Investigation on the characteristics of liquid wastes depending on their generation sources and study on optimum treatment method

Energy Technology Data Exchange (ETDEWEB)

Kim, Sang Guk; Kim, Dong Chan; Shin, Dae Hyun; Son, Seung Geun; Roh, Nam Sun; Woo, Je Kyung [Korea Inst. of Energy Research, Taejon (Korea, Republic of)

1995-12-01

The major research contents conducted this year are as follows: (1) environmental regulation with respect to the treatment of the liquid waste in the U.S.A., (2) the present status of the generation and treatment of liquid wastes for large producers(>1,000 ton/year), (3) analysis for heating value element, heavy metal content, halogenated species on collected samples, (4) investigation on estimation method of energy recovery rate from liquid waste, (5) design of a lab. scale reactor which could be capable of conducting thermal decomposition test with small quantity of sample. In this study, present status of liquid waste generation and treatment is investigated, and thermal decomposition characteristics are studied using a lab. scale thermal reactor. The purpose of this research is to divide liquid waste into groups and to present best treatment method for their each group. (author). 24 refs., 21 figs., 23 tabs.

Low-level-waste-treatment handbook

International Nuclear Information System (INIS)

Clinton, S.D.; Goeller, H.E.; Holladay, D.W.; Donaldson, T.L.

1982-01-01

The initial draft of the Low-Level Waste Treatment Handbook has been prepared and submitted to the DOE Low-Level Waste Management Program for review and comment. A revised draft is scheduled to be delivered to DOE Headquarters in December 1982. The Handbook is designed to be useful to all individuals and groups concerned with low-level wastes. It is one of several volumes that will ultimately comprise a Low-Level Waste Technology Handbook. The objective of the Low-Level Waste Treatment Handbook is to present an overview of current practices related to the segregation, classification, volume reduction, solidification, handling, packaging, and transportation of LLW for disposal in a shallow land burial facility. The Handbook is intended to serve as a guide to individuals interested in the treatment and handling of low-level radioactive waste. The Handbook will not explicitly tell the user how to design and operate LLW treatment facilities, but rather will identify (1) kinds of information required to evaluate the options, (2) methods that may be used to evaluate these options, and (3) limitations associated with the selection of the treatment options. The focus of the Handbook is providing guidance on how to do waste treatment for disposal by shallow land burial

Treatment of liquid radioactive waste: Precipitation

International Nuclear Information System (INIS)

Gompper, K.

1982-01-01

After introductory remarks about waste types to be treated, specific treatment methods are discussed and examples are given for treatment processes carried out with different types of liquid wastes from nuclear power plants, research centers and fuel reprocessing plants. (RW)

Treatment of waste

International Nuclear Information System (INIS)

1981-01-01

A method of treating radioactive waste to substantially reduce the volume and which is especially useful in the treatment of material which includes radioactive halogens such as 131 I, is described. A fluidised bed incinerator and calciner are used to reduce all the liquid and combustible solid waste to anhydrous granular solids, all of which is carried by fluidizing gases into an off-gas system designed for their collection. (U.K.)

Treatment of radioactive wastes containing plutonium

International Nuclear Information System (INIS)

Orlando, O.S.; Aparicio, G.; Greco, L.; Orosco, E.H.; Cassaniti, P.; Salguero, D.; Toubes, B.; Perez, A.E.; Menghini, J.E.; Esteban, A.; Adelfang, P.

1987-01-01

The radioactive wastes generated in the process of manufacture and control of experimental fuel rods of mixed oxides, (U,Pu)O 2 , require an specific treatment due to the plutonium content. The composition of liquid wastes, mostly arising from chemical checks, is variable. The salt content, the acidity, and the plutonium and uranium content are different, which makes necessary a chemical treatment before the inclusion in concrete. The solid waste, such as neoprene gloves, PVC sleeves, filter paper, disposable or broken laboratory material, etc. are also included in concrete. In this report the methods used to dispose of wastes at Alpha Facility are described. With regard to the liquid wastes, the glove box built to process them is detailed, as well as the applied chemical treatment, including neutralization, filtration and later solidification. As for the solid wastes, it is described the cementation method consisting in introducing them into an expanded metal matrix, of the basket type, that contains as a concentric drum of 200 liter capacity which is smaller than the matrix, and the filling with wet cement mortar. (Author)

Development of radioactive waste treatment technique

International Nuclear Information System (INIS)

Kikuchi, Makoto; Amamiya, Shigeru; Yusa, Hideo.

1984-01-01

The techniques of radioactive waste treatment are generally reviewed, placing emphasis on volume reduction and solidification techniques. After a brief description on the general process of radioactive waste treatment, some special technologies being developed by Hitachi Ltd. are explained. From the viewpoints of the volume reduction, long term management and final disposal of wastes, the pelletization of dried waste and the solidification with inorganic substances are considered. One of the features of the pelletization system is to treat various kinds of wastes such as concentrated liquid wastes and used resins by the same system. The flow diagram of the system and its special features are shown. The volume reduction achieved by this system as compared to the conventional method is about 1/7. The first commercial plant for the treatment of concentrated liquid waste is scheduled to begin operation in June, 1984. As for the solidification technique for waste disposal, the use of cement glass is considered. The solidification system being developed is shortly described. (Aoki, K.)

Methods of sampling airborne fungi in working environments of waste treatment facilities.

Science.gov (United States)

Černá, Kristýna; Wittlingerová, Zdeňka; Zimová, Magdaléna; Janovský, Zdeněk

2016-01-01

The objective of the present study was to evaluate and compare the efficiency of a filter based sampling method and a high volume sampling method for sampling airborne culturable fungi present in waste sorting facilities. Membrane filters method was compared with surface air system method. The selected sampling methods were modified and tested in 2 plastic waste sorting facilities. The total number of colony-forming units (CFU)/m3 of airborne fungi was dependent on the type of sampling device, on the time of sampling, which was carried out every hour from the beginning of the work shift, and on the type of cultivation medium (p airborne fungi ranged 2×102-1.7×106 CFU/m3 when using the membrane filters (MF) method, and 3×102-6.4×104 CFU/m3 when using the surface air system (SAS) method. Both methods showed comparable sensitivity to the fluctuations of the concentrations of airborne fungi during the work shifts. The SAS method is adequate for a fast indicative determination of concentration of airborne fungi. The MF method is suitable for thorough assessment of working environment contamination by airborne fungi. Therefore we recommend the MF method for the implementation of a uniform standard methodology of airborne fungi sampling in working environments of waste treatment facilities. This work is available in Open Access model and licensed under a CC BY-NC 3.0 PL license.

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.)

Study of field assessment methods and worker risks for processing alternatives to support principles for FUSRAP waste materials. Part 1: Treatment methods and comparative risks of thorium removal from waste residues

Energy Technology Data Exchange (ETDEWEB)

Porter, R.D.; Hamby, D.M.; Martin, J.E.

1997-07-01

This study was done to examine the risks of remediation and the effectiveness of removal methods for thorium and its associated radioactive decay products from various soils and wastes associated with DOE`s Formerly Utilized Sites Remedial Action Program (FUSRAP). Its purpose was to provide information to the Environmental Management Advisory Board`s FUSRAP Committee for use in its deliberation of guiding principles for FUSRAP sites, in particular the degree to which treatment should be considered in the FUSRAP Committee`s recommendations. Treatment of FUSRAP wastes to remove thorium could be beneficial to management of lands that contain thorium if such treatment were effective and cost efficient. It must be recognized, however, that treatment methods invariably require workers to process residues and waste materials usually with bulk handling techniques. These processes expose workers to the radioactivity in the materials, therefore, workers would incur radiological risks in addition to industrial accident risks. An important question is whether the potential reduction of future radiological risks to members of the public justifies the risks that are incurred by remediation workers due to handling materials. This study examines, first, the effectiveness of treatment and then the risks that would be associated with remediation. Both types of information should be useful for decisions on whether and how to apply thorium removal methods to FUSRAP waste materials.

Study of field assessment methods and worker risks for processing alternatives to support principles for FURSRAP waste materials. Part 1: Treatment methods and comparative risks of thorium removal from waste residues

International Nuclear Information System (INIS)

Porter, R.D.; Hamby, D.M.; Martin, J.E.

1997-07-01

This study was done to examine the risks of remediation and the effectiveness of removal methods for thorium and its associated radioactive decay products from various soils and wastes associated with DOE's Formerly Utilized Sites Remedial Action Program (FUSRAP). Its purpose was to provide information to the Environmental Management Advisory Board's FUSRAP Committee for use in its deliberation of guiding principles for FUSRAP sites, in particular the degree to which treatment should be considered in the FUSRAP Committee's recommendations. Treatment of FUSRAP wastes to remove thorium could be beneficial to management of lands that contain thorium if such treatment were effective and cost efficient. It must be recognized, however, that treatment methods invariably require workers to process residues and waste materials usually with bulk handling techniques. These processes expose workers to the radioactivity in the materials, therefore, workers would incur radiological risks in addition to industrial accident risks. An important question is whether the potential reduction of future radiological risks to members of the public justifies the risks that are incurred by remediation workers due to handling materials. This study examines, first, the effectiveness of treatment and then the risks that would be associated with remediation. Both types of information should be useful for decisions on whether and how to apply thorium removal methods to FUSRAP waste materials

METHODS FOR DETERMINING AGITATOR MIXING REQUIREMENTS FOR A MIXING & SAMPLING FACILITY TO FEED WTP (WASTE TREATMENT PLANT)

Energy Technology Data Exchange (ETDEWEB)

GRIFFIN PW

2009-08-27

The following report is a summary of work conducted to evaluate the ability of existing correlative techniques and alternative methods to accurately estimate impeller speed and power requirements for mechanical mixers proposed for use in a mixing and sampling facility (MSF). The proposed facility would accept high level waste sludges from Hanford double-shell tanks and feed uniformly mixed high level waste to the Waste Treatment Plant. Numerous methods are evaluated and discussed, and resulting recommendations provided.

Waste washing pre-treatment of municipal and special waste.

Science.gov (United States)

Cossu, Raffaello; Lai, Tiziana; Pivnenko, Kostyantyn

2012-03-15

Long-term pollution potential in landfills is mainly related to the quality of leachate. Waste can be conveniently treated prior to landfilling with an aim to minimizing future emissions. Washing of waste represents a feasible pre-treatment method focused on controlling the leachable fraction of residues and relevant impact. In this study, non-recyclable plastics originating from source segregation, mechanical-biological treated municipal solid waste (MSW), bottom ash from MSW incineration and automotive shredder residues (ASR) were treated and the removal efficiency of washing pre-treatment prior to landfilling was evaluated. Column tests were performed to simulate the behaviour of waste in landfill under aerobic and anaerobic conditions. The findings obtained revealed how waste washing treatment (WWT) allowed the leachability of contaminants from waste to be reduced. Removal rates exceeding 65% were obtained for dissolved organic carbon (DOC), chemical oxygen demand (COD) and Total Kjeldahl Nitrogen (TKN). A percentage decrease of approximately 60% was reached for the leachable fraction of chlorides, sulphates, fluoride and metals, as proved by a reduction in electric conductivity values (70%). Copyright © 2011 Elsevier B.V. All rights reserved.

Future-proof radioactive waste treatment technologies for nuclear power plants

Energy Technology Data Exchange (ETDEWEB)

Buettner, Klaus; Braehler, Georg [NUKEM Technologies Engineering Services GmbH, Alzenau (Germany)

2014-08-15

In order to select the optimal treatment method for radioactive waste three options can be considered. First, to treat the radioactive waste only to allow long term interim storage until the waste acceptance criteria are defined and the disposal sites are operable. Second, to select treatment methods just in compliance with the current state of discussion with the regard to the above. Third, taking also the future development in the field of waste acceptance criteria and disposal into account. When developing waste treatment systems for Nuclear Power Plants NUKEM Technologies follows the following targets, minimisation of the amount of radioactive waste, maximisation of free release material, volume reduction, avoidance of unwanted materials in the waste package, as well as efficient waste treatment solutions (low investment, high volume reduction). With its technologies produced waste packages fulfil the most stringent waste acceptance criteria.

The micro-electrolysis technique in waste water treatment

International Nuclear Information System (INIS)

Jiti Zhou; Weihen Yang; Fenglin Yang; Xuemin Xiang; Yulu Wang

1997-01-01

The micro-electrolysis is one of the efficient methods to treat some kinds of waste water. The experiments have shown its high efficiency in sewage treatment and some kinds of industrial waste water. It is suitable for pre-treatment of high concentrated waste water and deep treatment of waste water for reuse purpose. The disadvantage of micro-electrolysis is its high energy consumption in case of high electrolyte concentration. (author) 2 figs., 11 tabs., 2 refs

The micro-electrolysis technique in waste water treatment

Energy Technology Data Exchange (ETDEWEB)

Jiti Zhou; Weihen Yang; Fenglin Yang; Xuemin Xiang; Yulu Wang [Dalian Univ. of Technology, Dalian (China)

1997-12-31

The micro-electrolysis is one of the efficient methods to treat some kinds of waste water. The experiments have shown its high efficiency in sewage treatment and some kinds of industrial waste water. It is suitable for pre-treatment of high concentrated waste water and deep treatment of waste water for reuse purpose. The disadvantage of micro-electrolysis is its high energy consumption in case of high electrolyte concentration. (author) 2 figs., 11 tabs., 2 refs.

Magnetic Adsorption Method for the Treatment of Metal Contaminated Aqueous Waste

International Nuclear Information System (INIS)

Cotten, G.B.; Eldredge, H.B.; Navratil, J.D.

1999-01-01

There have been many recent developments in separation methods used for treating radioactive and non-radioactive metal bearing liquid wastes. These methods have included adsorption, ion exchange, solvent extraction and other chemical and physical techniques. To date very few, if any, of these processes can provide a low cost and environmentally benign solution. Recent research into the use of magnetite for wastewater treatment indicates the potential for magnetite both cost and environment drivers. A brief review of recent work in using magnetite as a sorbent is presented as well as recent work performed in our laboratory using supported magnetite in the presence of an external magnetic field. The application to groundwater and other aqueous waste streams is discussed. Recent research has focused on supporting magnetite in an economical (as compared to the magnetic polymine-epichlorohydrine resin) and inert (non-reactive, chemically or otherwise) environment that promotes both adsorption and satisfactory flow characteristics

A method for the treatment of waste waters

International Nuclear Information System (INIS)

McLaughlin, M.E.

1974-01-01

The invention relates to a method for the cooling of waste waters. It is characterized in that it comprises the steps of introducing waste waters into a tank in communication with a basin through gate-controlled orifices, successively opening and closing the gates so as to intermitently release an adjustable amount of water stored in the tank in order to generate waves promoting the airing of waste waters and their cooling, then expelling waters downstream of the basin. The invention relates to thermal and nuclear power stations [fr

Immobilization in ceramic waste forms of the residues from treatment of mixed wastes

International Nuclear Information System (INIS)

Oversby, V.M.; van Konynenburg, R.A.; Glassley, W.E.; Curtis, P.G.

1993-11-01

The Environmental Restoration and Waste Management Applied Technology Program at LLNL is developing a Mixed Waste Management Facility to demonstrate treatment technologies that provide an alternative to incineration. As part of that program, we are developing final waste forms using ceramic processing methods for the immobilization of the treatment process residues. The ceramic phase assemblages are based on using Synroc D as a starting point and varying the phase assemblage to accommodate the differences in chemistry between the treatment process residues and the defense waste for which Synroc D was developed. Two basic formulations are used, one for low ash residues resulting from treatment of organic materials contaminated with RCRA metals, and one for high ash residues generated from the treatment of plastics and paper products. Treatment process residues are mixed with ceramic precursor materials, dried, calcined, formed into pellets at room temperature, and sintered at 1150 to 1200 degrees C to produce the final waste form. This paper discusses the chemical composition of the waste streams and waste forms, the phase assemblages that serve as hosts for inorganic waste elements, and the changes in waste form characteristics as a function of variation in process parameters

Use of ionizing radiation in waste water treatment

International Nuclear Information System (INIS)

Cech, R.

1976-01-01

A survey is presented of methods and possibilities of applying ionizing radiation in industrial waste water treatment. The most frequently used radiation sources include the 60 Co and 137 Cs isotopes and the 90 Sr- 90 Y combined source. The results are reported and the methods used are described of waste water treatment by sedimenting impurities and decomposing organic and inorganic compounds by ionizing radiation. It was found that waste water irradiation accelerated sedimentation and decomposition processes. The doses used varied between 50 and 500 krads. Ionizing radiation may also be used in waste water disinfection in which the effects are used of radiation on microorganisms and of the synthesis of ozone which does not smell like normally used chlorine. The described methods are still controversial from the economic point of view but the cost of waste water treatment by irradiation will significantly be reduced by the use of spent fuel elements. (J.B.)

METHODS FOR DETERMINING AGITATOR MIXING REQUIREMENTS FOR A MIXING and SAMPLING FACILITY TO FEED WTP (WASTE TREATMENT PLANT)

International Nuclear Information System (INIS)

Griffin, P.W.

2009-01-01

The following report is a summary of work conducted to evaluate the ability of existing correlative techniques and alternative methods to accurately estimate impeller speed and power requirements for mechanical mixers proposed for use in a mixing and sampling facility (MSF). The proposed facility would accept high level waste sludges from Hanford double-shell tanks and feed uniformly mixed high level waste to the Waste Treatment Plant. Numerous methods are evaluated and discussed, and resulting recommendations provided.

Waste-to-energy, municipal solid waste treatment, and best available technology

DEFF Research Database (Denmark)

Wang, Zhenfeng; Ren, Jingzheng; Goodsite, Michael Evan

2018-01-01

The treatment of municipal solid waste (MSW) has become an urgently important task of many countries. This objective of this study is to present a novel group multi-attribute decision analysis method for prioritizing the MSW treatment alternatives based on the interval-valued fuzzy set theory...... (DEMATEL) method was developed to determine the weights of the evaluation criteria by considering the independent relationships among these criteria. The multi-actor interval-valued fuzzy grey relational analysis was developed to rank the waste-to-energy scenarios. Four alternative processes for MSW...

Treatment methods and comparative risks of thorium removal from waste residues

International Nuclear Information System (INIS)

Porter, R.D.; Hamby, D.M.; Martin, J.E.

1997-07-01

This study was done to examine the risks of remediation and the effectiveness of removal methods for thorium and its associated radioactive decay products from various soils and wastes associated with DOE's Formerly Utilized Sites Remedial Action Program (FUSRAP). Removal of 230 Th from uranium process residues would significantly reduce the buildup of 226 Ra (half-life of 1600 years), and since 230 Th concentrations at most of the important sites greatly exceed the 226 Ra concentrations, such removal would reduce the accumulation of additional radiation risks associated with 226 Ra and its products; and, if treatment also removed 226 Ra, these risks could be mitigated even further. Removal of 232 Th from thorium process residues would remove the source material for 228 Ra, and since 228 Ra has a half-life of 5.76 years, its control at FUSRAP sites could be done with land use controls for the 30--50 years required for 228 Ra and the risks associated with its decay products to decay away. It must be recognized, however, that treatment methods invariably require workers to process residues and waste materials usually with bulk handling techniques. These processes expose workers to the radioactivity in the materials, therefore, workers would incur radiological risks in addition to industrial accident risks. An important question is whether the potential reduction of future radiological risks to members of the public justifies the risks that are incurred by remediation workers due to handling materials. This study examines, first, the effectiveness of treatment and then the risks that would be associated with remediation

Mixed waste treatment at the Idaho National Engineering Laboratory

International Nuclear Information System (INIS)

Larsen, M.M.; Hunt, L.F.; Sanow, D.J.

1988-01-01

The Idaho Operations Office of the Department of Energy (DOE) made the decision in 1984 to prohibit the disposal of mixed waste (MW) (combustible waste-toxic metal waste) in the Idaho National Engineering Laboratory (INEL) low-level radioactive waste (LLW) disposal facility. As a result of this decision and due to there being no EPA-permitted MW treatment/storage/disposal (T/S/D) facilities, the development of waste treatment methods for MW was initiated and a storage facility was established to store these wastes while awaiting development of treatment systems. This report discusses the treatment systems developed and their status. 3 refs., 2 figs., 1 tab

A method for livestock waste management planning in NE Spain

International Nuclear Information System (INIS)

Teira-Esmatges, M.R.; Flotats, X.

2003-01-01

A method of decision-making on livestock wastes management in areas with nutrient surplus due to high livestock density is applied in Catalonia (NE Spain). Nutrient balance is made considering soil nitrogen application as the limiting factor. Special attention is paid to the centralized treatment option. The method presented consists of: - minimizing livestock waste generation (at farm scale) as a step previous to any other, both in amount and limiting components,; - applying the nitrogen balance method at regional and municipal scale and providing enough storage capacity in order to apply wastes in an agronomically correct way,; - spatially refining the results of the nitrogen balance by a proposed method that allows precisely pinpointing the hotspots of livestock waste generation, where centralized treatment might be an interesting option, and; - deciding on the waste treatment objectives, provided that treatments be necessary. Knowledge about the wastes, meeting the interests and merging the efforts of the various actors, as well as an adequate budget are necessary ingredients for the success of any waste management plan

Cyanide wastes treatment by bioremediation

International Nuclear Information System (INIS)

Deloya Martinez, Alma

2012-01-01

The results of the development of an autochthonous consortium of degrader microorganisms of the cyanide for the application in the biological treatment of the dangerous wastes of cyanide, were presented. The autochthonous microorganisms obtained were lyophilized in different protective environments, such as gelatin and lactose broth at different temperatures (-35, -45, -55 and -65). A pretreatment method in slurry was applied for the preliminary treatment of the cyanide wastes: for the preliminary leaching of the waste, with periods between 3 and 5 days and a posterior treatment, by aerated lagoons, applying the consortium of lyophilized microorganisms. Eight different lyophilized were obtained in different temperature conditions and with two lyophilization protective media that have presented excellent recovery at six months of lyophilization. The consortium of lyophilized microorganisms has presented 70 to 80 percent of viability, with cyanide removal percentages higher than 95% and it can be conserved active for a prolonged time (for years). The lyophilized microorganisms can be applied in the biodegradation of the cyanide wastes from the gold mines or any other cyanide waste such as metal electroplanting baths, as well as from jewelry manufacturing. (author) [es

Radiation treatment of solid wastes

International Nuclear Information System (INIS)

Brenner, W.; Rugg, B.; Rogers, C.

1977-01-01

Solid waste is now generally recognized as both a major problem and an underutilized renewable resource for materials and energy recovery. Current methods for dealing with solid wastes are admittedly inadequate for cost effective utilization of the latest material and energy values, especially of cellulose and other organics. Processes for production of energy from organic wastes including incineration, pyrolysis and biodegradation, are receiving considerable attention even though the heating value of dried organic wastes is substantially less than that of fossil fuels. An attractive alternative approach is conversion into chemical feedstocks for use as fuels, intermediates for plastics, rubbers, fibers etc., and in the preparation of foods. Radiation treatment of solid wastes offers attractive possibilities for upgrading the value of such organic waste components as cellulose and putrescible matter. The latter can be cold sterilized by radiation treatments for the production of animal feed supplements. The wide availability of cellulosic wastes warrants their consideration as an alternate feedstock to petrochemicals for fuels, intermediates and synthesis of single cell protein. The crucial step in this developing technology is optimizing the conversion of cellulose to its monomer glucose which can be accomplished by either acid or enzymatic hydrolysis. A combination pretreatment consisting of radiation of hydropulped cellulosic wastes has shown considerable promise in improving the yields of glucose for acid hydrolysis reactions at substantially lower cost than presently used methods such as grinding. Data are presented to compare the effectiveness of this pretreatment with other techniques which have been investigated. (author)

Hazardous waste treatment and environmental remediation research

International Nuclear Information System (INIS)

1989-01-01

Los Alamos National Laboratory (LANL) is currently evaluating hazardous waste treatment and environmental remediation technologies in existence and under development to determine applicability to remediation needs of the DOE facilities under the Albuquerque Operations Office and to determine areas of research need. To assist LANL is this effort, Science Applications International Corporation (SAIC) conducted an assessment of technologies and monitoring methods that have been demonstrated or are under development. The focus of this assessment is to: (1) identify existing technologies for hazardous waste treatment and environmental remediation of old waste sites; (2) identify technologies under development and the status of the technology; (3) assess new technologies that need development to provide adequate hazardous waste treatment and remedial action technologies for DOD and DOE sites; and (4) identify hazardous waste and remediation problems for environmental research and development. There are currently numerous research and development activities underway nationwide relating to environmental contaminants and the remediation of waste sites. To perform this effort, SAIC evaluated current technologies and monitoring methods development programs in EPA, DOD, and DOE, as these are the primary agencies through which developmental methods are being demonstrated. This report presents this evaluation and provides recommendations as to pertinent research needs or activities to address waste site contamination problems. The review and assessment have been conducted at a programmatic level; site-specific and contaminant-specific evaluations are being performed by LANL staff as a separate, related activity

Thermal plasma waste treatment

International Nuclear Information System (INIS)

Heberlein, Joachim; Murphy, Anthony B

2008-01-01

Plasma waste treatment has over the past decade become a more prominent technology because of the increasing problems with waste disposal and because of the realization of opportunities to generate valuable co-products. Plasma vitrification of hazardous slags has been a commercial technology for several years, and volume reduction of hazardous wastes using plasma processes is increasingly being used. Plasma gasification of wastes with low negative values has attracted interest as a source of energy and spawned process developments for treatment of even municipal solid wastes. Numerous technologies and approaches exist for plasma treatment of wastes. This review summarizes the approaches that have been developed, presents some of the basic physical principles, provides details of some specific processes and considers the advantages and disadvantages of thermal plasmas in waste treatment applications. (topical review)

Treatment strategies for transuranic wastes

International Nuclear Information System (INIS)

Schneider, K.J.; Ross, W.A.; Swanson, J.L.; Allen, R.P.; Yasutake, K.M.

1986-01-01

This paper presents an analysis of treatment options or strategies for transuranic wastes expected to be generated at a commercial nuclear fuel reprocessing plant. Six potential options were analyzed, ranging from no treatment to maximum volume reduction and high quality waste forms. Economics for the total management of these wastes (treatment, transportation, disposal) indicate life-cycle savings for extensive treatment are as high as $1.7 billion for 70,000 MTU. Evaluations of the waste processing and waste forms support the selection of a number of the extensive waste treatments. It is concluded that there are significant incentives for extensive treatment of transuranic wastes

Treatment strategies for transuranic wastes

International Nuclear Information System (INIS)

Schneider, K.J.; Swanson, J.L.; Ross, W.A.; Allen, R.P.; Yasutake, K.M.

1986-01-01

This paper presents an analysis of treatment options or strategies for transuranic wastes expected to be generated at a commercial nuclear fuel reprocessing plant. Six potential options were analyzed, ranging from no treatment to maximum volume reduction and high quality waste forms. Economics for the total management of these (treatment, transportation, disposal) indicate life-cycle savings for extensive treatment are as high as $1.7 billion for 70,000 MTU. Evaluations of the waste processing and waste forms support the selection of a number of the extensive waste treatments. It is concluded that there are significant incentives for extensive treatment of transuranic wastes

Treatment of fast reactor liquid waste- electrochemical method

International Nuclear Information System (INIS)

Mahato, Swapan Kumar; Sudha, R.; Anthonysamy, S.; Muralidaran, P.

2015-01-01

During the operation of fast reactors, components get wetted by sodium. The sodium wetted primary components such as pumps and intermediate heat exchangers (IHX) in fast reactors are cleaned free of sodium followed by suitable chemical decontamination process before taking them for maintenance or for disposal. This helps in reduction of radiation dose to the operating personnel. Sodium cleaning and decontamination generates large volumes of liquid effluent. The activity in the liquid effluent during sodium cleaning/decontamination is due to 22 Na, 54 Mn, 58 Co, 60 Co, 59 Fe, 137 Cs and 134 Cs. It is required to chemically treat the effluent to reduce the activity levels prior to storage in tanks and transportation to the waste management facility for final disposal. Conventionally the ion exchange method is used for removal of radionuclides which produces large quantities of secondary waste. A method which is suitable both for removal of radionuclides present in low concentration and that avoids generation of large quantities of secondary waste is required. Hence an electrochemical method for metal ion removal is attempted in this work which produces little or no secondary waste. Electrochemical method towards removal of manganese ions was finalized earlier using reticulated vitreous carbon (RVC) from simulated decontamination solution containing a mixture of sulphuric and phosphoric acids. In continuation of the experiments for the removal of cesium ions from simulated cleaning solution which has an alkaline pH, a thin film of nickel hexacyanoferrate (NiHCF) was deposited electrochemically on the surface of RVC. Hexacyanoferrates are known for selectively binding cesium. This NiHCF coated RVC was used for electrodeposition of Cs ions. NiHCF coated and Cs deposited RVC was characterized using SEM/EDX analysis. EDX analysis confirms the presence of Cs on NiHCF coated RVC. (author)

Evaluation of Secondary Streams in Mixed Waste Treatment

International Nuclear Information System (INIS)

Haywood, Fred F.; Goldsmith, William A.; Allen, Douglas F.; Mezga, Lance J.

1995-12-01

The United States Department of Energy (DOE) and its predecessors have generated waste containing radioactive and hazardous chemical components (mixed wastes) for over 50 years. Facilities and processes generating these wastes as well as the regulations governing their management have changed. Now, DOE has 49 sites where mixed waste streams exist. The Federal Facility Compliance Act of 1992 (1) required DOE to prepare and obtain regulatory approval of plans for treating these mixed waste streams. Each of the involved DOE sites submitted its respective plan to regulators in April 1995 (2). Most of the individual plans were approved by the respective regulatory agencies in October 1995. The implementation of these plans has begun accordance with compliance instruments (orders) issued by the cognizant regulatory authority. Most of these orders include milestones that are fixed, firm and enforceable as defined in each compliance order. In many cases, mixed waste treatment that was already being carried out and survived the alternative selection process is being used now to treat selected mixed waste streams. For other waste streams at sites throughout the DOE complex treatment methods and schedules are subject to negotiation as the realties of ever decreasing budgets begin to drive the available options. Secondary wastes generated by individual waste treatment systems are also mixed wastes that require treatment in the appropriate treatment system. These secondary wastes may be solid or liquid waste (or both). For example debris washing will generate wastewater requiring treatment; wastewater treatment, in turn, will generate sludge or other residuals requiring treatment; liquid effluents must meet applicable limits of discharge permits. At large DOE sites, secondary waste streams will be a major influence in optimizing design for primary treatment. Understanding these impacts is important not only foe system design, but also for assurances that radiation releases and

Rad-waste treatment

International Nuclear Information System (INIS)

1996-01-01

The spent fuel coming from Slovak NPPs have partially been transported to the former Soviet Union, and a part of it is stored in an interim spent fuel wet storage. In compliance with the worldwide practices, further medium-term possibilities of storing in dry storages are under preparation. Disposal of a spent fuel and other high-level active wastes in a deep geological formation repository is the final solution. At present, there are geological investigations of possible sites in progress in Slovakia. Mochovce repository is a factory for a final disposal of compacted low and intermediate level radioactive wastes coming from the Slovak NPPs. This is a near-surface facility of a construction similar to the one used for disposal of radioactive wastes in France, Spain, Japan, Czech Republic, U.S.A, etc. Quality of the design, construction and functioning of the Mochovce's repository was assessed by an international team of experts within a special IAEA programme (WATRP). Having familiarized with the final report of the IAEA mission, Nuclear Regulatory Authority of the Slovak Republic (NRA SR) issued its position early in 1995, in which NRA SR required additional adjustment of the repository itself. Based on the NRA SR's position, Mochovce NPP invited experts from a number of institutions in September 1995 to discuss the NRA SR's requirements. Following was recommended by the experts: (1) to perform a complementary engineering-geological investigation on the site, (2) to use geophysical methods to verify existence of geological faults. In the next part a radioactive wastes that were treated at radioactive waste treatment lines in 1995 are listed. In 1995, the Chief Inspector of NRA SR issued an instruction that radioactive waste department should start inspections of radioactive waste treatment right in hospitals, research institutes and industries. Therefore, a total of 14 such workplaces were incorporated into a plan of inspections in 1995

Waste treatment plant

International Nuclear Information System (INIS)

Adesanmi, C.A

2009-01-01

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

Treatment methods and comparative risks of thorium removal from waste residues

Energy Technology Data Exchange (ETDEWEB)

Porter, R.D.; Hamby, D.M.; Martin, J.E.

1997-07-01

This study was done to examine the risks of remediation and the effectiveness of removal methods for thorium and its associated radioactive decay products from various soils and wastes associated with DOE`s Formerly Utilized Sites Remedial Action Program (FUSRAP). Removal of {sup 230}Th from uranium process residues would significantly reduce the buildup of {sup 226}Ra (half-life of 1600 years), and since {sup 230}Th concentrations at most of the important sites greatly exceed the {sup 226}Ra concentrations, such removal would reduce the accumulation of additional radiation risks associated with {sup 226}Ra and its products; and, if treatment also removed {sup 226}Ra, these risks could be mitigated even further. Removal of {sup 232}Th from thorium process residues would remove the source material for {sup 228}Ra, and since {sup 228}Ra has a half-life of 5.76 years, its control at FUSRAP sites could be done with land use controls for the 30--50 years required for {sup 228}Ra and the risks associated with its decay products to decay away. It must be recognized, however, that treatment methods invariably require workers to process residues and waste materials usually with bulk handling techniques. These processes expose workers to the radioactivity in the materials, therefore, workers would incur radiological risks in addition to industrial accident risks. An important question is whether the potential reduction of future radiological risks to members of the public justifies the risks that are incurred by remediation workers due to handling materials. This study examines, first, the effectiveness of treatment and then the risks that would be associated with remediation.

Treatment of tributyl phosphate wastes by extraction cum pyrolysis process

International Nuclear Information System (INIS)

Deshingkar, D.S.; Ramaswamy, M.; Kartha, P.K.S.; Kutty, P.V.E.; Ramanujam, A.

1989-01-01

For the treatment of spent tri n-butyl phospate (TBP) wastes from Purex process, a method involving extraction of TBP with phosphoric acid followed by pyrolysis of TBP - phosphoric acid phase was investigated. The process was examined with respect to simulated waste, process solvent wastes and aged organic waste samples. These studies seem to offer a simple treatment method for the separation of bulk of diluent from spent solvent wastes. The diluent phase needs further purification for reuse in reprocessing plant; otherwise it can be incinerated. (author). 18 refs., 3 tabs., 6 figs

Waste treatment

International Nuclear Information System (INIS)

Hutson, G.V.

1996-01-01

Numerous types of waste are produced by the nuclear industry ranging from high-level radioactive and heat-generating, HLW, to very low-level, LLW and usually very bulky wastes. These may be in solid, liquid or gaseous phases and require different treatments. Waste management practices have evolved within commercial and environmental constraints resulting in considerable reduction in discharges. (UK)

Treatment for hydrazine-containing waste water solution

Science.gov (United States)

Yade, N.

1986-01-01

The treatment for waste solutions containing hydrazine is presented. The invention attempts oxidation and decomposition of hydrazine in waste water in a simple and effective processing. The method adds activated charcoal to waste solutions containing hydrazine while maintaining a pH value higher than 8, and adding iron salts if necessary. Then, the solution is aerated.

WASTE TREATMENT BUILDING SYSTEM DESCRIPTION DOCUMENT

Energy Technology Data Exchange (ETDEWEB)

F. Habashi

2000-06-22

The Waste Treatment Building System provides the space, layout, structures, and embedded subsystems that support the processing of low-level liquid and solid radioactive waste generated within the Monitored Geologic Repository (MGR). The activities conducted in the Waste Treatment Building include sorting, volume reduction, and packaging of dry waste, and collecting, processing, solidification, and packaging of liquid waste. The Waste Treatment Building System is located on the surface within the protected area of the MGR. The Waste Treatment Building System helps maintain a suitable environment for the waste processing and protects the systems within the Waste Treatment Building (WTB) from most of the natural and induced environments. The WTB also confines contaminants and provides radiological protection to personnel. In addition to the waste processing operations, the Waste Treatment Building System provides space and layout for staging of packaged waste for shipment, industrial and radiological safety systems, control and monitoring of operations, safeguards and security systems, and fire protection, ventilation and utilities systems. The Waste Treatment Building System also provides the required space and layout for maintenance activities, tool storage, and administrative facilities. The Waste Treatment Building System integrates waste processing systems within its protective structure to support the throughput rates established for the MGR. The Waste Treatment Building System also provides shielding, layout, and other design features to help limit personnel radiation exposures to levels which are as low as is reasonably achievable (ALARA). The Waste Treatment Building System interfaces with the Site Generated Radiological Waste Handling System, and with other MGR systems that support the waste processing operations. The Waste Treatment Building System interfaces with the General Site Transportation System, Site Communications System, Site Water System, MGR

WASTE TREATMENT BUILDING SYSTEM DESCRIPTION DOCUMENT

International Nuclear Information System (INIS)

Habashi, F.

2000-01-01

The Waste Treatment Building System provides the space, layout, structures, and embedded subsystems that support the processing of low-level liquid and solid radioactive waste generated within the Monitored Geologic Repository (MGR). The activities conducted in the Waste Treatment Building include sorting, volume reduction, and packaging of dry waste, and collecting, processing, solidification, and packaging of liquid waste. The Waste Treatment Building System is located on the surface within the protected area of the MGR. The Waste Treatment Building System helps maintain a suitable environment for the waste processing and protects the systems within the Waste Treatment Building (WTB) from most of the natural and induced environments. The WTB also confines contaminants and provides radiological protection to personnel. In addition to the waste processing operations, the Waste Treatment Building System provides space and layout for staging of packaged waste for shipment, industrial and radiological safety systems, control and monitoring of operations, safeguards and security systems, and fire protection, ventilation and utilities systems. The Waste Treatment Building System also provides the required space and layout for maintenance activities, tool storage, and administrative facilities. The Waste Treatment Building System integrates waste processing systems within its protective structure to support the throughput rates established for the MGR. The Waste Treatment Building System also provides shielding, layout, and other design features to help limit personnel radiation exposures to levels which are as low as is reasonably achievable (ALARA). The Waste Treatment Building System interfaces with the Site Generated Radiological Waste Handling System, and with other MGR systems that support the waste processing operations. The Waste Treatment Building System interfaces with the General Site Transportation System, Site Communications System, Site Water System, MGR

Solid and liquid radioactive waste treatment

International Nuclear Information System (INIS)

Rzyski, B.M.

1989-01-01

The technology for the treatment of low - and intermediate-level radioactive solid and liquid wastes is somewhat extensive. Some main guidance on the treatment methods are shown, based on informations contained in technical reports and complementary documents. (author) [pt

Treatment of ORNL liquid low-level waste

International Nuclear Information System (INIS)

Berry, J.B.; Brown, C.H. Jr.; Fowler, V.L.; Robinson, S.M.

1988-01-01

Discontinuation of the hydrofracture disposal method at Oak Ridge National Laboratory (ORNL) has caused intensive efforts to reduce liquid waste generation. Improving the treatment of slightly radioactive liquid waste, called process waste, has reduced the volume of the resulting contaminated liquid radioactive waste effluent by 66%. Proposed processing improvements could eliminate the contaminated liquid effluent and reduce solid low-level waste by an additional one-third. The improved process meets stringent discharge limits for radionuclides. Discharge limits for radionuclides are expected to be enforced at the outfall of the treatment plant to a creek; currently, limits are enforced at the reservation boundary. Plant discharge is monitored according to the National Pollutant Discharge Elimination System (NPDES) permit for ORNL. 1 ref., 4 figs., 2 tabs

Method of melting solid waste

International Nuclear Information System (INIS)

Ootsuka, Katsuyuki; Mizuno, Ryokichi; Kuwana, Katsumi; Sawada, Yoshihisa; Komatsu, Fumiaki.

1982-01-01

Purpose: To enable the volume reduction treatment of a HEPA filter containing various solid wastes, particularly acid digestion residue, or an asbestos separator at a relatively low temperature range. Method: Solid waste to be heated and molten is high melting point material treated by ''acid digestion treatment'' for treating solid waste, e.g. a HEPA filter or polyvinyl chloride, etc. of an atomic power facility treated with nitric acid or the like. When this material is heated and molten by an electric furnace, microwave melting furnace, etc., boron oxide, sodium boride, sodium carbonate, etc. is added as a melting point lowering agent. When it is molten in this state, its melting point is lowered, and it becomes remarkably fluid, and the melting treatment is facilitated. Solidified material thus obtained through the melting step has excellent denseness and further large volume reduction rate of the solidified material. (Yoshihara, H.)

Life cycle assessment of advanced waste water treatment

DEFF Research Database (Denmark)

Larsen, Henrik Fred; Hansen, Peter Augusto

The EU FP6 NEPTUNE project is related to the EU Water Framework Directive and the main goal is to develop new and optimize existing waste water treatment technologies (WWTT) and sludge handling methods for municipal waste water. Besides nutrients, a special focus area is micropollutants (e....... In total more that 20 different waste water and sludge treatment technologies are to be assessed. This paper will present the preliminary LCA results from running the induced versus avoided impact approach (mainly based on existing LCIA methodology) on one of the advanced treatment technologies, i...

Treatment of solid wastes. Preventing waste production, recovery, waste collection, waste disposal, sanitation. Procedures, technical processes, legal foundations. 2. rev. ed. Behandlung fester Abfaelle. Vermeiden, Verwerten, Sammeln, Beseitigen, Sanieren. Verfahrensweise, technische Realisierung, rechtliche Grundlagen

Energy Technology Data Exchange (ETDEWEB)

Sattler, K.; Emberger, J.

1990-01-01

The book 'Treatment of Solid Wastes' was compiled by the group 'Environmental Protection/Waste Disposal' and looks at disposal methods and processes. The initial chapters deal with technical methods of environmental protection, describe laws and legal regulations pertaining to waste disposal, explain the quantities and composition of the waste matter and give an overview of the treatments which are available. Methods and technical process of waste collection, transport, sorting, recapturing of valuable matter, biochemical and thermal conversion and depositing. Treatment of poisonous wastes and old sites are dealt with in the final chapters. (orig./EF).

Treatment of organic radioactive waste in decommissioning project

International Nuclear Information System (INIS)

Dimovic, S.; Plecas, I.

2003-01-01

This paper describes methods of treatment of organic radioactive waste in the aspect of its integral part of radioactive waste which will arise during decommissioning process of nuclear power reactor RA (author)

Analysis of waste treatment requirements for DOE mixed wastes: Technical basis

International Nuclear Information System (INIS)

1995-02-01

The risks and costs of managing DOE wastes are a direct function of the total quantities of 3wastes that are handled at each step of the management process. As part of the analysis of the management of DOE low-level mixed wastes (LLMW), a reference scheme has been developed for the treatment of these wastes to meet EPA criteria. The treatment analysis in a limited form was also applied to one option for treatment of transuranic wastes. The treatment requirements in all cases analyzed are based on a reference flowsheet which provides high level treatment trains for all LLMW. This report explains the background and basis for that treatment scheme. Reference waste stream chemical compositions and physical properties including densities were established for each stream in the data base. These compositions are used to define the expected behavior for wastes as they pass through the treatment train. Each EPA RCRA waste code was reviewed, the properties, chemical composition, or characteristics which are of importance to waste behavior in treatment were designated. Properties that dictate treatment requirements were then used to develop the treatment trains and identify the unit operations that would be included in these trains. A table was prepared showing a correlation of the waste physical matrix and the waste treatment requirements as a guide to the treatment analysis. The analysis of waste treatment loads is done by assigning wastes to treatment steps which would achieve RCRA compliant treatment. These correlation's allow one to examine the treatment requirements in a condensed manner and to see that all wastes and contaminant sets are fully considered

Chemical precipitation processes for the treatment of aqueous radioactive waste

International Nuclear Information System (INIS)

1992-01-01

Chemical precipitation by coagulation-flocculation and sedimentation has been commonly used for many years to treat liquid (aqueous) radioactive waste. This method allows the volume of waste to be substantially reduced for further treatment or conditioning and the bulk of the waste to de discharged. Chemical precipitation is usually applied in combination with other methods as part of a comprehensive waste management scheme. As with any other technology, chemical precipitation is constantly being improved to reduce cost to increase the effectiveness and safety on the entire waste management system. The purpose of this report is to review and update the information provided in Technical Reports Series No. 89, Chemical Treatment of Radioactive Wastes, published in 1968. In this report the chemical methods currently in use for the treatment of low and intermediate level aqueous radioactive wastes are described and illustrated. Comparisons are given of the advantages and limitations of the processes, and it is noted that good decontamination and volume reduction are not the only criteria according to which a particular process should be selected. Emphasis has been placed on the need to carefully characterize each waste stream, to examine fully the effect of segregation and the importance of looking at the entire operation and not just the treatment process when planning a liquid waste treatment facility. This general approach includes local requirements and possibilities, discharge authorization, management of the concentrates, ICRP recommendations and economics. It appears that chemical precipitation process and solid-liquid separation techniques will continue to be widely used in liquid radioactive waste treatment. Current research and development is showing that combining different processes in one treatment plant can provide higher decontamination factors and smaller secondary waste arisings. Some of these processes are already being incorporated into new and

Laboratory development of methods for centralized treatment of liquid low-level waste at Oak Ridge National Laboratory

International Nuclear Information System (INIS)

Arnold, W.D.; Bostick, D.T.; Burgess, M.W.; Taylor, P.A.; Perona, J.J.; Kent, T.E.

1994-10-01

Improved centralized treatment methods are needed in the management of liquid low-level waste (LLLW) at Oak Ridge National Laboratory (ORNL). LLLW, which usually contains radioactive contaminants at concentrations up to millicurie-per-liter levels, has accumulated in underground storage tanks for over 10 years and has reached a volume of over 350,000 gal. These wastes have been collected since 1984 and are a complex mixture of wastes from past nuclear energy research activities. The waste is a highly alkaline 4-5 M NaNO 3 solution with smaller amounts of other salts. This type of waste will continue to be generated as a consequence of future ORNL research programs. Future LLLW (referred to as newly generated LLLW or NGLLLW) is expected to a highly alkaline solution of sodium carbonate and sodium hydroxide with a smaller concentration of sodium nitrate. New treatment facilities are needed to improve the manner in which these wastes are managed. These facilities must be capable of separating and reducing the volume of radioactive contaminants to small stable waste forms. Treated liquids must meet criteria for either discharge to the environment or solidification for onsite disposal. Laboratory testing was performed using simulated waste solutions prepared using the available characterization information as a basis. Testing was conducted to evaluate various methods for selective removal of the major contaminants. The major contaminants requiring removal from Melton Valley Storage Tank liquids are 90 Sr and 137 Cs. Principal contaminants in NGLLLW are 9O Sr, 137 Cs, and 106 Ru. Strontium removal testing began with literature studies and scoping tests with several ion-exchange materials and sorbents

Method for aqueous radioactive waste treatment

Science.gov (United States)

Bray, L.A.; Burger, L.L.

1994-03-29

Plutonium, strontium, and cesium found in aqueous waste solutions resulting from nuclear fuel processing are removed by contacting the waste solutions with synthetic zeolite incorporating up to about 5 wt % titanium as sodium titanate in an ion exchange system. More than 99.9% of the plutonium, strontium, and cesium are removed from the waste solutions. 3 figures.

Challenges when performing economic optimization of waste treatment: A review

International Nuclear Information System (INIS)

Juul, N.; Münster, M.; Ravn, H.; Söderman, M. Ljunggren

2013-01-01

Highlights: • Review of main optimization tools in the field of waste management. • Different optimization methods are applied. • Different fractions are analyzed. • There is focus on different parameters in different geographical regions. • More research is needed which encompasses both recycling and energy solutions. - Abstract: Strategic and operational decisions in waste management, in particular with respect to investments in new treatment facilities, are needed due to a number of factors, including continuously increasing amounts of waste, political demands for efficient utilization of waste resources, and the decommissioning of existing waste treatment facilities. Optimization models can assist in ensuring that these investment strategies are economically feasible. Various economic optimization models for waste treatment have been developed which focus on different parameters. Models focusing on transport are one example, but models focusing on energy production have also been developed, as well as models which take into account a plant’s economies of scale, environmental impact, material recovery and social costs. Finally, models combining different criteria for the selection of waste treatment methods in multi-criteria analysis have been developed. A thorough updated review of the existing models is presented, and the main challenges and crucial parameters that need to be taken into account when assessing the economic performance of waste treatment alternatives are identified. The review article will assist both policy-makers and model-developers involved in assessing the economic performance of waste treatment alternatives

Challenges when performing economic optimization of waste treatment: A review

Energy Technology Data Exchange (ETDEWEB)

Juul, N., E-mail: njua@dtu.dk [DTU Management, Risø Campus, Technical University of Denmark (Denmark); Münster, M., E-mail: maem@dtu.dk [DTU Management, Risø Campus, Technical University of Denmark (Denmark); Ravn, H., E-mail: hans.ravn@aeblevangen.dk [RAM-løse edb, Æblevangen 55, 2765 Smørum (Denmark); Söderman, M. Ljunggren, E-mail: maria.ljunggren@chalmers.se [Energy and Environment, Chalmers University of Technology, Gothenburg (Sweden); IVL Swedish Environmental Research Institute, Gothenburg (Sweden)

2013-09-15

Highlights: • Review of main optimization tools in the field of waste management. • Different optimization methods are applied. • Different fractions are analyzed. • There is focus on different parameters in different geographical regions. • More research is needed which encompasses both recycling and energy solutions. - Abstract: Strategic and operational decisions in waste management, in particular with respect to investments in new treatment facilities, are needed due to a number of factors, including continuously increasing amounts of waste, political demands for efficient utilization of waste resources, and the decommissioning of existing waste treatment facilities. Optimization models can assist in ensuring that these investment strategies are economically feasible. Various economic optimization models for waste treatment have been developed which focus on different parameters. Models focusing on transport are one example, but models focusing on energy production have also been developed, as well as models which take into account a plant’s economies of scale, environmental impact, material recovery and social costs. Finally, models combining different criteria for the selection of waste treatment methods in multi-criteria analysis have been developed. A thorough updated review of the existing models is presented, and the main challenges and crucial parameters that need to be taken into account when assessing the economic performance of waste treatment alternatives are identified. The review article will assist both policy-makers and model-developers involved in assessing the economic performance of waste treatment alternatives.

Surrogate formulations for thermal treatment of low-level mixed waste, Part II: Selected mixed waste treatment project waste streams

Energy Technology Data Exchange (ETDEWEB)

Bostick, W.D.; Hoffmann, D.P.; Chiang, J.M.; Hermes, W.H.; Gibson, L.V. Jr.; Richmond, A.A. [Martin Marietta Energy Systems, Inc., Oak Ridge, TN (United States); Mayberry, J. [Science Applications International Corp., Idaho Falls, ID (United States); Frazier, G. [Univ. of Tennessee, Knoxville, TN (United States)

1994-01-01

This report summarizes the formulation of surrogate waste packages, representing the major bulk constituent compositions for 12 waste stream classifications selected by the US DOE Mixed Waste Treatment Program. These waste groupings include: neutral aqueous wastes; aqueous halogenated organic liquids; ash; high organic content sludges; adsorbed aqueous and organic liquids; cement sludges, ashes, and solids; chloride; sulfate, and nitrate salts; organic matrix solids; heterogeneous debris; bulk combustibles; lab packs; and lead shapes. Insofar as possible, formulation of surrogate waste packages are referenced to authentic wastes in inventory within the DOE; however, the surrogate waste packages are intended to represent generic treatability group compositions. The intent is to specify a nonradiological synthetic mixture, with a minimal number of readily available components, that can be used to represent the significant challenges anticipated for treatment of the specified waste class. Performance testing and evaluation with use of a consistent series of surrogate wastes will provide a means for the initial assessment (and intercomparability) of candidate treatment technology applicability and performance. Originally the surrogate wastes were intended for use with emerging thermal treatment systems, but use may be extended to select nonthermal systems as well.

Surrogate formulations for thermal treatment of low-level mixed waste, Part II: Selected mixed waste treatment project waste streams

International Nuclear Information System (INIS)

Bostick, W.D.; Hoffmann, D.P.; Chiang, J.M.; Hermes, W.H.; Gibson, L.V. Jr.; Richmond, A.A.; Mayberry, J.; Frazier, G.

1994-01-01

This report summarizes the formulation of surrogate waste packages, representing the major bulk constituent compositions for 12 waste stream classifications selected by the US DOE Mixed Waste Treatment Program. These waste groupings include: neutral aqueous wastes; aqueous halogenated organic liquids; ash; high organic content sludges; adsorbed aqueous and organic liquids; cement sludges, ashes, and solids; chloride; sulfate, and nitrate salts; organic matrix solids; heterogeneous debris; bulk combustibles; lab packs; and lead shapes. Insofar as possible, formulation of surrogate waste packages are referenced to authentic wastes in inventory within the DOE; however, the surrogate waste packages are intended to represent generic treatability group compositions. The intent is to specify a nonradiological synthetic mixture, with a minimal number of readily available components, that can be used to represent the significant challenges anticipated for treatment of the specified waste class. Performance testing and evaluation with use of a consistent series of surrogate wastes will provide a means for the initial assessment (and intercomparability) of candidate treatment technology applicability and performance. Originally the surrogate wastes were intended for use with emerging thermal treatment systems, but use may be extended to select nonthermal systems as well

Review of the treatment of actinides-bearing radioactive wastes

International Nuclear Information System (INIS)

Krause, H.

1983-01-01

Actinides bearing wastes are produced above all in the course of irradiated nuclear fuel reprocessing and during fabrication of mixed oxide fuel elements. Particular attention in research and development work must be paid to this type of waste, mainly on account of its longevity. In practical application, the specific character of the actinides bearing wastes has been largely recognized. Nevertheless, definitions and methods of treatment generally accepted worldwide are still missing today. This has no bearing as yet on present day treatment of radioactive wastes. But by the time of application of the breeder technology at the latest a special treatment concept should be available which complies with the high actinide contents and short precooling periods of the wastes

Anaerobic digester for treatment of organic waste

Energy Technology Data Exchange (ETDEWEB)

Sharma, V. K. [Indian Insitute of Technology, Delhi (India)]|[ENEA, Centro Ricerche Trisaia, Matera (Italy); Fortuna, F.; Canditelli, M.; Cornacchia, G. [ENEA, Centro Ricerche Trisaia, Matera (Italy). Dipt. Ambiente; Farina, R. [ENEA, centro Ricerche ``Ezio Clementel``, Bologna (Italy). Dipt. Ambiente

1997-09-01

The essential features of both new and more efficient reactor systems and their appropriate applications for various organic waste management situations, description of several working plants are discussed in the present communication. It is hoped that significant development reported here would be useful in opening a new vista to the application of anaerobic biotechnology for the waste treatment of both low/high organic strength and specialized treatment for toxic substances, using appropriate anaerobic methods.

Waste water treatment by flotation

Directory of Open Access Journals (Sweden)

Camelia Badulescu

2005-11-01

Full Text Available The flotation is succesfully applied as a cleaning method of waste water refineries, textile fabrics (tissues, food industry, paper plants, oils plants, etc. In the flotation process with the released air, first of all, the water is saturated with air compressed at pressures between 0,3 – 3 bar, followed by the relaxed phenomenon of the air-water solution in a flotation cell with slowly flowing. The supersaturation could be applied in the waste water treatment. In this case the waste water, which is in the atmospheric equilibrum, is introduced in a closed space where the depression is 0,3 – 0,5 bar. Our paper presents the hypobaric flotation cell and the technological flow of cleaning of domestic waste waters

Treatment needs for greater-than-Class C low-level wastes

International Nuclear Information System (INIS)

Ross, W.A.; Brouns, R.A.; Burkholder, H.C.

1988-01-01

Greater-than-Class C (GTCC) radioactive wastes are those low-level wastes that exceed the 10CFR61 limits for shallow-land burial but are not within the historical definition of high-level wastes (i.e., spent fuel and first-cycle reprocessing wastes). The GTCC category can include all transuranic (TRU) wastes, although for the purposes of this paper, contact-handled defense TRU wastes are excluded because of the major efforts in the past decade to prepare them for disposal at the Waste Isolation Pilot Plant (WIPP). Thus, the GTCC category includes all high-activity and remote-handled TRU wastes regardless of origin. This paper defines the need for treatment of existing and projected GTCC low-level radioactive wastes in the United States. The sources, characteristics, treatment considerations, and methods for treatment are reviewed

Radiation treatment of wastes: A review

International Nuclear Information System (INIS)

Feates, F.S.; George, D.

1975-01-01

Since 1945 over 70 papers have been published on various applications of radiation to waste treatment. Work carried out up to 1970 showed consistently that radiation is effective in degrading organic matter in wastes, destroying pathogenic organisms, and enhancing the sedimentation and filterability of sludges, but at a cost about ten times that of conventional treatment methods. Increased cost of energy, scarcity of potable water, environmental awareness and consequent legislation, and technical developments may be changing the picture. For example, ozone, already being widely used as an alternative to chlorine for sterilization, is claimed to be produced by gamma-irradiation of air or oxygen at half the cost of electrical methods. Radiation may solve specific problems associated with industrial wastes and evidence is reported of synergistic effects with oxygen and chlorine. In-situ reactivation of carbon used as an absorbent for textile dye wastes has been observed, and is being further studied. Prototype plant for complete sterilization of sewage sludge for use as fertilizer is in operation. Safety precautions necessary if large radiation sources are used by non-technical operatives will also be considered. (author)

Proposal of an environmental performance index to assess solid waste treatment technologies

International Nuclear Information System (INIS)

Goulart Coelho, Hosmanny Mauro; Lange, Liséte Celina; Coelho, Lineker Max Goulart

2012-01-01

Highlights: ► Proposal of a new concept in waste management: Cleaner Treatment. ► Development of an index to assess quantitatively waste treatment technologies. ► Delphi Method was carried out so as to define environmental indicators. ► Environmental performance evaluation of waste-to-energy plants. - Abstract: Although the concern with sustainable development and environment protection has considerably grown in the last years it is noted that the majority of decision making models and tools are still either excessively tied to economic aspects or geared to the production process. Moreover, existing models focus on the priority steps of solid waste management, beyond waste energy recovery and disposal. So, in order to help the lack of models and tools aiming at the waste treatment and final disposal, a new concept is proposed: the Cleaner Treatment, which is based on the Cleaner Production principles. This paper focuses on the development and validation of the Cleaner Treatment Index (CTI), to assess environmental performance of waste treatment technologies based on the Cleaner Treatment concept. The index is formed by aggregation (summation or product) of several indicators that consists in operational parameters. The weights of the indicator were established by Delphi Method and Brazilian Environmental Laws. In addition, sensitivity analyses were carried out comparing both aggregation methods. Finally, index validation was carried out by applying the CTI to 10 waste-to-energy plants data. From sensitivity analysis and validation results it is possible to infer that summation model is the most suitable aggregation method. For summation method, CTI results were superior to 0.5 (in a scale from 0 to 1) for most facilities evaluated. So, this study demonstrates that CTI is a simple and robust tool to assess and compare the environmental performance of different treatment plants being an excellent quantitative tool to support Cleaner Treatment implementation.

Method of decomposing radioactive organic solvent wastes

International Nuclear Information System (INIS)

Uki, Kazuo; Ichihashi, Toshio; Hasegawa, Akira; Sato, Tatsuaki

1986-01-01

Purpose: To decompose radioactive organic solvent wastes or radioactive hydrocarbon solvents separated therefrom into organic materials under moderate conditions, as well as greatly decrease the amount of secondary wastes generated. Method: Radioactive organic solvent wastes comprising an organic phosphoric acid ester ingredient and a hydrocarbon ingredient as a diluent therefor, or radioactive hydrocarbon solvents separated therefrom are oxidatively decomposed by hydrogen peroxide in an aqueous phosphoric acid solution of phosphoric acid metal salts finally into organic materials to perform decomposing treatment for the radioactive organic solvent wastes. The decomposing reaction is carried out under relatively moderate conditions and cause less burden to facilities or the likes. Further, since the decomposed liquid after the treatment can be reused for the decomposing reaction as a catalyst solution secondary wastes can significantly be decreased. (Yoshihara, H.)

Innovative hazardous waste treatment technology

International Nuclear Information System (INIS)

Freeman, H.M.; Sferra, P.R.

1990-01-01

This book contains 21 various biodegradation techniques for hazardous waste treatment. Topics include: cyclic vertical water table movement for enhancement of in situ biodegradation of diesel fuel; enhanced biodegradation of petroleum hydrocarbons; and evaluation of aeration methods to bioremediate fuel-contaminated soils

The environmental impact of mine wastes - roles of microorganisms and their significance in treatment of mine wastes

International Nuclear Information System (INIS)

Ledin, M.; Pedersen, K.

1996-01-01

Mine wastes constitute a potential source of contamination to the environment, as heavy metals and acid are released in large amounts. A great variety of microorganisms has been found in mine wastes and microbiological processes are usually responsible for the environmental hazard created by mine wastes. However, microorganisms can also be used to retard the adverse impact of mine wastes on the environment. Conventionally, the mine drainage as well as the waste itself can be treated with alkali to increase pH and precipitate metals. The main drawback of this method is that it has to be continuously repeated to be fully effective. There may also be negative effects on beneficial microorganisms. Several other treatment methods have been developed to stop weathering processes thereby reducing the environmental impact of mine wastes. The other main approach is to treat the drainage water. Various methods aim at using microorganisms for this in natural or engineered systems. Recently, much interest has been focused on the use of natural or artificial wetlands for treatment. In general, the activity of microorganisms is neglected in the design of mine waste treatment systems, and the treatments are created merely from a technical point of view. This can result in situations where unexpected microbial processes take over, and, in the worst scenario, the overall effect is opposite to the desired

Developing a dependable approach for evaluating waste treatment data

International Nuclear Information System (INIS)

Gering, K.L.

1997-01-01

Decision makers involved with hazardous waste treatment issues are faced with the challenge of making objective evaluations concerning treatment formulations. This work utilizes an effectiveness factor (denoted as η) as the basis for waste treatment evaluations, which was recently developed for application to mixed waste treatability studies involving solidification and stabilization at the Idaho National Engineering and Environmental Laboratory. The effectiveness factor incorporates an arbitrary treatment criterion Φ, which in practice could be the Toxicity Characteristic Leaching Procedure, Unconfined Compressive Strength, Leachability Index, or any other criterion used to judge treatment performance. Three values for Φ are utilized when assessing a given treatment formulation: before treatment, after treatment, and a reference value (typically a treatment standard). The expression for η also incorporates the waste loading as the prime experimental parameter, and accounts for the contribution that each hazard has upon the overall treatment performance. Also discussed are general guidelines for numerical boundaries and statistical interpretations of treatment data. Case studies are presented that demonstrate the usefulness of the effectiveness factor and related numerical methods, where the typical hazards encountered are toxic metals within mixed waste

SECONDARY WASTE MANAGEMENT STRATEGY FOR EARLY LOW ACTIVITY WASTE TREATMENT

Energy Technology Data Exchange (ETDEWEB)

TW, CRAWFORD

2008-07-17

This study evaluates parameters relevant to River Protection Project secondary waste streams generated during Early Low Activity Waste operations and recommends a strategy for secondary waste management that considers groundwater impact, cost, and programmatic risk. The recommended strategy for managing River Protection Project secondary waste is focused on improvements in the Effiuent Treatment Facility. Baseline plans to build a Solidification Treatment Unit adjacent to Effluent Treatment Facility should be enhanced to improve solid waste performance and mitigate corrosion of tanks and piping supporting the Effiuent Treatment Facility evaporator. This approach provides a life-cycle benefit to solid waste performance and reduction of groundwater contaminants.

Offgas treatment for radioactive waste incinerators

International Nuclear Information System (INIS)

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

1980-01-01

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

Treatment of solid non-active wastes

International Nuclear Information System (INIS)

Chmielewska, E.

2008-01-01

In this part of the text-book treatment of solid non-active wastes is described. This part consist of following chapters: (1) Law on wastes; (2) Present situation in waste management; (3) Strategic tendencies of waste management; (4) Incineration (disposal of solid wastes); (5) Disposal; (6) Composting; (7) Treatment of sludge from sewage clarification plant; (8) Biodegradation; (9) Recycling of wastes (assessing of secondary raw materials). Legal aspects of treatment of solid non-active wastes is presented

Methods for removing transuranic elements from waste solutions

International Nuclear Information System (INIS)

Slater, S.A.; Chamberlain, D.B.; Connor, C.; Sedlet, J.; Srinivasan, B.; Vandegrift, G.F.

1994-11-01

This report outlines a treatment scheme for separating and concentrating the transuranic (TRU) elements present in aqueous waste solutions stored at Argonne National Laboratory (ANL). The treatment method selected is carrier precipitation. Potential carriers will be evaluated in future laboratory work, beginning with ferric hydroxide and magnetite. The process will result in a supernatant with alpha activity low enough that it can be treated in the existing evaporator/concentrator at ANL. The separated TRU waste will be packaged for shipment to the Waste Isolation Pilot Plant

Experiences with treatment of mixed waste

International Nuclear Information System (INIS)

Dziewinski, J.; Marczak, S.; Smith, W.H.; Nuttall, E.

1996-01-01

During its many years of research activities involving toxic chemicals and radioactive materials, Los Alamos National Laboratory (Los Alamos) has generated considerable amounts of waste. Much of this waste includes chemically hazardous components and radioisotopes. Los Alamos chose to use an electrochemical process for the treatment of many mixed waste components. The electro-chemical process, which the authors are developing, can treat a great variety of waste using one type of equipment built at a moderate expense. Such a process can extract heavy metals, destroy cyanides, dissolve contamination from surfaces, oxidize toxic organic compounds, separate salts into acids and bases, and reduce the nitrates. All this can be accomplished using the equipment and one crew of trained operating personnel. Results of a treatability study of chosen mixed wastes from Los Alamos Mixed Waste Inventory are presented. Using electrochemical methods cyanide and heavy metals bearing wastes were treated to below disposal limits

Experiences with treatment of mixed waste

Energy Technology Data Exchange (ETDEWEB)

Dziewinski, J.; Marczak, S.; Smith, W.H. [Los Alamos National Lab., NM (United States); Nuttall, E. [Univ. of New Mexico, Albuquerque, NM (United States). Chemical and Nuclear Engineering Dept.

1996-04-10

During its many years of research activities involving toxic chemicals and radioactive materials, Los Alamos National Laboratory (Los Alamos) has generated considerable amounts of waste. Much of this waste includes chemically hazardous components and radioisotopes. Los Alamos chose to use an electrochemical process for the treatment of many mixed waste components. The electro-chemical process, which the authors are developing, can treat a great variety of waste using one type of equipment built at a moderate expense. Such a process can extract heavy metals, destroy cyanides, dissolve contamination from surfaces, oxidize toxic organic compounds, separate salts into acids and bases, and reduce the nitrates. All this can be accomplished using the equipment and one crew of trained operating personnel. Results of a treatability study of chosen mixed wastes from Los Alamos Mixed Waste Inventory are presented. Using electrochemical methods cyanide and heavy metals bearing wastes were treated to below disposal limits.

Evaluation of site-generated radioactive waste treatment and disposal methods for the Yucca Mountain repository

International Nuclear Information System (INIS)

Subramanian, C.V.; Jardine, L.J.

1989-01-01

This study identifies the sources of radioactive wastes that may be generated at the proposed high-level waste (HLW) repository at Yucca Mountain, NV, estimates the waste quantities and characteristics, compares technologies available for waste treatment and disposal, and develops recommended concepts for site-generated waste treatment and disposal. The scope of this study is limited to operations during the emplacement phase, in which 70,000 MTU of high-level waste will be received and emplaced at the proposed repository. The evaluations consider all radioactive wastes generated during normal operations in surface and underground facilities. Wastes generated as a result of accidents are not addressed; accidents that could result in large quantities of radioactive waste are expected to occur very infrequently and temporary, portable systems could be used for any necessary cleanup. The results of this study can be used to develop more definitive plans for managing the site-generated wastes and as a basis for the design of associated facilities at the proposed repository

Thermal treatment of organic radioactive waste

International Nuclear Information System (INIS)

Chrubasik, A.; Stich, W.

1993-01-01

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

Independent review of inappropriate identification, storage and treatment methods of polychlorinated biphenyl waste streams

International Nuclear Information System (INIS)

1997-07-01

The purpose of the review was to evaluate incidents involving the inappropriate identification, storage, and treatment methods associated with polychlorinated biphenyl (PCB) waste streams originating from the V-tank system at the Test Area North (TAN). The team was instructed to perform a comprehensive review of Lockheed Martin Idaho Technologies Company (LMITCO's) compliance programs related to these incidents to assess the adequacy and effectiveness of the management program in all respects including: adequacy of the waste management program in meeting all LMITCO requirements and regulations; adequacy of policies, plans, and procedures in addressing and implementing all federal and state requirements and regulations; and compliance status of LMITCO, LMITCO contract team members, and LMITCO contract/team member subcontractor personnel with established PCB management policies, plans, and procedures. The V-Tanks are part of an intermediate waste disposal system and are located at the Technical Support Facility (TSF) at TAN at the Idaho National Engineering and Environmental Laboratory (INEEL). The IRT evaluated how a waste was characterized, managed, and information was documented; however, they did not take control of wastes or ensure followup was performed on all waste streams that may have been generated from the V-Tanks. The team has also subsequently learned that the Environmental Restoration (ER) program is revising the plans for the decontamination and decommissioning of the intermediate waste disposal system based on new information listed and PCB wastes. The team has not reviewed those in-process changes. The source of PCB in the V-Tank is suspected to be a spill of hydraulic fluid in 1968

Low-level radioactive wastes: Their treatment, handling, disposal

Energy Technology Data Exchange (ETDEWEB)

Straub, Conrad P [Robert A. Taft Sanitary Engineering Center, Radiological Health Research Activities, Cincinnati, OH(United States)

1964-07-01

The release of low level wastes may result in some radiation exposure to man and his surroundings. This book describes techniques of handling, treatment, and disposal of low-level wastes aimed at keeping radiation exposure to a practicable minimum. In this context, wastes are considered low level if they are released into the environment without subsequent control. This book is concerned with practices relating only to continuous operations and not to accidental releases of radioactive materials. It is written by use for those interested in low level waste disposal problems and particularly for the health physicist concerned with these problems in the field. It should be helpful also to water and sewage works personnel concerned with the efficiency of water and sewage treatment processes for the removal of radioactive materials; the personnel engaged in design, construction, licensing, and operation of treatment facilities; and to student of nuclear technology. After an introduction the following areas are discussed: sources, quantities and composition of radioactive wastes; collection, sampling and measurement; direct discharge to the water, soil and air environment; air cleaning; removal of radioactivity by water-treatment processes and biological processes; treatment on site by chemical precipitation , ion exchange and absorption, electrodialysis, solvent extraction and other methods; treatment on site including evaporation and storage; handling and treatment of solid wastes; public health implications. Appendices include a glossary; standards for protection against radiation; federal radiation council radiation protection guidance for federal agencies; site selection criteria for nuclear energy facilities.

The Hybrid Treatment Process for mixed radioactive and hazardous waste treatment

International Nuclear Information System (INIS)

Ross, W.A.; Kindle, C.H.

1992-06-01

This paper describes a new process for treating mixed hazardous and radioactive waste, commonly called mixed waste. The process is called the Hybrid Treatment Process (HTP), so named because it is built on the 20 years of experience with vitrification of wastes in melters, and the 12 years of experience with treatment of wastes by the in situ vitrification (ISV) process. It also uses techniques from several additional technologies. Mixed wastes are being generated by both the US Department of Energy (DOE) and by commercial sources. The wastes are those that contain both a hazardous waste regulated under the US Environmental Protection Agency's (EPA) Resource, Conservation, and Recovery Act (RCRA) regulations and a radioactive waste with source, special nuclear, or byproduct materials. The dual regulation of the wastes increases the complexity of the treatment, handling, and storage of the waste. The DOE is the largest holder and generator of mixed waste. Its mixed wastes are classified as either high-level, transuranic (TRU), or low-level waste (LLW). High-level mixed wastes will be treated in vitrification plants. Transuranic wastes may be disposed of without treatment by obtaining a no-migration variance from the EPA. Lowlevel wastes, however, will require treatment, but treatment systems with sufficient capacity are not yet available to DOE. Various facilities are being proposed for the treatment of low-level waste. The concept described in this paper represents one option for establishing that treatment capacity

Handling and Treatment of Poultry Hatchery Waste: A Review

Directory of Open Access Journals (Sweden)

Belinda Rodda

2011-01-01

Full Text Available A literature review was undertaken to identify methods being used to handle and treat hatchery waste. Hatchery waste can be separated into solid waste and liquid waste by centrifuging or by using screens. Potential methods for treating hatchery waste on site include use of a furnace to heat the waste to produce steam to run a turbine generator or to use an in line composter to stabilise the waste. There is also potential to use anaerobic digestion at hatcheries to produce methane and fertilisers. Hatcheries disposing wastewater into lagoons could establish a series of ponds where algae, zooplankton and fish utilise the nutrients using integrated aquaculture which cleans the water making it more suitable for irrigation. The ideal system to establish in a hatchery would be to incorporate separation and handling equipment to separate waste into its various components for further treatment. This would save disposal costs, produce biogas to reduce power costs at plants and produce a range of value added products. However the scale of operations at many hatcheries is too small and development of treatment systems may not be viable.

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

CERN Document Server

American Society for Testing and Materials. Philadelphia

2003-01-01

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

Solid waste electron beam treatment

International Nuclear Information System (INIS)

Chmielewski, A.G.

1998-01-01

The possible applications of electron accelerators for solid waste treatment are discussed in the report. The elaborated technologies allow to recycle of materials (e.g. cellulosic materials in municipal waste), improve their hygienic standards (agricultural usage of sludge from municipal waste water treatment) and reduce harmful to environment chemical usage (cellulose degradation). These are environment friendly advanced technologies which meets demands waste recycling. (author)

Solid waste electron beam treatment

Energy Technology Data Exchange (ETDEWEB)

Chmielewski, A G

1998-07-01

The possible applications of electron accelerators for solid waste treatment are discussed in the report. The elaborated technologies allow to recycle of materials (e.g., cellulosic materials in municipal waste), improve their hygienic standards (agricultural usage of sludge from municipal waste water treatment) and reduce harmful to environment chemical usage (cellulose degradation). These are environment friendly advanced technologies which meets demands waste recycling. (author)

Thermal treatment for TRU waste sorting

International Nuclear Information System (INIS)

Sasaki, Toshiki; Aoyama, Yoshio; Yamashita, Toshiyuki

2009-03-01

A thermal treatment that can automatically unpack TRU waste and remove hazardous materials has been developed to reduce the risk of radiation exposure and save operation cost. The thermal treatment is a process of removing plastic wrapping and hazardous material from TRU waste by heating waste at 500 to 700degC. Plastic wrappings of simulated wastes were removed using a laboratory scale thermal treatment system. Celluloses and isoprene rubbers that must be removed from waste for disposal were pyrolyzed by the treatment. Although the thermal treatment can separate lead and aluminum from the waste, a further technical development is needed to separate lead and aluminum. A demonstration scale thermal treatment system that comprises a rotary kiln with a jacket water cooler and a rotating inner cage for lead and aluminum separation is discussed. A clogging prevention system against zinc chloride, a lead and aluminum accumulation system, and a detection system for spray cans that possibly cause explosion and fire are also discussed. Future technology development subjects for the TRU waste thermal treatment system are summarized. (author)

Methodology development for radioactive waste treatment of CDTN/BR - liquid low-level radioactive wastes

International Nuclear Information System (INIS)

Morais, Carlos Antonio de

1996-01-01

The radioactive liquid wastes generated in Nuclear Technology Development Centre (CDTN) were initially treated by precipitation/filtration and then the resulting wet solid wastes were incorporated in cement. These wastes were composed of different chemicals and different radioactivities and were generated by different sectors. The objective of the waste treatment method was to obtain minimum wet solid waste volume and decontamination and minimum operational cost. The composition of the solid wastes were taken into consideration for compatible cementation process. Approximately 5,400 litres of liquid radioactive wastes were treated by this process during 1992-1995. The volume reduction was 1/24 th and contained 20% solids. (author)

Method of processing liquid wastes

International Nuclear Information System (INIS)

Naba, Katsumi; Oohashi, Takeshi; Kawakatsu, Ryu; Kuribayashi, Kotaro.

1980-01-01

Purpose: To process radioactive liquid wastes with safety by distillating radioactive liquid wastes while passing gases, properly treating the distillation fractions, adding combustible and liquid synthetic resin material to the distillation residues, polymerizing to solidify and then burning them. Method: Radioactive substance - containing liquid wastes are distillated while passing gases and the distillation fractions containing no substantial radioactive substances are treated in an adequate method. Synthetic resin material, which may be a mixture of polymer and monomer, is added together with a catalyst to the distillation residues containing almost of the radioactive substances to polymerize and solidify. Water or solvent in such an extent as not hindering the solidification may be allowed if remained. The solidification products are burnt for facilitating the treatment of the radioactive substances. The resin material can be selected suitably, methacrylate syrup (mainly solution of polymethylmethacrylate and methylmethacrylate) being preferred. (Seki, T.)

DOE evaluates nine alternative thermal technologies for treatment of mixed waste

International Nuclear Information System (INIS)

Anon.

1995-01-01

In June 1993, the U.S. Department of Energy's (DOE's) Office of Technology Development commissioned a study to evaluate 19 thermal technologies for treating DOE's mixed waste. The study was divided into two phases: Phase I evaluated ten conventional incineration techniques (primarily rotary kiln), and Phase II looked at nine innovative, alternative thermal treatment technologies. The treatment processes were evaluated as part of an integrated waste treatment system, which would include all of the facilities, equipment, and methods required to treat and dispose DOE mixed waste. The relative merits and life-cycle costs were then developed for each of the 19 waste treatment systems evaluated. The study also identified the additional research and development, demonstration, and testing/evaluation steps that would be necessary for the waste treatment systems to successfully treat DOE mixed waste. 3 tabs., 2 refs

Treatment Study Plan for Nitrate Salt Waste Remediation Revision 1.0

Energy Technology Data Exchange (ETDEWEB)

Juarez, Catherine L. [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Funk, David John [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Vigil-Holterman, Luciana R. [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Naranjo, Felicia Danielle [Los Alamos National Lab. (LANL), Los Alamos, NM (United States)

2016-03-07

The two stabilization treatment methods that are to be examined for their effectiveness in the treatment of both the unremediated and remediated nitrate salt wastes include (1) the addition of zeolite and (2) cementation. Zeolite addition is proposed based on the results of several studies and analyses that specifically examined the effectiveness of this process for deactivating nitrate salts. Cementation is also being assessed because of its prevalence as an immobilization method used for similar wastes at numerous facilities around the DOE complex, including at Los Alamos. The results of this Treatment Study Plan will be used to provide the basis for a Resource Conservation and Recovery Act (RCRA) permit modification request of the LANL Hazardous Waste Facility Permit for approval by the New Mexico Environment Department-Hazardous Waste Bureau (NMED-HWB) of the proposed treatment process and the associated facilities.

Hanford Tank Waste - Near Source Treatment of Low Activity Waste

International Nuclear Information System (INIS)

Ramsey, William Gene

2013-01-01

Abstract only. Treatment and disposition of Hanford Site waste as currently planned consists of 100+ waste retrievals, waste delivery through up to 8+ miles of dedicated, in-ground piping, centralized mixing and blending operations- all leading to pre-treatment combination and separation processes followed by vitrification at the Hanford Tank Waste Treatment and Immobilization Plant (WTP). The sequential nature of Tank Farm and WTP operations requires nominally 15-20 years of continuous operations before all waste can be retrieved from many Single Shell Tanks (SSTs). Also, the infrastructure necessary to mobilize and deliver the waste requires significant investment beyond that required for the WTP. Treating waste as closely as possible to individual tanks or groups- as allowed by the waste characteristics- is being investigated to determine the potential to 1) defer, reduce, and/or eliminate infrastructure requirements, and 2) significantly mitigate project risk by reducing the potential and impact of single point failures. The inventory of Hanford waste slated for processing and disposition as LAW is currently managed as high-level waste (HLW), i.e., the separation of fission products and other radionuclides has not commenced. A significant inventory of this waste (over 20M gallons) is in the form of precipitated saltcake maintained in single shell tanks, many of which are identified as potential leaking tanks. Retrieval and transport (as a liquid) must be staged within the waste feed delivery capability established by site infrastructure and WTP. Near Source treatment, if employed, would provide for the separation and stabilization processing necessary for waste located in remote farms (wherein most of the leaking tanks reside) significantly earlier than currently projected. Near Source treatment is intended to address the currently accepted site risk and also provides means to mitigate future issues likely to be faced over the coming decades. This paper

Bulky waste quantities and treatment methods in Denmark

DEFF Research Database (Denmark)

Larsen, Anna Warberg; Petersen, Claus; Christensen, Thomas Højlund

2012-01-01

were identified of which ten were recyclable and constituted 50–60% of the total quantity. The others were combustible waste for incineration (30–40%) and non-combustible waste for landfilling (10%). The largest fractions by mass were combustible waste, bricks and tile, concrete, non-combustible waste....... In addition a sorting analysis was conducted on combustible waste, which is a major fraction of bulky waste in Denmark. The generation of bulky waste was found to be 150–250 kg capita−1 year−1, and 90% of the waste was collected at recycling centres; the rest through kerbside collection. Twelve main fractions......, wood, and metal scrap, which together made up more than 90% of the total waste amounts. The amount of combustible waste could be significantly reduced through better sorting. Many of the waste fractions consisted of composite products that underwent thorough separation before being recycled...

Radiation chemical studies on the treatment of waste water

International Nuclear Information System (INIS)

Sakumoto, Akihisa; Miyata, Teijiro; Arai, Michimasa; Arai, Hidehiko

1982-10-01

The radiation induced reaction in aqueous solution was studied to develope the radiation treatment as a new technique for waste water and to elevate the effectiveness of radiation. The effectiveness of radiation was enhanced by combination of radiation induced reaction with conventional methods such as biological treatment and coagulation treatment. The synergistic effect of radiation and ozone was studied by using phenol and ethylene glycol. The chain reaction was observed in the radiation induced oxidation. The combination of radiation and ozone is considered to be one of the most useful method. In this report, the mechanism of each reaction and the applicability of the reaction to the treatment of waste water are discussed. (author)

Method of solidifying radioactive waste

International Nuclear Information System (INIS)

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

1988-01-01

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

Choosing solidification or vitrification for low-level radioactive and mixed waste treatment

International Nuclear Information System (INIS)

Gimpel, R.F.

1992-01-01

Solidification (making concrete) and vitrification (making glass) are frequently the treatment methods recommended for treating inorganic or radioactive wastes. Solidification is generally perceived as the most economical treatment method. Whereas, vitrification is considered (by many) as the most effective of all treatment methods. Unfortunately, vitrification has acquired the stigma that it is too expensive to receive further consideration as an alternative to solidification in high volume treatment applications. Ironically, economic studies, as presented in this paper, show that vitrification may be more competitive in some high volume applications. Ex-situ solidification and vitrification are the competing methods for treating in excess of 450 000m 3 of low-level radioactive and mixed waste at the Fernald Environmental Management Project (FEMP or simply, Fernald) located near Cincinnati, Ohio. This paper summarizes how Fernald is choosing between solidification and vitrification as the primary waste treatment method

Choosing solidification or vitrification for low-level radioactive and mixed waste treatment

International Nuclear Information System (INIS)

Gimpel, R.F.

1992-01-01

Solidification (making concrete) and vitrification (making glass) are frequently the treatment methods recommended for treating inorganic or radioactive wastes. Solidification is generally perceived as the most economical treatment method. Whereas, vitrification is considered (by many) as the most effective of all treatment methods. Unfortunately, vitrification has acquired the stigma that it is too expensive to receive further consideration as an alternative to solidification in high volume treatment applications. Ironically, economic studies, as presented in this paper, show that vitrification may be more competitive in some high volume applications. Ex-situ solidification and vitrification are the competing methods for treating in excess of 450,000 m 3 of low-level radioactive and mixed waste at the Fernald Environmental Management Project (FEMP or simply, Fernald) located near Cincinnati, Ohio. This paper summarized how Fernald is choosing between solidification and vitrification as the primary waste treatment method

Method of decomposing treatment for radioactive organic phosphate wastes

International Nuclear Information System (INIS)

Uki, Kazuo; Ichihashi, Toshio; Hasegawa, Akira; Sato, Tatsuaki

1985-01-01

Purpose: To decompose the organic phosphoric-acid ester wastes containing radioactive material, which is produced from spent fuel reprocessing facilities, into inorganic materials using a simple device, under moderate conditions and at high decomposing ratio. Method: Radioactive organic phosphate wates are oxidatively decomposed by H 2 O 2 in an aqueous phosphoric-acid solution of metal phosphate salts. Copper phosphates are used as the metal phosphate salts and the decomposed solution of the radioactive organic phosphate wastes is used as the aqueous solution of the copper phosphate. The temperature used for the oxidizing decomposition ranges from 80 to 100 0 C. (Ikeda, J.)

Safety Evaluation for Hull Waste Treatment Process in JNC

International Nuclear Information System (INIS)

Kojima, H.; Kurakata, K.

2002-01-01

Hull wastes and some scrapped equipment are typical radioactive wastes generated from reprocessing process in Tokai Reprocessing Plant (TRP). Because hulls are the wastes remained in the fuel shearing and dissolution, they contain high radioactivity. Japan Nuclear Cycle Development Institute (JNC) has started the project of Hull Waste Treatment Facility (HWTF) to treat these solid wastes using compaction and incineration methods since 1993. It is said that Zircaloy fines generated from compaction process might burn and explode intensely. Therefore explosive conditions of the fines generated in compaction process were measured. As these results, it was concluded that the fines generated from the compaction process were not hazardous material. This paper describes the outline of the treatment process of hulls and results of safety evaluation

Mixed waste treatment model: Basis and analysis

International Nuclear Information System (INIS)

Palmer, B.A.

1995-09-01

The Department of Energy's Programmatic Environmental Impact Statement (PEIS) required treatment system capacities for risk and cost calculation. Los Alamos was tasked with providing these capacities to the PEIS team. This involved understanding the Department of Energy (DOE) Complex waste, making the necessary changes to correct for problems, categorizing the waste for treatment, and determining the treatment system requirements. The treatment system requirements depended on the incoming waste, which varied for each PEIS case. The treatment system requirements also depended on the type of treatment that was desired. Because different groups contributing to the PEIS needed specific types of results, we provided the treatment system requirements in a variety of forms. In total, some 40 data files were created for the TRU cases, and for the MLLW case, there were 105 separate data files. Each data file represents one treatment case consisting of the selected waste from various sites, a selected treatment system, and the reporting requirements for such a case. The treatment system requirements in their most basic form are the treatment process rates for unit operations in the desired treatment system, based on a 10-year working life and 20-year accumulation of the waste. These results were reported in cubic meters and for the MLLW case, in kilograms as well. The treatment system model consisted of unit operations that are linked together. Each unit operation's function depended on the input waste streams, waste matrix, and contaminants. Each unit operation outputs one or more waste streams whose matrix, contaminants, and volume/mass may have changed as a result of the treatment. These output streams are then routed to the appropriate unit operation for additional treatment until the output waste stream meets the treatment requirements for disposal. The total waste for each unit operation was calculated as well as the waste for each matrix treated by the unit

Treatment and storage of radioactive wastes at Institute for Energy Technology, Kjeller, Norway and a short survey of non-radioactive hazardous wastes in Norway

International Nuclear Information System (INIS)

Lundby, J.E.

1988-08-01

The treatment and storage of low-level and intermediate-level radioactive wastes in Norway is described. A survey of non-radioactive hazardous wastes and planned processing methods for their treatment in Norway is given. It seems that processing methods developed for radioactive wastes to a greater extent could be adopted to hazardous wastes, and that an increased interdisciplinary waste cooperation could be a positive contribution to the solution of the hazardous waste problems

A process for treatment of mixed waste containing chemical plating wastes

International Nuclear Information System (INIS)

Anast, K.R.; Dziewinski, J.; Lussiez, G.

1995-01-01

The Waste Treatment and Minimization Group at Los Alamos National Laboratory has designed and will be constructing a transportable treatment system to treat low-level radioactive mixed waste generated during plating operations. The chemical and plating waste treatment system is composed of two modules with six submodules, which can be trucked to user sites to treat a wide variety of aqueous waste solutions. The process is designed to remove the hazardous components from the waste stream, generating chemically benign, disposable liquids and solids with low level radioactivity. The chemical and plating waste treatment system is designed as a multifunctional process capable of treating several different types of wastes. At this time, the unit has been the designated treatment process for these wastes: Destruction of free cyanide and metal-cyanide complexes from spent plating solutions; destruction of ammonia in solution from spent plating solutions; reduction of Cr VI to Cr III from spent plating solutions, precipitation, solids separation, and immobilization; heavy metal precipitation from spent plating solutions, solids separation, and immobilization, and acid or base neutralization from unspecified solutions

Alternatives for the treatment and disposal of healthcare wastes in developing countries

International Nuclear Information System (INIS)

Diaz, L.F.; Savage, G.M.; Eggerth, L.L.

2005-01-01

Waste production in healthcare facilities in developing countries has brought about a variety of concerns due to the use of inappropriate methods of managing the wastes. Inappropriate treatment and final disposal of the wastes can lead to adverse impacts to public health, to occupational health and safety, and to the environment. Unfortunately, most economically developing countries suffer a variety of constraints to adequately managing these wastes. Generally in developing countries, few individuals in the staff of the healthcare facility are familiar with the procedures required for a proper waste management program. Furthermore, the management of wastes usually is delegated to poorly educated laborers who perform most activities without proper guidance and insufficient protection. This paper presents some of the most common treatment and disposal methods utilized in the management of infectious healthcare wastes in developing countries. The methods discussed include: autoclave; microwave; chemical disinfection; combustion (low-, medium-, and high-technology); and disposal on the ground (dump site, controlled landfill, pits, and sanitary landfill). Each alternative for treatment and disposal is explained, including a description of the types of wastes that can and cannot be treated. Background information on the technologies also is included in order to provide information to those who may not be familiar with the details of each alternative. In addition, a brief presentation of some of the emissions from each of the treatment and disposal alternatives is presented

Improvement for waste water treatment process of a uranium deposite and its effect

International Nuclear Information System (INIS)

Huang Jimao

2013-01-01

Uranium was recovered from alkaline uranium ores by heap leaching and traditional agitation leaching methods at a uranium mine, and the waste water (including waste water produced in hydrometallurgy process and mine drainage) was treated by using chemical precipitation method and chemical precipitation loading method. It was found that the removal rate of uranium by the waste water treatment process was not satisfactory after one year's run. So, the waste water treatment process was improved. After the improvement, removal rate of CO 3 2- ,HCO 3 - , U and Ra was enhanced and the treated waste water reached the standard of discharge. (author)

Preliminary analysis of treatment strategies for transuranic wastes from reprocessing plants

International Nuclear Information System (INIS)

Ross, W.A.; Schneider, K.J.; Swanson, J.L.; Yasutake, K.M.; Allen, R.P.

1985-07-01

This document provides a comparison of six treatment options for transuranic wastes (TRUW) resulting from the reprocessing of commercial spent fuel. Projected transuranic waste streams from the Barnwell Nuclear Fuel Plant (BNFP), the reference fuel reprocessing plant in this report, were grouped into the five categories of hulls and hardware, failed equipment, filters, fluorinator solids, and general process trash (GPT) and sample and analytical cell (SAC) wastes. Six potential treatment options were selected for the five categories of waste. These options represent six basic treatment objectives: (1) no treatment, (2) minimum treatment (compaction), (3) minimum number of processes and products (cementing or grouting), (4) maximum volume reduction without decontamination (melting, incinerating, hot pressing), (5) maximum volume reduction with decontamination (decontamination, treatment of residues), and (6) noncombustible waste forms (melting, incinerating, cementing). Schemes for treatment of each waste type were selected and developed for each treatment option and each type of waste. From these schemes, transuranic waste volumes were found to vary from 1 m 3 /MTU for no treatment to as low as 0.02 m 3 /MTU. Based on conceptual design requirements, life-cycle costs were estimated for treatment plus on-site storage, transportation, and disposal of both high-level and transuranic wastes (and incremental low-level wastes) from 70,000 MTU. The study concludes that extensive treatment is warranted from both cost and waste form characteristics considerations, and that the characteristics of most of the processing systems used are acceptable. The study recommends that additional combinations of treatment methods or strategies be evaluated and that in the interim, melting, incineration, and cementing be further developed for commercial TRUW. 45 refs., 9 figs., 32 tabs

Preliminary analysis of treatment strategies for transuranic wastes from reprocessing plants

Energy Technology Data Exchange (ETDEWEB)

Ross, W.A.; Schneider, K.J.; Swanson, J.L.; Yasutake, K.M.; Allen, R.P.

1985-07-01

This document provides a comparison of six treatment options for transuranic wastes (TRUW) resulting from the reprocessing of commercial spent fuel. Projected transuranic waste streams from the Barnwell Nuclear Fuel Plant (BNFP), the reference fuel reprocessing plant in this report, were grouped into the five categories of hulls and hardware, failed equipment, filters, fluorinator solids, and general process trash (GPT) and sample and analytical cell (SAC) wastes. Six potential treatment options were selected for the five categories of waste. These options represent six basic treatment objectives: (1) no treatment, (2) minimum treatment (compaction), (3) minimum number of processes and products (cementing or grouting), (4) maximum volume reduction without decontamination (melting, incinerating, hot pressing), (5) maximum volume reduction with decontamination (decontamination, treatment of residues), and (6) noncombustible waste forms (melting, incinerating, cementing). Schemes for treatment of each waste type were selected and developed for each treatment option and each type of waste. From these schemes, transuranic waste volumes were found to vary from 1 m/sup 3//MTU for no treatment to as low as 0.02 m/sup 3//MTU. Based on conceptual design requirements, life-cycle costs were estimated for treatment plus on-site storage, transportation, and disposal of both high-level and transuranic wastes (and incremental low-level wastes) from 70,000 MTU. The study concludes that extensive treatment is warranted from both cost and waste form characteristics considerations, and that the characteristics of most of the processing systems used are acceptable. The study recommends that additional combinations of treatment methods or strategies be evaluated and that in the interim, melting, incineration, and cementing be further developed for commercial TRUW. 45 refs., 9 figs., 32 tabs.

Method of processing radioactive wastes

International Nuclear Information System (INIS)

Katada, Katsuo.

1986-01-01

Purpose: To improve the management for radioactive wastes containers thereby decrease the amount of stored matters by arranging the radioactive wastes containers in the order of their radioactivity levels. Method: The radiation doses of radioactive wastes containers arranged in the storing area before volume-reducing treatment are previously measured by a dosemeter. Then, a classifying machine is actuated to hoist the containers in the order to their radiation levels and the containers are sent out passing through conveyor, surface contamination gage, weight measuring device and switcher to a volume-reducing processing machine. The volume-reduced products are packed each by several units to the storing containers. Thus, the storing containers after stored for a certain period of time can be transferred in an assembled state. (Kawakami, Y.)

Waste management system alternatives for treatment of wastes from spent fuel reprocessing

International Nuclear Information System (INIS)

McKee, R.W.; Swanson, J.L.; Daling, P.M.

1986-09-01

This study was performed to help identify a preferred TRU waste treatment alternative for reprocessing wastes with respect to waste form performance in a geologic repository, near-term waste management system risks, and minimum waste management system costs. The results were intended for use in developing TRU waste acceptance requirements that may be needed to meet regulatory requirements for disposal of TRU wastes in a geologic repository. The waste management system components included in this analysis are waste treatment and packaging, transportation, and disposal. The major features of the TRU waste treatment alternatives examined here include: (1) packaging (as-produced) without treatment (PWOT); (2) compaction of hulls and other compactable wastes; (3) incineration of combustibles with cementation of the ash plus compaction of hulls and filters; (4) melting of hulls and failed equipment plus incineration of combustibles with vitrification of the ash along with the HLW; (5a) decontamination of hulls and failed equipment to produce LLW plus incineration and incorporation of ash and other inert wastes into HLW glass; and (5b) variation of this fifth treatment alternative in which the incineration ash is incorporated into a separate TRU waste glass. The six alternative processing system concepts provide progressively increasing levels of TRU waste consolidation and TRU waste form integrity. Vitrification of HLW and intermediate-level liquid wastes (ILLW) was assumed in all cases

Hazardous waste treatment facility and skid-mounted treatment systems at Los Alamos

International Nuclear Information System (INIS)

Lussiez, G.W.; Zygmunt, S.J.

1993-01-01

To centralize treatment, storage, and staging areas for hazardous wastes, Los Alamos National Laboratory has designed a 12,000-ft 2 hazardous waste treatment facility. The facility will house a treatment room for each of four kinds of wastes: nonradioactive characteristic wastes, nonradioactive listed wastes radioactive characteristic wastes, and radioactive listed wastes. The facility will be used for repacking labpacks, bulking small organic waste volumes, processing scintillation vials, treating reactives such as lithium hydride and pyrophoric uranium, treating contaminated solids such as barium sand, and treating plating wastes. The treated wastes will then be appropriately disposed of. This report describes the integral features of the hazardous waste treatment facility

Treatment of low- and intermediate-level liquid radioactive wastes

International Nuclear Information System (INIS)

1984-01-01

This report aims at giving the reader details of the experience gained in the treatment of both low- and intermediate-level radioactive liquid wastes. The treatment comprises those operations to remove radioactivity from the wastes and those that change only its chemical composition, so as to permit its discharge. Considerable experience has been accumulated in the satisfactory treatment of such wastes. Although there are no universally accepted definitions for low- and intermediate-level liquid radioactive wastes, the IAEA classification (see section 3.2) is used in this report. The two categories differ from one another in the fact that for low-level liquids the actual radiation does not require shielding during normal handling of the wastes. Liquid wastes which are not considered in this report are those from mining and milling operations and the high-level liquid wastes resulting from fuel reprocessing. These are referred to in separate IAEA reports. Likewise, wastes from decommissioning operations are not within the scope of this report. Apart from the description of existing methods and facilities, this report is intended to provide advice to the reader for the selection of appropriate solutions to waste management problems. In addition, new and promising techniques which are either being investigated or being considered for the future are discussed

Sustainable treatment of municipal waste water

DEFF Research Database (Denmark)

Hansen, Peter Augusto; Larsen, Henrik Fred

The main goal of the EU FP6 NEPTUNE program is to develop new and improve existing waste water treatment technologies (WWTT) and sludge handling technologies for municipal waste water, in accordance with the concepts behind the EU Water Framework Directive. As part of this work, the project.......e. heavy metals, pharmaceuticals and endocrine disruptors) in the waste water. As a novel approach, the potential ecotoxicity and human toxicity impacts from a high number of micropollutants and the potential impacts from pathogens will be included. In total, more that 20 different waste water and sludge...... treatment technologies are to be assessed. This paper will present the first LCA results from running existing life cycle impact assessment (LCIA) methodology on some of the waste water treatment technologies. Keywords: Sustainability, LCA, micropollutants, waste water treatment technologies....

Membrane Treatment of Liquid Salt Bearing Radioactive Wastes

International Nuclear Information System (INIS)

Dmitriev, S. A.; Adamovich, D. V.; Demkin, V. I.; Timofeev, E. M.

2003-01-01

The main fields of introduction and application of membrane methods for preliminary treatment and processing salt liquid radioactive waste (SLRW) can be nuclear power stations (NPP) and enterprises on atomic submarines (AS) utilization. Unlike the earlier developed technology for the liquid salt bearing radioactive waste decontamination and concentrating this report presents the new enhanced membrane technology for the liquid salt bearing radioactive waste processing based on the state-of-the-art membrane unit design, namely, the filtering units equipped with the metal-ceramic membranes of ''TruMem'' brand, as well as the electrodialysis and electroosmosis concentrators. Application of the above mentioned units in conjunction with the pulse pole changer will allow the marked increase of the radioactive waste concentrating factor and the significant reduction of the waste volume intended for conversion into monolith and disposal. Besides, the application of the electrodialysis units loaded with an ion exchange material at the end polishing stage of the radioactive waste decontamination process will allow the reagent-free radioactive waste treatment that meets the standards set for the release of the decontaminated liquid radioactive waste effluents into the natural reservoirs of fish-farming value

Safety Aspects of Nuclear Waste Treatment

International Nuclear Information System (INIS)

Glubrecht, H.

1986-01-01

In the nuclear fuel cycle - like in most other industrial processes - some waste is produced which can be harmful to the environment and has to be stored safely and isolated from the Biosphere. This radioactive waste can be compared with toxic chemical waste under many aspects, but it has some special features, some of which make its handling more difficult, others make it easier. The difficulties are that radioactive waste does not only affect living organisms after incorporation, but also from some distance through its radiation. Therefore this waste has not only to be encapsuled, but also shielded. At higher concentrations radioactive waste produces heat and this has to be continuously derived from the storage area. On the other hand the control of even extremely small amounts of radioactive waste is very much easier than that of toxic chemical waste due to the high sensitivity of radiation detection methods. Furthermore radioactive waste is not persistent like most of the chemical waste. Of course some components will decay only after millennia, but a high percentage of radioactive waste becomes inactive after days, weeks or years. An important feature of safety aspects related to nuclear waste is the fact that problems of its treatment and storage have been discussed from the very beginning of Nuclear Energy Technology - what has not been the case in relation to most other industrial wastes

FY 1995 separation studies for liquid low-level waste treatment at Oak Ridge National Laboratory

International Nuclear Information System (INIS)

Bostick, D.T.; Arnold, W.D.; Burgess, M.W.

1995-01-01

During FY 1995, studies were continued to develop improved methods for centralized treatment of liquid low-level waste (LLLW) at Oak Ridge National Laboratory (ORNL). Focus in this reporting period was on (1) identifying the parameters that affect the selective removal of 90 Sr and 137 Cs, two of the principal radioactive contaminants expected in the waste; (2) validating the effectiveness of the treatment methods by testing an ac Melton Valley Storage Tank (MVST) supernate; (3) evaluating the optimum solid/liquid separation techniques for the waste; (4) identifying potential treatment methods for removal of technetium from LLLW; and (5) identifying potential methods for stabilizing the high-activity secondary solid wastes generated by the treatment

The Assessment of Radioactive Liquid Waste Treatment Generated From The Fuel Reprocessing Plant Using Chemical Coagulation Method

International Nuclear Information System (INIS)

Kuncoro Arief, H; M Birmano, Dj

1998-01-01

Reprocessing of nuclear spent fuel produced 8 lot of radioactive liquid waste still bearing uranium and transuranium. The assessment of the radioactive liquid waste treatment with FeCI 3 as coagulant has been done. Decontamination factor and separation efficiency can be calculated from known activities of initial and post-treatment wastes. It can be concluded that some factors i.e. pH of treatment process, quantity of coagulant, mixing rate, and mixing time have influenced the treatment product

Mixed waste treatment options for wastes generated at the Idaho National Engineering Laboratory

International Nuclear Information System (INIS)

Garcia, E.C.

1991-01-01

The Idaho National Engineering Laboratory has generated mixed wastes (MWs) during its daily operations. MWs contain both radioactive and hazardous components, as defined by the Department of Energy and the Environmental Protection Agency. Treatment and disposal of stored MWs, as well as future generated MWs, are required to meet all regulations specified by the regulating agencies. This report reviews proven and emerging technologies that can treat MWs. It also provides a method for selection of the appropriate technology for treatment of a particular waste stream. The report selects for further consideration various treatments that can be used to treat MWs that fall under Land Disposal Restrictions. The selection methodology was used to arrive at these treatments. 63 refs., 7 figs., 23 tabs

An innovative treatment method for an aqueous waste from the enhanced oil recovery process

International Nuclear Information System (INIS)

Alimahmoodi, M.; Mulligan, C.N.

2009-01-01

Anaerobic treatment was evaluated to determine its effectiveness in treating a waste stream from the process of Enhanced Oil Recovery (EOR) to remove solubilized CO 2 (98%) and petroleum hydrocarbons (83%) using formate (2 g/L) and sucrose (2.5 g/L) as electron donors in two consecutive reactors. The method of evolutionary operation (EVOP) factorial design was applied to optimize the system and the net energy ratio (NER) of 3.7 was calculated for the system which showed a sustainable biogas production. This method is less complex than other competitive methods, and in addition to its low energy requirements, it can produce CH 4 from CO 2 as a clean source of energy. (author)

Final treatment of liquid radioactive wastes

International Nuclear Information System (INIS)

Svolik, S.

2004-01-01

Final treatment of liquid radioactive wastes which are produced by 1 st and 2 nd bloc of the Mochovce NPP, prepares the NPP in its natural range. The purpose of the equipment is liquidation of wastes, which are formed at production. Wastes are warehoused in the building of active auxiliary plants in the present time, where are reservoirs in which they are deposited. Because they are already feeling and in 2006 year they should be filled definitely, it is necessary to treat them in that manner, so as they may be liquidated. Therefore the Board of directors of the Slovenske elektrarne has disposed about construction of final treatment of liquid radioactive wastes in the Mochovce NPP. Because of transport the wastes have to be treated in the locality of power plant. Technically, the final treatment of the wastes will be interconnected with building of active operation by bridges. These bridges will transport the wastes for treatment into processing centre

Research of Methods, Technologies and Materials for Drainage Water Treatment at the Municipal Solid Waste Landfill in Salaryevo

Directory of Open Access Journals (Sweden)

Gogina Elena

2016-01-01

Full Text Available The article deals with innovative methods, technologies and materials intended to reduce the adverse ecological impact of human waste and various industrial waste situated in municipal solid waste landfills (MSW, on water bodies, soil, and atmosphere. The existence of these factors makes the region less attractive for urban development. A comparison has been made of the methods intended to reduce the damage caused to the environment, in order to provide for sustainable development of cities, using the example of an actual landfill situated in the territory of Moscow. A scheme of reconstruction is recommended for the drainage water treatment plant at this landfill, which will lead to improvement of the environmental situation and contribute to the development of territories in the adjacent districts, and to reduction of pollution load on the river and atmosphere.

Treatment of radioactive wastes

International Nuclear Information System (INIS)

Machida, Chuji

1976-01-01

Japan Atomic Energy Research Institute (JAERI) is equipped with such atomic energy facilities as a power test reactor, four research reactors, a hot laboratory, and radioisotope-producing factory. All the radioactive wastes but gas generated from these facilities are treated by the waste treatment facilities established in JAERI. The wastes carried into JAERI through Japan Radioisotope Association are also treated there. Low level water solution is treated with an evaporating apparatus, an ion-exchange apparatus, and a cohesive precipitating apparatus, while medium level solution is treated with an evaporating apparatus, and low level combustible solid is treated with an incinerating apparatus. These treated wastes and sludges are mixed with Portland cement in drum cans to solidify, and stored in a concrete pit. The correct classification and its indication as well as the proper packing for the wastes are earnestly demanded by the treatment facilities. (Kobatake, H.)

A Database for Reviewing and Selecting Radioactive Waste Treatment Technologies and Vendors

International Nuclear Information System (INIS)

P. C. Marushia; W. E. Schwinkendorf

1999-01-01

Several attempts have been made in past years to collate and present waste management technologies and solutions to waste generators. These efforts have been manifested as reports, buyers' guides, and databases. While this information is helpful at the time it is assembled, the principal weakness is maintaining the timeliness and accuracy of the information over time. In many cases, updates have to be published or developed as soon as the product is disseminated. The recently developed National Low-Level Waste Management Program's Technologies Database is a vendor-updated Internet based database designed to overcome this problem. The National Low-Level Waste Management Program's Technologies Database contains information about waste types, treatment technologies, and vendor information. Information is presented about waste types, typical treatments, and the vendors who provide those treatment methods. The vendors who provide services update their own contact information, their treatment processes, and the types of wastes for which their treatment process is applicable. This information is queriable by a generator of low-level or mixed low-level radioactive waste who is seeking information on waste treatment methods and the vendors who provide them. Timeliness of the information in the database is assured using time clocks and automated messaging to remind featured vendors to keep their information current. Failure to keep the entries current results in a vendor being warned and then ultimately dropped from the database. This assures that the user is dealing with the most current information available and the vendors who are active in reaching and serving their market

Treatment and final conditioning of solid radioactive wastes

International Nuclear Information System (INIS)

Cerre, J.

1960-01-01

The storage of solid radioactive wastes on a site is so cumbersome and dangerous that we have developed a method of treatment and conditioning by means of which the volume of waste is considerably reduced and very long-lasting shielding can be provided. This paper describes the techniques adopted at Saclay, where the wastes are sheared, compressed and enveloped in concrete of variable thickness. The main part of the report is devoted to a description of the corresponding remote handling installation. (author) [fr

Technologies 1995: environment and wastes treatment

International Nuclear Information System (INIS)

Anon.

1995-03-01

From new technical or scientific developments, new products launching, and markets evolutions, this catalog gives informations selection on research and development projects, new fabrication processes, activities and plants strategies, licences or technology transfers opportunities. The covered fields are: atmospheric pollution controls, water and liquid wastes treatment, polluted soils treatments, noise and odors treatments, municipal and industrial wastes treatments (metal, plastic, paper, glass), clean materials and technologies, radioactive wastes, and european cooperation programs. (A.B.)

Waste form development and characterization in pyrometallurgical treatment of spent nuclear fuel

International Nuclear Information System (INIS)

Ackerman, J.

1998-01-01

Electrometallurgical treatment is a compact, inexpensive method that is being developed at Argonne National Laboratory to deal with spent nuclear fuel, primarily metallic and oxide fuels. In this method, metallic nuclear fuel constituents are electrorefined in a molten salt to separate uranium from the rest of the spent fuel. Oxide and other fuels are subjected to appropriate head end steps to convert them to metallic form prior to electrorefining. The treatment process generates two kinds of high-level waste--a metallic and a ceramic waste. Isolation of these wastes has been developed as an integral part of the process. The wastes arise directly from the electrorefiner, and waste streams do not contain large quantities of solvent or other process fluids. Consequently, waste volumes are small and waste isolation processes can be compact and rapid. This paper briefly summarizes waste isolation processes then describes development and characterization of the two waste forms in more detail

Standard test method for determining elements in waste Streams by inductively coupled plasma-atomic emission spectroscopy

CERN Document Server

American Society for Testing and Materials. Philadelphia

2010-01-01

1.1 This test method covers the determination of trace, minor, and major elements in waste streams by inductively coupled plasma-atomic emission spectroscopy (ICP-AES) following an acid digestion of the sample. Waste streams from manufacturing processes of nuclear and non-nuclear materials can be analyzed. This test method is applicable to the determination of total metals. Results from this test method can be used to characterize waste received by treatment facilities and to formulate appropriate treatment recipes. The results are also usable in process control within waste treatment facilities. 1.2 This test method is applicable only to waste streams that contain radioactivity levels that do not require special personnel or environmental protection. 1.3 A list of the elements determined in waste streams and the corresponding lower reporting limit is found in Table 1. 1.4 This test method has been used successfully for treatment of a large variety of waste solutions and industrial process liquids. The com...

Quantification of methane and nitrous oxide emissions from various waste treatment facilities by tracer dilution method

Science.gov (United States)

Mønster, Jacob; Rella, Chris; Jacobson, Gloria; Kjeldsen, Peter; Scheutz, Charlotte

2013-04-01

tracer gas concentrations while another measured the nitrous oxide concentration. We present the performance of these instruments at different waste treatment facilities (waste water treatment plants, composting facilities, sludge mineralization beds, anaerobic digesters and landfills) in Denmark, and discuss the strengths and limitations of the method of the method for quantifying methane and nitrous oxide emissions from the different sources. Furthermore, we have measured the methane emissions from 10 landfills with emission rates ranging from 5 to 135 kg/h depending on the age, state, content and aftercare of the landfill. In addition, we have studied 3 waste water treatment plants, and found nitrous oxide emission of 200 to 700 g/h from the aeration tanks and a total methane emission ranging from 2 to 15 kg/h, with the primary emission coming from the sludge treatment. References Galle, B., Samuelsson, J., Svensson, B.H., and Börjesson, G. (2001). Measurements of methane emissions from landfills using a time correlation tracer method based on FTIR absorption spectroscopy. Environmental Science & Technology 35 (1), 21-25 Scheutz, C., Samuelsson, J., Fredenslund, A. M., and Kjeldsen, P. (2011). Quantification of multiple methane emission sources at landfills using a double tracer technique. Waste Management, 31(5), 1009-17 Solomon, S., D. Qin, M. Manning, R.B. Alley, T. Berntsen, N.L. Bindoff, Z. Chen, A. Chidthaisong, J.M. Gregory, G.C. Hegerl, M. Heimann, B. Hewitson, B.J. Hoskins, F. Joos, J. Jouzel, V. Kattsov, U. Lohmann, T.Matsuno, M. Molina, N. Nicholls, J.Overpeck, G. Raga, V. Ramaswamy, J. Ren, M. Rusticucci, R. Somerville, T.F. Stocker, P. Whetton, R.A.Wood and D. Wratt, 2007: Technical Summary. In: Climate Change 2007: The Physical Science Basis. Contribution of Working Group I to the Fourth Assessment Report of the Intergovernmental Panel on Climate Change. Cambridge University Press, Cambridge, United Kingdom and New York, NY, USA.

Treatment of nanomaterial-containing waste in thermal waste treatment facilities; Behandlung nanomaterialhaltiger Abfaelle in thermischen Abfallbehandlungsanlagen

Energy Technology Data Exchange (ETDEWEB)

Vogel, Julia; Weiss, Volker [Umweltbundesamt, Dessau-Rosslau (Germany); Oischinger, Juergen; Meiller, Martin; Daschner, Robert [Fraunhofer Umsicht, Sulzbach-Rosenberg (Germany)

2016-09-15

There is already a multitude of products on the market, which contain synthetic nanomaterials (NM), and for the coming years an increase of such products can be expected. Consequently, it is predictable that more nanomaterial-containing waste will occur in the residual waste that is predominately disposed in thermal waste treatment plants. However, the knowledge about the behaviour and effects of nanomaterials from nanomaterial-containing waste in this disposal route is currently still low. A research project of the German Environment Agency on the ''Investigation of potential environmental impacts when disposing nanomaterial-containing waste in waste treatment plants'' will therefore dedicate itself to a detailed examination of emission pathways in the thermal waste treatment facilities. The tests carried out i.a. on an industrial waste incineration plant and a sludge incineration plant with controlled addition of titanium dioxide at the nanoscale, showed that no increase in the emissions of NM in the exhaust gas was detected. The majority of the NM was found in the combustion residues, particularly the slag.

Options Assessment Report: Treatment of Nitrate Salt Waste at Los Alamos National Laboratory

Energy Technology Data Exchange (ETDEWEB)

Robinson, Bruce Alan [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Stevens, Patrice Ann [Los Alamos National Lab. (LANL), Los Alamos, NM (United States)

2015-12-17

This report documents the methodology used to select a method of treatment for the remediated nitrate salt (RNS) and unremediated nitrate salt (UNS) waste containers at Los Alamos National Laboratory (LANL). The method selected should treat the containerized waste in a manner that renders the waste safe and suitable for transport and final disposal in the Waste Isolation Pilot Plant (WIPP) repository, under specifications listed in the WIPP Waste Acceptance Criteria (DOE/CBFO, 2013). LANL recognizes that the results must be thoroughly vetted with the New Mexico Environment Department (NMED) and that a modification to the LANL Hazardous Waste Facility Permit is a necessary step before implementation of this or any treatment option. Likewise, facility readiness and safety basis approvals must be received from the Department of Energy (DOE). This report presents LANL’s preferred option, and the documentation of the process for reaching the recommended treatment option for RNS and UNS waste, and is presented for consideration by NMED and DOE.

Options assessment report: Treatment of nitrate salt waste at Los Alamos National Laboratory

Energy Technology Data Exchange (ETDEWEB)

Robinson, Bruce Alan [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Stevens, Patrice Ann [Los Alamos National Lab. (LANL), Los Alamos, NM (United States)

2015-09-16

This report documents the methodology used to select a method of treatment for the remediated nitrate salt (RNS) and unremediated nitrate salt (UNS) waste containers at Los Alamos National Laboratory (LANL). The method selected should treat the containerized waste in a manner that renders the waste safe and suitable for transport and final disposal in the Waste Isolation Pilot Plant (WIPP) repository, under specifications listed in the WIPP Waste Acceptance Criteria (DOE/CBFO, 2013). LANL recognized that the results must be thoroughly vetted with the New Mexico Environment Department (NMED) and the a modification to the LANL Hazardous Waste Facility Permit is a necessary step before implementation of this or any treatment option. Likewise, facility readiness and safety basis approvals must be received from the Department of Energy (DOE). This report presents LANL's preferred option, and the documentation of the process for reaching the recommended treatment option for RNS and UNS waste, and is presented for consideration by NMED and DOE.

Process of liquid radioactive waste treatment in nuclear power plant and development trend

International Nuclear Information System (INIS)

Liu Jiean; Wang Xin; Liu Dan; Zhu Laiye; Chen Bin

2014-01-01

The popular liquid radioactive waste treatment methods in nuclear power plants (NPP) are Chemical precipitation, evaporation, ion exchange, membrane treatment, chemical coagulation and activated carbon absorption and so on. 'Filter + activated carbon absorption (Chemical coagulation) + ion exchange' has a good prospect for development, as its simple process, high decontamination factor, low energy consumption and smaller secondary wastes. Also the process is used in Sanmen and Haiyang Projects. The severe incident in NPP set an even higher demand on liquid radioactive waste treatment. The new type treatment materials, optimization of the existed treatment, combination of treatment and the mobile treatment facility is the development trend in liquid radioactive waste treatment in NPP. (authors)

Liquid Radioactive Wastes Treatment: A Review

Directory of Open Access Journals (Sweden)

Yung-Tse Hung

2011-05-01

Full Text Available Radioactive wastes are generated during nuclear fuel cycle operation, production and application of radioisotope in medicine, industry, research, and agriculture, and as a byproduct of natural resource exploitation, which includes mining and processing of ores, combustion of fossil fuels, or production of natural gas and oil. To ensure the protection of human health and the environment from the hazard of these wastes, a planned integrated radioactive waste management practice should be applied. This work is directed to review recent published researches that are concerned with testing and application of different treatment options as a part of the integrated radioactive waste management practice. The main aim from this work is to highlight the scientific community interest in important problems that affect different treatment processes. This review is divided into the following sections: advances in conventional treatment of aqueous radioactive wastes, advances in conventional treatment of organic liquid wastes, and emerged technological options.

Treatment of low and intermediate level wastes

International Nuclear Information System (INIS)

Hoehlein, G.

1978-05-01

The methods described of low and intermediate level waste treatment are based exclusively on operating experience gathered with the KfK facilities for waste management, the Karlsruhe Reprocessing Plant (WAK), the ALKEM fuel element fabrication plant, the MZFR, KNK and FR 2 reactors as well as at the Karlsruhe Nuclear Research Center and at the state collecting depot of Baden-Wuerttemberg. The processing capacities and technical status are similar to that in 1976. With an annual throughput of 10000 m 3 of solid and liquid raw wastes, an aggregate activity of 85000 Ci, 500 kg of U and 2 kg of Pu, final waste in the amount of 500 m 3 was produced which was stored in the ASSE II salt mine. (orig.) [de

Solid waste treatment processes for space station

Science.gov (United States)

Marrero, T. R.

1983-01-01

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

Chemical treatment of mixed waste at the FEMP

International Nuclear Information System (INIS)

Honigford, L.; Sattler, J.; Dilday, D.; Cook, D.

1996-01-01

The Chemical Treatment Project is one in a series of projects implemented by the Fernald Environmental Management Project (FEMP) to treat mixed waste. The projects were initiated to address concerns regarding treatment capacity for mixed waste and to comply with requirements established by the Federal Facility Compliance Act. The Chemical Treatment Project is designed to utilize commercially available mobile technologies to perform treatment at the FEMP site. The waste in the Project consists of a variety of waste types with a wide range of hazards and physical characteristics. The treatment processes to be established for the waste types will be developed by a systematic approach including waste streams evaluation, projectization of the waste streams, and categorization of the stream. This information is utilized to determine the proper train of treatment which will be required to lead the waste to its final destination (i.e., disposal). This approach allows flexibility to manage a wide variety of waste in a cheaper, faster manner than designing a single treatment technology diverse enough to manage all the waste streams

Waste minimization promotes biophysical treatment of complex petrochemical wastes in Israel

Energy Technology Data Exchange (ETDEWEB)

Lebel, A [Invirotreat International Ltd., Fulleron, CA (United States); Raveh, A [Raveh Ecology Ltd., Haifa (Israel)

1994-12-31

This work describes a full-scale waste treatment system which was put into operation in a petrochemical manufacturing plant in Israel for the purpose of detoxifying its complex organic waste stream. The treatment plant design incorporates an innovative waste management approach to accommodate the limited space allocated for the facility. Initial performance data indicate a high efficient inorganic waste reduction. 4 refs., 6 figs., 2 tabs.

Waste minimization promotes biophysical treatment of complex petrochemical wastes in Israel

Energy Technology Data Exchange (ETDEWEB)

Lebel, A. [Invirotreat International Ltd., Fulleron, CA (United States); Raveh, A. [Raveh Ecology Ltd., Haifa (Israel)

1993-12-31

This work describes a full-scale waste treatment system which was put into operation in a petrochemical manufacturing plant in Israel for the purpose of detoxifying its complex organic waste stream. The treatment plant design incorporates an innovative waste management approach to accommodate the limited space allocated for the facility. Initial performance data indicate a high efficient inorganic waste reduction. 4 refs., 6 figs., 2 tabs.

Comparative LCA of Alternative Scenarios for Waste Treatment: The Case of Food Waste Production by the Mass-Retail Sector

Directory of Open Access Journals (Sweden)

Giovanni Mondello

2017-05-01

Full Text Available Food waste is one of the most important issues taken into account by the European Union due to its negative environmental, economic and social impacts. The treatment of food waste through recycling processes represents a solution for food waste minimisation. Concerning, in particular, the retail sector, it is necessary to define strategies for retail-oriented sustainable food waste management. The aim of this study is to compare the potential environmental impacts related to five scenarios (landfill, incineration, composting, anaerobic digestion and bioconversion through insects for the disposal/treatment of food waste produced by a mass retail company operating in Messina (Italy through the application of the Life Cycle Assessment method, in order to find the best treatment solution. Results based on the treatment of a functional unit of 1 tonne of food waste show that the bioconversion scenario represents the most preferable solution considering all of the impact categories analysed through the CML 2 baseline 2000 method, except for Global Warming, for which higher environmental performances are connected to the anaerobic digestion scenario. The incineration and the bioconversion scenarios show the highest environmental benefits when the production of alternative energy sources and valuable materials is evaluated through the inclusion of the avoided productions in the analysis.

Standard test method for determining elements in waste streams by inductively coupled plasma-atomic emission spectroscopy

International Nuclear Information System (INIS)

Anon.

1989-01-01

This test method covers the determination of trace, minor, and major elements in waste streams by inductively coupled plasma-atomic emission spectroscopy (ICP-AES) following an acid digestion of the specimen. Waste streams from manufacturing processes of nuclear and nonnuclear materials can be analyzed. This test method is applicable to the determination of total metals. Results from this test method can be used to characterize waste received by treatment facilities and to formulate appropriate treatment recipes. The results are also usable to process control within waste treatment facilities. This test method is applicable only to waste streams that contain radioactivity levels which do not require special personnel or environmental protection. A list of the elements determined in waste streams and the corresponding lower reporting limit is included

Treatment and disposal of radioactive waste from nuclear power stations

International Nuclear Information System (INIS)

Baehr, W.

1981-01-01

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

Thermal treatment of municipal waste: An overview

International Nuclear Information System (INIS)

Sivaprasad, K.S.

2010-01-01

Waste generation, like a shadow accompanies all kinds of human activities. For a long time waste was ignored as of no consequence. Nevertheless in recent times the presence of Waste was felt by the adverse impact it began to have on human life. Attention was given to waste disposal. Various methods of disposal were developed. Actually a process of evolution was set in this area. Starting with Dumpsite it developed in to sanitary land fill. Adverse impact was beginning to be seen in leachate contaminating ground water, and long term emission of methane contributing to climate change. This set the thinking to seek other solutions. Waste was begun to be seen as a resource instead of a nuisance to be disposed off. Bio-methanation of waste for recovery of methane rich biogas was developed. The concept of thermal treatment of waste for disposal came in to being in order to reduce volume of disposal as only the ash will be disposed instead of the whole volume of waste when waste is subjected to thermal treatment. However, it was beset with certain pollution problems which needed to be addressed. Suitable pollution abatement systems were developed. In the meantime, with the increase in global population and lifestyle changes across the globe, demand for natural resources went up rapidly resulting in pressure on the finite resources of the earth. Emphasis shifted to recovery of value from waste while disposing. Recovery of Recyclables, and energy came in to focus. RDF technology was developed facilitating this making it possible to recover recyclables like plastics, metals etc besides generating the prepared fuel RDF for energy recovery. (Author)

Fixed-biofilm reactors applied to waste water treatment and aquacultural water recirculating systems

NARCIS (Netherlands)

Bovendeur, J.

1989-01-01

Fixed-biofilm waste water treatment may be regarded as one of the oldest engineered biological waste water treatment methods. With the recent introduction of modern packing materials, this type of reactor has received a renewed impuls for implementation in a wide field of water treatment.

In

Proposal of an environmental performance index to assess solid waste treatment technologies.

Science.gov (United States)

Coelho, Hosmanny Mauro Goulart; Lange, Liséte Celina; Coelho, Lineker Max Goulart

2012-07-01

Although the concern with sustainable development and environment protection has considerably grown in the last years it is noted that the majority of decision making models and tools are still either excessively tied to economic aspects or geared to the production process. Moreover, existing models focus on the priority steps of solid waste management, beyond waste energy recovery and disposal. So, in order to help the lack of models and tools aiming at the waste treatment and final disposal, a new concept is proposed: the Cleaner Treatment, which is based on the Cleaner Production principles. This paper focuses on the development and validation of the Cleaner Treatment Index (CTI), to assess environmental performance of waste treatment technologies based on the Cleaner Treatment concept. The index is formed by aggregation (summation or product) of several indicators that consists in operational parameters. The weights of the indicator were established by Delphi Method and Brazilian Environmental Laws. In addition, sensitivity analyses were carried out comparing both aggregation methods. Finally, index validation was carried out by applying the CTI to 10 waste-to-energy plants data. From sensitivity analysis and validation results it is possible to infer that summation model is the most suitable aggregation method. For summation method, CTI results were superior to 0.5 (in a scale from 0 to 1) for most facilities evaluated. So, this study demonstrates that CTI is a simple and robust tool to assess and compare the environmental performance of different treatment plants being an excellent quantitative tool to support Cleaner Treatment implementation. Copyright © 2012 Elsevier Ltd. All rights reserved.

Liquid waste treatment system. Final report

International Nuclear Information System (INIS)

Baker, M.N.; Houston, H.M.

1999-01-01

Pretreatment of high-level liquid radioactive waste (HLW) at the West Valley Demonstration Project (WVDP) involved three distinct processing operations: decontamination of liquid HLW in the Supernatant Treatment System (STS); volume reduction of decontaminated liquid in the Liquid Waste Treatment System (LWTS); and encapsulation of resulting concentrates into an approved cement waste form in the Cement Solidification System (CSS). Together, these systems and operations made up the Integrated Radwaste Treatment System (IRTS)

Hazardous Waste Treatment Facility and skid-mounted treatment systems at Los Alamos

International Nuclear Information System (INIS)

Lussiez, G.W.; Zygmunt, S.J.

1994-01-01

To centralize treatment, storage, and areas for hazardous wastes, Los Alamos National Laboratory has designed a 1115 m2 hazardous waste treatment facility. The facility will house a treatment room for each of four kinds of wastes: nonradioactive characteristic wastes, nonradioactive listed wastes, radioactive characteristic wastes, and radioactive listed wastes. The facility will be used for repacking labpacks; bulking small organic waste volumes; processing scintillation vials; treating reactives such as lithium hydride and pyrophoric uranium; treating contaminated solids such as barium sand; treating plating wastes and other solutions with heavy metals and oxidizing organics: Separate treatment rooms will allow workers to avoid mixing waste types and prevent cross-contamination. The ventilation air from the treatment areas may contain hazardous or radioactive dust. Gas may also leak from process equipment. The gas treatment process includes separating solids and gases and neutralization or adsorption of the hazardous gases. The ventilation air from each room will first be filtered before being scrubbed in a common gas caustic scrubber on an outside pad. There are two levels of exhaust in each treatment room, one for heavy gases and another for light gases. Several features help mitigate or eliminate hazards due to spills and releases: each treatment room is sealed and under slight negative pressure; each room has its own HEPA filtration; to avoid mixing of incompatible wastes and reagents, portable individual spill-containment trays are used for skids, to limit the danger of spills, the waste is directly transferred from outside storage to the treatment room; to mitigate the consequences of a gas release in the room, mobile hoods are connected to the exhaust-air treatment system; the floor, walls, ceilings, fixtures, ducts, and piping are made of acid-resistant material or are coated

Development of a laundry waste treatment system

Energy Technology Data Exchange (ETDEWEB)

Kikuchi, M; Sugimoto, Y; Yusa, H; Ebara, K [Hitachi Ltd., Ibaraki (Japan). Hitachi Research Lab.; Takeshima, M [Hitachi Ltd., Ibaraki (Japan). Hitachi Works

1977-12-01

Fundamental and pilot plant experiments developed a laundry waste treatment system for nuclear power plants, consisting of a reverse osmosis unit for removal of radioactive materials and pre-concentration, and an evaporator for the final concentration. A sponge ball cleaning method was employed for the reverse osmosis unit and a heat-resistant antifoam reagent for the evaporator. The pilot plant test, using simulated wastes, showed a decontamination factor of above 10/sup 3/ and a volume reduction ratio of 10/sup -3/.

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.

Conflicts concerning sites for waste treatment and waste disposal plants

International Nuclear Information System (INIS)

Werbeck, N.

1993-01-01

The erection of waste treatment and waste disposal flants increasingly meets with the disapproval of local residents. This is due to three factors: Firstly, the erection and operation of waste treatment plants is assumed to necessarily entail harmful effects and risks, which may be true or may not. Secondly, these disadvantages are in part considered to be non-compensable. Thirdly, waste treatment plants have a large catchment area, which means that more people enjoy their benefits than have to suffer their disadvantages. If residents in the vicinity of such plants are not compensated for damage sustained or harmed in ways that cannot be compensated for it becomes a rational stance for them, while not objecting to waste treatment and waste disposal plants in principle to object to their being in their own neighbourhood. The book comprehensively describes the subject area from an economic angle. The causes are analysed in detail and an action strategy is pointed, out, which can help to reduce acceptance problems. The individual chapters deal with emissions, risk potentials, optimization calculus considering individual firms or persons and groups of two or more firms or persons, private-economy approaches for the solving of site selection conflicts, collective decision-making. (orig./HSCH) [de

Treatability study of absorbent polymer waste form for mixed waste treatment

International Nuclear Information System (INIS)

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

2000-01-01

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

Commercial mixed waste treatment and disposal

International Nuclear Information System (INIS)

Vance, J.K.

1994-01-01

At the South Clive, Utah, site, Envirocare of Utah, Inc., (Envirocare), currently operates a commercial low-activity, low-level radioactive waste facility, a mixed waste RCRA Part B storage and disposal facility, and an 11e.(2) disposal facility. Envirocare is also in the process of constructing a Mixed Waste Treatment Facility. As the nation's first and only commercial treatment and disposal facility for such waste, the information presented in this segment will provide insight into their current and prospective operations

A perspective of hazardous waste and mixed waste treatment technology at the Savannah River Site

International Nuclear Information System (INIS)

England, J.L.; Venkatesh, S.; Bailey, L.L.; Langton, C.A.; Hay, M.S.; Stevens, C.B.; Carroll, S.J.

1991-01-01

Treatment technologies for the preparation and treatment of heavy metal mixed wastes, contaminated soils, and mixed mercury wastes are being considered at the Savannah River Site (SRS), a DOE nuclear material processing facility operated by Westinghouse Savannah River Company (WSRC). The proposed treatment technologies to be included at the Hazardous Waste/Mixed Waste Treatment Building at SRS are based on the regulatory requirements, projected waste volumes, existing technology, cost effectiveness, and project schedule. Waste sorting and size reduction are the initial step in the treatment process. After sorting/size reduction the wastes would go to the next applicable treatment module. For solid heavy metal mixed wastes the proposed treatment is macroencapsulation using a thermoplastic polymer. This process reduces the leachability of hazardous constituents from the waste and allows easy verification of the coating integrity. Stabilization and solidification in a cement matrix will treat a wide variety of wastes (i.e. soils, decontamination water). Some pretreatments may be required (i.e. Ph adjustment) before stabilization. Other pretreatments such as soil washing can reduce the amount of waste to be stabilized. Radioactive contaminated mercury waste at the SRS comes in numerous forms (i.e. process equipment, soils, and lab waste) with the required treatment of high mercury wastes being roasting/retorting and recovery. Any unrecyclable radioactive contaminated elemental mercury would be amalgamated, utilizing a batch system, before disposal

Discarding processing method for radioactive waste

International Nuclear Information System (INIS)

Komura, Shiro; Kato, Hiroaki; Hatakeyama, Takao; Oura, Masato.

1992-01-01

At first, in a discrimination step, extremely low level radioactive wastes are discriminated to metals and concretes and further, the metal wastes are discriminated to those having hollow portions and those not having hollow portions, and the concrete wastes are discriminated to those having block-like shape and those having other shapes respectively. Next, in a processing step, the metal wastes having hollow portions are applied with cutting, devoluming or packing treatment and block-like concrete wastes are applied with surface solidification treatment, and concrete wastes having other shapes are applied with crushing treatment respectively. Then, the extremely low level radioactive wastes contained in a container used exclusively for transportation are taken out, in a movable burying facility with diffusion inhibiter kept at a negative pressure as required, in a field for burying operation, and buried in a state that they are isolated from the outside. Accordingly, they can be buried safely and efficiently. (T.M.)

Treatment and disposal of radioactive wastes and countermeasures

International Nuclear Information System (INIS)

Nomura, Kiyoshi

1990-01-01

The treatment and disposal of radioactive wastes are one of important subjects, together with the development of dismantling techniques accompanying the decommissioning measures for nuclear power plants and the development of reprocessing techniques for nuclear fuel cycle. About 25 years have elapsed since the beginning of commercial nuclear power generation in 1966, and the time that the solution of the problems of waste treatment and disposal must be tackled on full scale has come. The features and the amount of generation of radioactive wastes, the way of thinking on the treatment and disposal, and the present status of the treatment and disposal are outlined. For securing the stable supply of energy and solving the environmental problem of the earth such as acid rain and warming, nuclear power generation accomplishes important roles. The objective of waste treatment is based on the way of thinking of 'as low as reasonably achievable (ALARA)'. The radioactive wastes are classified into alpha waste and beta-gamma waste. The present status of RI wastes, the techniques of treating radioactive wastes, the nuclide separation, extinction treatment and the disposal in strata of high level radioactive wastes and the disposal of low level wastes are reported. (K.I.)

Mixed and Low-Level Waste Treatment Facility project

International Nuclear Information System (INIS)

1992-04-01

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

Analysis of Blended Learning Implementation on Waste Treatment Subjects in Agricultural Vocational School

Science.gov (United States)

Sugiarti, Y.; Nurmayani, S.; Mujdalipah, S.

2018-02-01

Waste treatment is one of the productive subjects in vocational high school in programs of Agricultural Processing Technology which is one of the objectives learning has been assigned in graduate competency standards (SKL) of Vocational High School. Based on case studies that have been conducted in SMK Pertanian Pembangunan Negeri Lembang, waste treatment subjects had still use the lecture method or conventional method, and students are less enthusiastic in learning process. Therefore, the implementation of more interactive learning models such as blended learning with Edmodo is one of alternative models to resolve the issue. So, the purpose of this study is to formulate the appropriate learning syntax for the implementation of blended learning with Edmodo to agree the requirement characteristics of students and waste treatment subject and explain the learning outcome obtained by students in the cognitive aspects on the subjects of waste treatment. This research was conducted by the method of classroom action research (CAR) with a Mc. Tagart model. The result from this research is the implementation of blended learning with Edmodo on the subjects of waste treatment can improve student learning outcomes in the cognitive aspects with the maximum increase in the value of N-gain 0.82, as well as student learning completeness criteria reaching 100% on cycle 2. Based on the condition of subject research the formulation of appropriate learning syntax for implementation of blended learning model with Edmodo on waste treatment subject are 1) Self-paced learning, 2) Group networking, 3) Live Event- collaboration, 4) Association - communication, 5) Assessment - Performance material support. In summary, implementation of blended learning model with Edmodo on waste treatment subject can improve improve student learning outcomes in the cognitive aspects and conducted in five steps on syntax.

Treatment of Radioactive Organic Wastes by an Electrochemical Oxidation

International Nuclear Information System (INIS)

Kim, K.H.; Ryue, Y.G.; Kwak, K.K.; Hong, K.P.; Kim, D.H.

2007-01-01

A waste treatment system by using an electrochemical oxidation (MEO, Mediated Electrochemical Oxidation) was installed at KAERI (Korea Atomic Energy Research Institute) for the treatment of radioactive organic wastes, especially EDTA (Ethylene Diamine Tetraacetic Acid) generated during the decontamination activity of nuclear installations. A cerium and silver mediated electrochemical oxidation technique method has been developed as an alternative for an incineration process. An experiment to evaluate the applicability of the above two processes and to establish the conditions to operate the pilot-scale system has been carried out by changing the concentration of the catalyst and EDTA, the operational current density, the operating temperature, and the electrolyte concentration. As for the results, silver mediated oxidation was more effective in destructing the EDTA wastes than the cerium mediated oxidation process. For a constant volume of the EDTA wastes, the treatment time for the cerium-mediated oxidation was 9 hours and its conversion ratio of EDTA to water and CO 2 was 90.2 % at 80 deg. C, 10 A, but the treatment time for the silver-mediated oxidation was 3 hours and its conversion ratio was 89.2 % at 30 deg. C, 10 A. (authors)

Method and apparatus for treating gaseous effluents from waste treatment systems

Science.gov (United States)

Flannery, Philip A.; Kujawa, Stephan T.

2000-01-01

Effluents from a waste treatment operation are incinerated and oxidized by passing the gases through an inductively coupled plasmas arc torch. The effluents are transformed into plasma within the torch. At extremely high plasma temperatures, the effluents quickly oxidize. The process results in high temperature oxidation of the gases without addition of any mass flow for introduction of energy.

Investigations on the treatment of waste waters from pig breeding

Energy Technology Data Exchange (ETDEWEB)

Cute, E; Mambet, E; Juriari, E; Murgoci, C

1967-01-01

The introduction of intensive methods of pig breeding has caused changes in the characteristics, particularly the strength, of the piggeries waste waters; analytical data are tabulated for waste waters from 3 pig-breeding farms and 1 large pig-breeding combine in Romania. At older piggeries, waste waters are treated by sedimentation and sludge digestion in Imhoff tanks. In more recent establishments, treatment comprises primary sedimentation followed by storage of the settled waste waters in ponds to be used for irrigation, and separate digestion of sludge in open tanks. Experiments showed that precautions are necessary to prevent blocking of the sewerage system by easily-settleable material before reaching the sedimentation tanks; sedimentation is more efficient in horizontal sedimentation tanks than in the older Imhoff tanks; biological treatment is possible without addition of nutrients, but the waste waters must be diluted; and digestion requires a longer period than that for sewage sludge, difficulties being caused by the presence of coarse suspended particles of waste feeding stuffs.

Treatment of alpha bearing wastes

International Nuclear Information System (INIS)

1988-01-01

This report deals with the current state of the art of alpha waste treatment, which is an integral part of the overall nuclear waste management system. The International Atomic Energy Agency (IAEA) defines alpha bearing waste as 'waste containing one or more alpha emitting radionuclides, usually actinides, in quantities above acceptable limits'. The limits are established by national regulatory bodies. The limits above which wastes are considered as alpha contaminated refer to the concentrations of alpha emitters that need special consideration for occupational exposures and/or potential safety, health, or environmental impact during one or more steps from generation through disposal. Owing to the widespread use of waste segregation by source - that is, based upon the 'suspect origin' of the material - significant volumes of waste are being handled as alpha contaminated which, in fact, do not require such consideration by reason of risk or environmental concern. The quantification of de minimis concepts by national regulatory bodies could largely contribute to the safe reduction of waste volumes and associated costs. Other factors which could significantly contribute to the reduction of alpha waste arisings are an increased application of assaying and sorting, instrumentation and the use of feedback mechanisms to control or modify the processes which generate these wastes. Alpha bearing wastes are generated during fabrication and reprocessing of nuclear fuels, decommissioning of alpha contaminated facilities, and other activities. Most alpha wastes are contact handled, but a small portion may require shielding or remote handling because of high levels of neutron (n), beta (β), or gamma (γ) emissions associated with the waste material. This report describes the sources and characteristics of alpha wastes and strategies for alpha waste management. General descriptions of treatment processes for solid and liquid alpha wastes are included. 71 refs, 14 figs, 9 tabs

China's Scientific Investigation for Liquid Waste Treatment Solutions

International Nuclear Information System (INIS)

Liangjin, B.; Meiqiong, L.; Kelley, D.

2006-01-01

Post World War II created the nuclear age with several countries developing nuclear technology for power, defense, space and medical applications. China began its nuclear research and development programs in 1950 with the establishment of the China Institute of Atomic Energy (CIAE) located near Beijing. CIAE has been China's leader in nuclear science and technical development with its efforts to create advanced reactor technology and upgrade reprocessing technology. In addition, with China's new emphasis on environmental safety, CIAE is focusing on waste treatment options and new technologies that may provide solutions to legacy waste and newly generated waste from the full nuclear cycle. Radioactive liquid waste can pose significant challenges for clean up with various treatment options including encapsulation (cement), vitrification, solidification and incineration. Most, if not all, nuclear nations have found the treatment of liquids to be difficult, due in large part to the high economic costs associated with treatment and disposal and the failure of some methods to safely contain or eliminate the liquid. With new environmental regulations in place, Chinese nuclear institutes and waste generators are beginning to seek new technologies that can be used to treat the more complex liquid waste streams in a form that is safe for transport and for long-term storage or final disposal. [1] In 2004, CIAE and Pacific Nuclear Solutions, a division of Pacific World Trade, USA, began discussions about absorbent technology and applications for its use. Preliminary tests were conducted at CIAE's Department of Radiochemistry using generic solutions, such as lubricating oil, with absorbent polymers for solidification. Based on further discussions between both parties, it was decided to proceed with a more formal test program in April, 2005, and additional tests in October, 2005. The overall objective of the test program was to apply absorbent polymers to various waste streams

Treatment of Radioactive Contaminated Soil and Concrete Wastes Using the Regulatory Clearance

Energy Technology Data Exchange (ETDEWEB)

Kang, Il Sik; Ryu, W. S.; Kim, T. K.; Shon, J. S.; Ahn, S. J.; Lee, Y. H.; Bae, S. M.; Hong, D. S.; Ji, Y. Y.; Lee, B. C

2008-11-15

In the radioactive waste storage facilities at the Korea Atomic Energy Research Institute (KAERI) in Daejoen, there are thousands drums of radioactive contaminated soil and concrete wastes. The soil and concrete wastes were generated in 1988 during the decommissioning process of the research reactor and the attached radioactive waste treatment facility which were located in Seoul. The wastes were transported to Daejeon and have been stored since then. At the generation time, the radioactive contamination of the wastes was very low, and the radionuclides in the wastes was Co-60 and Cs-137. As the wastes have been stored for more than 20 years, the radioactivity concentration of the wastes has been decayed to become very extremely low. The wastes are needed to be treated because they take up large spaces at the storage facility. Also by treating the wastes, final disposal cost can be saved. So, the regulatory clearance was considered as a treatment method for the soil and concrete wastes with extremely low radioactivity concentration.

Mixed-waste treatment -- What about the residuals?

International Nuclear Information System (INIS)

Carlson, T.; Carpenter, C.; Cummins, L.; Haas, P.; MacInnis, J.; Maxwell, C.

1993-01-01

Incineration currently is the best demonstrated available technology for the large inventory of U.S. Department of Energy (DOE) mixed waste. However, molten salt oxidation (MSO) is an alternative thermal treatment technology with the potential to treat a number of these wastes. Of concern for both technologies is the final waste forms, or residuals, that are generated by the treatment process. An evaluation of the two technologies focuses on 10 existing DOE waste streams and current hazardous-waste regulations, specifically for the delisting of ''derived-from'' residuals. Major findings include that final disposal options are more significantly impacted by the type of waste treated and existing regulations than by the type of treatment technology; typical DOE waste streams are not good candidates for delisting; and mass balance calculations indicate that MSO and incineration generate similar quantities (dry) and types of residuals

Waste management and treatment or disguised disposal?

International Nuclear Information System (INIS)

Drum, D.A.; Lauber, J.

1992-01-01

A number of political action groups, environmental groups, and waste management industries have purposely used medical waste data and municipal solid waste test results to mislead public officials and communities. Waste management schemes and waste treatment technologies must be measured and compared by the same test criteria. For example, anti-incineration groups often use the toxic dioxin/furan data and/or toxic metal arguments to oppose waste-to-energy incineration technologies. Comparable test data on waste management techniques such as waste composting, autoclaving, and landfilling are either nonexistent or often inappropriately applied. Integrated waste management systems require technologically accurate and complete data, environmentally-appropriate designed systems, and fiscal responsibility. The primary emphasis of waste management and treatment practices must be directed toward minimization, reuse, destruction, and detoxification of municipal solid wastes and medical wastes. The issues and alternatives will be examined

Investigation of Oxidation Methods for Waste Soy Sauce Treatment

Directory of Open Access Journals (Sweden)

Hyun-Hee Jang

2017-10-01

Full Text Available To obtain a suitable oxidation method for removing the color and lowering the chemical oxygen demand (COD of waste soy sauce, Fenton (Fe2+, Fenton-like (Fe3+, and ozone (O3 oxidation methods are used as the target reactions. In experimental conditions for Fenton oxidation, the dose of Fe2+ and Fe3+ was varied between 100 mg/L and 300 mg/L. The dose of hydrogen peroxide for the reaction was injected from 100–1000 mg/L. For ozone oxidation, the pH was increased from 3 to 14 and the O3-containing gas was supplied continuously for 30 min through a gas diffuser at the bottom of the reactor at different applied O3 doses (10–90 mg/L. We subjected it to a simple 1:20 dilution with deionized water to identify the comparison result in detail. O3 oxidation shows the highest efficiencies of color removal (81.1% and COD lowering (64.9% among the three oxidation methods. This is mainly due to the fact that it has a relatively large amount of hydroxyl radical, resulting in the degradation of organics. Thus, O3 oxidation could be a promising method for removing the color and lowering the COD of waste soy sauce. The critical parameters (pH and applied O3 dose were varied systematically to optimize O3 oxidation. It was found that the optimum pH and applied O3 dose are 11.0 mg/L and 50.0 mg/L, respectively (color removal = 34.2%, COD removal = 27.4%.

Investigation of Oxidation Methods for Waste Soy Sauce Treatment.

Science.gov (United States)

Jang, Hyun-Hee; Seo, Gyu-Tae; Jeong, Dae-Woon

2017-10-07

To obtain a suitable oxidation method for removing the color and lowering the chemical oxygen demand (COD) of waste soy sauce, Fenton (Fe 2+ ), Fenton-like (Fe 3+ ), and ozone (O₃) oxidation methods are used as the target reactions. In experimental conditions for Fenton oxidation, the dose of Fe 2+ and Fe 3+ was varied between 100 mg/L and 300 mg/L. The dose of hydrogen peroxide for the reaction was injected from 100-1000 mg/L. For ozone oxidation, the pH was increased from 3 to 14 and the O₃-containing gas was supplied continuously for 30 min through a gas diffuser at the bottom of the reactor at different applied O₃ doses (10-90 mg/L). We subjected it to a simple 1:20 dilution with deionized water to identify the comparison result in detail. O 3 oxidation shows the highest efficiencies of color removal (81.1%) and COD lowering (64.9%) among the three oxidation methods. This is mainly due to the fact that it has a relatively large amount of hydroxyl radical, resulting in the degradation of organics. Thus, O₃ oxidation could be a promising method for removing the color and lowering the COD of waste soy sauce. The critical parameters (pH and applied O₃ dose) were varied systematically to optimize O₃ oxidation. It was found that the optimum pH and applied O₃ dose are 11.0 mg/L and 50.0 mg/L, respectively (color removal = 34.2%, COD removal = 27.4%).

Solidification of radioactive liquid wastes, Treatment options for spent resins and concentrates - 16405

International Nuclear Information System (INIS)

Roth, Andreas

2009-01-01

Ion exchange is one of the most common and effective treatment methods for liquid radioactive waste. However, spent ion exchange resins are considered to be problematic waste that in many cases require special approaches and pre-conditioning during its immobilization to meet the acceptance criteria for disposal. Because of the function that they fulfill, spent ion exchange resins often contain high concentrations of radioactivity and pose special handling and treatment problems. Another very common method of liquid radioactive waste treatment and water cleaning is the evaporation or diaphragm filtration. Both treatment options offer a high volume reduction of the total volume of liquids treated but generate concentrates which contain high concentrations of radioactivity. Both mentioned waste streams, spent resins as well as concentrates, resulting from first step liquid radioactive waste treatment systems have to be conditioned in a suitable manner to achieve stable waste products for final disposal. Spent resin and concentrate treatment often appear as a specific task in decommissioning projects, because in the past those waste streams typically had been stored in tanks for the lifetime of the plant and needs to be retrieved, conditioned and packed prior to dismantling activities. Additionally a large amount of contaminated liquids will be generated by utilizing decontamination processes and needs to be processed further on. Such treatment options need to achieve waste products acceptable for final disposal, because due to the closure of the site no interim storage can be envisaged. The most common method of treatment of such waste streams is the solidification in a solid matrix with additional inactive material like cement, polymer etc. In the past good results have been achieved and the high concentration of radioactivity can be reduced by adding the inactive material. On the other hand, under the environment of limited space for interim storage and the absence

Hanford Tank Waste Treatment and Immobilization Plant (WTP) Waste Feed Qualification Program Development Approach - 13114

Energy Technology Data Exchange (ETDEWEB)

Markillie, Jeffrey R.; Arakali, Aruna V.; Benson, Peter A.; Halverson, Thomas G. [Hanford Tank Waste Treatment and Immobilization Plant Project, Richland, WA 99354 (United States); Adamson, Duane J.; Herman, Connie C.; Peeler, David K. [Savannah River National Laboratory, Aiken, SC 29808 (United States)

2013-07-01

The Hanford Tank Waste Treatment and Immobilization Plant (WTP) is a nuclear waste treatment facility being designed and constructed for the U.S. Department of Energy by Bechtel National, Inc. and subcontractor URS Corporation (under contract DE-AC27-01RV14136 [1]) to process and vitrify radioactive waste that is currently stored in underground tanks at the Hanford Site. A wide range of planning is in progress to prepare for safe start-up, commissioning, and operation. The waste feed qualification program is being developed to protect the WTP design, safety basis, and technical basis by assuring acceptance requirements can be met before the transfer of waste. The WTP Project has partnered with Savannah River National Laboratory to develop the waste feed qualification program. The results of waste feed qualification activities will be implemented using a batch processing methodology, and will establish an acceptable range of operator controllable parameters needed to treat the staged waste. Waste feed qualification program development is being implemented in three separate phases. Phase 1 required identification of analytical methods and gaps. This activity has been completed, and provides the foundation for a technically defensible approach for waste feed qualification. Phase 2 of the program development is in progress. The activities in this phase include the closure of analytical methodology gaps identified during Phase 1, design and fabrication of laboratory-scale test apparatus, and determination of the waste feed qualification sample volume. Phase 3 will demonstrate waste feed qualification testing in support of Cold Commissioning. (authors)

Treatment and disposal of radioactive wastes from the viewpoint of the NUCLEX 78

Energy Technology Data Exchange (ETDEWEB)

Koerner, W [Staatliches Amt fuer Atomsicherheit und Strahlenschutz, Berlin (German Democratic Republic)

1980-02-01

The results and consequences of the NUCLEX 78 are considered in form of a progress report on treatment and disposal of radioactive wastes from the nuclear fuel cycle. Investigations performed in the USA, Western Europe, and Japan are concerned with rationalization of the treatment processes for low-level and intermediate-level radioactive wastes and with the development of industrial methods of high-level waste solidification. In the field of ultimate storage, utilization of stable rock layers in the deep underground - especially of salt rocks - is evaluated to be the only available method of long-term isolation of high-level radioactive wastes and wastes containing long-lived alpha emitters. After technical and economical as well as safety works will have been concluded, commissioning of repositories in the underground is to be expected in the mid nineties.

Recent Trends In The Methods Of Safety Assessment Of Rad Waste Treatment And Disposal

International Nuclear Information System (INIS)

Mahmoud, N.S.

2012-01-01

Radioactive waste management system involves a huge variety of processes and activities. This includes; collection and segregation, pretreatment, treatment, conditioning, storage and finally disposal. To assure the safety of the different facility of each step in the waste management system, the operator should prepare a safety analysis report to be assessed by the national regulatory body. The content of the safety analysis report must include all data about the site, facility design, operational phase, waste materials, and safety assessment methodologies. Safety assessment methodologies are iterative processes involving site-specific, prospective modeling evaluations of the pre-operational, operational, and post-closure time in case of disposal facilities. The safety assessment focuses primarily on a decision about compliance with performance objectives, rather than the much more difficult problem of predicting actual radiological impacts on the public at far future times. The recent organization processes of the safety assessment are improved by the ISAM working group from IAEA for waste disposal site. These safety assessment methodologies have been modified within SADRWMS IAEA project for the establishment of safety methodologies for the pre-disposal facilities (treatment and storage facilities) and the disposal site.

Combined methods for liquid radioactive waste treatment. Final report of a co-ordinated research project 1997-2001

Energy Technology Data Exchange (ETDEWEB)

NONE

2003-02-01

The report contains 13 papers presented at the final research co-ordination meeting of the CRP. The subjects covered include processes and technologies for treatment and conditioning of liquid radioactive wastes. It quite often includes the application of several steps, such as filtration, precipitation, sorption, ion exchange, evaporation and/or membrane separation to meet the requirements both for the release of decontaminated effluents into the environment and the conditioning of waste concentrates for disposal. Combination of the processes and their consecutive or simultaneous application is also described. It results in an improved decontamination, waste volume reduction, safety and overall cost effectiveness in the treatment, conditioning and disposal of these wastes.

Combined methods for liquid radioactive waste treatment. Final report of a co-ordinated research project 1997-2001

International Nuclear Information System (INIS)

2003-02-01

The report contains 13 papers presented at the final research co-ordination meeting of the CRP. The subjects covered include processes and technologies for treatment and conditioning of liquid radioactive wastes. It quite often includes the application of several steps, such as filtration, precipitation, sorption, ion exchange, evaporation and/or membrane separation to meet the requirements both for the release of decontaminated effluents into the environment and the conditioning of waste concentrates for disposal. Combination of the processes and their consecutive or simultaneous application is also described. It results in an improved decontamination, waste volume reduction, safety and overall cost effectiveness in the treatment, conditioning and disposal of these wastes

76 FR 34147 - Land Disposal Restrictions: Revision of the Treatment Standards for Carbamate Wastes

Science.gov (United States)

2011-06-13

... numeric concentration limits or methods of treatment that substantially diminish the hazardous waste's... methods), reinstated the LDR treatment standards expressed as numerical concentration limits for 32... treatment methods and numeric concentration limits provides maximum flexibility in the choice of treatment...

Mixed and low-level waste treatment facility project. Volume 3, Waste treatment technologies (Draft)

Energy Technology Data Exchange (ETDEWEB)

1992-04-01

The technology information provided in this report is only the first step toward the identification and selection of process systems that may be recommended for a proposed mixed and low-level waste treatment facility. More specific information on each technology will be required to conduct the system and equipment tradeoff studies that will follow these preengineering studies. For example, capacity, maintainability, reliability, cost, applicability to specific waste streams, and technology availability must be further defined. This report does not currently contain all needed information; however, all major technologies considered to be potentially applicable to the treatment of mixed and low-level waste are identified and described herein. Future reports will seek to improve the depth of information on technologies.

Integrated treatment process of hazardous and mixed wastes

International Nuclear Information System (INIS)

Shibuya, M.; Suzuki, K.; Fujimura, Y.; Nakashima, T.; Moriya, Y.

1993-01-01

An integrated waste treatment system was studied based on technologies developed for the treatment of liquid radioactive, organic, and aqueous wastes containing hazardous materials and soils contaminated with heavy metals. The system consists of submerged incineration, metal ion fixing and stabilization, and soil washing treatments. Introduction of this system allows for the simultaneous processing of toxic waste and contaminated soils. Hazardous organic wastes can be decomposed into harmless gases, and aqueous wastes can be converted into a dischargeable effluent. The contaminated soil is backfilled after the removal of toxic materials. Experimental data show that the integration system is practical for complicated toxic wastes

Solidification of radioactive liquid wastes. A comparison of treatment options for spent resins and concentrates

International Nuclear Information System (INIS)

Roth, A.; Willmann, F.; Ebata, M.; Wendt, S.

2008-01-01

Ion exchange is one of the most common and effective treatment methods for liquid radioactive waste. However, spent ion exchange resins are considered to be problematic waste that in many cases require special approaches and pre-conditioning during its immobilization to meet the acceptance criteria for disposal. Because of the function that they fulfill, spent ion exchange resins often contain high concentrations of radioactivity and pose special handling and treatment problems. Another very common method of liquid radioactive waste treatment and water cleaning is the evaporation or diaphragm filtration. Both treatment options offer a high volume reduction of the total volume of liquids treated but generate concentrates which contain high concentrations of radioactivity. Both mentioned waste streams, spent resins as well as concentrates, resulting from first step liquid radioactive waste treatment systems have to be conditioned in a suitable manner to achieve stable waste products for final disposal. The most common method of treatment of such waste streams is the solidification in a solid matrix with additional inactive material like cement, polymer etc. In the past good results have been achieved and the high concentration of radioactivity can be reduced by adding the inactive material. On the other hand, under the environment of limited space for interim storage and the absence of a final repository site, the built-up of additional volume has to be considered as very critical. Moreover, corrosive effects on cemented drums during long-term interim storage at the surface have raised doubts about the long-term stability of such waste products. In order to avoid such disadvantages solidification methods have been improved in order to get a well-defined product with a better load factor of wastes in the matrix. In a complete different approach, other technologies solidify the liquid radioactive wastes without adding of any inactive material by means of drying

Challenges when Performing Economic Optimization of Waste Treatment

DEFF Research Database (Denmark)

Juul, Nina; Münster, Marie; Ravn, Hans

2011-01-01

New investments in waste treatment facilities are needed due to a number of factors including continuously increasing waste amounts, political demands for efficient utilization of the waste resources in terms of recycling or energy production, and decommissioning of existing waste treatment...... facilities due to age and stricter environmental regulation. Optimization models can assist in ensuring that these investment strategies will be economically feasible. Various economic optimization models for waste treatment have been developed which focus on different parameters. Models focusing...... in multi criteria analysis have been developed. A thorough updated review of the existing models is presented and the main challenges and the crucial parameters to take into account when assessing the economic performance of waste treatment alternatives are identified. The review article will assist both...

Use of ferric- and ferrous-salts in liquid waste treatment processes

International Nuclear Information System (INIS)

Efremenkov, V.M.; Toropov, I.G.; Toropova, V.V.; Satsukevich, V.M.; Davidov, J.P.; Jabrodsky, V.N.; Prokshin, N.E.

1995-01-01

Treatment of spent decontamination solutions is the most complicated task in the whole problem of management of liquid radioactive waste, because quite often they have complex compositions, which makes it difficult to find for them effective and non-expensive treatment technology. New methods of treatment of such a waste is proposed based on use of specific sorption ability of ferro- and ferri-species in solution. These species are often present in solution as the by-products, and in combination with other components of decontamination solution they can be used as initial substances for synthesis of valuable sorbents directly in treating solution. Using specific compositions and conditions in solution, it is possible to make liquid waste treatment process more effective and less expensive. Particular examples of this process is presented in this work

Sodium-Bearing Waste Treatment Alternatives Implementation Study

Energy Technology Data Exchange (ETDEWEB)

Charles M. Barnes; James B. Bosley; Clifford W. Olsen

2004-07-01

The purpose of this document is to discuss issues related to the implementation of each of the five down-selected INEEL/INTEC radioactive liquid waste (sodium-bearing waste - SBW) treatment alternatives and summarize information in three main areas of concern: process/technical, environmental permitting, and schedule. Major implementation options for each treatment alternative are also identified and briefly discussed. This report may touch upon, but purposely does not address in detail, issues that are programmatic in nature. Examples of these include how the SBW will be classified with respect to the Nuclear Waste Policy Act (NWPA), status of Waste Isolation Pilot Plant (WIPP) permits and waste storage availability, available funding for implementation, stakeholder issues, and State of Idaho Settlement Agreement milestones. It is assumed in this report that the SBW would be classified as a transuranic (TRU) waste suitable for disposal at WIPP, located in New Mexico, after appropriate treatment to meet transportation requirements and waste acceptance criteria (WAC).

Analytical characterization of high-level mixed wastes using multiple sample preparation treatments

International Nuclear Information System (INIS)

King, A.G.; Baldwin, D.L.; Urie, M.W.; McKinley, S.G.

1994-01-01

The Analytical Chemistry Laboratory at the Pacific Northwest Laboratory in Richland, Washington, is actively involved in performing analytical characterization of high-level mixed waste from Hanford's single shell and double shell tank characterization programs. A full suite of analyses is typically performed on homogenized tank core samples. These analytical techniques include inductively-coupled plasma-atomic emission spectroscopy, total organic carbon methods and radiochemistry methods, as well as many others, all requiring some type of remote sample-preparation treatment to solubilize the tank sludge material for analysis. Most of these analytical methods typically use a single sample-preparation treatment, inherently providing elemental information only. To better understand and interpret tank chemistry and assist in identifying chemical compounds, selected analytical methods are performed using multiple sample-preparation treatments. The sample preparation treatments used at Pacific Northwest Laboratory for this work with high-level mixed waste include caustic fusion, acid digestion, and water leach. The type of information available by comparing results from different sample-prep treatments includes evidence for the presence of refractory compounds, acid-soluble compounds, or water-soluble compounds. Problems unique to the analysis of Hanford tank wastes are discussed. Selected results from the Hanford single shell ferrocyanide tank, 241-C-109, are presented, and the resulting conclusions are discussed

Operation and control of ion-exchange processes for treatment of radioactive wastes

International Nuclear Information System (INIS)

Emelity, L.A.

1967-01-01

A manual dealing with the application of ion-exchange materials to the treatment of radioactive wastes and reviewing the facilities currently using this method. This book is one of three commissioned by the IAEA on the principal methods of concentrating radioactive wastes. The content of this document is: (i) Historical review related to removal of radioactivity; (ii) Principles of ion exchange (iii) Ion-exchange materials; (iv) Limitations of ion exchangers; (v) Application of ion exchange to waste processing; (vi) Operational procedures and experiences; (vii) Cost-of-treatment by ion-exchange. The document also gives a list of producers of ion-exchange material and defines some relevant terms. 101 refs, 31 figs, 27 tabs

Operation and control of ion-exchange processes for treatment of radioactive wastes

Energy Technology Data Exchange (ETDEWEB)

Emelity, L A [Los Alamos National Lab., NM (United States)

1967-12-01

A manual dealing with the application of ion-exchange materials to the treatment of radioactive wastes and reviewing the facilities currently using this method. This book is one of three commissioned by the IAEA on the principal methods of concentrating radioactive wastes. The content of this document is: (i) Historical review related to removal of radioactivity; (ii) Principles of ion exchange (iii) Ion-exchange materials; (iv) Limitations of ion exchangers; (v) Application of ion exchange to waste processing; (vi) Operational procedures and experiences; (vii) Cost-of-treatment by ion-exchange. The document also gives a list of producers of ion-exchange material and defines some relevant terms. 101 refs, 31 figs, 27 tabs.

Treatment of Waste Lubricating Oil by Chemical and Adsorption Process Using Butanol and Kaolin

Science.gov (United States)

Riyanto; Ramadhan, B.; Wiyanti, D.

2018-04-01

Treatment of waste lubricating oil by chemical and adsorption process using butanol and kaolin has been done. Quality of lubricating oil after treatment was analysis using Atomic Absorption Spectrophotometer (AAS) and Gas Chromatography-Mass Spectrometry (GC-MS). The effects of the treatment of butanol, KOH, and kaolin to metals contain in waste lubricating oil treatment have been evaluated. Treatment of waste lubricating oil has been done using various kaolin weight, butanol, and KOH solution. The result of this research show metal content of Ca, Mg, Pb, Fe and Cr in waste lubricating oil before treatment are 1020.49, 367.02, 16.40, 36.76 and 1,80 ppm, respectively. The metal content of Ca, Mg, Pb, Fe and Cr in the waste lubricating oil after treatment are 0.17, 9.85, 34.07, 78.22 and 1.20 ppm, respectively. The optimum condition for treatment of waste lubricating oil using butanol, KOH, and kaolin is 30 mL, 3.0 g and 1.5 g, respectively. Chemical and adsorption method using butanol and kaolin can be used for decrease of metals contain in waste lubricating oil.

Organic waste treatment with organically modified clays

International Nuclear Information System (INIS)

Evans, J.C.; Pancoski, S.E.; Alther, G.

1989-01-01

The use of organically modified clays in hazardous waste management applications offers a significant new and untapped potential. These clays may be used in the stabilization of organic wastes and organically contaminated soils, for waste water treatment, for oil spill control, for liner systems beneath fuel oil storage tanks, and as a component within liner systems of hazardous waste storage treatment and disposal facilities. Organically modified clays (organophilic clays) may be employed in each of these systems to adsorb organic waste constituents, enhancing the performance of the applications

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

Method and apparatus for the treatment of radioactive or toxic waste waters

Energy Technology Data Exchange (ETDEWEB)

Hofstaetter, K; Glock, J; Jakusch, H

1976-05-26

A method is described which proposes to store radioactive or toxic waste water in a binder, e.g. bitumen, for disposal. First of all, the liquid contained in the waste water is evaporated so that the radioactive or toxic part remains in solid form. This solid, whose specific gravity must be higher than that of the binder, is put on the surface of the binder, e.g. bitumen. Due to gravity it is embedded by sedimentation and completely covered by the binder. An apparatus with two variants to carry out the process is described, with particular emphasis on the advantages as compared to conventional methods.

Evaluation procedure for radioactive waste treatment processes

International Nuclear Information System (INIS)

Whitty, W.J.

1979-11-01

An aspect of the Los Alamos Scientific Laboratory's nuclear waste management R and D programs has been to develop an evaluation procedure for radioactive waste treatment processes. This report describes the process evaluation method. Process worth is expressed as a numerical index called the Figure-of-Merit (FOM), which is computed using a hierarchial, linear, additive, scoring model with constant criteria weights and nonlinear value functions. A numerical example is used to demonstrate the procedure and to point out some of its strengths and weaknesses. Potential modifications and extensions are discussed, and an extensive reference list is included

Waste Characterization: Approaches and Methods

DEFF Research Database (Denmark)

Lagerkvist, A.; Ecke, H.; Christensen, Thomas Højlund

2011-01-01

Characterization of solid waste is usually a difficult task because of the heterogeneity of the waste and its spatial as well as temporal variations. This makes waste characterization costly if good and reliable data with reasonable uncertainty is to be obtained. Therefore, a waste characterization...... is often narrowly defined to meet specific needs for information. This may however limit the general usefulness of the information gained, for example, if the specific purpose limited the characterization to a subset of variables. In general, data available in the solid waste area are limited and often...... related to individual treatment processes and waste products are dealt with in the following chapters: Characteristic data on residential waste (Chapter 2.2), commercial and institutional waste (Chapter 2.3), industrial waste (Chapter 2.4) and construction and demolition waste (Chapter 2...

Evaluation of waste treatment technologies by LLWDDD [Low-Level Waste Disposal Development and Demonstration] Programs

International Nuclear Information System (INIS)

Kennerly, J.M.; Williams, L.C.; Dole, L.R.; Genung, R.K.

1987-01-01

Waste treatments are divided into four categories: (1) volume reduction; (2) conditioning to improve waste form performance; (3) segregation to achieve waste reduction; and (4) separation to remove radioactive (or hazardous) constituents. Two waste treatment demonstrations are described. In the first, volume reduction by mechanical means was achieved during the supercompaction of 300 55-gal drums of solid waste at ORNL. In the second demonstration, conditioning of waste through immobilization and packaging to improve the performance of the waste form is being evaluated. The final section of this paper describes potential scenarios for the management of uranium-contaminated wastes at the Y-12 Plant in Oak Ridge and emphasizes where demonstrations of treatment technology will be needed to implement the scenarios. Separation and thermal treatment are identified as the principal means for treating these wastes. 15 figs

Thermal co-treatment of combustible hazardous waste and waste incineration fly ash in a rotary kiln.

Science.gov (United States)

Huber, Florian; Blasenbauer, Dominik; Mallow, Ole; Lederer, Jakob; Winter, Franz; Fellner, Johann

2016-12-01

As current disposal practices for municipal solid waste incineration (MSWI) fly ash are either associated with significant costs or negative environmental impacts, an alternative treatment was investigated in a field scale experiment. Thereto, two rotary kilns were fed with hazardous waste, and moistened MSWI fly ash (water content of 23%) was added to the fuel of one kiln with a ratio of 169kg/Mg hazardous waste for 54h and 300kg/Mg hazardous waste for 48h while the other kiln was used as a reference. It was shown that the vast majority (>90%) of the inserted MSWI fly ash was transferred to the bottom ash of the rotary kiln. This bottom ash complied with the legal limits for non-hazardous waste landfills, thereby demonstrating the potential of the investigated method to transfer hazardous waste (MSWI fly ash) into non-hazardous waste (bottom ash). The results of a simple mixing test (MSWI fly ash and rotary kiln bottom ash have been mixed accordingly without thermal treatment) revealed that the observed transformation of hazardous MSWI fly ash into non-hazardous bottom ash during thermal co-treatment cannot be referred to dilution, as the mixture did not comply with legal limits for non-hazardous waste landfills. For the newly generated fly ash of the kiln, an increase in the concentration of Cd, K and Pb by 54%, 57% and 22%, respectively, was observed. In general, the operation of the rotary kiln was not impaired by the MSWI fly ash addition. Copyright © 2016 Elsevier Ltd. All rights reserved.

Alpha wastes treatment

International Nuclear Information System (INIS)

Thouvenot, P.

2000-01-01

Alter 2004, the alpha wastes issued from the Commissariat a l'Energie Atomique installations will be sent to the CEDRA plant. The aims of this installation are decontamination and wastes storage. Because of recent environmental regulations concerning ozone layer depletion, the use of CFC 113 in the decontamination unit, as previously planned, is impossible. Two alternatives processes are studied: the AVD process and an aqueous process including surfactants. Best formulations for both processes are defined issuing degreasing kinetics. It is observed that a good degreasing efficiency is linked to a good decontamination efficiency. Best results are obtained with the aqueous process. Furthermore, from the point of view of an existing waste treatment unit, the aqueous process turns out to be more suitable than the AVD process. (author)

Waste treatment

International Nuclear Information System (INIS)

Davies, D.; Hooper, E.W.

1981-01-01

In the treatment of wastes, such as liquid radioactive effluents, it is known to remove radionuclides by successive in situ precipitation of cobalt sulphide, an hydroxide, barium sulphate and a transition element ferrocyanide, followed by separation of the thereby decontaminated effluent. In this invention, use is made of precipitates such as obtained above in the treatment of further fresh liquid radioactive effluent, when it is found that the precipitates have additional capacity for extracting radionuclides. The resulting supernatant liquor may then be subjected to a further precipitation treatment such as above. Decontamination factors for radionuclides of Ce, Ru, Sr and Cs have been considerably enhanced. (author)

Life cycle assessment of electronic waste treatment.

Science.gov (United States)

Hong, Jinglan; Shi, Wenxiao; Wang, Yutao; Chen, Wei; Li, Xiangzhi

2015-04-01

Life cycle assessment was conducted to estimate the environmental impact of electronic waste (e-waste) treatment. E-waste recycling with an end-life disposal scenario is environmentally beneficial because of the low environmental burden generated from human toxicity, terrestrial ecotoxicity, freshwater ecotoxicity, and marine ecotoxicity categories. Landfill and incineration technologies have a lower and higher environmental burden than the e-waste recycling with an end-life disposal scenario, respectively. The key factors in reducing the overall environmental impact of e-waste recycling are optimizing energy consumption efficiency, reducing wastewater and solid waste effluent, increasing proper e-waste treatment amount, avoiding e-waste disposal to landfill and incineration sites, and clearly defining the duties of all stakeholders (e.g., manufacturers, retailers, recycling companies, and consumers). Copyright © 2015 Elsevier Ltd. All rights reserved.

EPA/DOE joint efforts on mixed waste treatment

International Nuclear Information System (INIS)

Lee, C.C.; Huffman, G.L.; Nalesnik, R.P.

1995-01-01

Under the requirements of the Federal Facility Compliance Act (FFCA), the Department of Energy (DOE) is directed to develop treatment plans for their stockpile of wastes generated at their various sites. As a result, DOE is facing the monumental problem associated with the treatment and ultimate disposal of their mixed (radioactive and hazardous) waste. Meanwhile, the Environmental Protection Agency (EPA) issued a final open-quotes Hazardous Waste Combustion Strategyclose quotes in November 1994. Under the Combustion Strategy, EPA permit writers have been given the authority to use the Omnibus Provision of the Resource Conservation and Recovery Act (RCRA) to impose more stringent emission limits for waste combustors prior to the development of new regulations. EPA and DOE established a multi-year Interagency Agreement (IAG) in 1991. The main objective of the IAG (and of the second IAG that was added in 1993) is to conduct a research program on thermal technologies for treating mixed waste and to establish permit procedures for these technologies particularly under the new requirements of the above-mentioned EPA Combustion Strategy. The objective of this Paper is to summarize the results of the EPA/DOE joint efforts on mixed waste treatment since the establishment of the original Interagency Agreement. Specifically, this Paper will discuss six activities that have been underway; namely: (1) National Technical Workgroup (NTW) on Mixed Waste Treatment, (2) State-of-the-Art Assessment of APC (Air Pollution Control) and Monitoring Technologies for the Rocky Flats Fluidized Bed Unit, (3) Initial Study of Permit open-quotes Roadmapclose quotes Development for Mixed Waste Treatment, (4) Risk Assessment Approach for a Mixed Waste Thermal Treatment Facility, (5) Development and Application of Technology Selection Criteria for Mixed Waste Thermal Treatment, and (6) Performance Testing of Mixed Waste Incineration: In-Situ Chlorine Capture in a Fluidized Bed Unit

Development of biological treatment of high concentration sodium nitrate waste liquid

International Nuclear Information System (INIS)

Ogawa, Naoki; Kuroda, Kazuhiko; Shibata, Katsushi; Kawato, Yoshimi; Meguro, Yoshihiro; Takahashi, Kuniaki

2009-01-01

An electrolytic reduction, chemical reduction, and biological reduction have been picked up as a method of nitrate liquid waste treatment system exhausted from the reprocessing process. As a result of comparing them, it was shown that the biological treatment was the most excellent method in safety and the economy. (author)

The Hybrid Treatment Process for treatment of mixed radioactive and hazardous wastes

International Nuclear Information System (INIS)

Ross, W.A.; Kindle, C.H.

1992-04-01

This paper describes a new process for treating mixed hazardous and radioactive waste, commonly called mixed waste. The process is called the Hybrid Treatment Process (HTP), so named because it is built on the 20 years of experience with vitrification of wastes in melters, and the 12 years of experience with treatment of wastes by the in situ vitrification (ISV) process

Challenges when performing economic optimization of waste treatment: A review

DEFF Research Database (Denmark)

Juul, Nina; Münster, Marie; Ravn, H.

2013-01-01

-criteria analysis have been developed.A thorough updated review of the existing models is presented, and the main challenges and crucial parameters that need to be taken into account when assessing the economic performance of waste treatment alternatives are identified. The review article will assist both policy...... example, but models focusing on energy production have also been developed, as well as models which take into account a plant’s economies of scale, environmental impact, material recovery and social costs. Finally, models combining different criteria for the selection of waste treatment methods in multi...

Research and practice of informatization construction in waste treatment and management

International Nuclear Information System (INIS)

Kong Jinsong; Guo Weiqun; Yu Ren; Xiang Xinmin

2013-01-01

The goal, content and requirement of the informatization construction in waste treatment and management in nuclear power system are discussed in the paper, as well as some key problems in this process. Taking the engineering practice of informatization construction in a waste treatment center as an example, the composition and architecture of the information system, the consideration and the solution methods of some key problems in system design and development are introduced in the paper. (authors)

Waste Management, Treatment, and Disposal for the Food Processing Industry. Special Circular 113.

Science.gov (United States)

Wooding, N. Henry

This publication contains information relating to waste prevention, treatment and disposal, and waste product utilization. Its primary purpose is to provide information that will help the food industry executive recognize waste problems and make wise management decisions. The discussion of the methods, techniques, and the state-of-the-art is…

Treatment of mercury containing waste

Science.gov (United States)

Kalb, Paul D.; Melamed, Dan; Patel, Bhavesh R; Fuhrmann, Mark

2002-01-01

A process is provided for the treatment of mercury containing waste in a single reaction vessel which includes a) stabilizing the waste with sulfur polymer cement under an inert atmosphere to form a resulting mixture and b) encapsulating the resulting mixture by heating the mixture to form a molten product and casting the molten product as a monolithic final waste form. Additional sulfur polymer cement can be added in the encapsulation step if needed, and a stabilizing additive can be added in the process to improve the leaching properties of the waste form.

Evaluating the technical aspects of mixed waste treatment technologies

International Nuclear Information System (INIS)

Bagaasen, L.M.; Scott, P.A.

1992-10-01

This report discusses treatment of mixed wastes which is thought to be more complicated than treatment of either hazardous or radioactive wastes. In fact, the treatment itself is no more complicated: however, the regulations that define acceptability of the final waste disposal system are significantly more entangled, and sometimes in apparent conflict. This session explores the factors that influence the choice of waste treatment technologies, and expands on some of the limitations to their application. The objective of the presentation is to describe the technical factors that influence potential treatment processes and the ramifications associated with particular selections (for example, the generation of secondary waste streams). These collectively provide a framework for making informed treatment process selections

Demonstration of New Technologies Required for the Treatment of Mixed Waste Contaminated with {ge}260 ppm Mercury

Energy Technology Data Exchange (ETDEWEB)

Morris, M.I.

2002-02-06

The Resource Conservation and Recovery Act (RCRA) defines several categories of mercury wastes, each of which has a defined technology or concentration-based treatment standard, or universal treatment standard (UTS). RCRA defines mercury hazardous wastes as any waste that has a TCLP value for mercury of 0.2 mg/L or greater. Three of these categories, all nonwastewaters, fall within the scope of this report on new technologies to treat mercury-contaminated wastes: wastes as elemental mercury; hazardous wastes with less than 260 mg/kg [parts per million (ppm)] mercury; and hazardous wastes with 260 ppm or more of mercury. While this report deals specifically with the last category--hazardous wastes with 260 ppm or more of mercury--the other two categories will be discussed briefly so that the full range of mercury treatment challenges can be understood. The treatment methods for these three categories are as follows: Waste as elemental mercury--RCRA identifies amalgamation (AMLGM) as the treatment standard for radioactive elemental mercury. However, radioactive mercury condensates from retorting (RMERC) processes also require amalgamation. In addition, incineration (IMERC) and RMERC processes that produce residues with >260 ppm of radioactive mercury contamination and that fail the RCRA toxicity characteristic leaching procedure (TCLP) limit for mercury (0.20 mg/L) require RMERC, followed by AMLGM of the condensate. Waste with <260 ppm mercury--No specific treatment method is specified for hazardous wastes containing <260 ppm. However, RCRA regulations require that such wastes (other than RMERC residues) that exceed a TCLP mercury concentration of 0.20 mg/L be treated by a suitable method to meet the TCLP limit for mercury of 0.025 mg/L. RMERC residues must meet the TCLP value of {ge}0.20 mg/L, or be stabilized and meet the {ge}0.025 mg/L limit. Waste with {ge}260 ppm mercury--For hazardous wastes with mercury contaminant concentrations {ge}260 ppm and RCRA

Waste minimization in analytical methods

International Nuclear Information System (INIS)

Green, D.W.; Smith, L.L.; Crain, J.S.; Boparai, A.S.; Kiely, J.T.; Yaeger, J.S. Schilling, J.B.

1995-01-01

The US Department of Energy (DOE) will require a large number of waste characterizations over a multi-year period to accomplish the Department's goals in environmental restoration and waste management. Estimates vary, but two million analyses annually are expected. The waste generated by the analytical procedures used for characterizations is a significant source of new DOE waste. Success in reducing the volume of secondary waste and the costs of handling this waste would significantly decrease the overall cost of this DOE program. Selection of appropriate analytical methods depends on the intended use of the resultant data. It is not always necessary to use a high-powered analytical method, typically at higher cost, to obtain data needed to make decisions about waste management. Indeed, for samples taken from some heterogeneous systems, the meaning of high accuracy becomes clouded if the data generated are intended to measure a property of this system. Among the factors to be considered in selecting the analytical method are the lower limit of detection, accuracy, turnaround time, cost, reproducibility (precision), interferences, and simplicity. Occasionally, there must be tradeoffs among these factors to achieve the multiple goals of a characterization program. The purpose of the work described here is to add waste minimization to the list of characteristics to be considered. In this paper the authors present results of modifying analytical methods for waste characterization to reduce both the cost of analysis and volume of secondary wastes. Although tradeoffs may be required to minimize waste while still generating data of acceptable quality for the decision-making process, they have data demonstrating that wastes can be reduced in some cases without sacrificing accuracy or precision

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

International Nuclear Information System (INIS)

1997-07-01

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

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

Energy Technology Data Exchange (ETDEWEB)

NONE

1997-07-01

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

Life cycle assessment of electronic waste treatment

International Nuclear Information System (INIS)

Hong, Jinglan; Shi, Wenxiao; Wang, Yutao; Chen, Wei; Li, Xiangzhi

2015-01-01

Highlights: • Life cycle assessment of electronic waste recycling is quantified. • Key factors for reducing the overall environmental impact are indentified. • End-life disposal processes provide significant environmental benefits. • Efficiently reduce the improper disposal amount of e-waste is highly needed. • E-waste incineration can generate significant environmental burden. - Abstract: Life cycle assessment was conducted to estimate the environmental impact of electronic waste (e-waste) treatment. E-waste recycling with an end-life disposal scenario is environmentally beneficial because of the low environmental burden generated from human toxicity, terrestrial ecotoxicity, freshwater ecotoxicity, and marine ecotoxicity categories. Landfill and incineration technologies have a lower and higher environmental burden than the e-waste recycling with an end-life disposal scenario, respectively. The key factors in reducing the overall environmental impact of e-waste recycling are optimizing energy consumption efficiency, reducing wastewater and solid waste effluent, increasing proper e-waste treatment amount, avoiding e-waste disposal to landfill and incineration sites, and clearly defining the duties of all stakeholders (e.g., manufacturers, retailers, recycling companies, and consumers)

Life cycle assessment of electronic waste treatment

Energy Technology Data Exchange (ETDEWEB)

Hong, Jinglan, E-mail: hongjing@sdu.edu.cn [Shandong Provincial Key Laboratory of Water Pollution Control and Resource Reuse, School of Environmental Science and Engineering, Shandong University, Jinan 250100 (China); Shandong University Climate Change and Health Center, Public Health School, Shandong University, Jinan 250012 (China); Shi, Wenxiao [Shandong Provincial Key Laboratory of Water Pollution Control and Resource Reuse, School of Environmental Science and Engineering, Shandong University, Jinan 250100 (China); Wang, Yutao [School of Life Science, Shandong University, Shanda South Road 27, Jinan 250100 (China); Chen, Wei [Shandong Provincial Key Laboratory of Water Pollution Control and Resource Reuse, School of Environmental Science and Engineering, Shandong University, Jinan 250100 (China); Li, Xiangzhi, E-mail: xiangzhi@sdu.edu.cn [School of Medicine, Shandong University, Jinan 250012 (China)

2015-04-15

Highlights: • Life cycle assessment of electronic waste recycling is quantified. • Key factors for reducing the overall environmental impact are indentified. • End-life disposal processes provide significant environmental benefits. • Efficiently reduce the improper disposal amount of e-waste is highly needed. • E-waste incineration can generate significant environmental burden. - Abstract: Life cycle assessment was conducted to estimate the environmental impact of electronic waste (e-waste) treatment. E-waste recycling with an end-life disposal scenario is environmentally beneficial because of the low environmental burden generated from human toxicity, terrestrial ecotoxicity, freshwater ecotoxicity, and marine ecotoxicity categories. Landfill and incineration technologies have a lower and higher environmental burden than the e-waste recycling with an end-life disposal scenario, respectively. The key factors in reducing the overall environmental impact of e-waste recycling are optimizing energy consumption efficiency, reducing wastewater and solid waste effluent, increasing proper e-waste treatment amount, avoiding e-waste disposal to landfill and incineration sites, and clearly defining the duties of all stakeholders (e.g., manufacturers, retailers, recycling companies, and consumers)

An experimental method for designing the municipal solid waste biodrying

International Nuclear Information System (INIS)

Rada, E.C.; Politecnico Univ., Bucarest; Franzinelli, A.; Taiss, M.; Ragazzi, M.; Panaitescu, V.; Apostol, T.

2005-01-01

In the management of Municipal Solid Waste (MSW), in agreement with the new European directives concerning the valorization of materials and energy recovery, a recent approach based on a one-stream Biological Mechanical Treatment (BMT) is spreading as an alternative to the traditional two-stream approach. The bio-mechanical treatment of MSW is an increasing option either as a pre-treatment before land filling or as a pre-treatment before combustion. In the present paper an experimental method for designing the Municipal Solid Waste bio-drying is proposed. That means this paper deals with the option of energy recovery. The aim is to provide design criteria for bio-drying plants independent from the patents available in the sector [it

Waste treatment at the La Hague and Marcoule sites

International Nuclear Information System (INIS)

1995-04-01

In this report, an overview of waste treatment and solidification facilities located at the La Hague and Marcoule sites, which are owned and/or operated by Cogema, provided. The La Hague facilities described in this report include the following: The STE3 liquid effluent treatment facility (in operation); the AD2 solid waste processing facility (also in operation); and the UCD alpha waste treatment facility (under construction). The Marcoule facilities described in this report, both of which are in operation, include the following: The STEL-EVA liquid effluent treatment facilities for the entire site; and the alpha waste incinerator of the UPI plant. This report is organized into four sections: this introduction, low-level waste treatment at La Hague, low-level waste treatment at Marcoule, and new process development. including the solvent pyrolysis process currently in the development stage for Cogema's plants

Waste treatment at the La Hague and Marcoule sites

Energy Technology Data Exchange (ETDEWEB)

NONE

1995-04-01

In this report, an overview of waste treatment and solidification facilities located at the La Hague and Marcoule sites, which are owned and/or operated by Cogema, provided. The La Hague facilities described in this report include the following: The STE3 liquid effluent treatment facility (in operation); the AD2 solid waste processing facility (also in operation); and the UCD alpha waste treatment facility (under construction). The Marcoule facilities described in this report, both of which are in operation, include the following: The STEL-EVA liquid effluent treatment facilities for the entire site; and the alpha waste incinerator of the UPI plant. This report is organized into four sections: this introduction, low-level waste treatment at La Hague, low-level waste treatment at Marcoule, and new process development. including the solvent pyrolysis process currently in the development stage for Cogema`s plants.

Grout treatment facility dangerous waste permit application

International Nuclear Information System (INIS)

1992-07-01

The Grout Treatment Facility (GTF) will provide permanent disposal for approximately 43 Mgal of radioactive liquid waste currently being stored in underground tanks on the Hanford Site. The first step in permanent disposal is accomplished by solidifying the low-level liquid waste with cementitious dry materials. The resulting grout is cast within underground vaults. This report on the GTF contains information on the following: Hanford Site Maps, road evaluation for the grout treatment facility, Department of Ecology certificate of non-designation for centralia fly ash, double-shell tank waste compositional modeling, laboratory analysis reports for double-shell tank waste, stored in tanks 241-AN-103, 241-AN-106, and 241-AW-101, grout vault heat transfer results for M-106 grout formulation, test results for extraction procedure toxicity testing, test results for toxicity testing of double-shell tank grout, pilot-scale grout production test with a simulated low-level waste, characterization of simulated low-level waste grout produced in a pilot-scale test, description of the procedure for sampling nonaging waste storage tanks, description of laboratory procedures, grout campaign waste composition verification, variability in properties of grouted phosphate/sulfate N-reactor waste, engineering drawings, description of operating procedures, equipment list--transportable grout equipment, grout treatment facility--tank integrity assessment plan, long-term effects of waste solutions on concrete and reinforcing steel, vendor information, grout disposal facilities construction quality assurance plan, and flexible membrane liner/waste compatibility test results

Physical, chemical and mineralogical characterization of water treatment plant waste for use in soil-cement brick

International Nuclear Information System (INIS)

Pessin, L.R.; Destefani, A.Z.; Holanda, J.N.F.

2011-01-01

The water treatment plants (WTP) for human consumption generate huge amounts of waste in the form of sludge (sludge) that have been over the years mostly inadequately prepared in water resources and the environment. Moreover, traditional methods of disposal of waste water treatment plants commonly used are generally costly activities. An alternative method for disposal of this waste abundant is its incorporation in ceramic products. This work is focused on the physical-chemical and mineralogical composition of a sample of waste water treatment plants from the region of Campos dos Goytacazes-RJ to their use in the manufacture of soil-cement brick. Several characterization techniques were used including X-ray diffraction, X-ray fluorescence, scanning electron microscopy, picnometry, particle size analysis and plasticity. The experimental results indicate that the waste water treatment plants have the potential to be used in the manufacture of ecologic soil-cement bricks. (author)

Nuclear Waste Treatment Program: Annual report for FY 1986

International Nuclear Information System (INIS)

Burkholder, H.C.; Brouns, R.A.; Powell, J.A.

1987-09-01

To support DOE's attainment of its goals, Nuclear Waste Treatment Program (NWTP) is to provide technology necessary for the design and operation of nuclear waste treatment facilities by commercial enterprises as part of a licensed waste management system and problem-specific treatment approaches, waste form and treatment process adaptations, equipment designs, and trouble-shooting. This annual report describes progress during FY 1986 toward meeting these two objectives. 29 refs., 59 figs., 25 tabs

Nuclear Waste Treatment Program: Annual report for FY 1986

Energy Technology Data Exchange (ETDEWEB)

Burkholder, H.C.; Brouns, R.A. (comps.); Powell, J.A. (ed.)

1987-09-01

To support DOE's attainment of its goals, Nuclear Waste Treatment Program (NWTP) is to provide technology necessary for the design and operation of nuclear waste treatment facilities by commercial enterprises as part of a licensed waste management system and problem-specific treatment approaches, waste form and treatment process adaptations, equipment designs, and trouble-shooting. This annual report describes progress during FY 1986 toward meeting these two objectives. 29 refs., 59 figs., 25 tabs.

300 Area waste acid treatment system closure plan

International Nuclear Information System (INIS)

LUKE, S.N.

1999-01-01

The Hanford Facility Dangerous Waste Permit Application is considered to be a single application organized into a General Information Portion (document number DOERL-91-28) and a Unit-Specific Portion. The scope of the Unit-Specific Portion includes closure plan documentation submitted for individual, treatment, storage, and/or disposal units undergoing closure, such as the 300 Area Waste Acid Treatment System. Documentation contained in the General Information Portion is broader in nature and could be used by multiple treatment, storage, and/or disposal units (e.g., the glossary provided in the General Information Portion). Whenever appropriate, 300 Area Waste Acid Treatment System documentation makes cross-reference to the General Information Portion, rather than duplicating text. This 300 Area Waste Acid Treatment System Closure Plan (Revision 2) includes a Hanford Facility Dangerous Waste Permit Application, Part A, Form 3. Information provided in this closure plan is current as of April 1999

300 Area waste acid treatment system closure plan

Energy Technology Data Exchange (ETDEWEB)

LUKE, S.N.

1999-05-17

The Hanford Facility Dangerous Waste Permit Application is considered to be a single application organized into a General Information Portion (document number DOERL-91-28) and a Unit-Specific Portion. The scope of the Unit-Specific Portion includes closure plan documentation submitted for individual, treatment, storage, and/or disposal units undergoing closure, such as the 300 Area Waste Acid Treatment System. Documentation contained in the General Information Portion is broader in nature and could be used by multiple treatment, storage, and/or disposal units (e.g., the glossary provided in the General Information Portion). Whenever appropriate, 300 Area Waste Acid Treatment System documentation makes cross-reference to the General Information Portion, rather than duplicating text. This 300 Area Waste Acid Treatment System Closure Plan (Revision 2) includes a Hanford Facility Dangerous Waste Permit Application, Part A, Form 3. Information provided in this closure plan is current as of April 1999.

Design and evaluation of in situ biorestoration methods for the treatment of sludges and soils at waste disposal sites

Energy Technology Data Exchange (ETDEWEB)

Berry-Spark, K L; Barker, J F; Mayfield, C I

1990-12-31

In-situ methods for treatment of waste sludges hold great promise for efficient remediation of sludge at waste disposal sites, such as the diverse and complex sludges from the O.E. MacDougall site near Brockville, Ontario. This report presents results of laboratory testing of natural bioremediation techniques using six representative soils and sludges obtained from the MacDougall site. Four of six samples contained concentrations of hydrocarbons typical of petroleum products and solvents. The report includes descriptions of the characterisation of the organic chemistry and microbial populations of the soils, as well as of the experiments conducted under aerobic, methane oxidising, anaerobic-denitrifying, sulphate reducing, and methanogenic conditions.

Development of new waste form for treatment and disposal of concentrated liquid radioactive waste

International Nuclear Information System (INIS)

Kwak, Kyung Kil; Ji, Young Yong

2010-12-01

The radioactive waste form should be meet the waste acceptance criteria of national regulation and disposal site specification. We carried out a characterization of rad waste form, especially the characteristics of radioactivity, mechanical and physical-chemical properties in various rad waste forms. But asphalt products is not acceptable waste form at disposal site. Thus we are change the product materials. We select the development of the new process or new materials. The asphalt process is treatment of concentrated liquid and spent-resin and that we decide the Development of new waste form for treatment and disposal of concentrated liquid radioactive waste

The development of radioactive waste treatment technology(IV)

International Nuclear Information System (INIS)

Kim, Joon Hyung; Yim, Sung Paal; Lee, Kune Woo; Yoo, Jeong Woo; Kim, Young Min; Park, Seong Chul

1992-03-01

Following studies were performed in the project of development of radioactive waste treatment technology. 1) Treatment of radioactive borated liquid wastes by reverse osmosis : Separation characteristics of boric acid were estimated using cellulose acetate membrane and aromatic polyamide membrane. The performance of reverse osmosis process was evaluated in terms of boric acid recovery, radiochemical rejection, and membrane flux by operating variables such as applied pressure and feed concentration. 2) Oily waste treatment : The mathematical model to estimate oil removal efficiency is to be proposed at coalescence column. 3) Treatment of radioactive laundry waste 4) Comparison of evaporation and ion-exchange 5) State of the art of high integrity container. (Author)

Performance Enhancements to the Hanford Waste Treatment and Immobilization Plant Low-Activity Waste Vitrification System

International Nuclear Information System (INIS)

Hamel, W. F.; Gerdes, K.; Holton, L. K.; Pegg, I.L.; Bowan, B.W.

2006-01-01

The U.S Department of Energy Office of River Protection (DOE-ORP) is constructing a Waste Treatment and Immobilization Plant (WTP) for the treatment and vitrification of underground tank wastes stored at the Hanford Site in Washington State. The WTP comprises four major facilities: a pretreatment facility to separate the tank waste into high level waste (HLW) and low-activity waste (LAW) process streams, a HLW vitrification facility to immobilize the HLW fraction; a LAW vitrification facility to immobilize the LAW fraction, and an analytical laboratory to support the operations of all four treatment facilities. DOE has established strategic objectives to optimize the performance of the WTP facilities and the LAW and HLW waste forms to reduce the overall schedule and cost for treatment and vitrification of the Hanford tank wastes. This strategy has been implemented by establishing performance expectations in the WTP contract for the facilities and waste forms. In addition, DOE, as owner-operator of the WTP facilities, continues to evaluate 1) the design, to determine the potential for performance above the requirements specified in the WTP contract; and 2) improvements in production of the LAW and HLW waste forms. This paper reports recent progress directed at improving production of the LAW waste form. DOE's initial assessment, which is based on the work reported in this paper, is that the treatment rate of the WTP LAW vitrification facility can be increased by a factor of 2 to 4 with a combination of revised glass formulations, modest increases in melter glass operating temperatures, and a second-generation LAW melter with a larger surface area. Implementing these improvements in the LAW waste immobilization capability can benefit the LAW treatment mission by reducing the cost of waste treatment. (authors)

Radioactive Waste Evaporation: Current Methodologies Employed for the Development, Design, and Operation of Waste Evaporators at the Savannah River Site and Hanford Waste Treatment Plant

International Nuclear Information System (INIS)

Calloway, T.B.

2003-01-01

Evaporation of High level and Low Activity (HLW and LAW) radioactive wastes for the purposes of radionuclide separation and volume reduction has been conducted at the Savannah River and Hanford Sites for more than forty years. Additionally, the Savannah River Site (SRS) has used evaporators in preparing HLW for immobilization into a borosilicate glass matrix. This paper will discuss the methodologies, results, and achievements of the SRTC evaporator development program that was conducted in support of the SRS and Hanford WTP evaporator processes. The cross pollination and application of waste treatment technologies and methods between the Savannah River and Hanford Sites will be highlighted. The cross pollination of technologies and methods is expected to benefit the Department of Energy's Mission Acceleration efforts by reducing the overall cost and time for the development of the baseline waste treatment processes

Mixed and Low-Level Waste Treatment Facility Project

International Nuclear Information System (INIS)

1992-04-01

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

Technical report on natural evaporation system for radioactive liquid waste treatment arising from TRIGA research reactors' decontamination and decommissioning activities

International Nuclear Information System (INIS)

Moon, J. S.; Jung, K. J.; Baek, S. T.; Jung, U. S.; Park, S. K.; Jung, K. H.

1999-01-01

This technical report described that radioactive liquid waste treatment for dismantling/decontamination of TRIGA Mark research reactor in Seoul. That is, we try safety treatment of operation radioactive liquid waste during of operating TRIGA Mark research reactor and dismantling radioactive liquid waste during R and D of research reactor hereafter, and by utilizing of new natural evaporation facility with describing design criteria of new natural evaporation facility. Therefore, this technical report described the quantity of present radioactive liquid waste and dismantling radioactive liquid waste hereafter, analysis the status of radial-rays/radioactivity, and also treatment method of this radioactive liquid waste. Also, we derived the method that the safeguard of outskirts environment and the cost down of radioactive liquid waste treatment by minimize of the radioactive liquid waste quantities, through-out design/operation of new natural evaporation facility for treatment of operation radioactive liquid waste and dismantling radioactive liquid waste. (author). 6 refs., 12 tabs., 5 figs

Research and development on treatment of liquid radioactive wastes in Thailand

Energy Technology Data Exchange (ETDEWEB)

Yamkate, P; Sinakhom, F; Punnachaiya, M; Ya-anan, N; Srisorn, S [Office of Atomic Energy for Peace, Bangkok (Thailand). Waste Management Div.

1997-02-01

The studies have been directed towards treatment technologies for low level waste. The simple physico-chemical method has been studied for applying to various kinds of waste streams such as reactor waste, isotope production waste and liquid waste from the hospitals. The characterization of inorganic ion exchangers including the effect of pH, equilibrium time, temperature and concentration of such exchangers were tested. The results revealed that the local simple brand-washed detergents, which are very cheap, can be successfully used for decontamination instead of a more expensive imported decontaminating agent. It was also revealed that chemical precipitation can be successfully used for the treatment of such wastes. In considering an immobilization process for the treated waste, cementation was selected. The basic properties of the cemented waste forms have been investigated including leachability of the cemented sludge resulted from the chemical precipitation of the decontamination waste. The results revealed that the cemented inorganic ion exchangers and the sludge waste exhibit high compressive strength and low leach rates. The compressive strength of 118-207 kg/cm{sup 2} and 15% and 20% waste loading was found to be optimum for the waste forms. A cumulative fraction leached rate from the cemented sludge was found to be about 30 x 10{sup -3} cm/day at 30 day leaching time. (author). 5 refs, 7 tabs.

Research and development on treatment of liquid radioactive wastes in Thailand

International Nuclear Information System (INIS)

Yamkate, P.; Sinakhom, F.; Punnachaiya, M.; Ya-anan, N.; Srisorn, S.

1997-01-01

The studies have been directed towards treatment technologies for low level waste. The simple physico-chemical method has been studied for applying to various kinds of waste streams such as reactor waste, isotope production waste and liquid waste from the hospitals. The characterization of inorganic ion exchangers including the effect of pH, equilibrium time, temperature and concentration of such exchangers were tested. The results revealed that the local simple brand-washed detergents, which are very cheap, can be successfully used for decontamination instead of a more expensive imported decontaminating agent. It was also revealed that chemical precipitation can be successfully used for the treatment of such wastes. In considering an immobilization process for the treated waste, cementation was selected. The basic properties of the cemented waste forms have been investigated including leachability of the cemented sludge resulted from the chemical precipitation of the decontamination waste. The results revealed that the cemented inorganic ion exchangers and the sludge waste exhibit high compressive strength and low leach rates. The compressive strength of 118-207 kg/cm 2 and 15% and 20% waste loading was found to be optimum for the waste forms. A cumulative fraction leached rate from the cemented sludge was found to be about 30 x 10 -3 cm/day at 30 day leaching time. (author). 5 refs, 7 tabs

The role of biotechnology on the treatment of wastes | Buyukgungor ...

African Journals Online (AJOL)

The role of biotechnology on the treatment of wastes. ... treatment, gas treatment and disposal of solid wastes in environmental engineering. Also ... units and biogas reactors are used extensively among the waste treatment technologies.

Introduction to Effluent Treatment and Industrial Methods

Indian Academy of Sciences (India)

Home; Journals; Resonance – Journal of Science Education; Volume 5; Issue 11. Techniques of WasteWater Treatment - Introduction to Effluent Treatment and Industrial Methods. Amol A Kulkarni Mugdha Deshpande A B Pandit. General Article Volume 5 Issue 11 November 2000 pp 56-68 ...

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)

300 Area waste acid treatment system closure plan. Revision 1

International Nuclear Information System (INIS)

1996-03-01

This section provides a description of the Hanford Site, identifies the proposed method of 300 Area Waste Acid Treatment System (WATS) closure, and briefly summarizes the contents of each chapter of this plan

300 Area waste acid treatment system closure plan. Revision 1

Energy Technology Data Exchange (ETDEWEB)

NONE

1996-03-01

This section provides a description of the Hanford Site, identifies the proposed method of 300 Area Waste Acid Treatment System (WATS) closure, and briefly summarizes the contents of each chapter of this plan.

Techniques of material-flow-specific residual waste treatment; Techniken der stoffstromspezifischen Restabfallbehandlung

Energy Technology Data Exchange (ETDEWEB)

Maak, D.; Collins, H.J. [Technische Univ. Braunschweig, Leichtweiss - Inst. fuer Wasserbau (Germany)

1998-09-01

The success achieved with large-scale plants for mechanical-biological residual waste treatment has led to a change of course in waste pretreatment. In view of the low emissions via the water and gas routes from landfilled wastes and the low costs of waste treatment some authorising authorities have meanwhile issued special licences pursuant to clause no. 2.4 of the Technical Code on Household Waste, thus enabling mechanical-biological residual waste treatment plants to continue operations beyond the year 2005. Beside offering a means of treatment and disposal, cost-effective mechanical-biological pretreatment also provides an opportunity for going over to material-flow-specific residual waste treatment. These process stages permit recirculating valuable materials and using other materials for energy production. They can be retrofitted on a modular basis in existing plants. If these advantages of the present innovative pretreatment methods are not used, then mechanical-biological pretreatment can still serve as a preparatory stage for thermal treatment. To date there has been no practical experience with this innovative method of residual waste treatment. However, industrial-scale trials have shown that each individual treatment stage is capable of being carried out successfully. [Deutsch] Die guten Erfolge im grosstechnischen Betrieb von Anlagen zur mechanisch-biologischen Restabfallbehandlung haben zu einer Kursaenderung bei der Vorbehandlung von Abfaellen gefuehrt. Geringe Emissionen der deponierten Abfaelle auf dem Gas- und Wasserpfad sowie geringe Kosten fuer die Behandlung der Abfaelle haben dazu gefuehrt, dass inzwischen bereits einige Genehmigungsbehoerden eine Ausnahmegenehmigung nach Nr. 2.4 der TA Siedlungsabfall erteilt haben und damit der Betrieb von mechanisch-biologischen Restabfallbehandlungsanlagen auch nach 2005 ermoeglicht wird. Neben der alleinigen Behandlung und Deponierung bietet die kostenguenstige Vorbehandlung mit mechanisch

Waste water treatment today and tomorrow

International Nuclear Information System (INIS)

1992-01-01

The papers discuss waste water treatment in the legislation of the EC, the German state, the Laender and communities, as well as water protection by preventing waste production and pollutant emissions. (EF) [de

Ventilation and air conditioning system in waste treatment and storage facilities

International Nuclear Information System (INIS)

Kinoshita, Hirotsugu; Sugawara, Kazushige.

1987-01-01

So far, the measures concerning the facilities for treating and storing radioactive wastes in nuclear fuel cycle in Japan were in the state which cannot be said to be sufficient. In order to cope with this situation, electric power companies constructed and operated radioactive waste concentration and volume reduction facilities, solid waste storing facilities for drums, high level solid waste storing facilities, spent fuel cask preserving facilities and so on successively in the premises of nuclear power stations, and for the wastes expected in future, the research and the construction plan of the facilities for treating and storing low, medium and high level wastes have been advanced. The ventilation and air conditioning system for these facilities is the important auxiliary system which has the mission of maintaining safe and pleasant environment in the facilities and lowering as far as possible the release of radioactive substances to outside. The outline of waste treatment and storage facilities is explained. The design condition, ventilation and air conditioning method, the features of respective waste treatment and storage facilities, and the problems for the future are described. Hereafter, mechanical ventilation system continues to be the main system, and filters become waste, while the exchange of filters is accompanied by the radiation exposure of workers. (Kako, I.)

Regional waste treatment facilities with underground monolith disposal for all low-heat-generating nuclear wastes

International Nuclear Information System (INIS)

Forsberg, C.W.

1982-01-01

An alternative system for treatment and disposal of all ''low-heat-generating'' nuclear wastes from all sources is proposed. The system, Regional Waste Treatment Facilities with Underground Monolith Disposal (RWTF/UMD), integrates waste treatment and disposal operations into single facilities at regional sites. Untreated and/or pretreated wastes are transported from generation sites such as reactors, hospitals, and industries to regional facilities in bulk containers. Liquid wastes are also transported in bulk after being gelled for transport. The untreated and pretreated wastes are processed by incineration, crushing, and other processes at the RWTF. The processed wastes are mixed with cement. The wet concrete mixture is poured into large low-cost, manmade caverns or deep trenches. Monolith dimensions are from 15 to 25 m wide, and 20 to 60 m high and as long as required. This alternative waste system may provide higher safety margins in waste disposal at lower costs

An overview of in situ waste treatment technologies

International Nuclear Information System (INIS)

Walker, S.; Hyde, R.A.; Piper, R.B.; Roy, M.W.

1992-01-01

In situ technologies are becoming an attractive remedial alternative for eliminating environmental problems. In situ treatments typically reduce risks and costs associated with retrieving, packaging, and storing or disposing-waste and are generally preferred over ex situ treatments. Each in situ technology has specific applications, and, in order to provide the most economical and practical solution to a waste problem, these applications must be understood. This paper presents an overview of thirty different in situ remedial technologies for buried wastes or contaminated soil areas. The objective of this paper is to familiarize those involved in waste remediation activities with available and emerging in situ technologies so that they may consider these options in the remediation of hazardous and/or radioactive waste sites. Several types of in situ technologies are discussed, including biological treatments, containment technologies, physical/chemical treatments, solidification/stabilization technologies, and thermal treatments. Each category of in situ technology is briefly examined in this paper. Specific treatments belonging to these categories are also reviewed. Much of the information on in situ treatment technologies in this paper was obtained directly from vendors and universities and this information has not been verified

Nuclear waste treatment using Iranian natural zeolites

International Nuclear Information System (INIS)

Kazemian, H.; Ghannadi Maraghe, M.

2001-01-01

Full text: The zeolite researches in Iran is a relatively new subject which has started about 10 years ago. The motivation for this scientific and interesting field was provided after discovery of significant deposits of natural zeolites in different regions of Iran as well as further developments of research institutions and the national concern to environmental protection especially the wastewater clean-up in point of view of recycling of such waste water to compensate some needs to water in other utilizations. This paper intends to review and describes scientific researches which have done on using zeolites in the field of nuclear waste treatment in Iran to introduce the potential resources to the world in more details. Zeolite tuffs are widely distributed in huge deposits in different regions of Iran. So far, the clinoptilolite tuffs are the most abundant natural zeolite which exist with zeolite content of 65%- 95%. Nowadays several different types of Iranian natural zeolites are characterized in point of view of chemical composition, type of structure, chemical, thermal, and radiation resistance using different instrumental and classical methods such as; X-ray diffraction (XRD), X-ray fluoresce (XRF), thermal methods of analysis (TA), scanning electron microscopy (SEM), analytical chemistry and radioanalytical methods as well as different ion-exchange techniques (e.g.3-7). The ability of Iranian natural clinoptilolite for removal of some fission products from nuclear wastewaters have been investigated. The selectivity of all investigated zeolites toward radiocesium and radiostrontium have been promising (e.g. 8-10). The successful synthesize of P zeolite from Iranian clinoptilolite-reach tuffs under different conditions were performed. The compatibility of zeolites with glass and cement matrices, for final disposal of radwaste, as well as their selectivity toward most dangerous heat generating radionuclides (e.g. 137 Cs and 90 Sr) is very important in using

Chromium Waste Treatment from Leather Manufacture Using Electron Beam Radiation Technic

International Nuclear Information System (INIS)

Didiek Herhady, R.; Sukarsono, R.

2007-01-01

Leather manufacture chromium waste treatment using chemical methods have an essential disadvantage, because of the production of the secondary contamination of wastes and separated sediments used by reagents. Therefore, a new technique is needed to solve this problem. The aim of the research to learn the advantages of electron beam radiation for chromium waste treatment. Water radiolysis can be produced by the interaction between electron beam and water or liquid substances. This phenomenon produces many reducing agents and ions that could reduce chromium concentrations in the liquid waste. Ethyl alcohol as a scavenger was added in the waste samples, then the pH of varied from 1, 4, 8 to 12, then were irradiated. Irradiation were done by Electron Beam Machine with dose 15, 25, and 35 kGy. After irradiation, chromium concentration in the samples were analyzed by AAS and UV-vis spectrophotometer. The results had shown that chromium could be reduced by high dose electron beam. The optimum reduction of chromium was achieved at liquid waste pH 8 and irradiation dose 35 kGy. (author)

Treatment of radioactive mixed wastes in commercial low-level wastes

International Nuclear Information System (INIS)

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

1985-01-01

Management options for three generic categories of radioactive mixed waste in commercial low-level wastes have been identified and evaluated. These wastes were characterized as part of a BNL study in which a large number of generators were surveyed for information on potentially hazardous low-level wastes. The general management targets adopted for mixed wastes are immobilization, destruction, and reclamation. It is possible that these targets may not be practical for some wastes, and for these, goals of stabilization or reduction of hazard are addressed. Solidification, absorption, incineration, acid digestion, segregation, and substitution have been considered for organic liquid wastes. Containment, segregation, and decontamination and re-use have been considered for lead metal wastes which have themselves been contaminated and are not used for purposes of waste disposal shielding, packaging, or containment. For chromium-containing wastes, solidification, incineration, containment, substitution, chemical reduction, and biological removal have been considered. For each of these wastes, the management option evaluation has necessarily included assessment/estimation of the effect of the treatment on both the radiological and potential chemical hazards present. 10 refs

Nuclear waste treatment program: Annual report for FY 1987

International Nuclear Information System (INIS)

Brouns, R.A.; Powell, J.A.

1988-09-01

Two of the US Department of Energy's (DOE) nuclear waste management-related goals are to ensure that waste management is not an obstacle to the further development of light-water reactors and the closure of the nuclear fuel cycle and to fulfill its institutional responsibility for providing safe storage and disposal of existing and future nuclear wastes. As part of its approach to achieving these goals, the Office of Remedial Action and Waste Technology of DOE established what is now called the Nuclear Waste Treatment Program (NWTP) at the Pacific Northwest Laboratory during the second half of FY 1982. To support DOE's attainment of its goals, the NWTP is to provide technology necessary for the design and operation of nuclear waste treatment facilities by commercial enterprises as part of a licensed waste management system and problem-specific treatment approaches, waste form and treatment process adaptations, equipment designs, and trouble-shooting assistance, as required to treat existing wastes. This annual report describes progress during FY 1987 towards meeting these two objectives. 24 refs., 59 figs., 24 tabs

Radioactive sodium waste treatment and conditioning. Review of main aspects

International Nuclear Information System (INIS)

2007-01-01

This publication reviews the main aspects relating to the treatment and conditioning of radioactive sodium waste. This waste arises from the operation of liquid metal fast reactors (LMFRs). In this type of reactor, sodium (Na) or sodium-potassium alloys (NaK) are used as a low-effect neutron moderating coolant medium for extracting and transferring thermal energy from the core and they represent a significant technical and safety challenge during operation and decommissioning. This publication provides the reader with technologically oriented information on the present status of sodium waste management approaches and recent achievements related to treatment and conditioning, with the objective of facilitating planning and preparatory work for the decommissioning of LMFRs. This publication provides a comprehensive review of the hazards associated with sodium waste management. Given the large quantities of sodium waste arising during decommissioning or reactor refurbishment, as well as the challenges and varied techniques associated with removal of 100% of all sodium and NaK bulk quantities and residues during decommissioning, a hazards review and analysis is a critical component in planning the dismantling and waste management activities. Roughly half of this publication focuses on sodium waste generating, handling and treatment processes. This includes draining sodium and NaK from plant systems; in situ treatment of residual sodium; cutting techniques for pumps, valves, piping and other components; cleaning of components; potential reuse of sodium; and removal of selected radionuclides from sodium waste with the objective of reducing the waste classification or converting it to exempt waste. The focus is on proven techniques and technologies, and each discussed method includes a review of the associated principle or theory, practical applications, advantages and disadvantages, limitations, industry experience, and final waste products. A review is provided of final

SOLAR ENERGY APPLICATION IN WASTE TREATMENT- A REVIEW

African Journals Online (AJOL)

This review is an exposure on the various ways that solar energy can be harnessed for numerous waste treatment processes. Almost all forms of waste treatment require energy which is scarcely available considering the global energy crisis. The objective of this study is to enumerate the solar energy applications in waste ...

Radioactive wastes: sources, treatment, and disposal

International Nuclear Information System (INIS)

Wymer, R.G.; Blomeke, J.O.

1975-01-01

Sources, treatment, and disposal of radioactive wastes are analyzed in an attempt to place a consideration of the problem of permanent disposal at the level of established or easily attainable technology. In addition to citing the natural radioactivity present in the biosphere, the radioactive waste generated at each phase of the fuel cycle (mills, fabrication plants, reactors, reprocessing plants) is evaluated. The three treatment processes discussed are preliminary storage to permit decay of the short-lived radioisotopes, solidification of aqueous wastes, and partitioning the long-lived α emitters for separate and long-term storage. Dispersion of radioactive gases to the atmosphere is already being done, and storage in geologically stable structures such as salt mines is under active study. The transmutation of high-level wastes appears feasible in principle, but exceedingly difficult to develop

Commercial waste treatment R and D needs in the United States

International Nuclear Information System (INIS)

Burkholder, H.C.

1982-05-01

The mission of the commercial waste treatment program is to establish treatment technology for safe and efficient management of high-level and transuranic wastes from reprocessing and fuel fabrication and special wastes from other fuel cycle activities. The four functional objectives that must be achieved to fulfill the mission are: (1) define waste product and treatment process performance requirements; (2) specify adequately safe waste products and verify their performance; (3) specify adequately efficient treatment processes and equipment and verify their performance; (4) solve existing waste treatment problems using verified products and processes. Although commercial waste treatment technology is in many respects highly advanced, there remains a number of areas where significant research and development is needed. These are: (1) technically-based performance requirements for both waste products and treatment processes; (2) pilot-scale radioactive demonstration of liquid-fed ceramic melting process and equipment for borosilicate glass; (3) non-glass TRU waste product and treatment process development; (4) waste product performance testing and predictive modeling; (5) quality verification for treatment processes

Preliminary study for treatment methodology establishment of liquid waste containing uranium in refining facility lagoon

Energy Technology Data Exchange (ETDEWEB)

Lee, Byung Jik; Lee, Kune Woo; Won, Hui Jun; Ahn, Byung Gil; Shim, Joon Bo

1999-12-01

The preliminary study which establishes the treatment methodology of the sludge waste containing uranium in the conversion facility lagoon was performed. The property of lagoon liquid waste such as the initial water content, the density including radiochemical analysis results were obtained using the samples taken from the lagoon. The objective of this study is to provide some basically needed materials for selection of the most proper lagoon waste treatment methodology by reviewing the effective processes and methods for minimizing the secondary waste resulting from the treatment and disposition of large amount of radioactive liquid waste according to the facility closing. The lagoon waste can be classified into two sorts, such as supernatant and precipitate. The supernatants contain uranium less than 5 ppm and their water content are about 35 percent. Therefore, supernatants are solutions composed of mainly salt components. However, the precipitates have lots of uranium compound contained in the coagulation matrix, and are formed as two kinds of crystalline structures. The most proper method minimizing the secondary waste would be direct drying and solidification of the supernatants and precipitates after separation of them by filtering. (author)

Startup of the remote laboratory-scale waste-treatment facility

International Nuclear Information System (INIS)

Knox, C.A.; Siemens, D.H.; Berger, D.N.

1981-01-01

The Remote Laboratory-Scale Waste-Treatment Facility was designed as a system to solidify small volumes of radioactive liquid wastes. The objectives in operating this facility are to evaluate solidification processes, determine the effluents generated, test methods for decontaminating the effluents, and provide radioactive solidified waste products for evaluation. The facility consists of a feed-preparation module, a waste-solidification module and an effluent-treatment module. The system was designed for remote installation and operation. Several special features for remotely handling radioactive materials were incorporated into the design. The equipment was initially assembled outside of a radiochemical cell to size and fabricate the connecting jumpers between the modules and to complete some preliminary design-verification tests. The equipment was then disassembled and installed in the radiochemical cell. When installation was completed the entire system was checked out with water and then with a nonradioactive simulated waste solution. The purpose of these operations was to start up the facility, find and solve operational problems, verify operating procedures and train personnel. The major problems experienced during these nonradioactive runs were plugging of the spray calciner nozzle and feed tank pumping failures. When these problems were solved, radioactive operations were started. This report describes the installation of this facility, its special remote design feature and the startup operations

Standardized waste form test methods

International Nuclear Information System (INIS)

Slate, S.C.

1984-01-01

The Materials Characterization Center (MCC) is developing standard tests to characterize nuclear waste forms. Development of the first thirteen tests was originally initiated to provide data to compare different high-level waste (HLW) forms and to characterize their basic performance. The current status of the first thirteen MCC tests and some sample test results are presented: the radiation stability tests (MCC-6 and 12) and the tensile-strength test (MCC-11) are approved; the static leach tests (MCC-1, 2, and 3) are being reviewed for full approval; the thermal stability (MCC-7) and microstructure evaluation (MCC-13) methods are being considered for the first time; and the flowing leach test methods (MCC-4 and 5), the gas generation methods (MCC-8 and 9), and the brittle fracture method (MCC-10) are indefinitely delayed. Sample static leach test data on the ARM-1 approved reference material are presented. Established tests and proposed new tests will be used to meet new testing needs. For waste form production, tests on stability and composition measurement are needed to provide data to ensure waste form quality. In transporation, data are needed to evaluate the effects of accidents on canisterized waste forms. The new MCC-15 accident test method and some data are presented. Compliance testing needs required by the recent draft repository waste acceptance specifications are described. These specifications will control waste form contents, processing, and performance

Standardized waste form test methods

International Nuclear Information System (INIS)

Slate, S.C.

1984-11-01

The Materials Characterization Center (MCC) is developing standard tests to characterize nuclear waste forms. Development of the first thirteen tests was originally initiated to provide data to compare different high-level waste (HLW) forms and to characterize their basic performance. The current status of the first thirteen MCC tests and some sample test results is presented: The radiation stability tests (MCC-6 and 12) and the tensile-strength test (MCC-11) are approved; the static leach tests (MCC-1, 2, and 3) are being reviewed for full approval; the thermal stability (MCC-7) and microstructure evaluation (MCC-13) methods are being considered for the first time; and the flowing leach tests methods (MCC-4 and 5), the gas generation methods (MCC-8 and 9), and the brittle fracture method (MCC-10) are indefinitely delayed. Sample static leach test data on the ARM-1 approved reference material are presented. Established tests and proposed new tests will be used to meet new testing needs. For waste form production, tests on stability and composition measurement are needed to provide data to ensure waste form quality. In transportation, data are needed to evaluate the effects of accidents on canisterized waste forms. The new MCC-15 accident test method and some data are presented. Compliance testing needs required by the recent draft repository waste acceptance specifications are described. These specifications will control waste form contents, processing, and performance. 2 references, 2 figures

Waste characterization methods at belgoprocess and the importance of NDA

International Nuclear Information System (INIS)

Botte, J.; Luycx, P.

2003-01-01

Waste characterization in the end cycle becomes more and more important. Several methods are available for a radiological characterization: from copying the waste producers declaration over a calculation based on known characteristics or measured values to combinations of several techniques. The decision on what technique(s) to be used will be based on several criteria. One also has to evaluate at what stage of the waste treatment process the characterization has to be performed. Recently belgoprocess has performed large efforts and investments to assure a good waste characterization. These are concentrated in studies on historical and recent waste, resulting in isotopic vectors and the purchase of several NDA devices in order to cover the whole scala of waste the company treats. The measuring results always need to be integrated with isotopic vectors. (orig.)

Assessing mixed waste treatment technologies

International Nuclear Information System (INIS)

Berry, J.B.; Bloom, G.A.; Hart, P.W.

1994-01-01

The US Department of Energy (DOE) is responsible for the management and treatment of its mixed low-level wastes (MLLW). As discussed earlier in this conference MLLW are regulated under both the Resource Conservation and Recovery Act and various DOE orders. During the next 5 years, DOE will manage over 1,200,000 m 3 of MLLW and mixed transuranic (MTRU) waste at 50 sites in 22 states (see Table 1). The difference between MLLW and MTRU waste is in the concentration of elements that have a higher atomic weight than uranium. Nearly all of this waste will be located at 13 sites. More than 1400 individual mixed waste streams exist with different chemical and physical matrices containing a wide range of both hazardous and radioactive contaminants. Their containment and packaging vary widely (e.g., drums, bins, boxes, and buried waste). This heterogeneity in both packaging and waste stream constituents makes characterization difficult, which results in costly sampling and analytical procedures and increased risk to workers

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

Incineration as an effective means in Malaysian municipal solid waste treatment

International Nuclear Information System (INIS)

Sharifah, A.S.A.K.; Subari, F.; Zainal Abidin, H.

2006-01-01

Malaysia is in dire need of an alternative to current method in municipal solid waste treatment. An industrial pilot plant incinerator has been constructed at Universiti Teknologi Mara Shah Alam campus. A study has been performed to investigate the performance of the locally developed and manufactured rotary kiln incinerator. On the overall, the temperature profiles are well in agreement with species concentration observed. The emission quality satisfy the air pollution standards and on the overall the rotary kiln incinerator shows great potential in municipal solid waste treatment. (Author)

Commercial waste treatment program annual progress report for FY 1983

Energy Technology Data Exchange (ETDEWEB)

McElroy, J.L.; Burkholder, H.C. (comps.)

1984-02-01

This annual report describes progress during FY 1983 relating to technologies under development by the Commercial Waste Treatment Program, including: development of glass waste form and vitrification equipment for high-level wastes (HLW); waste form development and process selection for transuranic (TRU) wastes; pilot-scale operation of a radioactive liquid-fed ceramic melter (LFCM) system for verifying the reliability of the reference HLW treatment proces technology; evaluation of treatment requirements for spent fuel as a waste form; second-generation waste form development for HLW; and vitrification process control and product quality assurance technologies.

Review and evaluation of metallic TRU nuclear waste consolidation methods

International Nuclear Information System (INIS)

Montgomery, D.R.; Nesbitt, J.F.

1983-08-01

The US Department of Energy established the Commercial Waste Treatment Program to develop, demonstrate, and deploy waste treatment technology. In this report, viable methods are identified that could consolidate the volume of metallic wastes generated in a fuel reprocessing facility. The purpose of this study is to identify, evaluate, and rate processes that have been or could be used to reduce the volume of contaminated/irradiated metallic waste streams and to produce an acceptable waste form in a safe and cost-effective process. A technical comparative evaluation of various consolidation processes was conducted, and these processes were rated as to the feasibility and cost of producing a viable product from a remotely operated radioactive process facility. Out of the wide variety of melting concepts and consolidation systems that might be applicable for consolidating metallic nuclear wastes, the following processes were selected for evaluation: inductoslay melting, rotating nonconsumable electrode melting, plasma arc melting, electroslag melting with two nonconsumable electrodes, vacuum coreless induction melting, and cold compaction. Each process was evaluated and rated on the criteria of complexity of process, state and type of development required, safety, process requirements, and facility requirements. It was concluded that the vacuum coreless induction melting process is the most viable process to consolidate nuclear metallic wastes. 11 references

Treatment of radioactive organics liquid wastes

International Nuclear Information System (INIS)

Morales Galarce, Tania

1999-01-01

Because of the danger that radioactive wastes can pose to society and to the environment a viable treatment alternative must be developed to prepare these wastes for final disposal. The waste studied in this work is a liquid organic waste contaminated with the radioisotope tritium. This must be treated and then changed into solid form in a 200 liter container. This study defined an optimum formulation that immobilizes the liquid waste. The organic waste is first submitted to an absorption treatment, with Celite absorbent, which had the best physical characteristics from the point of view of radioactive waste management. Then this was solidified by forming a cement mortar, using a highly resistant local cement, Polpaico 400. Various mixes were tested, with different water/cement, waste/absorbent and absorbed waste/cement ratios, until a mixture that met the quality control requirements was achieved. The optimum mixture obtained has a water/cement ratio of 0.35 (p/p) that is the amount of water needed to make the mixture workable, and minimum water for hydrating the cement; a waste/absorbent ration of 0.5 (v/v), where the organic liquid is totally absorbed, and is incorporated in the solid's crystalline network; and an absorbed waste/cement ratio of 0.8 (p/p), which represents the minimum amount of cement needed to obtain a solid product with the required mechanical resistance. The mixture's components join together with no problem, to produce a good workable mixture. It takes about 10 hours for the mixture to harden. After 14 days, the resulting solid product has a resistance to compression of 52 Kgf/cm2. The formulation contains 22.9% immobilized organic waste, 46.5% cement, 14.3% Celite and 16.3% water. Organic liquid waste can be treated and a solid product obtained, that meets the qualitative and quantitative parameters required for its disposal. (CW)

Treatment of low level waste water by reverse osmosis

International Nuclear Information System (INIS)

Li Kaijun; Zhang Chuanzhi; Xue Qinhua; Liu Meijun

1987-11-01

A Study on the removal of certain radioactive elements Such as 141 Ce, 51 Cr 134 Cu, 106 Ru and 131 I by Reverse Osmosis and the effect of surface activity agent on property of membrance are described in this paper. RO model is carried out to examine the treatment of actual reactor waste water and radioactive laundry waste water. The removal efficiency of total β is 98%. Three preprocessing (cloth pocket filtrator, hivefiltrator and zone) and membrane cleaning methods (acid, ozone and spongeball) are also investigated

Stabilization Using Phosphate Bonded Ceramics. Salt Containing Mixed Waste Treatment. Mixed Waste Focus Area. OST Reference No. 117

International Nuclear Information System (INIS)

1999-01-01

Throughout the Department of Energy (DOE) complex there are large inventories of homogeneous mixed waste solids, such as wastewater treatment residues, fly ashes, and sludges that contain relatively high concentrations (greater than 15% by weight) of salts. The inherent solubility of salts (e.g., nitrates, chlorides, and sulfates) makes traditional treatment of these waste streams difficult, expensive, and challenging. One alternative is low-temperature stabilization by chemically bonded phosphate ceramics (CBPCs). The process involves reacting magnesium oxide with monopotassium phosphate with the salt waste to produce a dense monolith. The ceramic makes a strong environmental barrier, and the metals are converted to insoluble, low-leaching phosphate salts. The process has been tested on a variety of surrogates and actual mixed waste streams, including soils, wastewater, flyashes, and crushed debris. It has also been demonstrated at scales ranging from 5 to 55 gallons. In some applications, the CBPC technology provides higher waste loadings and a more durable salt waste form than the baseline method of cementitious grouting. Waste form test specimens were subjected to a variety of performance tests. Results of waste form performance testing concluded that CBPC forms made with salt wastes meet or exceed both RCRA and recommended Nuclear Regulatory Commission (NRC) low-level waste (LLW) disposal criteria. Application of a polymer coating to the CBPC may decrease the leaching of salt anions, but continued waste form evaluations are needed to fully assess the deteriorating effects of this leaching, if any, over time.

Basic factors for the treatment and disposal of radioactive wastes

International Nuclear Information System (INIS)

1967-01-01

This manual discusses factors such as type of waste, legislation, climate, location and availability of materials, equipment and services, etc., which must be taken into account before the preliminary evaluation can be made to decide which treatment and disposal methods should be further investigated. As an aid in selecting the most suitable type of waste management system, a questionnaire has been prepared drawing attention to those factors which should be taken into consideration.

STUDY ON WASTE WATER TREATMENT PLANTS

Directory of Open Access Journals (Sweden)

Mariana DUMITRU

2015-04-01

Full Text Available Biogas is more and more used as an alternative source of energy, considering the fact that it is obtained from waste materials and it can be easily used in cities and rural communities for many uses, between which, as a fuel for households. Biogas has many energy utilisations, depending on the nature of the biogas source and the local demand. Generally, biogas can be used for heat production by direct combustion, electricity production by fuel cells or micro-turbines, Combined Hest and Power generation or as vehicle fuel. In this paper we search for another uses of biogas and Anaerobe Digestion substrate, such as: waste water treatment plants and agricultural wastewater treatment, which are very important in urban and rural communities, solid waste treatment plants, industrial biogas plants, landfill gas recovery plants. These uses of biogas are very important, because the gas emissions and leaching to ground water from landfill sites are serious threats for the environment, which increase more and more bigger during the constant growth of some human communities. That is why, in the developed European countries, the sewage sludge is treated by anaerobe digestion, depending on national laws. In Romania, in the last years more efforts were destined to use anaerobe digestion for treating waste waters and management of waste in general. This paper can be placed in this trend of searching new ways of using with maximum efficiency the waste resulted in big communities.

Radiological, physical, and chemical characterization of additional alpha contaminated and mixed low-level waste for treatment at the advanced mixed waste treatment project

International Nuclear Information System (INIS)

Hutchinson, D.P.

1995-07-01

This document provides physical, chemical, and radiological descriptive information for a portion of mixed waste that is potentially available for private sector treatment. The format and contents are designed to provide treatment vendors with preliminary information on the characteristics and properties for additional candidate portions of the Idaho National Engineering Laboratory (INEL) and offsite mixed wastes not covered in the two previous characterization reports for the INEL-stored low-level alpha-contaminated and transuranic wastes. This report defines the waste, provides background information, briefly reviews the requirements of the Federal Facility Compliance Act (P.L. 102-386), and relates the Site Treatment Plans developed under the Federal Facility Compliance Act to the waste streams described herein. Each waste is summarized in a Waste Profile Sheet with text, charts, and tables of waste descriptive information for a particular waste stream. A discussion of the availability and uncertainty of data for these waste streams precedes the characterization descriptions

Radiological, physical, and chemical characterization of additional alpha contaminated and mixed low-level waste for treatment at the advanced mixed waste treatment project

Energy Technology Data Exchange (ETDEWEB)

Hutchinson, D.P.

1995-07-01

This document provides physical, chemical, and radiological descriptive information for a portion of mixed waste that is potentially available for private sector treatment. The format and contents are designed to provide treatment vendors with preliminary information on the characteristics and properties for additional candidate portions of the Idaho National Engineering Laboratory (INEL) and offsite mixed wastes not covered in the two previous characterization reports for the INEL-stored low-level alpha-contaminated and transuranic wastes. This report defines the waste, provides background information, briefly reviews the requirements of the Federal Facility Compliance Act (P.L. 102-386), and relates the Site Treatment Plans developed under the Federal Facility Compliance Act to the waste streams described herein. Each waste is summarized in a Waste Profile Sheet with text, charts, and tables of waste descriptive information for a particular waste stream. A discussion of the availability and uncertainty of data for these waste streams precedes the characterization descriptions.

Absorbing method of iodine in radioactive gaseous wastes

International Nuclear Information System (INIS)

Fukutome, Yutaka; Mifuji, Hiroshi; Ito, Sakae.

1983-01-01

Purpose: To maintain an iodine adsorbing efficiency at a high level by keeping the adsorbing atmosphere to more than a predetermined temperature to thereby suppress the degradation and the activity reduction in zeolite. Method: Adsorption and desorption-regeneration of gaseous wastes are performed in parallel by heating gaseous wastes in a heater and switchingly supplying the same to adsorption columns by way of valve operation. Processed gases are cooled in a cooler and desorbed gases are supplied to an after-treatment device to eliminate or recover iodine 131. In the adsorption column, iodine in gaseous wastes is adsorbed to remove by using zeolite, wherein the adsorbing atmosphere is kept at a temperature higher than 40 0 C. This can prevent the formation of an aqueous HNO 3 solution from NO 2 and H 2 O contained in the gaseous wastes and prevent the degradation of the zeolite adsorption layer. (Kawakami, Y.)

Hanford Site waste treatment/storage/disposal integration

International Nuclear Information System (INIS)

MCDONALD, K.M.

1999-01-01

In 1998 Waste Management Federal Services of Hanford, Inc. began the integration of all low-level waste, mixed waste, and TRU waste-generating activities across the Hanford site. With seven contractors, dozens of generating units, and hundreds of waste streams, integration was necessary to provide acute waste forecasting and planning for future treatment activities. This integration effort provides disposition maps that account for waste from generation, through processing, treatment and final waste disposal. The integration effort covers generating facilities from the present through the life-cycle, including transition and deactivation. The effort is patterned after the very successful DOE Complex EM Integration effort. Although still in the preliminary stages, the comprehensive onsite integration effort has already reaped benefits. These include identifying significant waste streams that had not been forecast, identifying opportunities for consolidating activities and services to accelerate schedule or save money; and identifying waste streams which currently have no path forward in the planning baseline. Consolidation/integration of planned activities may also provide opportunities for pollution prevention and/or avoidance of secondary waste generation. A workshop was held to review the waste disposition maps, and to identify opportunities with potential cost or schedule savings. Another workshop may be held to follow up on some of the long-term integration opportunities. A change to the Hanford waste forecast data call would help to align the Solid Waste Forecast with the new disposition maps

Solid waste treatment volume reduction by compaction or incineration

International Nuclear Information System (INIS)

Vigreux, B.; Carpentier, S.

1985-01-01

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

Solid waste treatment volume reduction by compaction or incineration

International Nuclear Information System (INIS)

Vigreux, B.; Carpentier, S.

1986-01-01

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

Comparative environmental analysis of waste brominated plastic thermal treatments

International Nuclear Information System (INIS)

Bientinesi, M.; Petarca, L.

2009-01-01

The aim of this research activity is to investigate the environmental impact of different thermal treatments of waste electric and electronic equipment (WEEE), applying a life cycle assessment methodology. Two scenarios were assessed, which both allow the recovery of bromine: (A) the co-combustion of WEEE and green waste in a municipal solid waste combustion plant, and (B) the staged-gasification of WEEE and combustion of produced syngas in gas turbines. Mass and energy balances on the two scenarios were set and the analysis of the life cycle inventory and the life cycle impact assessment were conducted. Two impact assessment methods (Ecoindicator 99 and Impact 2002+) were slightly modified and then used with both scenarios. The results showed that scenario B (staged-gasification) had a potentially smaller environmental impact than scenario A (co-combustion). In particular, the thermal treatment of staged-gasification was more energy efficient than co-combustion, and therefore scenario B performed better than scenario A, mainly in the impact categories of 'fossil fuels' and 'climate change'. Moreover, the results showed that scenario B allows a higher recovery of bromine than scenario A; however, Br recovery leads to environmental benefits for both the scenarios. Finally the study demonstrates that WEEE thermal treatment for energy and matter recovery is an eco-efficient way to dispose of this kind of waste

Mixed Waste Treatment Project: Computer simulations of integrated flowsheets

International Nuclear Information System (INIS)

Dietsche, L.J.

1993-12-01

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

ECOLOGICAL AND ECONOMIC SUBSTANTIATION OF SELECTION OF THE METHOD FOR PLASTIC WASTE MANAGEMENT

Directory of Open Access Journals (Sweden)

T. P. Shanina

2015-11-01

Full Text Available Analysis of the classifications of plastic waste from production and consumption is made by various criteria. Distinctive features of the specifi ed waste behavior under various treatment methods (deposition at landfill, incineration and recycling are discussed. Clustering of the polymeric waste by hazard categories of the combustion products is performed. The polyvinyl-chlorides and polycarbonates which generate the most hazardous products under  the combustion are singled out in a particular cluster. The qualitative and quantitative descrip- The qualitative and quantitative description of the plastic waste generated in Ukraine from 2011 to 2013 is provided. Grossemissions of the polyvinylchloride and polystyrene waste incineration products are calculated. Evaluation of the environmental damage resulting from implementation of various methods for plastic waste management is based on an environmental tax rate having a compensatory nature. Potential profit from selling the secondary raw materials, produced from plastic waste, is analysed. Ranking of the potential methods for plastic waste management is presented in the context of ecological and economic substantiation: the most preferable method is production of secondary raw materials (recycled resources; the least preferable one is incineration of the specified wastes.

Treatment and final storage of radioactive wastes from the nuclear fuel cycle

Energy Technology Data Exchange (ETDEWEB)

Krause, H [Kernforschungszentrum Karlsruhe (Germany, F.R.)

1977-05-01

Types, amounts and activity concentrations of the radioactive wastes arising from the different sections of the fuel cycle are described as well as the methods of their treatment and final disposal. By conversion to glass products, highly active fission product solutions can be transferred into a form well suited for final disposal. Low and medium level waste waters are purified so far that safe discharge or reuse is possible. The concentrates thus produced are incorporated into concrete or bitumen. Baling lends itself for treatment of non-combustible solid wastes. Combustible wastes can be incinerated, the residues are incorporated into concrete. For final storage of the conditioned wastes, salt formations in the deep underground are chosen in the Federal Republic of Germany. They offer a series of favourable preconditions for this purpose and guarantee the isolation of the radionuclides from the biocycle over secular periods of time.

Water Mock-up for the Sodium Waste Treatment Process

Energy Technology Data Exchange (ETDEWEB)

Nam, Ho Yun; Kim, Jong Man; Kim, Byung Ho; Lee, Yong Bum [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

2011-05-15

It is important to safely treat the waste sodium which was produced from the sodium cooled fast reactors and the sodium facilities. About 1.3 tons of sodium waste has accumulated at KAERI from the sodium experiments which have been carried out since 1990. Also, large scaled sodium experiments are scheduled to verify the design of the sodium cooled fast reactor. As a treatment method for the waste sodium produced at the sodium facility, an investigation of the reaction procedure of the waste sodium with the sodium hydroxide aqueous has been developed. The NOAH process was developed in France for the treatment of waste sodium produced from sodium facilities and reactors. In the NOAH process, a small amount of sodium waste is continuously injected into the upper space which is formed on the free surface of the aqueous and slowly reacted with sodium hydroxide aqueous. Since the density of the sodium is lower than that of the aqueous, the injected sodium waste sometimes accumulates above the free surface of the sodium hydroxide aqueous, and its reaction rate becomes slow or suddenly increases. In the improved process, the sodium was injected into a reaction vessel filled with a sodium hydroxide aqueous through an atomizing nozzle installed on a lower level than that of the aqueous to maintain the reaction uniformly. Fig.1 shows the sodium waste process which was proposed in KAERI. The aqueous is composed of 60% sodium hydroxide, and its temperature is about 60 .deg. C. The process is an exothermic reaction. The hydrogen gas is generated, and the concentration of the sodium hydroxide increases in this process. It needs several systems for the process, i.e. a waste sodium injection, a cooling of the aqueous, hydrogen ventilation, and neutralization with nitric acid. The atomizing nozzle was designed to inject the sodium with the nitrogen gas which supplies a heat to the sodium to prevent its solidification and to uniformly mix the sodium with the aqueous. There are

Chemical treatment of mixed waste can be done.....Today exclamation point

International Nuclear Information System (INIS)

Honigford, L.; Dilday, D.; Cook, D.; Sattler, J.

1996-01-01

The Chemical Treatment Project is one in a series of projects implemented by the FEMP to treat mixed waste. The projects were initiated to address concerns regarding treatment capacity for mixed waste and to comply with requirements established by the Federal Facility Compliance Act. The Chemical Treatment Project is designed to utilize commercially available mobile technologies to perform treatment at the FEMP site. The waste in the Project consists of a variety of waste types with a wide range of hazards and physical characteristics. The treatment processes to be established for the waste types will be developed by a systematic approach including waste streams evaluation, projectization of the waste streams, and categorization of the stream. This information is utilized to determine the proper train of treatment which will be required to lead the waste to its final destination (i.e., disposal). This approach allows flexibility to manage a wide variety of waste in a cheaper, faster manner than designing a single treatment technology diverse enough to manage all the waste streams

Method for calcining radioactive wastes

International Nuclear Information System (INIS)

Bjorklund, W.J.; McElroy, J.L.; Mendel, J.E.

1979-01-01

A method for the preparation of radioactive wastes in a low leachability form involves calcining the radioactive waste on a fluidized bed of glass frit, removing the calcined waste to melter to form a homogeneous melt of the glass and the calcined waste, and then solidifying the melt to encapsulate the radioactive calcine in a glass matrix

Method of processing solidification product of radioactive waste

International Nuclear Information System (INIS)

Daime, Fumiyoshi.

1988-01-01

Purpose: To improve the long-time stability of solidification products by providing solidification products with liquid tightness, gas tightness, abrasion resistance, etc., of the products in the course of the solidification for the treatment of radioactive wastes. Method: The surface of solidification products prepared by mixing solidifying agents with powder or pellets is entirely covered with high molecular polymer such as epoxy resin. The epoxy resin has excellent properties such as radiation-resistance, heat resistance, water proofness and chemical resistance, as well as have satisfactory mechanical properties. This can completely isolate the solidification products of radioactive wastes from the surrounding atmosphere. (Yoshino, Y.)

Treatment and immobilization of intermediate-level radioactive wastes

International Nuclear Information System (INIS)

Lerch, R.E.; Greenhalgh, W.O.; Partridge, J.A.; Richardson, G.L.

1979-01-01

A new program underway at the Hanford Engineering Development Laboratory (HEDL) to develop and demonstrate treatment and immobilization technologies for intermediate-level wastes (ILW) generated in the nuclear fuel cycle is discussed. ILW are defined as those liquid and solid radioactive wastes, other than high-level wastes and fuel cladding hulls, that in packaged form have radiation dose readings greater than 200 millirem/hr at the packaged surface and 10 millirem/hr at three feet from the surface. The IAEA value of 10 4 Ci/m 3 for ILW defines the upper limit. For comparative purposes, reference is also made to certain aspects of low-level radioactive wastes (LLW). Initial work has defined the sources, quantities and types of wastes which comprise ILW. Because of the wide differences in composition (e.g., acids, salt solutions, resins and zeolites, HEPA filters, etc.) the wastes may require different treatments, particularly those wastes containing volatile contaminants. The various types of ILW have been grouped into categories amenable to similar treatment. Laboratory studies are underway to define treatment technologies for liquid ILW which contain volatile contaminants and to define immobilization parameters for the residues resulting from treatment of ILW. Immobilization agents initially being evaluated for the various residues include cement, urea-formaldehyde, and bitumen although other immobilization agents will be studied. The program also includes development of acceptable test procedures for the final immobilized products as well as development of proposed criteria for storage, transportation, and disposal of the immobilized ILW

Development of plasma melting technology for treatment of low level radioactive waste. Pt. 9. Treatment method for combustible wastes

International Nuclear Information System (INIS)

Yasui, Shinji; Adachi, Kazuo; Amakawa, Masashi

1996-01-01

This paper describes the incineration method for the miscellaneous solid waste containing the low level radioactive combustibles (wood, PE, PVC) in a plasma furnace. The maximum weights of the respective combustibles to be fed into the plasma furnace and the incineration conditions for continuous feeding of the respective combustibles were examined experimentally. As a result, a experimental equation which expresses the maximum weights of the respective combustibles to be fed in reference to the residence time in the plasma furnace was obtained by using apparent reaction rate constants. Furthermore, a calculation method for the feeding intervals in reference to the weights of the combustibles fed each time was obtained for the continuous feeding in the plasma furnace, and the method was found to be consistent with experimental results. (author)

Densified waste form and method for forming

Science.gov (United States)

Garino, Terry J.; Nenoff, Tina M.; Sava Gallis, Dorina Florentina

2015-08-25

Materials and methods of making densified waste forms for temperature sensitive waste material, such as nuclear waste, formed with low temperature processing using metallic powder that forms the matrix that encapsulates the temperature sensitive waste material. The densified waste form includes a temperature sensitive waste material in a physically densified matrix, the matrix is a compacted metallic powder. The method for forming the densified waste form includes mixing a metallic powder and a temperature sensitive waste material to form a waste form precursor. The waste form precursor is compacted with sufficient pressure to densify the waste precursor and encapsulate the temperature sensitive waste material in a physically densified matrix.

Treatment of Bottled Liquid Waste During Remediation of the Hanford 618-10 Burial Ground - 13001

International Nuclear Information System (INIS)

Faulk, Darrin E.; Pearson, Chris M.; Vedder, Barry L.; Martin, David W.

2013-01-01

A problematic waste form encountered during remediation of the Hanford Site 618-10 burial ground consists of bottled aqueous waste potentially contaminated with regulated metals. The liquid waste requires stabilization prior to landfill disposal. Prior remediation activities at other Hanford burial grounds resulted in a standard process for sampling and analyzing liquid waste using manual methods. Due to the highly dispersible characteristics of alpha contamination, and the potential for shock sensitive chemicals, a different method for bottle processing was needed for the 618-10 burial ground. Discussions with the United States Department of Energy (DOE) and United States Environmental Protection Agency (EPA) led to development of a modified approach. The modified approach involves treatment of liquid waste in bottles, up to one gallon per bottle, in a tray or box within the excavation of the remediation site. Bottles are placed in the box, covered with soil and fixative, crushed, and mixed with a Portland cement grout. The potential hazards of the liquid waste preclude sampling prior to treatment. Post treatment verification sampling is performed to demonstrate compliance with land disposal restrictions and disposal facility acceptance criteria. (authors)

Treatment of Bottled Liquid Waste During Remediation of the Hanford 618-10 Burial Ground - 13001

Energy Technology Data Exchange (ETDEWEB)

Faulk, Darrin E.; Pearson, Chris M.; Vedder, Barry L.; Martin, David W. [Washington Closure Hanford, LLC, Richland, WA 99354 (United States)

2013-07-01

A problematic waste form encountered during remediation of the Hanford Site 618-10 burial ground consists of bottled aqueous waste potentially contaminated with regulated metals. The liquid waste requires stabilization prior to landfill disposal. Prior remediation activities at other Hanford burial grounds resulted in a standard process for sampling and analyzing liquid waste using manual methods. Due to the highly dispersible characteristics of alpha contamination, and the potential for shock sensitive chemicals, a different method for bottle processing was needed for the 618-10 burial ground. Discussions with the United States Department of Energy (DOE) and United States Environmental Protection Agency (EPA) led to development of a modified approach. The modified approach involves treatment of liquid waste in bottles, up to one gallon per bottle, in a tray or box within the excavation of the remediation site. Bottles are placed in the box, covered with soil and fixative, crushed, and mixed with a Portland cement grout. The potential hazards of the liquid waste preclude sampling prior to treatment. Post treatment verification sampling is performed to demonstrate compliance with land disposal restrictions and disposal facility acceptance criteria. (authors)

Operation technology of the ventilation system of the radioactive waste treatment facility(II) - Design and operation note

Energy Technology Data Exchange (ETDEWEB)

Lee, K. M.; Lee, B. C.; Bae, S. M. [Korea Atomic Energy Research Institute, Taejon (Korea)

1999-12-01

As the radioactive waste treatment work, such as compaction and/or solidification of wastes, are done directly by the workers in the Radioactive Waste Treatment Facility, the reasonable design and operation of the ventilation system is essential. In this report, the design criteria and specification of the ventilation equipment, system operation method are described for the effective design and operation of ventilation system in the radioactive waste treatment facility. And the anti-vibration work which was done in the Radioactive Waste Treatment Facility in KAERI to reduce the effect of vibration due to the continuous operation of big rotational equipment, the intake fans and the exhaust fans, are described in the report. 11 refs., 10 figs., 12 tabs. (Author)

Process evaluation for treatment of aluminium bearing declad waste

International Nuclear Information System (INIS)

Banerjee, D.; Rao, Manjula A.; Srinivas, C.; Wattal, P.K.

2012-01-01

Declad waste generated by the process of chemical decladding of Al-cladded uranium metal fuel is characterized by highly alkaline, high Al bearing intermediate level waste. It was found that the process developed and adopted in India for plant scale treatment of alkaline intermediate level waste (ILW) is unsuitable for treatment of declad waste. This is mainly due to its exotic characteristics, notably substantial amounts of aluminium in the declad waste. As part of development of treatment scheme for this waste, 137 Cs removal by RFPR has been demonstrated earlier and the present paper reports the results of further processing of the Cs-lean effluent. The waste simulated with respect to the major chemical constituents of stored Al-bearing alkaline ILW after 137 Cs and 90 Sr removal by ion exchange, is used in this study

Experiences in the treatment of radioactive wastes

Energy Technology Data Exchange (ETDEWEB)

Krause, H [Kernforschungszentrum Karlsruhe (Germany, F.R.)

1977-04-01

Low and medium level wastes have been routinely treated for many years at the technical scale with good success and processed to products safe for final storage so that inadmissible contamination of the environment whatsoever has not occurred. In the majority of cases the maximum permissible values were not reached by far. The treatment of highly active and ..cap alpha..-wastes has not yet been demonstrated at the technical scale because these accumulate to a larger extent only in a further developed nuclear technology. The methods developed for this have proved their feasibility and reached such a degree of maturity that it can be assumed that they will be available to the extent and at the time given by the general development of nuclear technology.

Experiences in the treatment of radioactive wastes

International Nuclear Information System (INIS)

Krause, H.

1977-01-01

Low and medium level wastes have been routinely treated for many years at the technical scale with good success and processed to products safe for final storage so that inadmissible contamination of the environment whatsoever has not occurred. In the majority of cases the maximum permissible values were not reached by far. The treatment of highly active and α-wastes has not yet been demonstrated at the technical scale because these accumulate to a larger extent only in a further developed nuclear technology. The methods developed for this have proved their feasibility and reached such a degree of maturity that it can be assumed that they will be available to the extent and at the time given by the general development of nuclear technology. (orig.) [de

Radioactive Demonstrations Of Fluidized Bed Steam Reforming As A Supplementary Treatment For Hanford's Low Activity Waste And Secondary Wastes

International Nuclear Information System (INIS)

Jantzen, C.; Crawford, C.; Cozzi, A.; Bannochie, C.; Burket, P.; Daniel, G.

2011-01-01

The U.S. Department of Energy's Office of River Protection (ORP) is responsible for the retrieval, treatment, immobilization, and disposal of Hanford's tank waste. Currently there are approximately 56 million gallons of highly radioactive mixed wastes awaiting treatment. A key aspect of the River Protection Project (RPP) cleanup mission is to construct and operate the Waste Treatment and Immobilization Plant (WTP). The WTP will separate the tank waste into high-level and low-activity waste (LAW) fractions, both of which will subsequently be vitrified. The projected throughput capacity of the WTP LAW Vitrification Facility is insufficient to complete the RPP mission in the time frame required by the Hanford Federal Facility Agreement and Consent Order, also known as the Tri-Party Agreement (TPA), i.e. December 31, 2047. Therefore, Supplemental Treatment is required both to meet the TPA treatment requirements as well as to more cost effectively complete the tank waste treatment mission. The Supplemental Treatment chosen will immobilize that portion of the retrieved LAW that is not sent to the WTP's LAW Vitrification facility into a solidified waste form. The solidified waste will then be disposed on the Hanford site in the Integrated Disposal Facility (IDF). In addition, the WTP LAW vitrification facility off-gas condensate known as WTP Secondary Waste (WTP-SW) will be generated and enriched in volatile components such as Cs-137, I-129, Tc-99, Cl, F, and SO4 that volatilize at the vitrification temperature of 1150 C in the absence of a continuous cold cap. The current waste disposal path for the WTP-SW is to recycle it to the supplemental LAW treatment to avoid a large steady state accumulation in the pretreatment-vitrification loop. Fluidized Bed Steam Reforming (FBSR) offers a moderate temperature (700-750 C) continuous method by which LAW and/or WTP-SW wastes can be processed irrespective of whether they contain organics, nitrates, sulfates/sulfides, chlorides

Plasma technology for waste treatment

International Nuclear Information System (INIS)

Cohn, D.R.

1995-01-01

Improved environmental cleanup technology is needed to meet demanding goals for remediation and treatment of future waste streams. Plasma technology has unique features which could provide advantages of reduced secondary waste, lower cost, and onsite treatment for a wide variety of applications. Plasma technology can provide highly controllable processing without the need for combustion heating. It can be used to provide high temperature processing (∼10,000 degrees C). Plasma technology can also be employed for low temperature processing (down to room temperature range) through selective plasma chemistry. A graphite electrode arc plasma furnace at MIT has been used to investigate high temperature processing of simulated solid waste for Department of Energy environmental cleanup applications. Stable, non-leachable glass has been produced. To ensure reliable operation and to meet environmental objectives, new process diagnostics have been developed to measure furnace temperature and to determine metals emissions in the gaseous effluent. Selective plasma destruction of dilute concentrations of hazardous compounds in gaseous waste streams has been investigated using electron beam generated plasmas. Selective destruction makes it possible to treat the gas steam at relatively low temperatures in the 30-300 degrees C range. On-line infrared measurements have been used in feedback operation to maximize efficiency and ensure desired performance. Plasma technology and associated process diagnostics will be used in future studies of a wide range of waste streams

Radioactive Demonstration Of Final Mineralized Waste Forms For Hanford Waste Treatment Plant Secondary Waste By Fluidized Bed Steam Reforming Using The Bench Scale Reformer Platform

International Nuclear Information System (INIS)

Crawford, C.; Burket, P.; Cozzi, A.; Daniel, W.; Jantzen, C.; Missimer, D.

2012-01-01

The U.S. Department of Energy's Office of River Protection (ORP) is responsible for the retrieval, treatment, immobilization, and disposal of Hanford's tank waste. Currently there are approximately 56 million gallons of highly radioactive mixed wastes awaiting treatment. A key aspect of the River Protection Project (RPP) cleanup mission is to construct and operate the Waste Treatment and Immobilization Plant (WTP). The WTP will separate the tank waste into high-level and low-activity waste (LAW) fractions, both of which will subsequently be vitrified. The projected throughput capacity of the WTP LAW Vitrification Facility is insufficient to complete the RPP mission in the time frame required by the Hanford Federal Facility Agreement and Consent Order, also known as the Tri-Party Agreement (TPA), i.e. December 31, 2047. Therefore, Supplemental Treatment is required both to meet the TPA treatment requirements as well as to more cost effectively complete the tank waste treatment mission. In addition, the WTP LAW vitrification facility off-gas condensate known as WTP Secondary Waste (WTP-SW) will be generated and enriched in volatile components such as 137 Cs, 129 I, 99 Tc, Cl, F, and SO 4 that volatilize at the vitrification temperature of 1150 C in the absence of a continuous cold cap (that could minimize volatilization). The current waste disposal path for the WTP-SW is to process it through the Effluent Treatment Facility (ETF). Fluidized Bed Steam Reforming (FBSR) is being considered for immobilization of the ETF concentrate that would be generated by processing the WTP-SW. The focus of this current report is the WTP-SW. FBSR offers a moderate temperature (700-750 C) continuous method by which WTP-SW wastes can be processed irrespective of whether they contain organics, nitrates, sulfates/sulfides, chlorides, fluorides, volatile radionuclides or other aqueous components. The FBSR technology can process these wastes into a crystalline ceramic (mineral) waste form

Membrane technologies for liquid radioactive waste treatment

International Nuclear Information System (INIS)

Chmielewski, A.G.; Harasimowicz, M.; Zakrzewska-Trznadel, G.

1998-01-01

At Institute of Nuclear Chemistry and Technology (INCT) the membrane method for purification of radioactive wastes applied such processes as ultrafiltration (UF), 'seeded' ultrafiltration and reverse osmosis (RO) was developed. On the basis of the results obtained in laboratory experiments the pilot plant for radioactive effluents treatment was built. The plant was composed of UF unit (AMICON H 26P30 capillary module) and two RO units (NITTO NTR 739 HF S-4 spiral wound LPRO modules). The capacity of the pilot plant was up to 200 L/h and the specific activity of wastes purified in the system - below 10 4 Bq/L. Decontamination factor for entire system is higher than 5 x10 3 . Another possibility for radioactive wastes treatment is membrane distillation (MD), non-isothermal process employing hydrophobic polymer membrane, which is developed at INCT now. Preliminary tests with liquid radwaste were carried out on laboratory unit with permeation test-cell holding flat sheet membrane. As a hydrophobic barrier membranes made of two polymers were used: polytetrafluoroethylene (PTFE) and polypropylene (PP). The process was arranged in direct contact membrane distillation configuration. The permeate condensed directly in the cold stream (distilled water) and retentate was enriched in radionuclides. The further experiments carried out with capillary module BFMF 06-30-33 (Euro-Sep Ltd.) with polypropylene capillaries, diameter 0.33 mm and cut off 0.6 μm proved previous results. A pilot plant employing GORE-TEX membrane distillation was constructed. The plant can clean the low-level radioactive wastes from nuclear centre, at a throughput about 0.05 m 3 /h

Greater-Than-Class C low-level radioactive waste treatment technology evaluation

International Nuclear Information System (INIS)

Garrison, T.W.; Fischer, D.K.

1993-01-01

This report was developed to provide the Greater-Than-Class C Low-Level Radioactive Waste Management Program with criteria and a methodology to select candidate treatment technologies for Greater-Than-Class C low-level radioactive waste (GTCC LLW) destined for dedicated storage and ultimately disposal. The technology selection criteria are provided in a Lotus spreadsheet format to allow the methodology to evolve as the GTCC LLW Program evolves. It is recognized that the final disposal facility is not yet defined; thus, the waste acceptance criteria and other facility-specific features are subject to change. The spreadsheet format will allow for these changes a they occur. As additional treatment information becomes available, it can be factored into the analysis. The technology selection criteria were established from program goals, draft waste acceptance criteria for dedicated storage (including applicable regulations), and accepted remedial investigation methods utilized under the Comprehensive Environmental Response, Compensation, and Liability Act. Kepner-Tregoe decisionmaking techniques are used to compare and rank technologies against the criteria

Technology for safe treatment of radioisotope organic wastes

Energy Technology Data Exchange (ETDEWEB)

Oh, Won Jin; Park, Chong Mook; Choi, W. K.; Lee, K. W.; Moon, J. K.; Yang, H. Y.; Kim, B. T.; Park, S. C

1999-12-01

An examination of chemical and radiological characteristics of RI organic liquid waste, wet oxidation by Fenton reaction and decomposition liquid waste treatment process were studied. These items will be applied to develop the equipment of wet oxidation and decomposition liquid waste treatment mixed processes for the safe treatment of RI organic liquid waste which is consisted of organic solvents such as toluene, alcohol and acetone. Two types of toluene solutions were selected as a candidate decomposition material. As for the first type, the concentration of toluene was above 20 vol percent. As for the second type, the solubility of toluene was considered. The decomposition ration by Fenton reaction was above 95 percent for both of them. From the adsorption equilibrium tests, a -Na{sup +} substituted/acid treated activated carbon and Zeocarbon mixed adsorbent was selected for the fixed adsorption column. This mixed adsorbent will be used to obtain the basic design data of liquid waste purification equipment for the treatment of decomposition liquid waste arising from the wet oxidation process. Solidification and degree of strength tests were performed with the simulated sludge/spent adsorbent of MgO as an oxide type and KH{sub 2}PO{sub 4}. From the test results, the design and fabrication of wet oxidation and liquid waste purification process equipment was made, and a performance test was carried out. (author)

Technology for safe treatment of radioisotope organic wastes

International Nuclear Information System (INIS)

Oh, Won Jin; Park, Chong Mook; Choi, W. K.; Lee, K. W.; Moon, J. K.; Yang, H. Y.; Kim, B. T.; Park, S. C.

1999-12-01

An examination of chemical and radiological characteristics of RI organic liquid waste, wet oxidation by Fenton reaction and decomposition liquid waste treatment process were studied. These items will be applied to develop the equipment of wet oxidation and decomposition liquid waste treatment mixed processes for the safe treatment of RI organic liquid waste which is consisted of organic solvents such as toluene, alcohol and acetone. Two types of toluene solutions were selected as a candidate decomposition material. As for the first type, the concentration of toluene was above 20 vol percent. As for the second type, the solubility of toluene was considered. The decomposition ration by Fenton reaction was above 95 percent for both of them. From the adsorption equilibrium tests, a -Na + substituted/acid treated activated carbon and Zeocarbon mixed adsorbent was selected for the fixed adsorption column. This mixed adsorbent will be used to obtain the basic design data of liquid waste purification equipment for the treatment of decomposition liquid waste arising from the wet oxidation process. Solidification and degree of strength tests were performed with the simulated sludge/spent adsorbent of MgO as an oxide type and KH 2 PO 4 . From the test results, the design and fabrication of wet oxidation and liquid waste purification process equipment was made, and a performance test was carried out. (author)

Incorporating regulatory considerations into waste treatment technology development

International Nuclear Information System (INIS)

Siegel, M.R.; Powell, J.A.; Williams, T.A.; Kuusinen, T.L.; Lesperance, A.M.

1991-02-01

It is generally recognized that the development of new and innovative waste treatment technologies can significantly benefit the US Department of Energy's (DOE) environmental restoration and waste management program. DOE has established a research, development, demonstration, testing, and evaluation (RDDT ampersand E) program, managed by its Office of Technology Development, to encourage and direct the development of new waste treatment and management technologies. The treatment, storage, and disposal of hazardous and radioactive waste is heavily regulated both at the federal and state levels. In order to achieve the goals of applying the best new technologies in the fastest and most cost-effective manner possible, it is essential that regulatory factors be considered early and often during the development process. This paper presents a number of regulatory issues that are relevant to any program intended to encourage the development of new waste treatment and management technologies. It will also address how the use of these basic regulatory considerations can help ensure that technologies that are developed are acceptable to regulators and can therefore be deployed in the field. 2 refs

Conceptual project of waste treatment plant of CDTN

International Nuclear Information System (INIS)

Gabriel, J.L.; Astolfi, D.

1983-01-01

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

A Low Temperature Detoxification Method for Treatment of Chrysotile-Containing Waste Roofing Slate

Directory of Open Access Journals (Sweden)

Hwanju Jo

2017-08-01

Full Text Available In this study, we evaluated a two-step process for detoxification of waste roofing slate, involving cement hydrate removal and low temperature detoxification using oxalic acid. These treatments were conducted on raw material and intermediate product, respectively. Cement hydrate removal effectively eliminated most Ca-containing cement hydrate components from the raw material under the following conditions: HCl to solid ratio: 0.456 g/g, reaction time: 2 h, and solid to liquid ratio: 0.124 g/mL. Following low temperature (~100 °C detoxification of intermediate product obtained after cement hydrate removal, chrysotile in waste roofing slate was effectively transformed to Mg-oxalate under conditions of oxalic acid to solid ratio of >0.67 g/g.

The integral treatment of urban solid wastes. Experience at Spain

International Nuclear Information System (INIS)

Calderon U, R.

1995-01-01

In this work, which is the origin of the urban solid wastes in a City, how is it classify and which are the most important methods for its elimination, once have been collected are presented. Statistics on the Spanish Case, how is the treatment system and which are the most representative methods for its elimination is describe

Fabrication of hydroxyapatite from fish bones waste using reflux method

Science.gov (United States)

Cahyanto, A.; Kosasih, E.; Aripin, D.; Hasratiningsih, Z.

2017-02-01

The aim of this present study was to investigate the fabrication of hydroxyapatites, which were synthesized from fish bone wastes using reflux method. The fish bone wastes collected from the restaurant were brushed and boiled at 100°C for 10 minutes to remove debris and fat. After drying, the fish bones were crushed, and ball milled into a fine powder. The fish bone wastes were then processed by refluxing using KOH and H3PO4 solutions. The samples were calcined at 900°C and characterized by X-Ray Diffraction (XRD) and Fourier Transform Infrared Spectrometry (FT-IR). The XRD pattern of samples after treatment revealed that the peak of hydroxyapatite was observed and the bands of OH- and PO4 3- were observed by FT-IR. The scanning electron microscope evaluation of sample showed the entangled crystal and porous structure of hydroxyapatite. In conclusion, the hydroxyapatite was successfully synthesized from fish bone wastes using reflux method.

Study of the Treatment of the Liquid Radioactive Waste Nong Son Uranium Ore Processing

International Nuclear Information System (INIS)

Nguyen Ba Tien; Trinh Giang Huong; Luu Cao Nguyen; Harvey, L.K.; Tran Van Quy

2011-01-01

Liquid waste from Nong Son uranium ore processing is treated with concentrated acid, agglomerated, leached, run through ion exchange and then treated with H 2 O 2 to precipitate yellowcake. The liquid radioactive waste has a pH of 1.86 and a high content of radioactive elements, such as: [U] 143.898 ppm and [Th] = 7.967 ppm. In addition, this waste contains many polluted chemical elements with high content, such as arsenic, mercury, aluminum, iron, zinc, magnesium, manganese and nickel. The application of the general method as one stage precipitation or precipitation in coordination with BaCl 2 is not effective. These methods generated a large amount of sludge with poor settling characteristics. The volume of final treated waste was large. This paper introduces the investigation of the treatment of this liquid radioactive waste by the method of two stage of precipitation in association with polyaluminicloride (PAC) and polymer. The impact of factors: pH, neutralizing agents, quantity of PAC and polymer to effect precipitation and improve the settling characteristics during processing was studied. The results showed that the processing of liquid radioactive waste treatment through two stages: first stage at pH = 3 and the second stage at pH = 8.0 with limited PAC and polymer (A 101) resulted in significant reduced volume of the treated waste. The discharged liquid satisfied the requirement of the National Technical Regulation on Industrial Waste Water (QCVN 24:2009). (author)

US Department of Energy interim mixed waste inventory report: Waste streams, treatment capacities and technologies

International Nuclear Information System (INIS)

1993-04-01

The United States Department of Energy (DOE) has prepared this report to provide an inventory of its mixed wastes and treatment capacities and technologies in response to section 3021(a) of the Resource Conservation and Recovery Act (RCRA), as amended by section 105(a) of the Federal Facility Compliance Act (FFCA) of 1992 (Pub. L. No. 102-386). DOE has prepared this report for submission to EPA and the States in which DOE stores, generates, or treats mixed wastes. As required by the FFCA, this report contains: a national inventory of all mixed wastes in the DOE system that are currently stored or will be generated over the next five years, including waste stream name, description, EPA waste codes, basis for characterization (i.e., sampling and analysis or process knowledge), effect of radionuclides on treatment, quantity stored that is subject to the Land Disposal Restrictions (LDRs) storage prohibition, quantity stored that is not subject to the LDRS, expected generation over the next five years, Best Demonstrated Available Technology (BDAT) used for developing the LDR requirements, and waste minimization activities; and a national inventory of mixed waste treatment capacities and technologies, including information such as the descriptions, capacities, and locations of all existing and proposed treatment facilities, explanations for not including certain existing facilities in capacity evaluations, information to support decisions on unavailability of treatment technologies for certain mixed wastes, and the planned technology development activities

Waste Treatment Technology Process Development Plan For Hanford Waste Treatment Plant Low Activity Waste Recycle

International Nuclear Information System (INIS)

McCabe, Daniel J.; Wilmarth, William R.; Nash, Charles A.

2013-01-01

The purpose of this Process Development Plan is to summarize the objectives and plans for the technology development activities for an alternative path for disposition of the recycle stream that will be generated in the Hanford Waste Treatment Plant Low Activity Waste (LAW) vitrification facility (LAW Recycle). This plan covers the first phase of the development activities. The baseline plan for disposition of this stream is to recycle it to the WTP Pretreatment Facility, where it will be concentrated by evaporation and returned to the LAW vitrification facility. Because this stream contains components that are volatile at melter temperatures and are also problematic for the glass waste form, they accumulate in the Recycle stream, exacerbating their impact on the number of LAW glass containers. Approximately 32% of the sodium in Supplemental LAW comes from glass formers used to make the extra glass to dilute the halides to acceptable concentrations in the LAW glass, and reducing the halides in the Recycle is a key component of this work. Additionally, under possible scenarios where the LAW vitrification facility commences operation prior to the WTP Pretreatment facility, this stream does not have a proven disposition path, and resolving this gap becomes vitally important. This task seeks to examine the impact of potential future disposition of this stream in the Hanford tank farms, and to develop a process that will remove radionuclides from this stream and allow its diversion to another disposition path, greatly decreasing the LAW vitrification mission duration and quantity of glass waste. The origin of this LAW Recycle stream will be from the Submerged Bed Scrubber (SBS) and the Wet Electrostatic Precipitator (WESP) from the LAW melter off-gas system. The stream is expected to be a dilute salt solution with near neutral pH, and will likely contain some insoluble solids from melter carryover or precipitates of scrubbed components (e.g. carbonates). The soluble

Waste Treatment Technology Process Development Plan For Hanford Waste Treatment Plant Low Activity Waste Recycle

Energy Technology Data Exchange (ETDEWEB)

McCabe, Daniel J.; Wilmarth, William R.; Nash, Charles A.

2013-08-29

The purpose of this Process Development Plan is to summarize the objectives and plans for the technology development activities for an alternative path for disposition of the recycle stream that will be generated in the Hanford Waste Treatment Plant Low Activity Waste (LAW) vitrification facility (LAW Recycle). This plan covers the first phase of the development activities. The baseline plan for disposition of this stream is to recycle it to the WTP Pretreatment Facility, where it will be concentrated by evaporation and returned to the LAW vitrification facility. Because this stream contains components that are volatile at melter temperatures and are also problematic for the glass waste form, they accumulate in the Recycle stream, exacerbating their impact on the number of LAW glass containers. Approximately 32% of the sodium in Supplemental LAW comes from glass formers used to make the extra glass to dilute the halides to acceptable concentrations in the LAW glass, and reducing the halides in the Recycle is a key component of this work. Additionally, under possible scenarios where the LAW vitrification facility commences operation prior to the WTP Pretreatment facility, this stream does not have a proven disposition path, and resolving this gap becomes vitally important. This task seeks to examine the impact of potential future disposition of this stream in the Hanford tank farms, and to develop a process that will remove radionuclides from this stream and allow its diversion to another disposition path, greatly decreasing the LAW vitrification mission duration and quantity of glass waste. The origin of this LAW Recycle stream will be from the Submerged Bed Scrubber (SBS) and the Wet Electrostatic Precipitator (WESP) from the LAW melter off-gas system. The stream is expected to be a dilute salt solution with near neutral pH, and will likely contain some insoluble solids from melter carryover or precipitates of scrubbed components (e.g. carbonates). The soluble

MOCVD waste gas treatment

International Nuclear Information System (INIS)

Geelen, A. van; Bink, P.H.M.; Giling, L.J.

1993-01-01

A large scale production of GaAs based solar cells with MOCVD will give rise to a considerable use of arsine. Therefore a gas treatment system is needed to convert the waste gases into less toxic compounds. In this study seven different gas treatment systems for MOCVD are compared by quantifying the environmental aspects. The systems are divided in wet systems, adsorption systems and thermal systems. The smallest amount of waste is produced by adsorption and thermal systems. Adsorption systems use the smallest amount of energy. The amount of primary materials used for the equipment varies per system. All systems are safe, but adsorption systems are simplest. At the moment, adsorption systems are probably the best choice from an environmental point of view. Nevertheless thermal systems have some potential advantages which make them interesting for the future

Grout treatment facility dangerous waste permit application

International Nuclear Information System (INIS)

1992-07-01

The Grout Treatment Facility (GTF) will provide permanent disposal for approximately 43 Mgal of low-level radioactive liquid waste currently being stored in underground tanks on the Hanford Site. The first step in permanent disposal is accomplished by solidifying the liquid waste with cementitious dry materials. The resulting grout is cast within underground vaults. This report on the GTF contains information on the following: Geologic data, hydrologic data, groundwater monitoring program, information, detection monitoring program, groundwater characterization drawings, building emergency plan--grout treatment facility, response action plan for grout treatment facility, Hanford Facility contingency plan, training course descriptions, overview of the Hanford Facility Grout Performance, assessment, bland use and zoning map, waste minimization plan, cover design engineering report, and clay liners (ADMIXTURES) in semiarid environments

Mixed and Low-Level Waste Treatment Facility project

International Nuclear Information System (INIS)

1992-04-01

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

Health-Care Waste Treatment Technology Selection Using the Interval 2-Tuple Induced TOPSIS Method

Directory of Open Access Journals (Sweden)

Chao Lu

2016-06-01

Full Text Available Health-care waste (HCW management is a major challenge for municipalities, particularly in the cities of developing nations. Selecting the best treatment technology for HCW can be regarded as a complex multi-criteria decision making (MCDM issue involving a number of alternatives and multiple evaluation criteria. In addition, decision makers tend to express their personal assessments via multi-granularity linguistic term sets because of different backgrounds and knowledge, some of which may be imprecise, uncertain and incomplete. Therefore, the main objective of this study is to propose a new hybrid decision making approach combining interval 2-tuple induced distance operators with the technique for order preference by similarity to an ideal solution (TOPSIS for tackling HCW treatment technology selection problems with linguistic information. The proposed interval 2-tuple induced TOPSIS (ITI-TOPSIS can not only model the uncertainty and diversity of the assessment information given by decision makers, but also reflect the complex attitudinal characters of decision makers and provide much more complete information for the selection of the optimum disposal alternative. Finally, an empirical example in Shanghai, China is provided to illustrate the proposed decision making method, and results show that the ITI-TOPSIS proposed in this paper can solve the problem of HCW treatment technology selection effectively.

Treatment of Uranium-Contaminated Concrete for Reducing Secondary Radioactive Waste

Energy Technology Data Exchange (ETDEWEB)

Kim, Seung Soo; Han, G. S; Park, U. K; Kim, G. N.; Moon, J. K. [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

2014-10-15

A volume reduction of the concrete waste by appropriate treatment technologies will decrease the amount of waste to be disposed of and result in a reduction of the disposal cost and an enhancement of the efficiency of the disposal site. Our group has developed a decontamination process for uranium-contaminated (U-contaminated) concrete, and some experiments were performed to reduce the second radioactive waste. A decontamination process was developed to remove uranium from concrete waste. The yellow or brown colored surface of the wall brick with high concentration of uranium was removed by a chisel until the radioactivity of remaining block reached less than 1 Bq/g. The concrete waste coated with epoxy was directly burned by an oil flame, and the burned surface was then removed using the same method as the treatment of the brick. The selective mechanical removal of the concrete block reduced the amount of secondary radioactive waste. The concrete blocks without an epoxy were crushed to below 30 mm and sifted to 1 mm. When the concrete pieces larger than 1 mm were sequentially washed with a clear recycle solution and 1.0 M of nitric acid, their radioactivity reached below the limit value of uranium for self-disposal. For the concrete pieces smaller than 1 mm, a rotary washing machine and electrokinetic equipment were also used.

Treatment of Uranium-Contaminated Concrete for Reducing Secondary Radioactive Waste

International Nuclear Information System (INIS)

Kim, Seung Soo; Han, G. S; Park, U. K; Kim, G. N.; Moon, J. K.

2014-01-01

A volume reduction of the concrete waste by appropriate treatment technologies will decrease the amount of waste to be disposed of and result in a reduction of the disposal cost and an enhancement of the efficiency of the disposal site. Our group has developed a decontamination process for uranium-contaminated (U-contaminated) concrete, and some experiments were performed to reduce the second radioactive waste. A decontamination process was developed to remove uranium from concrete waste. The yellow or brown colored surface of the wall brick with high concentration of uranium was removed by a chisel until the radioactivity of remaining block reached less than 1 Bq/g. The concrete waste coated with epoxy was directly burned by an oil flame, and the burned surface was then removed using the same method as the treatment of the brick. The selective mechanical removal of the concrete block reduced the amount of secondary radioactive waste. The concrete blocks without an epoxy were crushed to below 30 mm and sifted to 1 mm. When the concrete pieces larger than 1 mm were sequentially washed with a clear recycle solution and 1.0 M of nitric acid, their radioactivity reached below the limit value of uranium for self-disposal. For the concrete pieces smaller than 1 mm, a rotary washing machine and electrokinetic equipment were also used

Waste treatment of ships. Change in understanding of wastes and trend of waste treatment systems; Senjo no haikibutsu shori. 1. Haikibutsu ni taisuru ninshiki no henka to shori hoshiki no doko

Energy Technology Data Exchange (ETDEWEB)

Inatomi, M. [Hitachi Zosen Corp., Osaka (Japan)

1996-07-25

This paper explains treatment of wastes produced in ships. Wastes produced in ships should be essentially treated on ships. Since storage and transport of difficult-to-treat wastes to harbor for land treatment is expensive, wastes produced in ships are treated on ships as much as possible. Combustibles such as waste oil, plastics, paper and wood fiber waste are treated by incinerator. Food waste is dumped into the sea after crushing by disposer. Excrement and urine are dumped into the sea through a waste water treatment plant. Oil content in oily bilge is burned after heating and vapor separation. Food waste is temporarily stored in ships because its dumping along the coast and into harbor is impossible. Kitchen refuse decomposer utilizing bacteria was proposed for ships. Press for used cans and crushing/thermal compaction/storage equipment for plastics were also put on the market. The primary regulation on diesel engine exhaust gas may be cleared by improvement of engine bodies. 1 ref., 1 fig., 1 tab.

Seminar on waste treatment and disposal

International Nuclear Information System (INIS)

Sneve, Malgorzata Karpow; Snihs, Jan Olof

1999-01-01

Leading abstract. A seminar on radioactive waste treatment and disposal was held 9 - 14 November 1998 in Oskarshamn, Sweden. The objective of the seminar was to exchange information on national and international procedures, practices and requirements for waste management. This information exchange was intended to promote the development of a suitable strategy for management of radioactive waste in Northwest Russia to be used as background for future co-operation in the region. The seminar focused on (1) overviews of international co-operation in the waste management field and national systems for waste management, (2) experiences from treatment of low- and intermediate-level radioactive waste, (3) the process of determining the options for final disposal of radioactive waste, (4) experiences from performance assessments and safety analysis for repositories intended for low- and intermediate level radioactive waste, (5) safety of storage and disposal of high-level waste. The seminar was jointly organised and sponsored by the Swedish Radiation Protection Institute (SSI), the Norwegian Radiation Protection Authority (NRPA), the Nordic Nuclear Safety Research (NKS) and the European Commission. A Russian version of the report is available. In brief, the main conclusions are: (1) It is the prerogative of the Russian federal Government to devise and implement a waste management strategy without having to pay attention to the recommendations of the meeting, (2) Some participants consider that many points have already been covered in existing governmental documents, (3) Norway and Sweden would like to see a strategic plan in order to identify how and where to co-operate best, (4) There is a rigorous structure of laws in place, based on over-arching environmental laws, (5) Decommissioning of submarines is a long and complicated task, (6) There are funds and a desire for continued Norway/Sweden/Russia co-operation, (7) Good co-operation is already taking place

Seminar on waste treatment and disposal

Energy Technology Data Exchange (ETDEWEB)

Sneve, Malgorzata Karpow; Snihs, Jan Olof

1999-07-01

Leading abstract. A seminar on radioactive waste treatment and disposal was held 9 - 14 November 1998 in Oskarshamn, Sweden. The objective of the seminar was to exchange information on national and international procedures, practices and requirements for waste management. This information exchange was intended to promote the development of a suitable strategy for management of radioactive waste in Northwest Russia to be used as background for future co-operation in the region. The seminar focused on (1) overviews of international co-operation in the waste management field and national systems for waste management, (2) experiences from treatment of low- and intermediate-level radioactive waste, (3) the process of determining the options for final disposal of radioactive waste, (4) experiences from performance assessments and safety analysis for repositories intended for low- and intermediate level radioactive waste, (5) safety of storage and disposal of high-level waste. The seminar was jointly organised and sponsored by the Swedish Radiation Protection Institute (SSI), the Norwegian Radiation Protection Authority (NRPA), the Nordic Nuclear Safety Research (NKS) and the European Commission. A Russian version of the report is available. In brief, the main conclusions are: (1) It is the prerogative of the Russian federal Government to devise and implement a waste management strategy without having to pay attention to the recommendations of the meeting, (2) Some participants consider that many points have already been covered in existing governmental documents, (3) Norway and Sweden would like to see a strategic plan in order to identify how and where to co-operate best, (4) There is a rigorous structure of laws in place, based on over-arching environmental laws, (5) Decommissioning of submarines is a long and complicated task, (6) There are funds and a desire for continued Norway/Sweden/Russia co-operation, (7) Good co-operation is already taking place.

Study on treatment of distilled ammonia waste water from coke plant with activated carbon-NaClO catalytic oxidation method

Energy Technology Data Exchange (ETDEWEB)

Luo, D.; Yi, P.; Liu, J.; Chen, A. [Xiangtan Polytechnic University, Xiangtan (China). Dept. of Chemical Enginering

2001-12-01

Catalytic oxidation method for the treatment of distilled ammonia waste water from coke plant was investigated using activated carbon as catalyst and NaClO as oxidant. The influences of main factors, such as NaClO, activated carbon, pH and reactionary time were discussed. The results showed that under the conditions of 25{degree}C, NaClO/CODO=1.5, carbon/NaClO=0.6 and pH=3.0, the reaction completed within 120 minutes with 99.5% of phenol removal and 75.8% of COD removal when the distilled ammonia waste water from coke plant which containing phenol 510 mg/L and CODO 8420 mg/L was treated. 13 refs., 4 figs.

Research and development on low level liquid waste treatment in Thailand

International Nuclear Information System (INIS)

Yamkate, P.; Sinakhom, F.; Punnachaiya, M.; Chantaraprachoom, N.; Srisorn, S.

1996-01-01

The studies have been directed towards several subjects concerning the treatment technologies of low level waste. The simple physico-chemical method has been studied for applying to many kind of waste streams such as reactor waste, isotope production waste and liquid waste from the hospital. The characterization of inorganic ion-exchangers including the effect of pH, equilibrium time, temperature and concentration of such ion-exchangers were tested and the optimum condition of the sorption of C x on the exchangers are reported. The results from the investigation on the efficiencies of detergents in the radioactive decontamination reveal that the local simple brand machine-washed detergents. which is very cheap, can be best used as the decontaminating agent instead of the more expensive imported one. It is found that chemical precipitation methods i.e. phosphate coagulation, copper ferrocyanide coagulation and cobalt precipitation method can be used for treating of the waste stream arising successfully. In considering of the immobilizing process of treated waste, cementation is advised to be used and, therefore, subjects to be evaluated. The basic properties of cement-waste products as well the leachability of a particular types of sludge waste at 15-40% waste loading were investigated. The result reveals that, cement waste forms of inorganic ion-exchanger and of sludge waste from chemical precipitation of decontamination waste, exhibit high compressive strength and a low leach rates. The compressive strength of 118-207 Kg/cm 2 were found for the optimum waste products originated from various exchangers and 15-20% loading of sludge waste. The leachability of Co-60, Cs-134 and Sr-85 from 15-40% loading of cement waste for 30 days were studied. The cumulative fraction leached rate of Cs-134 from sludge-cement wastes was found to be about 17 x 10 - 3 g/cm 2 for 25 degree C and 50 degree C at 30 days leaching time respectively, while there were no leaching of Sr-85 and

Radiobiological waste treatment-ashing treatment and immobilization with cement

Energy Technology Data Exchange (ETDEWEB)

Shengtao, Feng; Li, Gong; Li, Cheng; Benli, Wang; Lihong, Wang [China Inst. for Radiation Protection, Taiyuan, Shanxi (China)

1997-02-01

This report describes the results of the study on the treatment of radioactive biological waste in the China Institute for Radiation Protection (CIRP). The possibility of radiobiological waste treatment was investigated by using a RAF-3 type rapid ashing apparatus together with the immobilization of the resulted ash. This rapid ashing apparatus, developed by CIRP, is usually used for pretreatment of samples prior to chemical analysis and physical measurements. The results show that it can ash 3 kg of animal carcasses a batch, the ashing time is 5-7 h and the ash content is less than 4 wt%. The ashing temperature not exceeding 450 deg. C was used without any risk of high losses of radionuclides. The ash from the rapid ashing apparatus was demonstrated to be immobilized with ordinary silicate cement. The optimum cement/ash/water formulation of the cemented waste form was 35 {+-} 5 wt% cement, 29 {+-} 2 wt% water, and 36 {+-} 6 wt% ash. The performance of the waste form was in compliance with the technical requirements except for impact resistance. Mixing additives in immobilization formulations can improve the performance of the cemented ash waste form. The additives chosen were DH{sub 4A} flow promoter as a cement additive and vermiculite or zeolite as a supplement. The recommended formulation, i.e. an improved formulation of the cemented ash waste form is that additives DH{sub 4A} flow promoter and vermiculite (or zeolite) are added on the ground of optimum cement/ash/water formulation of the cemented waste form, the dosage of water, DH{sub 4A} and vermiculite (or zeolite) is 70 wt%, 0.5 wt% and {<=} 5 wt% of the cement dosage, respectively. The cemented ash waste forms obtained meet all the requirements for disposal. (author). 12 refs, 7 figs, 13 tabs.

Radiobiological waste treatment-ashing treatment and immobilization with cement

International Nuclear Information System (INIS)

Feng Shengtao; Gong Li; Cheng Li; Wang Benli; Wang Lihong

1997-01-01

This report describes the results of the study on the treatment of radioactive biological waste in the China Institute for Radiation Protection (CIRP). The possibility of radiobiological waste treatment was investigated by using a RAF-3 type rapid ashing apparatus together with the immobilization of the resulted ash. This rapid ashing apparatus, developed by CIRP, is usually used for pretreatment of samples prior to chemical analysis and physical measurements. The results show that it can ash 3 kg of animal carcasses a batch, the ashing time is 5-7 h and the ash content is less than 4 wt%. The ashing temperature not exceeding 450 deg. C was used without any risk of high losses of radionuclides. The ash from the rapid ashing apparatus was demonstrated to be immobilized with ordinary silicate cement. The optimum cement/ash/water formulation of the cemented waste form was 35 ± 5 wt% cement, 29 ± 2 wt% water, and 36 ± 6 wt% ash. The performance of the waste form was in compliance with the technical requirements except for impact resistance. Mixing additives in immobilization formulations can improve the performance of the cemented ash waste form. The additives chosen were DH 4A flow promoter as a cement additive and vermiculite or zeolite as a supplement. The recommended formulation, i.e. an improved formulation of the cemented ash waste form is that additives DH 4A flow promoter and vermiculite (or zeolite) are added on the ground of optimum cement/ash/water formulation of the cemented waste form, the dosage of water, DH 4A and vermiculite (or zeolite) is 70 wt%, 0.5 wt% and ≤ 5 wt% of the cement dosage, respectively. The cemented ash waste forms obtained meet all the requirements for disposal. (author). 12 refs, 7 figs, 13 tabs

Summary Report of Laboratory Testing to Establish the Effectiveness of Proposed Treatment Methods for Unremediated and Remediated Nitrate Salt Waste Streams

Energy Technology Data Exchange (ETDEWEB)

Anast, Kurt Roy [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Funk, David John [Los Alamos National Lab. (LANL), Los Alamos, NM (United States)

2016-05-12

The inadvertent creation of transuranic waste carrying hazardous waste codes D001 and D002 requires the treatment of the material to eliminate the hazardous characteristics and allow its eventual shipment and disposal at the Waste Isolation Pilot Plant (WIPP). This report documents the effectiveness of two treatment methods proposed to stabilize both the unremediated and remediated nitrate salt waste streams (UNS and RNS, respectively). The two technologies include the addition of zeolite (with and without the addition of water as a processing aid) and cementation. Surrogates were developed to evaluate both the solid and liquid fractions expected from parent waste containers, and both the solid and liquid fractions were tested. Both technologies are shown to be effective at eliminating the characteristic of ignitability (D001), and the addition of zeolite was determined to be effective at eliminating corrosivity (D002), with the preferred option1 of zeolite addition currently planned for implementation at the Waste Characterization, Reduction, and Repackaging Facility. During the course of this work, we established the need to evaluate and demonstrate the effectiveness of the proposed remedy for debris material, if required. The evaluation determined that Wypalls absorbed with saturated nitrate salt solutions exhibit the ignitability characteristic (all other expected debris is not classified as ignitable). Follow-on studies will be developed to demonstrate the effectiveness of stabilization for ignitable Wypall debris. Finally, liquid surrogates containing saturated nitrate salts did not exhibit the characteristic of ignitability in their pure form (those neutralized with Kolorsafe and mixed with sWheat did exhibit D001). As a result, additional nitrate salt solutions (those exhibiting the oxidizer characteristic) will be tested to demonstrate the effectiveness of the remedy.

Maximizing Production Capacity from an Ultrafiltration Process at the Hanford Department of Waste Treatment Facility

International Nuclear Information System (INIS)

Foust, Henry C.; Holton, Langdon K.; Demick, Laurence E.

2005-01-01

The Department of Energy has contracted Bechtel National, Inc. to design, construct and commission a Waste Treatment and Immobilization Plant (WTP) to treat radioactive slurry currently stored in underground waste storage tanks. A critical element of the waste treatment capacity for the WTP is the proper operation of an ultrafiltration process (UFP). The UFP separates supernate solution from radioactive solids. The solution and solid phases are separately immobilized. An oversight review of the UFP design and operation has identified several methods to improve the capacity of the ultrafiltration process, which will also improve the capacity of the WTP. Areas explored were the basis of design, an analysis of the WTP capacity, process chemistry within the UFP, and UFP process control. This article discusses some of the findings of this oversight review in terms of sodium and solid production, which supports the treatment of low activity waste (LAW) associated with the facility, and solid production, which supports the treatment of high level waste (HLW) associated with the facility

Waste Treatment & Immobilization Plant Project

Data.gov (United States)

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

Advanced mixed waste treatment project draft environmental impact statement

International Nuclear Information System (INIS)

1998-07-01

The AMWTP DEIS assesses the potential environmental impacts associated with four alternatives related to the construction and operation of a proposed waste treatment facility at the INEEL. Four alternatives were analyzed: The No Action Alternative, the Proposed Action, the Non-Thermal Treatment Alternative, and the Treatment and Storage Alternative. The proposed AMWTP facility would treat low-level mixed waste, alpha-contaminated low-level mixed waste, and transuranic waste in preparation for disposal. Transuranic waste would be disposed of at the Waste isolation Pilot Plant in New Mexico. Low-level mixed waste would be disposed of at an approval disposal facility depending on decisions to be based on DOE's Final Waste Management Programmatic Environmental Impact Statement. Evaluation of impacts on land use, socio-economics, cultural resources, aesthetic and scenic resources, geology, air resources, water resources, ecological resources, noise, traffic and transportation, occupational and public health and safety, INEEL services, and environmental justice were included in the assessment. The AMWTP DEIS identifies as the Preferred Alternative the Proposed Action, which is the construction and operation of the AMWTP facility

Waste container and method for containing waste

International Nuclear Information System (INIS)

Ono, Akira; Matsushita, Mitsuhiro; Doi, Makoto; Nakatani, Seiichi.

1990-01-01

In a waste container, water-proof membranes and rare earth element layers are formed on the inner surface of a steel plate concrete container in which steel plates are embedded. Further, rear earth element detectors are disposed each from the inner side of the steel plate concrete container by way of a pressure pipe to the outer side of the container. As a method for actually containing wastes, when a plurality of vessels in which wastes are fixed are collectively enhoused to the waste container, cussioning materials are attached to the inner surface of the container and wastes fixing containers are stacked successively in a plurality of rows in a bag made of elastic materials. Subsequently, fixing materials are filled and tightly sealed in the waste container. When the waste container thus constituted is buried underground, even if it should be deformed to cause intrusion of rain water to the inside of the container, the rare earth elements in the container dissolved in the rain water can be detected by the detectors, the containers are exchanged before the rain water intruding to the inner side is leached to the surrounding ground, to previously prevent the leakage of radioactive nuclides. (K.M.)

Treatment of NPP wastes using vitrification

International Nuclear Information System (INIS)

Sobolev, I.A.; Lifanov, F.A.; Stefanovsky, S.V.; Kobelev, A.P.; Savkin, A.E.; Kornev, V.I.

1998-01-01

Glass-based materials to immobilize various liquid and solid radioactive wastes generated at nuclear power plants (NPP) were designed. Glassy waste forms can be produced using electric melting including a cold crucible melting. Leach rate of cesium was found to be 10 -5 -10 -6 g/(cm 2 day) (IAEA technique). Volume reduction factor after vitrification reached 4-5. Various technologies for NPP waste vitrification were developed. Direct vitrification means feeding of source waste into the melter with formation of glassy waste form to be disposed. Joule heated ceramic melter, and cold crucible were tested. Process variables at treatment of Kursk, Chernobyl (RBMK), Kalinin, Novovoronezh (VVER) NPP wastes were determined. The most promising melter was found to be the cold crucible. Pilot plant based on the cold crucibles has been designed and constructed. Solid burnable NPP wastes are incinerated and slags are incorporated in glass. (author)

Tank waste treatment science task quarterly report, April 1995--June 1995

International Nuclear Information System (INIS)

LaFemina, J.P.

1995-07-01

This report describes the work performed by the Pacific Northwest Laboratory (PNL) during the third quarter of FY 1995 under the Tank Waste Treatment Science Task of the Tank Waste Remediation System (TWRS) Pretreatment Technology Development Project. Work was performed in the following areas: (1) analytical methods development, (2) sludge dissolution modeling, (3) sludge characterization studies, (4) sludge component speciation, (5) pretreatment chemistry evaluation, and (6) colloidal studies for solid-liquid separations

Alternatives for managing wastes from reactors and post-fission operations in the LWR fuel cycle. Volume 2. Alternatives for waste treatment

International Nuclear Information System (INIS)

1976-05-01

Volume II of the five-volume report is devoted to the description of alternatives for waste treatment. The discussion is presented under the following section titles: fuel reprocessing modifications; high-level liquid waste solidification; treatment and immobilization of chop-leach fuel bundle residues; treatment of noncombustible solid wastes; treatment of combustible wastes; treatment of non-high-level liquid wastes; recovery of transuranics from non-high-level wastes; immobilization of miscellaneous non-high-level wastes; volatile radioisotope recovery and off-gas treatment; immobilization of volatile radioisotopes; retired facilities (decontamination and decommissioning); and, modification and use of selected fuel reprocessing wastes

Alternatives for managing wastes from reactors and post-fission operations in the LWR fuel cycle. Volume 2. Alternatives for waste treatment

Energy Technology Data Exchange (ETDEWEB)

1976-05-01

Volume II of the five-volume report is devoted to the description of alternatives for waste treatment. The discussion is presented under the following section titles: fuel reprocessing modifications; high-level liquid waste solidification; treatment and immobilization of chop-leach fuel bundle residues; treatment of noncombustible solid wastes; treatment of combustible wastes; treatment of non-high-level liquid wastes; recovery of transuranics from non-high-level wastes; immobilization of miscellaneous non-high-level wastes; volatile radioisotope recovery and off-gas treatment; immobilization of volatile radioisotopes; retired facilities (decontamination and decommissioning); and, modification and use of selected fuel reprocessing wastes. (JGB)

RADIOACTIVE DEMONSTRATION OF FINAL MINERALIZED WASTE FORMS FOR HANFORD WASTE TREATMENT PLANT SECONDARY WASTE BY FLUIDIZED BED STEAM REFORMING USING THE BENCH SCALE REFORMER PLATFORM

Energy Technology Data Exchange (ETDEWEB)

Crawford, C.; Burket, P.; Cozzi, A.; Daniel, W.; Jantzen, C.; Missimer, D.

2012-02-02

The U.S. Department of Energy's Office of River Protection (ORP) is responsible for the retrieval, treatment, immobilization, and disposal of Hanford's tank waste. Currently there are approximately 56 million gallons of highly radioactive mixed wastes awaiting treatment. A key aspect of the River Protection Project (RPP) cleanup mission is to construct and operate the Waste Treatment and Immobilization Plant (WTP). The WTP will separate the tank waste into high-level and low-activity waste (LAW) fractions, both of which will subsequently be vitrified. The projected throughput capacity of the WTP LAW Vitrification Facility is insufficient to complete the RPP mission in the time frame required by the Hanford Federal Facility Agreement and Consent Order, also known as the Tri-Party Agreement (TPA), i.e. December 31, 2047. Therefore, Supplemental Treatment is required both to meet the TPA treatment requirements as well as to more cost effectively complete the tank waste treatment mission. In addition, the WTP LAW vitrification facility off-gas condensate known as WTP Secondary Waste (WTP-SW) will be generated and enriched in volatile components such as {sup 137}Cs, {sup 129}I, {sup 99}Tc, Cl, F, and SO{sub 4} that volatilize at the vitrification temperature of 1150 C in the absence of a continuous cold cap (that could minimize volatilization). The current waste disposal path for the WTP-SW is to process it through the Effluent Treatment Facility (ETF). Fluidized Bed Steam Reforming (FBSR) is being considered for immobilization of the ETF concentrate that would be generated by processing the WTP-SW. The focus of this current report is the WTP-SW. FBSR offers a moderate temperature (700-750 C) continuous method by which WTP-SW wastes can be processed irrespective of whether they contain organics, nitrates, sulfates/sulfides, chlorides, fluorides, volatile radionuclides or other aqueous components. The FBSR technology can process these wastes into a crystalline

Application of interval 2-tuple linguistic MULTIMOORA method for health-care waste treatment technology evaluation and selection.

Science.gov (United States)

Liu, Hu-Chen; You, Jian-Xin; Lu, Chao; Shan, Meng-Meng

2014-11-01

The management of health-care waste (HCW) is a major challenge for municipalities, particularly in the cities of developing countries. Selection of the best treatment technology for HCW can be viewed as a complicated multi-criteria decision making (MCDM) problem which requires consideration of a number of alternatives and conflicting evaluation criteria. Additionally, decision makers often use different linguistic term sets to express their assessments because of their different backgrounds and preferences, some of which may be imprecise, uncertain and incomplete. In response, this paper proposes a modified MULTIMOORA method based on interval 2-tuple linguistic variables (named ITL-MULTIMOORA) for evaluating and selecting HCW treatment technologies. In particular, both subjective and objective importance coefficients of criteria are taken into consideration in the developed approach in order to conduct a more effective analysis. Finally, an empirical case study in Shanghai, the most crowded metropolis of China, is presented to demonstrate the proposed method, and results show that the proposed ITL-MULTIMOORA can solve the HCW treatment technology selection problem effectively under uncertain and incomplete information environment. Copyright © 2014 Elsevier Ltd. All rights reserved.

Chemical decontamination method for radioactive metal waste

International Nuclear Information System (INIS)

Onuma, Tsutomu; Akimoto, Hidetoshi

1991-01-01

The invention relates to a decontamination method for radioactive metal waste products derived from equipment that handles radioactive materials whose surfaces have been contaminated; in particular it concerns a decontamination method that reduces the amount of radioactive waste by decontaminating radioactive waste substances to a level of radioactivity in line with normal waste products. In order to apply chemical decontamination to metal waste products whose surfaces are divided into carbon steel waste and stainless steel waste; the carbon steel waste is treated using only a primary process in which the waste is immersed in a sulfuric acid solution, while the stainless steel waste must be treated with both the primary process and then electrolytically reduces it for a specific length of time and a secondary process that uses a solution of sulfuric acid mixed with oxidizing metal salts. The method used to categorize metal waste into carbon steel waste and stainless steel waste involves determining the presence, or absence, of magnetism. Voltage is applied for a fixed duration; once that has stopped, electrolytic reduction repeats the operative cycle of applying, then stopping voltage until the potential of the radioactive metal waste is retained in the active region. 1 fig. 2 tabs

National Institutes of Health: Mixed waste minimization and treatment

International Nuclear Information System (INIS)

1995-08-01

The Appalachian States Low-Level Radioactive Waste Commission requested the US Department of Energy's National Low-Level Waste Management Program (NLLWMP) to assist the biomedical community in becoming more knowledgeable about its mixed waste streams, to help minimize the mixed waste stream generated by the biomedical community, and to identify applicable treatment technologies for these mixed waste streams. As the first step in the waste minimization process, liquid low-level radioactive mixed waste (LLMW) streams generated at the National Institutes of Health (NIH) were characterized and combined into similar process categories. This report identifies possible waste minimization and treatment approaches for the LLMW generated by the biomedical community identified in DOE/LLW-208. In development of the report, on site meetings were conducted with NIH personnel responsible for generating each category of waste identified as lacking disposal options. Based on the meetings and general waste minimization guidelines, potential waste minimization options were identified

National Institutes of Health: Mixed waste minimization and treatment