use of selective waste sorting. Radioactivity control for the waste management sites is no matter of discussion in Germany. The procedures to follow for waste containing radioactive traces is elaborated at the level of the Laender. In Belgium and in the Netherlands, the situations are somewhere in between these two extreme approaches. In the Wallonie Region of Belgium, a regulation in force since February 2003 requires landfills operators to equip their sites with radioactivity detector systems.. In Flanders three incinerators are equipped with detection systems on a voluntary base, in order to protect their installations and reassure the surrounding population. One of the three incinerators is involved in a pilot study meant to come up with solutions for waste site protection and prevention from radioactive contamination. In the Netherlands, a regulation from January 2003 requires scrap metal dealers to perform a control on the metal waste they collect or receive at their site. (authors)

Development of methods for treatment and conditioning of biological radioactive waste in the Czech Republic

International Nuclear Information System (INIS)

Holub, J.

1997-01-01

Incineration of biological radioactive waste was performed in a facility manufactured in the Czech Republic for combustion of burnable, radioactive and non-radioactive residues. The equipment has shown an adequate capability for combustion of biological waste. Basic technical parameters of the incinerator SP-603 can guarantee combustion of majority of wastes from different radionuclide users in the country. To ensure proper further handling with the resulting ash, three conditioning options were studied, the bituminization process, incorporation into cement, and embedding of ash into a mixture of bituminous and cementitious materials. Mechanical properties of the conditioned ash were in good compliance with those published elsewhere. Bituminized ash exhibits lowest leachibility, followed by the ash conditioned by means of the mixed process. Potential abnormal operation conditions were evaluated and their consequences assessed. The evaluation encompassed sensitivity analysis of the consequences potentially affecting the operating staff, nearby population and the environment. Cost estimate was carried out using a national approach for the calculation. From the results it can be seen that there are no large differences between the conditioning and disposal of wastes resulting from different conditioning processes. (author). 16 refs, 4 figs, 15 tabs

Development of methods for treatment and conditioning of biological radioactive waste in the Czech Republic

Energy Technology Data Exchange (ETDEWEB)

Holub, J [NYCOM, Prague (Czech Republic)

1997-02-01

Incineration of biological radioactive waste was performed in a facility manufactured in the Czech Republic for combustion of burnable, radioactive and non-radioactive residues. The equipment has shown an adequate capability for combustion of biological waste. Basic technical parameters of the incinerator SP-603 can guarantee combustion of majority of wastes from different radionuclide users in the country. To ensure proper further handling with the resulting ash, three conditioning options were studied, the bituminization process, incorporation into cement, and embedding of ash into a mixture of bituminous and cementitious materials. Mechanical properties of the conditioned ash were in good compliance with those published elsewhere. Bituminized ash exhibits lowest leachibility, followed by the ash conditioned by means of the mixed process. Potential abnormal operation conditions were evaluated and their consequences assessed. The evaluation encompassed sensitivity analysis of the consequences potentially affecting the operating staff, nearby population and the environment. Cost estimate was carried out using a national approach for the calculation. From the results it can be seen that there are no large differences between the conditioning and disposal of wastes resulting from different conditioning processes. (author). 16 refs, 4 figs, 15 tabs.

Radioactivity in sludge: tank cleaning procedures and sludge disposal

International Nuclear Information System (INIS)

Bradley, D.A.

1995-01-01

In the oil and gas industry management of alpha-active sludge is made more complex by the presence of hydrocarbons and heavy metals. This presentation discusses the origin of radioactivity in sludge, management of risk in terms of safe working procedures, storage and possible disposal options. The several options will generally involve aspects of dilution or of concentration; issues to be discussed will include sludge farming, bioremediation and incineration. (author)

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)

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.

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

International Nuclear Information System (INIS)

Beylot, Antoine; Villeneuve, Jacques

2013-01-01

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 x emissions. • E.g. climate change impact ranges from −58 to 408 kg CO 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 2 -eq to a relatively large burden of 408 kg CO 2 -eq, with 294 kg CO 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 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

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.

The 1985 United Kingdom radioactive waste inventory

International Nuclear Information System (INIS)

Fletcher, A.M.; Wear, F.J.; Haselden, H.; Shepherd, J.; Tymons, B.J.

1986-07-01

This report provides a compilation of stocks of radioactive wastes in the UK by volume, as at 1 January 1985, and estimates of future arisings to the year 2030. It includes radionuclide contents as available, together with specific activities, notional conditioning factors and disposal routes. In the main the stock volumes are given as unconditioned waste. However for clarity and precision some of the data relates to treated wastes (ie compacted wastes, incinerator ash, etc). These are clearly marked in the Tables. (author)

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

International Nuclear Information System (INIS)

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

2005-10-01

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

Incineration of alpha-active solid waste by microwaves

Energy Technology Data Exchange (ETDEWEB)

Mallik, G K; Bhargava, V K; Kamath, H S; Purushotham, D S.C. [Bhabha Atomic Research Centre, Tarapur (India). Advanced Fuel Fabrication Facility

1996-12-31

The conventional techniques for treatment of alpha-active compressible solid waste involve incineration using electrically heated incinerators and subsequent recovery of special nuclear materials (SNM) from the ash by acid leaching. A microwave incineration followed by microwave digestion and SNM recovery from ash has specific advantages from maintenance and productivity consideration. The paper describes a preliminary work carried out with simulated uranium containing compressible solid waste using microwave heating technique. (author). 3 refs., 1 tab.

10 CFR 20.2004 - Treatment or disposal by incineration.

Science.gov (United States)

2010-01-01

... 10 Energy 1 2010-01-01 2010-01-01 false Treatment or disposal by incineration. 20.2004 Section 20... § 20.2004 Treatment or disposal by incineration. (a) A licensee may treat or dispose of licensed material by incineration only: (1) As authorized by paragraph (b) of this section; or (2) If the material...

Recycling of radioactive oil sludge waste into pavement brick

International Nuclear Information System (INIS)

Meor Yusoff Meor Sulaiman; Hishamuddin Hussein; Choo Thye Foo; Nurul Wahida Ahmad Khairuddin; MAsliana MUslimin; Wilfred Sylvester Paulus

2010-01-01

Malaysia produces about 1450 tons of radioactive oil sludge waste per year and there is an urgent need to find a permanent solution to the storage and disposal of this radioactive waste problem. Several treatment methods such bacteria farming, ultracentrifuge, steam reforming and incineration are currently being used but the core issue of the radioactive material in the oil sludge had not been solved. The paper relates a study on utilizing the radioactive component of the oil sludge and turning them into pavement brick. Characteristic study of this radioactive component by XRD and XRF show that it mainly comprised of quartz and anorthite minerals. While the radioactivity analysis by gamma technique shows that more than 90 % of this radioactivity comes from this soil component with Ra-226 and Ra-228 as the main radionuclides. A vitrified brick was then produced from this sediment by mixing it with low radioactive local red clay. The result also shows that the formation of the vitrified layer may be due high content of K in the red clay. Tensile test on the brick shows that it has more than four times the strength of commercial clay brick. Long duration leaching test on the brick also shows that there is no dissolution of radionuclide from the brick. (author)

Decontamination flowsheet development for a waste oil containing mixed radioactive contaminants

International Nuclear Information System (INIS)

Vijayan, S.; Buckley, L.P.

1993-01-01

The majority of waste oils contaminated with both radioactive and hazardous components are generated in nuclear power plant, research lab. and uranium-refinery operations. The waste oils are complex, requiring a detailed examination of the waste management strategies and technology options. It may appear that incineration offers a total solution, but this may not be true in all cases. An alternative approach is to decontaminate the waste oils to very low contaminant levels, so that the treated oils can be reused, burned as fuel in boilers, or disposed of by commercial incineration. This paper presents selected experimental data and evaluation results gathered during the development of a decontamination flowsheet for a specific waste oil stores at Chalk River Labs. (CRL). The waste oil contains varying amounts of lube oils, grease, paint, water, particulates, sludge, light chloro- and fluoro-solvents, polychlorinated biphenyls (PCB), complexing chemicals, uranium, chromium, iron, arsenic and manganese. To achieve safe management of this radioactive and hazardous waste, several treatment and disposal methods were screened. Key experiments were performed at the laboratory-scale to confirm and select the most appropriate waste-management scheme based on technical, environmental and economic criteria. The waste-oil-decontamination flowsheet uses a combination of unit operations, including prefiltration, acid scrubbing, and aqueous-leachage treatment by precipitation, microfiltration, filter pressing and carbon adsorption. The decontaminated oil containing open-quotes de minimisclose quotes levels of contaminants will undergo chemical destruction of PCBs and final disposal by incineration. The recovered uranium will be recycled to a uranium milling process

Dioxins in processes of incineration of wastes

International Nuclear Information System (INIS)

Perez John; Espinel Jorge; Ocampo Alonso; Londono Carlos

2001-01-01

This paper is a door to come into the subject of dioxins, which is a little bit known in Colombia. In this way, in order to clarify and to get a wider knowledge about dioxins and waste incineration process, it has been divided in three main sections. The first one gives a basic information about origin, effects on the human health and a chemical definition of dioxins; in the second one the main kind of incinerator processes are given to know, also a deeper knowledge of reaction formation. The last part emphasizes options to control dioxins emissions in incineration systems

WILCI: a LCA tool dedicated to MSW incineration in France

OpenAIRE

Beylot , Antoine; Muller , Stéphanie; Descat , Marie; Ménard , Yannick; Michel , Pascale; Villeneuve , Jacques

2017-01-01

International audience; Life Cycle Assessment (LCA) has been increasingly used in the last decades to evaluate the global environmental performance of waste treatment options. This is in particular the case considering incineration that is the major treatment route for Municipal Solid Waste (MSW) in France (28% of French MSW are incinerated, in 126 MSW incineration plants; ADEME, 2015). In this context, this article describes a new Excel-tool, WILCI (for Waste Incineration Life Cycle Inventor...

Regional waste treatment with monolith disposal for low-level radioactive waste

International Nuclear Information System (INIS)

Forsberg, C.W.

1983-01-01

An alternative system is proposed for the disposal of low-level radioactive waste. This system, called REgional Treatment with MOnolith Disposal (RETMOD), is based on integrating three commercial technologies: automated package warehousing, whole-barrel rotary kiln incineration, and cement-based grouts for radioactive waste disposal. In the simplified flowsheet, all the sludges, liquids, resins, and combustible wastes are transported to regional facilities where they are incinerated. The ash is then mixed with special cement-based grouts, and the resulting mixture is poured into trenches to form large waste-cement monoliths. Wastes that do not require treatment, such as damaged and discarded equipment, are prepositioned in the trenches with the waste-cement mixture poured on top. The RETMOD system may provide higher safety margins by conversion of wastes into a solidified low-leach form, creation of low-surface area waste-cement monoliths, and centralization of waste processing into a few specialized facilities. Institutional problems would be simplified by placing total responsibility for safe disposal on the disposal site operator. Lower costs may be realized through reduced handling costs, the economics of scale, simplified operations, and less restrictive waste packaging requirements

Bench-scale treatability studies for simulated incinerator scrubber blowdown containing radioactive cesium and strontium

International Nuclear Information System (INIS)

Coroneos, A.C.; Taylor, P.A.; Arnold, W.D. Jr.; Bostick, D.A.; Perona, J.J.

1994-12-01

The purpose of this report is to document the results of bench-scale testing completed to remove 137 Cs and 90 Sr from the Oak Ridge K-25 Site Toxic Substances Control Act (TSCA) Incinerator blowdown at the K-25 Site Central Neutralization Facility, a wastewater treatment facility designed to remove heavy metals and uranium from various wastewaters. The report presents results of bench-scale testing using chabazite and clinoptilolite zeolites to remove cesium and strontium; using potassium cobalt ferrocyanide (KCCF) to remove cesium; and using strontium chloride coprecipitation, sodium phosphate coprecipitation, and calcium sulfate coprecipitation to remove strontium. Low-range, average-range, and high-range concentration blowdown surrogates were used to complete the bench-scale testing

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)

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...

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

CO{sub 2} laser-aided waste incineration

Energy Technology Data Exchange (ETDEWEB)

Costes, J R; Guiberteau, P [CEA Centre d` Etudes de la Vallee du Rhone, 30 - Marcoule (France). Dept. d` Exploitation du Retraitement et de Demantelement; Caminat, P; Bournot, P

1994-12-31

Lasers are widely employed in laboratories and in certain industrial applications, notably for welding, cutting and surface treatments. This paper describes a new application, incineration, which appears warranted when the following features are required: high-temperature incineration (> 1500 deg C) with close-tolerance temperature control in an oxidizing medium while ensuring containment of toxic waste. These criteria correspond to the application presented here. Following a brief theoretical introduction concerning the laser/surface interaction, the paper describes the incineration of graphite waste contaminated with alpha-emitting radionuclides. Process feasibility has been demonstrated on a nonradioactive prototype capable of incinerating 10 kg{sup -h-1} using a 7 kW CO{sub 2} laser. An industrial facility with the same capacity, designed to operate within the constraints of an alpha-tight glove box environment, is now at the project stage. Other types of applications with similar requirements may be considered. (authors). 3 refs., 7 figs.

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. 

Beta-gamma contaminated solid waste incinerator facility

International Nuclear Information System (INIS)

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 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

Radwaste incineration, is it ready for use

International Nuclear Information System (INIS)

Coplan, B.W.

1982-01-01

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

Development and testing of prototype alpha waste incinerator off-gas systems

International Nuclear Information System (INIS)

Freed, E.J.; Becker, G.W.

1982-01-01

A test program is in progress at Savannah River Laboratory (SRL) to confirm and develop incinerator design technology for an SRP production Alpha Waste Incinerator (AWI) to be built in the mid-1980's. The Incinerator Components Test Facility (ICTF) is a full-scale (5 kg/h), electrically heated, controlled-air prototype incinerator built to burn nonradioactive solid waste. The incinerator has been operating successfully at SRL since March 1979 and has met or exceeded all design criteria. During the first 1-1/2 years of operation, liquid scrubbers were used to remove particulates and hydrochloric acid from the incinerator exhaust gases. A dry off-gas system is currently being tested to provide data to Savannah River Plant's proposed AWI

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....

Incinerator technology overview

Science.gov (United States)

Santoleri, Joseph J.

1993-03-01

Many of the major chemical companies in the U.S. who regarded a safe environment as their responsibility installed waste treatment and disposal facilities on their plant sites in the last two decades. Many of these plants elected to use incinerators as the treatment process. This was not always the most economical method, but in many cases it was the only method of disposal that provided a safe and sure method of maximum destruction. Environmental concern over contamination from uncontrolled land disposal sites, and the emergence of tougher regulations for land disposal provide incentives for industry to employ a wide variety of traditional and advanced technologies for managing hazardous wastes. Incineration systems utilizing proper design, operation, and maintenance provides the safest, and in the long run, the most economical avenue to the maximum level of destruction of organic hazardous wastes.

Research and development plan for the Slagging Pyrolysis Incinerator

International Nuclear Information System (INIS)

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

1979-01-01

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

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

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

Energy Technology Data Exchange (ETDEWEB)

Herman, M; Stanculescu, A [International Atomic Energy Agency, Vienna (Austria); Paver, N [University of Trieste and INFN, Trieste (Italy)

2003-06-15

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.

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

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

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

Analysis of Discharged Gas from Incinerator using Simulated Organic Solution

International Nuclear Information System (INIS)

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

2014-01-01

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

Analysis of Discharged Gas from Incinerator using Simulated Organic Solution

Energy Technology Data Exchange (ETDEWEB)

Kim, Seungil; Kim, Hyunki; Heo, Jun; Kang, Dukwon [HaJI Co., Ltd., Radiation Eng. Center, Siheung (Korea, Republic of); Kim, Yunbok; Kwon, Youngbock [KORAD, Daejeon (Korea, Republic of)

2014-05-15

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

40 CFR 60.2885 - Does this subpart apply to my incineration unit?

Science.gov (United States)

2010-07-01

... incineration unit? 60.2885 Section 60.2885 Protection of Environment ENVIRONMENTAL PROTECTION AGENCY (CONTINUED... for Other Solid Waste Incineration Units for Which Construction is Commenced After December 9, 2004....2885 Does this subpart apply to my incineration unit? Yes, if your incineration unit meets all the...

40 CFR 60.2010 - Does this subpart apply to my incineration unit?

Science.gov (United States)

2010-07-01

... incineration unit? 60.2010 Section 60.2010 Protection of Environment ENVIRONMENTAL PROTECTION AGENCY (CONTINUED... for Commercial and Industrial Solid Waste Incineration Units for Which Construction Is Commenced After... Applicability § 60.2010 Does this subpart apply to my incineration unit? Yes, if your incineration unit meets...

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.)

Durability of incinerator ash waste encapsulated in modified sulfur cement

International Nuclear Information System (INIS)

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

1991-01-01

Waste form stability under anticipated disposal conditions is an important consideration for ensuring continued isolation of contaminants from the accessible environment. Modified sulfur cement is a relatively new material and has only recently been applied as a binder for encapsulation of mixed wastes. Little data are available concerning its long-term durability. Therefore, a series of property evaluation tests for both binder and waste-binder combinations have been conducted to examine potential waste form performance under storage and disposal conditions. These tests include compressive strength, biodegradation, radiation stability, water immersion, thermal cycling, and leaching. Waste form compressive strength increased with ash waste loadings to 30.5 MPa at a maximum incinerator ash loading of 43 wt %. Biodegradation testing resulted in no visible microbial growth of either bacteria or fungi. Initial radiation stability testing did not reveal statistically significant deterioration in structural integrity. Results of 90 day water immersion tests were dependent on the type of ash tested. There were no statistically significant changes in compressive strength detected after completion of thermal cycle testing. Radionuclides from ash waste encapsulated in modified sulfur cement leached between 5 and 8 orders of magnitude slower than the leach index criterion established by the Nuclear Regulatory Commission (NRC) for low-level radioactive waste. Modified sulfur cement waste forms containing up to 43 wt % incinerator fly ash passed EPA Toxicity Characteristic Leaching Procedure (TCLP) criteria for lead and cadmium leachability. 11 refs., 2 figs., 5 tabs

EXPERIMENTAL INVESTIGATION OF PIC FORMATION IN CFC INCINERATION

Science.gov (United States)

The report gives results of the collection of combustion emission characterization data from chlorofluorocarbon (CFC) incineration. A bench scale test program to provide emission characterization data from CFC incineration was developed and performed, with emphasis on the format...

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....

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

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

Energy Technology Data Exchange (ETDEWEB)

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.

Characterization, treatment and conditioning of radioactive graphite from decommissioning of nuclear reactors

International Nuclear Information System (INIS)

2006-09-01

Graphite has been used as a moderator and reflector of neutrons in more than 100 nuclear power plants and in many research and plutonium-production reactors. It is used primarily as a neutron reflector or neutron moderator, although graphite is also used for other features of reactor cores, such as fuel sleeves. Many of the graphite-moderated reactors are now quite old, with some already shutdown. Therefore radioactive graphite dismantling and the management of radioactive graphite waste are becoming an increasingly important issue for a number of IAEA Member States. Worldwide, there are more than 230 000 tonnes of radioactive graphite which will eventually need to be managed as radioactive waste. Proper management of radioactive graphite waste requires complex planning and the implementation of several interrelated operations. There are two basic options for graphite waste management: (1) packaging of non-conditioned graphite waste with subsequent direct disposal of the waste packages, and (2) conditioning of graphite waste (principally either by incineration or calcination) with separate disposal of any waste products produced, such as incinerator ash. In both cases, the specific properties of graphite - such as Wigner energy, graphite dust explosibility, and radioactive gases released from waste graphite - have a potential impact on the safety of radioactive graphite waste management and need to be carefully considered. Radioactive graphite waste management is not specifically addressed in IAEA publications. Only general and limited information is available in publications dealing with decommissioning of nuclear reactors. This report provides a comprehensive discussion of radioactive graphite waste characterization, handling, conditioning and disposal throughout the operating and decommissioning life cycle. The first draft report was prepared at a meeting on 23-27 February 1998. A technical meeting (TM) was held in October 1999 in coincidence with the Seminar on

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

Assessment of relative POHC destruction at EPA's incineration research facility

International Nuclear Information System (INIS)

Carroll, G.J.; Lee, J.W.

1992-01-01

As part of their permitting process, hazardous waste incinerators must undergo demonstration tests, or trial burns, during which their ability to meet EPA performance standards is evaluated. Among the performance standards is a minimum destruction and removal efficiency (DRE) for principal organic hazardous constituents (POHCs) in the incinerator waste feed. In accordance with the regulations promulgated under the Resource Conservation and Recovery Act (RCRA), selection POHCs for incinerator trial burns is to be based on the degree of difficulty of incineration of the organic constituents in the waste and on their concentration or mass in the waste feed. In order to predict the relative difficulty of incineration specific compounds, several incinerability ranking approaches have been proposed, including a system based on POHC heats of combustion and a system based on thermal stability under pyrolytic condition. The latter ranking system was developed by the University of Dayton Research Institute (UDRI) under contract to the US EPA Risk Reduction Engineering Laboratory (RREL). The system is supported largely by non-flame, laboratory-scale data and is based on kinetic calculations indicating that contributor to emissions of undestroyed organic compounds. The subject tests were conducted to develop data on POHC behavior in a larger-scale, conventional incineration environment. 5 refs., 3 tabs

Radioactive waste problems in the Kozloduy NPP

Energy Technology Data Exchange (ETDEWEB)

Videnov, N; Stanchev, V [Kombinat Atomna Energetika, Kozloduj (Bulgaria)

1996-12-31

An average volume of 1400 m{sup 3} a year of solid radioactive waste (RAW) is generated in the Kozloduy NPP. The adopted waste processing sequence is collection, sorting and compaction with a 1000 tons force providing decrease in volume by factor of 15. A temporary storage facility at the Kozloduy NPP is licensed by ISUAE and CPPUAE. The treatment of liquid wastes is performed by Westinghouse formula and a technology using an automated solidification system. Contaminated oils are burned using an oil incinerator. A special 2-year programme for RAW management is being developed.

Radioactive waste problems in the Kozloduy NPP

International Nuclear Information System (INIS)

Videnov, N.; Stanchev, V.

1995-01-01

An average volume of 1400 m 3 a year of solid radioactive waste (RAW) is generated in the Kozloduy NPP. The adopted waste processing sequence is collection, sorting and compaction with a 1000 tons force providing decrease in volume by factor of 15. A temporary storage facility at the Kozloduy NPP is licensed by ISUAE and CPPUAE. The treatment of liquid wastes is performed by Westinghouse formula and a technology using an automated solidification system. Contaminated oils are burned using an oil incinerator. A special 2-year programme for RAW management is being developed

Shredder and incinerator technology for treatment of commercial transuranic wastes

International Nuclear Information System (INIS)

Oma, K.H.; Westsik, J.H. Jr.; Ross, W.A.

1985-10-01

This report describes the selection and evaluation of process equipment to accomplish the shredding and incineration of commercial TRU wastes. The primary conclusions derived from this study are: Shredding and incineration technology appears effective for converting simulated commercial TRU wastes to a noncombustible form. The gas-heated controlled-air incinerator received the highest technical ranking. On a scale of 1 to 10, the incinerator had a Figure-of-Merit (FOM) number of 7.0. This compares to an FOM of 6.1 for the electrically heated controlled-air incinerator and an FOM of 5.8 for the rotary kiln incienrator. The present worth costs of the incineration processes for a postulated commercial reprocessing plant were lowest for the electrically heated and gas-heated controlled-air incinerators with costs of $16.3 M and $16.9 M, respectively (1985 dollars). Due to higher capital and operating costs, the rotary kiln process had a present worth cost of $20.8 M. The recommended process from the three evaluated for the commercial TRU waste application is the gas-heated controlled-air incinerator with a single stage of shredding for feed pretreatment. This process had the best cost-effectiveness ratio of 1.0 (normalized). The electrically heated controller-air incinerator had a rating of 1.2 and the rotary kiln rated a 1.5. Most of the simulated wastes were easily processed by the low-speed shredders evaluated. The HEPA filters proved difficult to process, however. Wood-framed HEPA filters tended to ride on the cutter wheels and spacers without being gripped and shredded. The metal-framed HEPA filters and other difficult to shred items caused the shredders to periodically reach the torque limit and go into an automatic reversal cycle; however, the filters were eventually processed by the units. All three incinerators were ineffective for oxidizing the aluminum metal used as spacers in HEPA filters

EXPERIMENTAL INVESTIGATION OF PIC FORMATION DURING CFC INCINERATION

Science.gov (United States)

The report gives results of experiments to assess: (1) the effect of residual copper retained in an incineration facility on polychlorinated dibenzo-p-dioxin and dibenzofuran (PCDD/PCDF) formation during incineration of non-copper-containing chlorofluorocarbons (CFCs); and (2) th...

Energy utilization: municipal waste incineration. Final report

Energy Technology Data Exchange (ETDEWEB)

LaBeck, M.F.

1981-03-27

An assessment is made of the technical and economical feasibility of converting municipal waste into useful and useable energy. The concept presented involves retrofitting an existing municipal incinerator with the systems and equipment necessary to produce process steam and electric power. The concept is economically attractive since the cost of necessary waste heat recovery equipment is usually a comparatively small percentage of the cost of the original incinerator installation. Technical data obtained from presently operating incinerators designed specifically for generating energy, documents the technical feasibility and stipulates certain design constraints. The investigation includes a cost summary; description of process and facilities; conceptual design; economic analysis; derivation of costs; itemized estimated costs; design and construction schedule; and some drawings.

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

Incineration by accelerator

International Nuclear Information System (INIS)

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

1997-01-01

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

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)

Glass ceramics for incinerator ash immobilization

Energy Technology Data Exchange (ETDEWEB)

Malinina, G.A.; Stefanovsky, O.I. [SIA Radon, 7th Rostovskii lane 2/14, Moscow 119121 (Russian Federation); Stefanovsky, S.V., E-mail: profstef@mtu-net.ru [SIA Radon, 7th Rostovskii lane 2/14, Moscow 119121 (Russian Federation)

2011-09-01

Calcined solid radioactive waste (incinerator slag) surrogate and either Na{sub 2}Si{sub 2}O{sub 5} or Na{sub 2}B{sub 4}O{sub 7} (borax) at various mass ratios were melted in silicon carbide crucibles in a resistive furnace at temperatures of up to 1775 K (slag without additives). Portions of the melts were poured onto a metal plate; the residues were slowly cooled in turned-off furnace. Both quenched and slowly cooled materials were composed of the same phases. At high slag contents in silicate-based materials nepheline and britholite were found to be major phases. Britholite formed at higher slag content (85 wt.%) became major phase in the vitrified slag. In the system with borax at low slag contents (25 and 50 wt.%) material are composed of predominant vitreous and minor calcium silicate larnite type phase Ca{sub 2}SiO{sub 4} where Ca{sup 2+} ions are replaced by different cations. The materials containing slag in amount of 75 wt.% and more are chemically durable. The changes in the structure of anionic motif of quenched samples depending on slag loading were studied by IR spectroscopy.

Glass ceramics for incinerator ash immobilization

International Nuclear Information System (INIS)

Malinina, G.A.; Stefanovsky, O.I.; Stefanovsky, S.V.

2011-01-01

Calcined solid radioactive waste (incinerator slag) surrogate and either Na 2 Si 2 O 5 or Na 2 B 4 O 7 (borax) at various mass ratios were melted in silicon carbide crucibles in a resistive furnace at temperatures of up to 1775 K (slag without additives). Portions of the melts were poured onto a metal plate; the residues were slowly cooled in turned-off furnace. Both quenched and slowly cooled materials were composed of the same phases. At high slag contents in silicate-based materials nepheline and britholite were found to be major phases. Britholite formed at higher slag content (85 wt.%) became major phase in the vitrified slag. In the system with borax at low slag contents (25 and 50 wt.%) material are composed of predominant vitreous and minor calcium silicate larnite type phase Ca 2 SiO 4 where Ca 2+ ions are replaced by different cations. The materials containing slag in amount of 75 wt.% and more are chemically durable. The changes in the structure of anionic motif of quenched samples depending on slag loading were studied by IR spectroscopy.

Processing method and device for radioactive waste containing surfactant

International Nuclear Information System (INIS)

Yukita, Atsushi; Yoshikawa, Ryozo; Izumida, Tatsuo; Nishi, Takashi; Hattori, Yasuo.

1997-01-01

Washing liquid wastes generated in washing facilities in a nuclear power plant are collected in a liquid waste collecting tank. A suspension containing a powdery active carbon is supplied to the liquid waste collecting tank. Organic ingredients such as of a surfactant, oil ingredients and radioactive materials in the form of ions contained in the washing liquid wastes are adsorbed to the powdery active carbon. The washing liquid wastes containing the powdery active carbon and granular radioactive materials are led into an active carbon separating and drying device. The powdery active carbon and granular radioactive materials contained in the washing liquid wastes are filtered and separated by a filtering plate, and accumulated as filtered materials on the surface of the filtering plate. The purified washing liquid wastes are discharged to the outside. The filtered materials are dried by hot steams (or hot water) and dried air. The filtered materials are peeled from the filtering plate. The filtered materials, in other word, dried powdery active carbon and granular radioactive materials are transported to and burnt in an incinerator. (I.N.)

Elemental composition of suspended particles released in refuse incineration

International Nuclear Information System (INIS)

Mamuro, Tetsuo; Mizohata, Akira

1979-01-01

Suspended particles released in refuse incineration were subjected to multielement analysis by means of instrumental neutron activation method and energy dispersive X-ray fluorescence spectrometry. The analytical results were compared with the elemental concentrations observed in the urban atmosphere, and the contribution of the refuse incineration to the urban atmosphere was roughly estimated. Greenberg et al. pointed out on the basis of their analyses that the refuse incineration can account for major portions of the Zn, Cd and Sb observed on urban aerosols. According to our results, the contribution of the refuse incineration for Zn, Cd and Sb is not negligible, but not so serious as in U.S.A. big cities. In Japan big cities there must be other more important sources of these elements. (author)

EXPERIENCE IN INCINERATION APPLICABLE TO SUPERFUND SITE REMEDIATION

Science.gov (United States)

This document can be used as a reference tool for hazardous waste site remediation where incineration is used as a treatment alternative. It provides the user with information garnered from the experiences of others who use incineration. The document presents useful lessons in ev...

[Effects of chlorides on Cd transformation in a simulated grate incinerator during sludge incineration process ].

Science.gov (United States)

Liu, Jing-yong; Zhuo, Zhong-xu; Sun, Shui-yu; Luo, Guang-qian; Li, Xiao-ming; Xie, Wu-ming; Wang, Yu- jie; Yang, Zuo-yi; Zhao, Su-ying

2014-09-01

The effects of organic chloride-PVC and inorganic chloride-NaCl on Cd partitioning during sludge incineration with adding Cd(CH3COO)2 . 2H2O to the real sludge were investigated using a simulated tubular incineration furnace. And transformation and distribution of Cd were studied in different sludge incineration operation conditions. The results indicated that the partitioning of Cd tended to be enhanced in the fly ash and fule gas as the chloride content increasing. The migration and transformation of Cd-added sludge affected by different chloride were not obvious with the increasing of chloride content. With increasing temperature, organic chloride (PVC) and inorganic chloride (NaC1) can reduce the Cd distribution in the bottom ash. However, the effect of chlorides, the initial concentration and incineration time on Cd emissions had no significant differences. Using SEM-EDS and XRD technique, different Cd compounds including CdCl2, Na2CdCl4, K2CdCl6, K2CdSiO4 and NaCdO2 were formed in the bottom ash and fly ash after adding NaCl to the sludge. In contrast, after adding PVC to the sludge, the Na2CdCl4 and CdCl2 were the main forms of Cd compounds, at the same time, K4CdCI6 and K6CdO4 were also formed. The two different mechanisms of chlorides effects on Cd partitioning were affected by the products of Cd compound types and forms.

Operating experience and data on revolving type fluidized bed incineration plants

International Nuclear Information System (INIS)

Nakayama, J.

1990-01-01

In refuse incinerators operating by revolving fluidization (Revolving Type Fluidized Bed Incinerator) a broad range of wastes, from low caloric refuse of high moisture content to high caloric value material including a wide variety of plastics, can be incinerated at high efficiency because the unit is outstanding in terms of distribution of waste in the incinerator bed and uniformity of heat. In addition, its vigorous revolving fluidization action is very effective in pulverizing refuse, so even relatively strict emission standards can be met without fine pre-shredding. Residues are discharged in a clean, dry form free of putrescible material. Data on practical operation of the revolving fluidized bed incinerator are presented in this paper

Small-scale medical waste incinerators - experiences and trials in South Africa

International Nuclear Information System (INIS)

Rogers, David E.C.; Brent, Alan C.

2006-01-01

Formal waste management services are not accessible for the majority of primary healthcare clinics on the African continent, and affordable and practicable technology solutions are required in the developing country context. In response, a protocol was established for the first quantitative and qualitative evaluation of relatively low cost small-scale incinerators for use at rural primary healthcare clinics. The protocol comprised the first phase of four, which defined the comprehensive trials of three incineration units. The trials showed that all of the units could be used to render medical waste non-infectious, and to destroy syringes or render needles unsuitable for reuse. Emission loads from the incinerators are higher than large-scale commercial incinerators, but a panel of experts considered the incinerators to be more acceptable compared to the other waste treatment and disposal options available in under-serviced rural areas. However, the incinerators must be used within a safe waste management programme that provides the necessary resources in the form of collection containers, maintenance support, acceptable energy sources, and understandable operational instructions for the incinerators, whilst minimising the exposure risks to emissions through the correct placement of the units in relation to the clinic and the surrounding communities. On-going training and awareness building are essential in order to ensure that the incinerators are correctly used as a sustainable waste treatment option

40 CFR 270.62 - Hazardous waste incinerator permits.

Science.gov (United States)

2010-07-01

... WASTES (CONTINUED) EPA ADMINISTERED PERMIT PROGRAMS: THE HAZARDOUS WASTE PERMIT PROGRAM Special Forms of Permits § 270.62 Hazardous waste incinerator permits. When an owner or operator of a hazardous waste... 40 Protection of Environment 26 2010-07-01 2010-07-01 false Hazardous waste incinerator permits...

Environmental assessment of incinerator residue utilisation

OpenAIRE

Toller, Susanna; Kärrman, Erik; Gustafsson, Jon Petter; Magnusson, Y.

2009-01-01

Incineration ashes may be treated either as a waste to be dumped in landfill, or as a resource that is suit able for re-use. In order to choose the best management scenario, knowledge is needed on the potential environmental impact that may be expected, including not only local, but also regional and global impact. In this study. A life cycle assessment (LCA) based approach Was Outlined for environmental assessment of incinerator residue utilisation, in which leaching of trace elements as wel...

Operation of chemical incinerator for disposal of legacy chemicals

International Nuclear Information System (INIS)

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

2017-01-01

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

Municipal waste processing: Technical/economic comparison of composting and incineration options

International Nuclear Information System (INIS)

Bertanza, G.

1993-01-01

The first part of this paper which assessed the state-of-the-art of municipal waste composting and incineration technologies indicated that the advanced level of available technologies in this field now allows the realization of reliable and safe plants. This second part of the paper deals with the economics of the composting and incineration options. Cost benefit analyses using the discounted cash flow method are made for waste processing plants featuring composting alone, incineration only and mixed composting and incineration. The economic analyses show that plants employing conventional composting techniques work well for the case of exclusively organic waste materials. Incineration schemes are shown to be economically effective when they incorporate suitable energy recovery systems. The integrated composting-incineration waste processing plant appears to be the least attractive option in terms of economics. Current R ampersand D activities in this field are being directed towards the development of systems with lower environmental impacts and capital and operating costs

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.

Effects of a chemical weapons incineration plant on red-tailed tropicbirds

Science.gov (United States)

Schreiber, E.A.; Doherty, P.F.; Schenk, G.A.

2001-01-01

From 1990 to 2000, the Johnston Atoll Chemical Agent Disposal System (JACADS) incinerated part of the U.S. stockpile of chemical weapons on Johnston Atoll, central Pacific Ocean, which also is a National Wildlife Refuge and home to approximately a half-million breeding seabirds. The effect on wildlife of incineration of these weapons is unknown. Using a multi-strata mark-recapture analysis, we investigated the effects of JACADS on reproductive success, survival, and movement probabilities of red-tailed tropicbirds (Phaethon rubricauda) nesting both downwind and upwind of the incineration site. We found no effect of chemical incineration on these tropicbird demographic parameters over the 8 years of our study. An additional 3 years of monitoring tropicbird demography will take place, post-incineration.

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...

Exploitation of the FLK-60 slagging incinerator for different alpha waste streams and study of the feasibility of medium-level alpha-beta-gamma waste incineration in FLK-60

International Nuclear Information System (INIS)

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

1985-01-01

The FLK-60 high temperature slagging incinerator and its peripherals were developed by SCK/CEN with the help of the Commission of the European Communities in the framework of contract no. EUR-017-76-7 WAS-B. This second contract, which covered the period between October 1980 and December 1982, aimed at gaining exploitation experience by running the FLK-60 installation with beta-gamma radioactive waste in semi-industrial conditions. At the end of those 27 months, the system was ready for exploitation in alpha-conditions with plutonium-containing materials. This report describes the various plant parameters during the 25 runs carried out in the framework of this contract and the results of characterization tests carried out on the final product and the secondary waste streams. In the meantime, typical operation balances are computed

A solution to level 3 dismantling of gas-cooled reactors: Graphite incineration

International Nuclear Information System (INIS)

Dubourg, M.

1993-01-01

This paper presents an approach developed to solve the specific decommissioning problems of the G2 and G3 gas cooled reactors at Marcoule and the strategy applied with emphasis in incinerating the graphite core components, using a fluidized-bed incinerator developed jointly between the CEA and FRAMATOME. The incineration option was selected over subsurface storage for technical and economic reasons. Studies have shown that gaseous incineration releases are environmentally acceptable

Radioactive contamination in the Tokyo metropolitan area in the early stage of the Fukushima Daiichi Nuclear Power Plant (FDNPP accident and its fluctuation over five years.

Directory of Open Access Journals (Sweden)

Masanobu Ishida

Full Text Available Radioactive contamination in the Tokyo metropolitan area in the immediate aftermath of the Fukushima Daiichi Nuclear Power Plant (FDNPP accident was analyzed via surface soil sampled during a two-month period after the accident. 131I, 134Cs, and 137Cs were detected in these soil samples. The activity and inventory of radioactive material in the eastern part of Tokyo tended to be high. The 134Cs/137Cs activity ratio in soil was 0.978 ± 0.053. The 131I/137Cs ratio fluctuated widely, and was 19.7 ± 9.0 (weighted average 18.71 ± 0.13, n = 14 in the Tokyo metropolitan area. The radioactive plume with high 131I activity spread into the Tokyo metropolitan area and was higher than the weighted average of 6.07 ± 0.04 (n = 26 in other areas. The radiocesium activity and inventory surveyed in soil from a garden in Chiyoda Ward in the center of Tokyo, fell approximately 85% in the four months after the accident, and subsequently tended to rise slightly while fluctuating widely. It is possible that migration and redistribution of radiocesium occurred. The behavior of radiocesium in Tokyo was analyzed via monitoring of radiocesium in sludge incineration ash. The radiocesium activity in the incineration ash was high at wastewater treatment centers that had catchment areas in eastern Tokyo and low at those with catchment areas in western Tokyo. Similar to the case of the garden soil, even in incineration ash, the radiocesium activity dropped rapidly immediately after the accident. The radiocesium activity in the incineration ash fell steadily from the tenth month after the accident until December 2016, and its half-life was about 500 days. According to frequency analysis, in central Tokyo, the cycles of fluctuation of radiocesium activity in incineration ash and rainfall conformed, clearly showing that radiocesium deposited in urban areas was resuspended and transported by rainfall run-off.

Pilot-scale incineration testing of an oxygen-enhanced combustion system

International Nuclear Information System (INIS)

Waterland, L.R.; Lee, J.W.; Staley, L.J.

1989-01-01

This paper discusses a series of demonstration tests of the American Combustion, Inc., Thermal Destruction System performed under the Superfund innovative technology evaluation (SITE) program. This oxygen-enhanced combustion system was retrofit to the pilot-scale rotary kiln incinerator at EPA's Combustion Research Facility. This system's performance was tested firing contaminated soil from the Stringfellow Superfund Site, both alone and mixed with a hazardous coal tar waste (decanter tank tar sludge form coking operations - K087). Comparative performance with conventional incinerator operation was tested. Test results show that compliance with the hazardous waste incinerator performance standards of 99.99 percent principal organic hazardous constituent (POHC) destruction and removal efficiency (DRE) and particulate emissions of less than 180 mg/dscm at 7 percent O 2 was achieved for all tests. The Pyretron oxygen-enhanced combustion system allowed in-compliance operation at double the mixed waste feedrate possible with conventional incineration, and with a 60 percent increase in charge weight than possible with conventional incineration

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

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

Hazardous waste incinerator permitting in Texas from inception to operation

International Nuclear Information System (INIS)

Simms, M.D.; McDonnell, R.G. III

1991-01-01

The regulatory permitting process for hazardous waste incinerators i a long and arduous proposition requiring a well-developed overall strategy. In Texas, RCRA permits for the operation of hazardous waste incinerator facilities are issued through the federally delegated Texas Water Commission (TWC). While the TWC has primacy in the issuance of RCRA permits for hazardous waste incinerators, the Texas Air Control Board (TACB) provides a significant portion of the Part B application review and provides much of the permit language. In addition to dealing with regulatory agencies, RCRA permitting provides by significant public involvement. Often the lack of public support becomes a major roadblock for an incinerator project. In order to establish an effective strategy which addresses the concerns of regulatory agencies and the public, it is important to have an understanding of the steps involved in obtaining a permit. A permit applicant seeking to construct a new hazardous waste incinerator can expect to go through a preapplication meeting with government regulators, a site selection process, file an application, respond to calls for additional technical information from both the TACB and the TWC, defend the application in a hearing, have a recommendation from a TWC hearing examiner and, finally, receive a determination from the TWC's Commissioners. Presuming a favorable response from the Commission, the permittee will be granted a trial burn permit and may proceed with the construction, certification and execution of a trial burn at the facility. Subsequent to publication of the trial burn results and approval by the TWC, the permittee will possess an operational hazardous waste incinerator permit. The paper describes the major steps required to receive an operational permit for a hazardous waste incinerator in the State of Texas. Important issues involved in each step will be discussed including insights gained from recent incinerator permitting efforts

TRU waste cyclone drum incinerator and treatment system: January--March 1978

International Nuclear Information System (INIS)

Klingler, L.M.; Batchelder, D.M.; Lewis, E.L.

1978-01-01

The cyclone incinerator was operated throughout the past quarter, generating additional data on system characteristics, equipment life expectancies, and by-product generation. Several changes in the incinerator system are in various stages of completion. The lid assembly, secondary chamber, and expansion unit for the new exhaust equipment are nearly ready for installation. A new heat exchanger has been installed in the scrubber system. An ash handling system has been designed for possible future addition to the system. Continuing studies will determine the best delivery mechanism for continuously feeding the cyclone incinerator. Preliminary investigations are being conducted to select an independent system to treat incinerator scrubber solution for recycling and to remove salts and sludge for disposal. Metal samples of two possible materials for incinerator construction were examined for corrosion degradation suffered at the incinerator exhaust outlet. Controlled experiments were conducted on the pressed ash-cement pellet matrix to define compressive strength, mechanical stability, density, and effect of curing environment (wet cure and dry cure). Leachability studies were initiated on pressed sludge/cement matrix in distilled water at ambient temperature. Compressive strengths of sludge/cement pressed matrix samples were investigated. Physical and chemical attributes of incinerated ash were evaluated in relationship to the ash/cement matrix

Elution behavior of heavy metals from cement solidified products of incinerated ash waste - 59102

International Nuclear Information System (INIS)

Meguro, Yoshihiro; Kawato, Yoshimi; Nakayama, Takuya; Tomioka, Osamu; Mitsuda, Motoyuki

2012-01-01

A method, in which incinerated ash is solidified with a cement material, has been developed to dispose radioactive incinerated ash waste. In order to bury the solidified product, it is required that elution of hazardous heavy metals included in the ash from the solidified products is inhibited. In this study, the elution behavior of the heavy metals from the synthetic solidified products, which included Pb(II), Cd(II), and Cr(VI) and were prepared using ordinary portland cement (OPC), blast furnace slag cement (BFS), or a cement material that showed low alkalinity (LA-Cement), was investigated. Several chemicals and materials were added as additive agents to prevent the elution of the heavy metals. When OPC was used, Cd elution was inhibited, but Pb and Cr were not enough even using the additive agent examined. FeSO 4 and Na 2 S additive agents worked effective to inhibit elution of Cr. When BFS was used, the elution of Pb, Cd and Cr was inhibited for the all products prepared. In the case of LA-Cement, the elution of Pb and Cd was inhibited for the all products, but only the product that was added FeSO 4 showed good result of the elution of Cr. (authors)

Environmental assessment of waste incineration in a life-cycle-perspective (EASEWASTE)

DEFF Research Database (Denmark)

Riber, Christian; Bhander, Gurbakhash Singh; Christensen, Thomas Højlund

2008-01-01

of the wet waste incinerated. Emissions are either process-specific (related to the amount of waste incinerated) or input-specific (related to the composition of the waste incinerated), while mass transfer to solid outputs are governed by transfer coefficients specified by the user. The waste input......A model for life-cycle assessment of waste incinerators is described and applied to a case study for illustrative purposes. As life-cycle thinking becomes more integrated into waste management, quantitative tools for assessing waste management technologies are needed. The presented model...... in identifying the various processes and substances that contributed to environmental loadings as well as to environmental savings. The model was instrumental in demonstrating the importance of the energy recovery system not only for electricity but also heat from the incinerator....

Fundamental characteristics of input waste of small MSW incinerators in Korea.

Science.gov (United States)

Choi, Ki-In; Lee, Suk-Hui; Lee, Dong-Hoon; Osako, Masahiro

2008-11-01

Waste incineration in a small incinerator is a simple and convenient way of treating waste discharged from small areas or from large facilities and buildings such as business centers, marketplaces, factories, and military units. Despite their ostensible advantages, however, many small incinerators frequently suffer from serious problems, e.g., unsystematic waste feeding, unstable combustion, deficient air pollution control devices, and consequently, environmental pollution. To obtain a better understanding of the characterization of wastes in small incinerators, we investigated a series of fundamental characteristics, i.e., physical composition, bulk density, proximate and ultimate analysis, potential energy content, and so on. The main waste components in small incinerators were identified as paper and plastic; the proportion of food waste was less than that in large incinerators. Especially, a low ratio of food waste had a strong influence on other waste characteristics, e.g., lower moisture content and bulk density, and higher potential energy. On the other hand, in contrast with that of HCl, there was no distinguishable linear relationship between Cl content in waste and PCDD/DF concentration in combustion gas.

Refuse derived fuel incineration: Fuel gas monitoring and analysis

International Nuclear Information System (INIS)

Ranaldi, E.; Coronidi, M.; De Stefanis, P.; Di Palo, C.; Zagaroli, M.

1993-11-01

Experience and results on refuse derived fuel (selected from municipal solid wastes) incineration are reported. The study involved the investigation of inorganic compounds (heavy metals, acids and toxic gases) emissions, and included feeding materials and incineration residues characterization and mass balance

Incineration of hazardous waste: A critical review update

International Nuclear Information System (INIS)

Dempsey, C.R.; Oppelt, E.T.

1993-01-01

Over the last 15 years, concern over improper disposal practices of the past has manifested itself in the passage of a series of federal and state-level hazardous waste cleanup and control statutes of unprecedented scope. The more traditional and lowest-cost methods of direct landfilling, storage in surface impoundments and deep-well injection are being replaced in large measure by waste minimization at the source of generation, waste reuse, physical/chemical/biological treatment, incineration and chemical stabilization/solidification methods. Of all of the 'permanent' treatment technologies, properly designed incineration systems are capable of the highest overall degree of destruction and control for the broadest range of hazardous waste streams. Substantial design and operation experience exists in this area and a wide variety of commercial systems are available. Consequently, significant growth is anticipated in the use of incineration and other thermal destruction methods. The objective of this review is to examine the current state of knowledge regarding hazardous waste incineration in an effort to put these technological and environmental issues into perspective

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

The use of oxygen in hazardous waste incineration

International Nuclear Information System (INIS)

Ho, M.D.; Ding, M.G.

1989-01-01

The use of advanced oxygen combustion technologies in hazardous waste (such as PCBs and hydrocarbons) incineration has emerged in the last two years as one of the most significant breakthroughs among all the competing treatment technologies. For many years, industrial furnaces have used oxygen enrichment of the combustion air and oxygen-fuel burners, but with conventional technologies a high oxygen level generally poses problems. The flame temperature is high, leading to high NOx formation and local overeating. Different technical approaches to overcome these problems and their respective effectiveness will be reviewed. Previously, commercial oxygen enrichment in incinerators was limited to a rather modest level applications of much higher oxygen enrichment levels in hazardous waste incinerators

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

Quantification of the resource recovery potential of municipal solid waste incineration bottom ashes

DEFF Research Database (Denmark)

Allegrini, Elisa; Maresca, Alberto; Olsson, Mikael Emil

2014-01-01

Municipal solid waste incineration (MSWI) plays an important role in many European waste management systems. However, increasing focus on resource criticality has raised concern regarding the possible loss of critical resources through MSWI. The primary form of solid output from waste incinerators....... The lack of REE enrichment in BAs indicated that the post-incineration recovery of these resources may not be a likely option with current technology. Based on these results, it is recommended to focus on limiting REE-containing products in waste for incineration and improving pre-incineration sorting...

Environmental assessment of waste incineration in a life-cycle-perspective (EASEWASTE).

Science.gov (United States)

Riber, Christian; Bhander, Gurbakhash S; Christensen, Thomas H

2008-02-01

A model for life-cycle assessment of waste incinerators is described and applied to a case study for illustrative purposes. As life-cycle thinking becomes more integrated into waste management, quantitative tools for assessing waste management technologies are needed. The presented model is a module in the life-cycle assessment model EASEWASTE. The module accounts for all uses of materials and energy and credits the incinerator for electricity and heat recovered. The energy recovered is defined by the user as a percentage of the energy produced, calculated on the lower heating value of the wet waste incinerated. Emissions are either process-specific (related to the amount of waste incinerated) or input-specific (related to the composition of the waste incinerated), while mass transfer to solid outputs are governed by transfer coefficients specified by the user. The waste input is defined by 48 material fractions and their chemical composition. The model was used to quantify the environmental performance of the incineration plant in Aarhus, Denmark before and after its upgrading in terms of improved flue gas cleaning and energy recovery. It demonstrated its usefulness in identifying the various processes and substances that contributed to environmental loadings as well as to environmental savings. The model was instrumental in demonstrating the importance of the energy recovery system not only for electricity but also heat from the incinerator.

WIS decontamination factor demonstration test with radioactive nuclides

International Nuclear Information System (INIS)

Kanbe, Hiromi; Mayuzumi, Masami; Ono, Tetsuo; Nagae, Madoka; Sekiguchi, Ryosaku; Takaoku, Yoshinobu.

1987-01-01

A radioactive Waste Incineration System (WIS) with suspension combustion is noticed as effective volume reduction technology of low level radiactive wastes that are increasing every year. In order to demonstrate the decontamination efficiency of ceramic filter used on WIS, this test has been carried out with the test facilities as joint research of Central Research Institute of Electric Power Industry (CRIEPI) and Sumitomo Heavy Industries, Ltd. Miscellaneous combustible waste and power resin, to which 5 nuclides (Mn-54, Fe-59, Co-60, Zn-65, Cs-137) were added, were used as samples for incineration. As the result of the test, it was verified that Decontamination Factor (DF) of the single stage ceramic filter was usually kept over 10 5 for every nuclide, and from the results of above DF, over 10 8 is expected for real commercial plant as a total system. Therefore, it is realized that the off-gas clean up system of the WIS composed of only single stage of ceramic filter is capable of sufficiently efficient decontamination of exhaust gas to be released to stack. (author)

Incineration process for plutonium-contaminated waste

International Nuclear Information System (INIS)

Vincent, J.J.; Longuet, T.; Cartier, R.; Chaudon, L.

1992-01-01

A reprocessing plant with an annual throughput of 1600 metric tons of fuel generates 50 m 3 of incinerable α-contaminated waste. The reference treatment currently adopted for these wastes is to embed them in cement grout, with a resulting conditioned waste volume of 260 m 3 . The expense of mandatory geological disposal of such volumes justifies examination of less costly alternative solutions. After several years of laboratory and inactive pilot-scale research and development, the Commissariat a l'Energie Atomique has developed a two-step incineration process that is particularly suitable for α-contaminated chlorinated plastic waste. A 4 kg-h -1 pilot unit installed at the Marcoule Nuclear Center has now logged over 3500 hours in operation, during which the operating parameters have been optimized and process performance characteristics have been determined. Laboratory research during the same period has also determined the volatility of transuranic nuclides (U, Am and Pu) under simulated incineration conditions. A 100 g-h -1 laboratory prototype has been set up to obtain data for designing the industrial pilot facility

Nanomaterial disposal by incineration

Science.gov (United States)

As nanotechnology-based products enter into widespread use, nanomaterials will end up in disposal waste streams that are ultimately discharged to the environment. One possible end-of-life scenario is incineration. This review attempts to ascertain the potential pathways by which ...

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...

Heat Recovery From Tail Gas Incineration To Generate Power

Energy Technology Data Exchange (ETDEWEB)

Tawfik, Tarek

2010-09-15

Many industrial processes result in tail gas wastes that must be flared or incinerated to abide with environmental guidelines. Tail gas incineration occurs in several chemical processes resulting in high-temperature exhaust gas that simply go to the stack, thus wasting all that valuable heat! This paper discusses useful heat recovery and electric power generation utilizing available heat in exhaust gas from tail gas incinerators. This heat will be recovered in a waste-heat recovery boiler that will produce superheated steam to expand in a steam turbine to generate power. A detailed cost estimate is presented.

Life cycle assessment of sewage sludge co-incineration in a coal-based power station.

Science.gov (United States)

Hong, Jingmin; Xu, Changqing; Hong, Jinglan; Tan, Xianfeng; Chen, Wei

2013-09-01

A life cycle assessment was conducted to evaluate the environmental and economic effects of sewage sludge co-incineration in a coal-fired power plant. The general approach employed by a coal-fired power plant was also assessed as control. Sewage sludge co-incineration technology causes greater environmental burden than does coal-based energy production technology because of the additional electricity consumption and wastewater treatment required for the pretreatment of sewage sludge, direct emissions from sludge incineration, and incinerated ash disposal processes. However, sewage sludge co-incineration presents higher economic benefits because of electricity subsidies and the income generating potential of sludge. Environmental assessment results indicate that sewage sludge co-incineration is unsuitable for mitigating the increasing pressure brought on by sewage sludge pollution. Reducing the overall environmental effect of sludge co-incineration power stations necessitates increasing net coal consumption efficiency, incinerated ash reuse rate, dedust system efficiency, and sludge water content rate. Copyright © 2013 Elsevier Ltd. All rights reserved.

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

Review of organic nitrile incineration at the Toxic Substances Control Act Incinerator

International Nuclear Information System (INIS)

1997-10-01

Lockheed Martin Energy Systems, Inc. (LMES) operates the East Tennessee Technology Park (ETTP), formerly called the Oak Ridge K-25 Site, where uranium was enriched under contract with the US Department of Energy (DOE). Currently, ETTP missions include environmental management, waste management (WM), and the development of new technologies. As part of its WM mission, ETTP operates the TSCA (Toxic Substances Control Act) Incinerator (TSCAI) for treatment of hazardous waste and polychlorinated biphenyls (PCBs) contaminated with low-level radioactivity. Beginning in the autumn of 1995, employees from diverse ETTP buildings and departments reported experiencing headaches, fatigue, depression, muscle aches, sleeplessness, and muscle tremors. These symptoms were judged by a physician in the ETTP Health Services Department to be consistent with chronic exposures to hydrogen cyanide (HCN). The National Institute for Occupational Safety and Health (NIOSH) was called in to perform a health hazard evaluation to ascertain whether the employees' illnesses were in fact caused by occupational exposure to HCN. The NIOSH evaluation found no patterns for employees' reported symptoms with respect to work location or department. NIOSH also conducted a comprehensive air sampling study, which did not detect airborne cyanides at the ETTP. Employees, however, expressed concerns that the burning of nitrile-bearing wastes at the TSCAI might have produced HCN as a combustion product. Therefore, LMES and DOE established a multidisciplinary team (TSCAI Technical Review Team) to make a more detailed review of the possibility that combustion of nitrile-bearing wastes at the TSCAI might have either released nitriles or created HCN as a product of incomplete combustion (PIC)

Alkali activation processes for incinerator residues management.

Science.gov (United States)

Lancellotti, Isabella; Ponzoni, Chiara; Barbieri, Luisa; Leonelli, Cristina

2013-08-01

Incinerator bottom ash (BA) is produced in large amount worldwide and in Italy, where 5.1 millionstons of municipal solid residues have been incinerated in 2010, corresponding to 1.2-1.5 millionstons of produced bottom ash. This residue has been used in the present study for producing dense geopolymers containing high percentage (50-70 wt%) of ash. The amount of potentially reactive aluminosilicate fraction in the ash has been determined by means of test in NaOH. The final properties of geopolymers prepared with or without taking into account this reactive fraction have been compared. The results showed that due to the presence of both amorphous and crystalline fractions with a different degree of reactivity, the incinerator BA geopolymers exhibit significant differences in terms of Si/Al ratio and microstructure when reactive fraction is considered. Copyright © 2013 Elsevier Ltd. All rights reserved.

Economic sensitivity of DAW incineration to PVC content

International Nuclear Information System (INIS)

Rossmassler, R.L.

1986-01-01

Economic analyses of the volume reduction of low level radwaste, including the incinerator of Dry Active Waste (DAW), spent resins and filter sludges, are performed using the microcomputer code VOLREDUCER. Based on BWR and PWR data taken from previous EPRI work, the sensitivity of incinerator economics to polyvinyl chloride (PVC) content in DAW is examined. An annual cost penalty associated with the presence of PVC in the waste is formulated, and the sensitivity of this penalty to a variety of parameters is determined. The alternative of sorting out PVC from the rest of the waste is compared to incineration with regard to this annual cost penalty. These penalties may range as high as $100,000 annually depending on the waste characteristics and percent of PVC

Review of biosolids management options and co-incineration of a biosolid-derived fuel.

Science.gov (United States)

Roy, Murari Mohon; Dutta, Animesh; Corscadden, Kenny; Havard, Peter; Dickie, Lucas

2011-11-01

This paper reviews current biosolids management options, and identifies incineration as a promising technology. Incineration is attractive both for volume reduction and energy recovery. Reported emissions from the incineration of biosolids were compared to various regulations to identify the challenges and future direction of biosolids incineration research. Most of the gaseous and metal emissions were lower than existing regulations, or could be met by existing technologies. This paper also presents the results of an experimental study to investigate the potential use of biosolids for co-incineration with wood pellets in a conventional wood pellet stove. Pilot scale combustion tests revealed that co-incineration of 10% biosolids with 90% premium grade wood pellets resulted in successful combustion without any significant degradation of efficiency and emissions. Copyright © 2011 Elsevier Ltd. All rights reserved.

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

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)

Incineration ash conditioning processes

International Nuclear Information System (INIS)

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

1990-01-01

Incinerable wastes consist of the following standard composition corresponding to projected wastes from a future mixed oxide fuel fabrication plant with an annual throughput of 1700 kg (i.e. 5.7 m 3 ) of ashes produced by the incineration facility: . 50% polyvinyl chloride (glove box sleeves), . 5% polyethylene (bags), . 35% rubber (equal amounts of latex and neoprene), . 10% cellulose (equal amounts of cotton and cleansing tissues). The work focused mainly on compaction by high-temperature isostatic pressing, is described in some detail with the results obtained. An engineering study was also carried out to compare this technology with two other ash containment processes: direct-induction (cold crucible) melting and cement-resin matrix embedding. Induction melting is considerably less costly than isostatic pressing; the operating costs are about 1.5 times higher than for cement-resin embedding, but the volume reduction is nearly 3 times greater

Clearance of radioactive materials during reactor dismantling. Permanent enclosure instead of demolition and renaturation?

International Nuclear Information System (INIS)

2016-01-01

During reactor dismantling besides high-level radioactive wastes a large amount of low-level contaminated steel and concrete has to be disposed. In case that radioactivity falls below defined dose limits (10 micro Sv/person and year) these materials may be disposed in domestic waste landfill or in municipal incineration facilities. The issue is discussed in detail including the fact that many power plants are dismantled at the same time so that the contaminated materials might accumulate. Another issue is the occupational safety of contract workers during dismantling. The permanent enclosure could avoid this environmental contamination of decommissioned power plants might also be less expensive.

New treatment centers for radioactive waste from Russian designed VVER-reactors

International Nuclear Information System (INIS)

Chrubasik, A.

1997-01-01

The nuclear power plants using Russian designed VVER-type reactors, were engineered and designed without any wastes treatment facilities. The liquid and solid waste were collected in storage tanks and shelters. After many years of operation, the storage capabilities are exhausted. The treatment of the stored and still generated waste represents a problem of reactor safety and requires a short term solution. NUKEM has been commissioned to design and construct several new treatment centers to remove and process the stored waste. This paper describes the process and lessons learned on the development of this system. The new radioactive waste treatment center (RWTC) includes comprehensive systems to treat both liquid and solid wastes. The process includes: 1) treatment of evaporator concentrates, 2) treatment of ion exchange resins, 3) treatment of solid burnable waste, 4) treatment of liquid burnable waste, 5) treatment of solid decontaminable waste, 6) treatment of solid compactible waste. To treat these waste streams, various separate systems and facilities are needed. Six major facilities are constructed including: 1. A sorting facility with systems for waste segregation. 2. A high-force compactor facility for volume reduction of non-burnable waste. 3. An incinerator facility for destruction of: 1) solid burnable waste, 2) liquid burnable waste, 3) low level radioactive ion exchange resins. 4. A facility for melting of incineration residue. 5. A cementation facility for stabilization of: 1) medium level radioactive ion exchange resins, 2) solid non compactible waste, 3) compacted solid waste. 6. Separation of radionuclides from evaporator concentrates. This presentation will address the facilities, systems, and lessons learned in the development of the new treatment centers. (author)

Greenlandic Waste Incineration Fly And Bottom Ash As Secondary Resource In Mortar

DEFF Research Database (Denmark)

Kirkelund, Gunvor Marie; Ottosen, Lisbeth M.; Jensen, Pernille Erland

2016-01-01

Today, 900 tons incineration fly ash is shipped abroad annually from Greenland for deposits, whereas the 6,000 tons incineration bottom ash is deposited locally. These incineration ashes could be valuable in concrete production, where the cement has to be shipped to Greenland. For this purpose...... and cement with fly ash. Based on the compressive strength tests, it is found that using Greenlandic incineration ashes in mortar as 5% cement replacement could consume all ash instead of disposals, and could thus turn the ashes into a local resource and simultaneously reduce the import of cement....

Assessing potential health effects from municipal sludge incinerators: screening methodology

Energy Technology Data Exchange (ETDEWEB)

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

1987-04-01

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

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

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

International Nuclear Information System (INIS)

Bujak, J.

2009-01-01

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

Recovery of plutonium from incinerator ash at Rocky Flats

International Nuclear Information System (INIS)

Johnson, T.C.

1976-01-01

Incineration of combustible materials highly contaminated with plutonium produces a residue of incinerator ash. Recovery of plutonium from incinerator ash residues at Rocky Flats is accomplished by a continuous leaching operation with nitric acid containing fluoride ion. Special equipment used in the leaching operation consists of a screw feeder, air-lift dissolvers, filters, solids dryer, and vapor collection system. Each equipment item is described in detail. The average dissolution efficiency of plutonium experienced with the process was 68% on the first pass, 74% on the second pass, and 64% on each subsequent pass. Total-solids dissolution efficiencies averaged 47% on the first pass and about 25% on each subsequent pass

Fluidized bed incinerator development

International Nuclear Information System (INIS)

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

1976-01-01

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

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.

Incineration method for plutonium recovery from alpha contaminated organic compounds

International Nuclear Information System (INIS)

Yahata, Taneaki; Abe, Jiro; Kato, Michiharu; Kurihara, Masayoshi

1985-01-01

An incineration method for plutonium recovery from α contaminated organic compounds in a flow of controlled oxygen gas is stated. The species of such thermal decomposition products as hydrocarbons, free carbon, carbon monoxide and hydrogen were determined by mass spectrography. The mixture of the products which are the source of tar or soot was converted to CO 2 and H 2 O in contact with copper oxide catalyst without flaming. This incineration method is composed of two stages. The first stage is the decomposition of organic compounds in the streams of gas mixtures containing oxygen in low ratios. The second stage is the incineration of the decomposition products by catalytic reaction in the streams of gas with higher oxygen ratios. Plutonium was recovered as the form of plutonium dioxide from the incineration residues of the first stage. The behavior of oil was examined as a representative of liquid organic compounds. It was found to evaporate below ca. 500 0 C, but was completely incinerated by the catalytic reaction with copper oxide catalyst in the flow of gas with controlled oxygen amount and was changed to CO 2 and H 2 O. (author)

Operation of a prototype high-level alpha solid waste incinerator

International Nuclear Information System (INIS)

Hootman, H.E.; Trapp, D.J.; Warren, J.H.; Dworjanyn, L.O.

1979-01-01

A full-scale (5 kg waste/hour) controlled-air incinerator is presently being tested as part of a program to develop technology for incineration of Savannah River Plant solid transuranic wastes. This unit is designed specifically to incinerate relatively small quantities of solid combustible wastes that are contaminated up to 10 5 times the present nominal 10 nCi/g threshold value for such isotopes as 238 Pu, 239 Pu, 242 Cm and 252 Cf. Automatic feed preparation and incinerator operation and control have been incorporated into the design to simulate the future plant design which will minimize operator radiation exposure. Over 250 kg of nonradioactive wastes characteristic of plutonium finishing operations have been incinerated at throughputs exceeding 5 kg/hr for periods up to 6 hours. Safety and reliability were major design objectives. Upon completion of an initial experimental phase to determine process sensitivity and flexibility, the facility will be used to develop bases for the production unit's safety analysis report, technical standards, and operating procedures. An ultimate use of the experimental unit will be the testing of actual production unit components and the training of Savannah River Plant operating personnel

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

Science.gov (United States)

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

2013-12-01

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

Conditioning processes for incinerator ashes

International Nuclear Information System (INIS)

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

1990-01-01

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

Risk identification for PPP waste-to-energy incineration projects in China

International Nuclear Information System (INIS)

Song, Jinbo; Song, Danrong; Zhang, Xueqing; Sun, Yan

2013-01-01

Municipal solid waste (MSW) is regarded as a renewable energy source. In China, the sharp increase of MSW has precipitated the rapid growth of waste-to-energy (WTE) incineration plants. Private capital has been getting into the WTE incineration industry through the public–private partnership (PPP) arrangement. Due to the large construction cost and the long concession period commonly associated with this arrangement, a number of failures have emerged in PPP WTE incineration projects. The aim of this paper is to investigate the key risks of PPP WTE incineration projects in China and study the strategies for managing these risks by drawing experience and learning lessons from these projects. First, we analyzed the MSW management practices, relevant legislations and policies, and the development of PPP WTE incineration projects in China. Second, we identified ten key risks through interviews, surveys and visits to some selected projects, and provided detailed analysis of these risks. Lastly, we developed response strategies for these risks from the perspectives of both public and private sectors. - Highlights: • We analyze MSW management practices, relevant legislations and policies in China. • Through case study on PPP WTE incineration projects, ten key risks are identified. • Response strategies for key risks are developed

Testing of TSCA incinerator for destruction of PCBs in uranium-contaminated wastes

International Nuclear Information System (INIS)

Anderson, R.W.

1988-01-01

A Toxic Substances Control Act (TSCA) incinerator for environmentally safe destruction of PCBs and hazardous organic materials contaminated with low-level radioactive wastes from seven DOE facilities has been constructed at the Oak Ridge Gaseous Diffusion Plant, and has undergone performance testing with PCB surrogates. The system incorporates state-of-the-art off-gas treatment, a highly instrumented kiln and secondary combustion chamber, and an inert-atmosphere solids-handling feed system. Release of organic during an upset event, which triggers opening of the secondary combustion-chamber relief vent, will be prevented by maintaining excess oxygen in the kiln and a high temperature in the secondary combustion chamber with an operating burner. Mixtures of chlorinated benzenes used in performance testing to simulate destruction of PCB, worst-case studies to satisfy regulatory concerns, and implications of performance test results are discussed. 4 references

Expertise on the project for the decommissioning of the pilot incineration plant at the Paul Scherrer Institute

International Nuclear Information System (INIS)

2012-12-01

This expertise report published by the Swiss Federal Nuclear Safety Inspectorate ENSI takes a look at the proposed decommissioning of the pilot incineration plant at the Paul Scherrer Institute PSI in Switzerland. Details concerning the operator PSI, the installation, the documentation and criteria used in the expertise are presented. Experience in the decommissioning of nuclear installations is reviewed. Decommissioning variants and the concept proposed are described and details concerning radiation sources and problematical materials such as asbestos are reviewed. The views of the Swiss Federal Nuclear Safety Inspectorate ENSI are presented and proposals for the disposal of radioactive wastes are examined. Finally, the costs incurred are reviewed

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.

Transformation of Silver Nanoparticles in Sewage Sludge during Incineration.

Science.gov (United States)

Meier, Christoph; Voegelin, Andreas; Pradas del Real, Ana; Sarret, Geraldine; Mueller, Christoph R; Kaegi, Ralf

2016-04-05

Silver nanoparticles (Ag-NP) discharged into the municipal sewer system largely accumulate in the sewage sludge. Incineration and agricultural use are currently the most important strategies for sewage sludge management. Thus, the behavior of Ag-NP during sewage sludge incineration is essential for a comprehensive life cycle analysis and a more complete understanding of the fate of Ag-NP in the (urban) environment. To address the transformation of Ag-NP during sewage sludge incineration, we spiked metallic Ag(0)-NP to a pilot wastewater treatment plant and digested the sludge anaerobically. The sludge was then incinerated on a bench-scale fluidized bed reactor in a series of experiments under variable conditions. Complementary results from X-ray absorption spectroscopy (XAS) and electron microscopy-energy dispersive X-ray (EM-EDX) analysis revealed that Ag(0)-NP transformed into Ag2S-NP during the wastewater treatment, in agreement with previous studies. On the basis of a principal component analysis and subsequent target testing of the XAS spectra, Ag(0) was identified as a major Ag component in the ashes, and Ag2S was clearly absent. The reformation of Ag(0)-NP was confirmed by EM-EDX. The fraction of Ag(0) of the total Ag in the ashes was quantified by linear combination fitting (LCF) of XAS spectra, and values as high as 0.8 were found for sewage sludge incinerated at 800 °C in a synthetic flue gas atmosphere. Low LCF totals (72% to 94%) indicated that at least one relevant reference spectrum was missing in the LCF analysis. The presence of spherical Ag-NP with a diameter of incineration, as demonstrated in this study, needs to be considered in the life cycle assessment of engineered Ag-NP.

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

Gaseous emissions from industrial processes: Municipal solid waste incinerators

Energy Technology Data Exchange (ETDEWEB)

Cassitto, L.; Gallarini, V.; Magnani, P.; Rizzi, A. (Politecnico di Milano, Milan (Italy). Impianti Condizionamento e Fisica Tecnica Artea, Milan (Italy))

A survey of European Communities proposed air pollution standards is coupled with an examination of the technical feasibility of building and operating municipal solid waste incineration plants that can successfully meet those standards. The results of the analysis indicate that modern incineration plants equipped with cogeneration and current-technology materials and energy recovery systems offer a significant contribution to meeting Italian national energy requirements and contemporaneously provide a decisive answer to the pressing need for safe and effective urban area waste disposal. The paper cautions however any final decision making must be based on extensive cost benefit analyses to determine the optimum combination of incinerator plant energy production and pollution control systems.

Chloride leaching from municipal solid waste incineration (MSWI) bottom ash

NARCIS (Netherlands)

Alam, Q.; Schollbach, K.; Florea, M.V.A.; Brouwers, H.J.H.; Vlastimil, Bilek; Kersner, Zbynek; Simonova, Hana

2017-01-01

The presence of chlorides in the Municipal Solid Waste Incineration bottom ashes (BA) hinders their potential for recycling in building materials. The contaminant content in the incineration residues is strictly regulated by the Dutch legislation Soil Quality Decree (2013). The fine fraction

Influence of heat transfer modes on the scale-up of solvent pool burning in controlled-air incinerators

International Nuclear Information System (INIS)

Gandhi, P.D.; Orloff, D.I.

1982-01-01