WorldWideScience

Sample records for chemical waste treatment

  1. Chemical treatment of radioactive wastes

    International Nuclear Information System (INIS)

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

  2. Chemical Industry Waste water Treatment

    International Nuclear Information System (INIS)

    Treatment of chemical industrial wastewater from building and construction chemicals factory and plastic shoes manufacturing factory was investigated. The two factories discharge their wastewater into the public sewerage network. The results showed the wastewater discharged from the building and construction chemicals factory was highly contaminated with organic compounds. The average values of COD and BOD were 2912 and 150 mg O2/l. Phenol concentration up to 0.3 mg/l was detected. Chemical treatment using lime aided with ferric chloride proved to be effective and produced an effluent characteristics in compliance with Egyptian permissible limits. With respect to the other factory, industrial wastewater was mixed with domestic wastewater in order to lower the organic load. The COD, BOD values after mixing reached 5239 and 2615 mg O2/l. The average concentration of phenol was 0.5 mg/l. Biological treatment using activated sludge or rotating biological contactor (RBe) proved to be an effective treatment system in terms of producing an effluent characteristic within the permissible limits set by the law

  3. Chemicals and Allied Products Waste Treatment

    Directory of Open Access Journals (Sweden)

    Yung-Tse Hung

    2011-06-01

    Full Text Available A review of the literature published from 2008 to 2010 on topics related to chemicals and allied products is presented. The review considered several sections such as waste management, physicochemical treatment, aerobic treatment, anaerobic treatment, air emissions, soils and groundwater, and reuse.

  4. Chemical aspects of nuclear waste treatment

    International Nuclear Information System (INIS)

    The chemical aspects of the treatment of gaseous, liquid, and solid wastes are discussed in overview. The role of chemistry and the chemical reactions in waste treatment are emphasized. Waste treatment methods encompass the chemistry of radioactive elements from every group of the periodic table. In most streams, the radioactive elements are present in relatively low concentrations and are often associated with moderately large amounts of process reagents, or materials. In general, it is desirable that waste treatment methods are based on chemistry that is selective for the concentration of radionuclides and does not require the addition of reagents that contribute significantly to the volume of the treated waste. Solvent extraction, ion exchange, and sorbent chemistry play a major role in waste treatment because of the high selectivity provided for many radionuclides. This paper deals with the chemistry of the onsite treatment methods that is typically used at nuclear installations and is not concerned with the chemistry of the various alternative materials proposed for long-term storage of nuclear wastes. The chemical aspects are discussed from a generic point of view in which the chemistry of important radionuclides is emphasized

  5. Citric waste saccharification under different chemical treatments

    Directory of Open Access Journals (Sweden)

    Carlos Eduardo de Farias Silva

    2015-10-01

    Full Text Available Second generation ethanol from lignocellulose materials has been used in applications for food processing wastes. Since Brazil has a leading position in orange juice exports, the influence of acid and alkali pretreatments on liquor saccharification, solubilization of solid fraction and mass yield was evaluated. Time and Cacid or Calkaline at different concentrations of solids (low to moderate, 1 to 9% and high catalyst concentrations were analyzed. A hydrothermal pretreatment was conducted under the same conditions of acid and alkaline treatments to investigate the relative selectivity increase in using the catalysts. The chemical analyses of wastes indicated a 70% total carbohydrate level denoting a promising raw material for bioethanol production. Pretreatment caused acid saccharifications between 25 and 65% in total reducing sugars (TRS and mass yields (MY between 30 and 40%. In alkaline pretreatment, these rates ranged between 2 and 22.5% and between 30 and 80, respectively. In hydrothermal pretreatment, solubilized TRS varied between 3 and 37%, whereas MY remained between 45 and 60%, respectively. Cbiomass strongly influenced the three variables; in the same way, time affected MY.

  6. Hong kong chemical waste treatment facilities: a technology overview

    Energy Technology Data Exchange (ETDEWEB)

    Siuwang, Chu [Enviropace Ltd., Hong Kong (Hong Kong)

    1993-12-31

    The effective management of chemical and industrial wastes represents one of the most pressing environmental problems confronting the Hong Kong community. In 1990, the Hong Kong government contracted Enviropace Limited for the design, construction and operation of a Chemical Waste Treatment Facility. The treatment and disposal processes, their integration and management are the subject of discussion in this paper

  7. Chemical precipitation processes for the treatment of aqueous radioactive waste

    International Nuclear Information System (INIS)

    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

  8. Chemical treatment of mixed waste at the FEMP

    International Nuclear Information System (INIS)

    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

  9. Chemical treatment of chelated metal finishing wastes.

    Science.gov (United States)

    McFarland, Michael J; Glarborg, Christen; Ross, Mark A

    2012-12-01

    This study evaluated two chemical approaches for treatment of commingled cadmium-cyanide (Cd-CN) and zinc-nickel (Zn-Ni) wastewaters. The first approach, which involved application of sodium hypochlorite (NaOCl), focused on elimination of chelating substances. The second approach evaluated the use of sodium dimethyldithiocarbamate (DMDTC) to specifically target and precipitate regulated heavy metals. Results demonstrated that by maintaining a pH of 10.0 and an oxidation-reduction potential (ORP) value of +600 mV, NaOCl treatment was effective in eliminating all chelating substances. Cadmium, chromium, nickel, and zinc solution concentrations were reduced from 0.27, 4.44, 0.06, and 0.10 ppm to 0.16, 0.17, 0.03, and 0.06 ppm, respectively. Similarly, a 1% DMDTC solution reduced these same metal concentrations in commingled wastewater to 0.009, 1.142, 0.036, and 0.320 ppm. Increasing the DMDTC concentration to 2% improved the removal of all regulated heavy metals except zinc, the removal of which at high pH values is limited by its amphotericity. PMID:23342939

  10. Physical/chemical treatment of mixed waste soils

    International Nuclear Information System (INIS)

    This report discusses the results and findings of the demonstration testing of a physical/chemical treatment technology for mixed wastes. The principal objective of the tests was to demonstrate the capability of the low temperature thermal separation (LTTS) technology for rendering PCB-contaminated mixed waste soils as nonhazardous and acceptable for low level radioactive waste disposal. The demonstration testing of this technology was a jointly-conducted project by the US Department of Energy (DOE), the Martin Marietta Energy Systems (Energy Systems) Waste Management Technology Center at the Oak Ridge National Laboratory, and IT Corporation. This pilot-scale demonstration program testing of IT's thermal separator technology in Oak Ridge was conducted as part of the DOE Model Program. This program has private industry, regulators, and universities helping to solve DOE waste management problems. Information gained from the DOE Model is shared with the participating organizations, other federal agencies, and regulatory agencies. The following represent the most significant findings from these demonstration tests: Thermal separation effectively separated PCB contamination from a mixed waste to enable the treated soil to be managed as low level radioactive waste. At the same operating conditions, mercury contamination of 0.8 ppM was reduced to less than 0.1 ppM. The majority of uranium and technetium in the waste feeds oil remained in the treated soil. Radionuclide concentration in cyclone solids is due to carry-over of entrained particles in the exit gas and not due to volatilization/condensation. Thermal separation also effectively treated all identified semi-volatile contaminants in the waste soil to below detection limits with the exception of di-n-butylphthalate in one of the two runs. 4 refs., 1 fig., 6 tabs

  11. A process for treatment of mixed waste containing chemical plating wastes

    International Nuclear Information System (INIS)

    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 CrVI to CrIII 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

  12. Chemical treatment of radioactive liquid wastes from medical applications

    International Nuclear Information System (INIS)

    This work is a study about the treatment of the most important radioactive liquid wastes from medical usages, generated in medical institutions with nuclear medicine services. The radionuclides take in account are 32 P, 35 S, 125 I. The treatments developed and improved were specific chemical precipitations for each one of the radionuclides. This work involve to precipitate the radionuclide from the liquid waste, making a chemical compound insoluble in the aqueous phase, for this process the radionuclide stay in the precipitate, lifting the aqueous phase with a very low activity than the begin. The 32 P precipitated in form of Ca332 P O4 and Ca2 H 32 P O4 with a value for Decontamination Factor (DF) at the end of the treatment of 32. The 35 S was precipitated in form of Ba35 SO4 with a DF of 26. The 125 I was precipitated in Cu 125 I to obtain a DF of 24. The results of the treatments are between the limits given for the International Atomic Energy Agency and the 10 Code of Federal Regulation 20, for the safety release at the environment. (Author)

  13. Combustible radioactive waste treatment by incineration and chemical digestion

    International Nuclear Information System (INIS)

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

  14. Low level radioactive waste treatment at the Siberian Chemical Combine

    International Nuclear Information System (INIS)

    Safety codes require that open surface disposal sites for liquid low-level wastes at radiochemical works be closed down. At the Siberian Chemical Works, the first operation was to stop the flow of wastes into the pulp repository. The presence of burial sites predetermined the choice of precisely this method as an alternative for dumping wastes into open disposal sites. The results of a study of the physicochemical characteristics of the wastes flowing into the pulp repository PKh-1,2 from four plants at the Works made it possible to develop a unified scheme for preparing them for disposal - wastes are put into a deep repository and maximum use is made of the individual properties of reprocessed wastes, which decreases the consumption of additional reagents substantially, i.e., it decreases the cost of the preparation process. The scheme developed has successfully passed commercial prototype tests and is now in the design stage

  15. Chemical precipitation processes for the treatment of low and medium level liquid waste

    International Nuclear Information System (INIS)

    Chemical precipitation processes for the treatment of various radioactive low and medium level liquid waste are described. Application to waste from reprocessing plants, removal of the main gamma emitters, actinide separation, utility liquid wastes generated during pwr operation, and combination of ultrafiltration with chemical precipitation, are all discussed. (U.K.)

  16. Radiation chemical studies on the treatment of waste water

    International Nuclear Information System (INIS)

    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)

  17. Emissions model of waste treatment operations at the Idaho Chemical Processing Plant

    International Nuclear Information System (INIS)

    An integrated model of the waste treatment systems at the Idaho Chemical Processing Plant (ICPP) was developed using a commercially-available process simulation software (ASPEN Plus) to calculate atmospheric emissions of hazardous chemicals for use in an application for an environmental permit to operate (PTO). The processes covered by the model are the Process Equipment Waste evaporator, High Level Liquid Waste evaporator, New Waste Calcining Facility and Liquid Effluent Treatment and Disposal facility. The processes are described along with the model and its assumptions. The model calculates emissions of NOx, CO, volatile acids, hazardous metals, and organic chemicals. Some calculated relative emissions are summarized and insights on building simulations are discussed

  18. Treatment of chemical waste piassava for application in polymeric composites

    International Nuclear Information System (INIS)

    Piassava fibers were investigated with the aim of adding new business value. The surface of the fibers were treated with NaOH and H2SO4 for 1 h at room temperature. The samples were characterized by FTIR, TGA, DSC, chemical composition, XRD, SEM and tensile tests. The micrographs of the fibers showed that treatment with NaOH cleaned the fiber surface of a large amount of impurities and cause fibrillation. Chemical analysis, using the Van Soest method, showed that the palm fiber is a fiber rich in lignin, as evidenced by their brown color and with alkali treatment there was partial removal of hemicellulose and lignin, increasing the crystallinity index of the fiber, observed by XRD. The acid treatment caused no significant changes in the properties of the fiber. Therefore, the mercerisation was efficient in the fiber of palm fiber, improving their properties, enabling thus their use as reinforcement in polymer composites. (author)

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

    International Nuclear Information System (INIS)

    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

  20. Treatment and disposal of steam generator and heat exchanger chemical cleaning wastes

    International Nuclear Information System (INIS)

    Wet air oxidation was effective in reducing the organic loading of Ontario Hydro's EDTA-based steam generator cleaning wastes and the organic acid formulation used for heat exchanger chemical cleaning. Destruction of the complexing agents resulted in direct precipitation of iron from the waste steam generator magnetite solvent and from the heat exchanger cleaning waste. The oxidized liquors contain lower molecular weight organic acids, ammonia and amines, suitable for secondary biological treatment. The oxidized copper waste requires further treatment to reduce dissolved copper levels prior to biological digestion. A preliminary evaluation of UV and ozone degradation of these wastes showed less promise than wet air oxidation. 24 refs., 1 fig., 4 tabs

  1. 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.

  2. 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)

    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

  3. Calculation of chemical quantities for the radioactive liquid waste treatment facility

    Energy Technology Data Exchange (ETDEWEB)

    Del Signore, John C. [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); McClenahan, Robert L. [Los Alamos National Lab. (LANL), Los Alamos, NM (United States)

    2007-03-01

    The Radioactive Liquid Waste Treatment Facility (RLWTF) receives, stores, and treats both low-level and transuranic radioactive liquid wastes (RLW). Treatment of RLW requires the use of different chemicals. Examples include the use of calcium oxide to precipitate metals and radioactive elements from the radioactive liquid waste, and the use of hydrochloric acid to clean membrane filters that are used in the treatment process. The RL WTF is a Hazard Category 2 nuclear facility, as set forth in the LANL Final Safety Analysis Report of October 1995, and a DOE letter of March 11, 1999. A revised safety basis is being prepared for the RLWTF, and will be submitted to the NNSA in early 2007. This set of calculations establishes maximum chemical quantities that will be used in the 2007 safety basis.

  4. Degradation of Refractory Organic Compounds in Aqueous Wastes employing a combination of biological and chemical treatments

    OpenAIRE

    Chindris, Anuta

    2011-01-01

    In this study the removal of refractory organic compounds (ROCs) in Aqueous Wastes (AW) employing a combination of biological and chemical treatment were investigated at Department of Chemical Engineering and Materials Science, University of Cagliari, Italy and Department of Engineering, Oxford University, UK. The main objectives were to stimulate and optimise the degradation of ROCs with efficient removal of them in AW. This project is divided in two sections, a theoreti...

  5. Patterns of waste generation, treatment and disposal in the chemical and allied industries in Ghana

    Directory of Open Access Journals (Sweden)

    Osei-Wusu Achaw

    2012-09-01

    Full Text Available Environmental pollution and degradation in urban Ghana has been on the increase as a result of the nations drive towards industrialization, a generally weak regulatory regime, and a lack of capacity to manage the environment. This situation is affecting the well-being and livelihood of affected communities. As part of an effort to address the issue, a thirteen (13 item questionnaire was designed and distributed to seventy (70 companies in the chemical and allied industry to solicit and analyze data and information on the their waste management situation. Forty-seven, representing 67.1%, of the distributed questionnaires were completed and returned. The responses were analyzed using tables, percentages and bar charts. The results revealed that while 80.9% of the respondents generate waste as a result of the operation of the plants, 23.3% directly dump their waste into the environment without any prior treatment. Only one company was found that incinerate its waste, and only four (8.5% had comprehensive waste water treatment plants. The low numbers of companies treating the waste they generate prior to disposal means that the chemical and allied industry is contributing to the environmental pollution and degradation in the country.

  6. Chemical hazards associated with treatment of waste electrical and electronic equipment

    International Nuclear Information System (INIS)

    This review paper summarizes the existing knowledge on the chemical hazards associated with recycling and other end-of-life treatment options of waste electrical and electronic equipment (e-waste). The hazards arise from the presence of heavy metals (e.g., mercury, cadmium, lead, etc.), flame retardants (e.g., pentabromophenol, polybrominated diphenyl ethers (PBDEs), tetrabromobisphenol-A (TBBPA), etc.) and other potentially harmful substances in e-waste. If improperly managed, the substances may pose significant human and environmental health risks. The review describes the potentially hazardous content of e-waste, examines the existing e-waste management practices and presents scientific data on human exposure to chemicals, workplace and environmental pollution associated with the three major e-waste management options, i.e., recycling, incineration and landfilling. The existing e-waste management practices and associated hazards are reviewed separately for developed and developing countries. Finally, based on this review, the paper identifies gaps in the existing knowledge and makes some recommendations for future research.

  7. Chemical precipitation processes for the treatment of low- and medium-level liquid waste

    International Nuclear Information System (INIS)

    New applications of chemical precipitation processes for the treatment of various radioactive low and medium level liquid waste have been investigated. For reducing the overall management cost and improving the long-term safety of disposal, partitioning of the reprocessing concentrate into different streams for separate conditioning, packaging and disposal has been studied through chemical precipitation of the whole activity (actinides + main gamma emitters) or the actinides only. Results achieved on testing of real sample of reprocessing concentrate (lab-scale) are presented and discussed. In order to comply with the ALARA principle, an industrial flocculator prototype has been constructed and successfully operated for the treatment of utility liquid waste arising at the Chooz PWR site. Combination of chemical precipitation with ultrafiltration seems quite promising for improving both decontamination and volume reduction factors for the treatment of various radwastes. On the basis of experimental tests performed successively on lab and technical scales, a pilot plant has been designed, constructed and commissioned for the treatment of Harwell low and medium level liquid wastes. First active runs confirm the merits of the process

  8. Chemical treatment of liquid radioactive waste at the Boris Kidric Institute

    International Nuclear Information System (INIS)

    The results of lab-scale experiments on the chemical treatment of radioactive liquid waste collected at the Boris Kidric Institute are presented. The radioactive waste was treated by cobalt hexacyanoferrate precipitation followed by flocculation with polyelectrolyte flocculating agents. The main parameters investigated were standing time, pH and ratio of reagents. The flocculating agents were tested by filtration test and floccule stability test. Satisfactory decontamination factors by precipitation at pH 10 and good separation of solid and liquid phase by applying Praestol polyelectrolytes were obtained (author)

  9. Mechanism of waste biomass pyrolysis: Effect of physical and chemical pre-treatments.

    Science.gov (United States)

    Das, Oisik; Sarmah, Ajit K

    2015-12-15

    To impart usability in waste based biomass through thermo-chemical reactions, several physical and chemical pre-treatments were conducted to gain an insight on their mode of action, effect on the chemistry and the change in thermal degradation profiles. Two different waste biomasses (Douglas fir, a softwood and hybrid poplar, a hardwood) were subjected to four different pre-treatments, namely, hot water pre-treatment, torrefaction, acid (sulphuric acid) and salt (ammonium phosphate) doping. Post pre-treatments, the changes in the biomass structure, chemistry, and thermal makeup were studied through electron microscopy, atomic absorption/ultra violet spectroscopy, ion exchange chromatography, and thermogravimetry. The pre-treatments significantly reduced the amounts of inorganic ash, extractives, metals, and hemicellulose from both the biomass samples. Furthermore, hot water and torrefaction pre-treatment caused mechanical disruption in biomass fibres leading to smaller particle sizes. Torrefaction of Douglas fir wood yielded more solid product than hybrid poplar. Finally, the salt pre-treatment increased the activation energies of the biomass samples (especially Douglas fir) to a great extent. Thus, salt pre-treatment was found to bestow thermal stability in the biomass. PMID:26282766

  10. Design of chemical treatment unit for radioactive liquid wastes in Serpong nuclear facilities

    International Nuclear Information System (INIS)

    The chemical treatment unit for radioactive liquid wastes arising from nuclear fuel fabrication, radioisotopes production and radiometallurgy facility has been designed. The design of chemical processing unit is based on the characteristics of liquid wastes containing fluors from uranium fluoride conversion process to ammonium uranyl carbonate on the fuel fabrication. The chemical treatment has the following process steps: coagulation-precipitation of fluoride ion by calcium hydroxide coagulant, separation of supernatant solution from sludge, coagulation of remaining fluoride on the supernatant solution by alum, separation of supernatant from sludge, and than precipitation of fluors on the supernatant by polymer resin WWS 116. The processing unit is composed of 3 storage tanks for raw liquid wastes (capacity 1 m3 per tank), 5 storage tanks for chemicals (capacity 0.5 m3 per tank), 2 mixing reactors (capacity 0.5 m3 per reactor), 1 storage tank for supernatant solution (capacity 1 m3), and 1 storage tank for sludge (capacity 1 m3)

  11. Automation of the liquid wastes chemical treatment plant of the radioactive waste management plant

    International Nuclear Information System (INIS)

    This report shows the goals achieved in the elaboration and implementation of a pilot program of processes supervision and control based in the use of a programmable logic controller (PLC) which is carried out in the plant of liquid effluent (water) chemical treatment containing radioactive elements such as Co-60, Cs-137, I-131, Sr-90, Tc-99m, Mo-99 from the radioactive decay tanks of the RP-10 reactor and the Radioisotopes Production Plant (PPR)

  12. Digestibility and energetic value of some agricultural wastes as affected by gamma irradiation and chemical treatments

    International Nuclear Information System (INIS)

    Experiments were carried out to study the changes in the values of in-vitro apparent organic matter digestibility (IVOMD), metabolizable energy (ME) and net energy lactation (NEL) of wheat straw, sunflower seed shell, olive cake wood, date palm seeds and peanut shell after spraying with different concentrations of hydrobromic acid (HBr) and sodium hydroxide (NaOH) (0,3,6 ml HBr and 3,6 g NaOH/25 ml water/100 g DM) or after exposure to various doses of gamma radiation (0, 20, 40, 60 kGy). Results indicated that, except for the date palm seeds, the chemical treatments with either HBr or NaOH significantly (P<0.05) increased IVOMD, Me and NEL values for all treated samples. The experimental agricultural wastes did not respond equally to the chemical treatments investigated, i.e. they differ in the induced increases pertaining to their IVOMD, ME and NEL. The highest changes in the studied parameters due to chemical treatments were obtained when applying the 6% concentration. There was no significant effect (P<0.05) of irradiation on IVOMD, ME and NEL values for all treated samples. Moreover, the combined treatments of irradiation and hydrobromic acid or sodium hydroxide were found to have no significant affects on the IVOMD, ME and NEL values compared to the individual chemical treatments. (author)

  13. Chemical Process for Treatment of Tellurium and Chromium Liquid Waste from I-131 Radioisotope Production

    International Nuclear Information System (INIS)

    The I-131 radioisotope is used in nuclear medicine for diagnosis and therapy. The I-131 radioisotope is produced by wet distillation at Bandung Nuclear Research Center and generated about 4,875 Itr of liquid waste containing 2,532.8 ppm of tellurium and 1,451.8 ppm chromium at pH 1. Considering its negative impact to the environment caused by toxic behaviour of tellurium and chromium, it is necessary to treat chemically that's liquid waste. The research of chemical treatment of tellurium and chromium liquid waste from I-131 radioisotope production has been done. The steps of process are involved of neutralisation with NaOH, coagulation-flocculation process for step I using Ca(OH)2 coagulant for precipitation of sulphate, sulphite, oxalic, chrome Cr3+, and coagulation-flocculation process for step II using BaCI2 coagulant for precipitation of chrome Cr6+ and tellurium from the supernatant of coagulation in step I. The best result of experiment was achieved at 0.0161 ppm of chromium concentration on the supernatant from coagulation-flocculation of step I using 3.5 g Ca(OH)2 for 100 ml of liquid waste, and 0.95 ppm of tellurium concentration on the final supernatant from coagulation-flocculation by of step II using 0.7 g BaCI2 for supernatant from coagulation of step I. (author)

  14. Treatment, Processing and Future Disposal of Radioactive Wastes at the Idaho Chemical Processing Plant

    International Nuclear Information System (INIS)

    Acidic wastes from the recovery of enriched uranium from aluminium, zirconium, and stainless-steel fuels at the Idaho Chemical Processing Plant are stored in underground tanks of two configurations and nominal sizes of 30,000 and 300,000 gallons. The design and operation of the waste-tank farm as well as the methods of environmental disposal of low-level wastes is described. The ''concentrate and contain'' philosophy of waste disposal has as its ultimate aim the production of a solid mass containing the fission products. The disadvantage of increased treatment costs may or may not be offset by reduction in storage costs. The low thermal conductivity of solids makes storage temperature considerations more important than for liquids. The acid aluminium nitrate wastes from the processing of fuels of the Material Testing Reactor type may be converted to granular alumina by calcining in a fluidized bed from 350° to 550° C. The major process components are the NaK heated calciner, an off-gas cleaning system and the solids storage vessels. The process design and the research and development programme are reviewed. On the basis of the successful demonstration of fluidized-bed calcining and high-temperature solids storage in conjunction with other considerations, a number of future storage concepts and their environmental connotations are discussed. (author)

  15. Efficiency of Chemical Treatments on Reduction of COD and Turbidity of Deinked Pulp Waste Water

    Directory of Open Access Journals (Sweden)

    Shademan Pourmousa

    2013-12-01

    Full Text Available The effect of poly aluminum chloride with cationic or anionic polymers in treatment of deinked waste water has been studied. The experiments were carried out in jar tests with poly aluminum chloride dosages range of 5-20 mg/l, cationic or anionic polymers dosages range of 1-3 mg/l, pH range of 7.2-8.2, rapid mixing at 100rpm for 2minute, followed by slow mixing at 40 rpm for 10minute and settling for 20minute. The effectiveness of poly aluminum chloride with cationic or anionic polymers were measured based on reduction of turbidity and chemical oxygen demand. The combination of poly aluminum chloride with cationic or anionic polymers is found to give the increase efficiency of purification in the treatment of the deinked waste waters.it can achieve almost66.82 % of turbidity and 63.04 %ofchemical oxygen demand reduction at an optimum dosage of 15mg/l poly aluminum chloride with 3mg/l cationic polymers andpH of 8.2.Theresult suggests that the waste water purified can be used for internal process applications but for injection it to environments goals can be passed biological treatments.

  16. Tank waste treatment science

    International Nuclear Information System (INIS)

    Remediation efforts at the U.S. Department of Energy's Hanford Site require that many technical and scientific principles be combined for effectively managing and disposing the variety of wastes currently stored in underground tanks. Based on these principles, pretreatment technologies are being studied and developed to separate waste components and enable the most suitable treatment methods to be selected for final disposal of these wastes. The Tank Waste Treatment Science Task at Pacific Northwest Laboratory is addressing pretreatment technology development by investigating several aspects related to understanding and processing the tank contents. The experimental work includes evaluating the chemical and physical properties of the alkaline wastes, modeling sludge dissolution, and evaluating and designing ion exchange materials. This paper gives some examples of results of this work and shows how these results fit into the overall Hanford waste remediation activities. This work is part of series of projects being conducted for the Tank Waste Remediation System

  17. Treatment of ammonia in waste air using packed column coupling with chemical reaction

    Directory of Open Access Journals (Sweden)

    Thepchai, R.

    2007-05-01

    Full Text Available Ammonia is a common chemical used in various industries. Emission of air contaminated with ammonia to the atmosphere without any treatment causes several effects on human health and environment.A high efficiency method for ammonia removal from waste air is then necessary. In this research, an absorption coupling with chemical reaction was investigated for ammonia removal from waste air using a packedcolumn. The packed column of 10 cm diameter and 200 cm height was packed with 1.4x1.4 cm Raschig rings. Three liquids including water, NaOCl and H2SO4 solution were used as an absorbent for the investigation.The objectives of this research were to determine a suitable absorbent and the optimum condition for ammonia removal from waste air. The packed column was operated at room temperature and atmosphericpressure. The tested conditions were as follows: the gas to liquid ratio (G:L ratio was 35-90 m3 gas/m3 liquid, the inlet concentration of ammonia was 150-500 ppm and the air flow rate was 18 m3/h. The results showedthat the ammonia removal efficiency depends on type of the absorbent and the operating condition. The efficiencies increased with decreasing of G:L ratio and with increasing absorbent concentration. They were70%, 80-92%, and 95-100% for pure water, sodium hypochlorite solution and sulphuric acid solution, respectively. The efficiency decreased with time when water was used as an absorbent while it was almostconstant when NaOCl and H2SO4 solution were applied. The ammonia removal efficiency when using H2SO4 as the absorbent was not dependent on G:L ratio and inlet ammonia concentration, in the range used in thisinvestigation. Since H2SO4 solution gave the highest removal efficiency and can reduce ammonia concentration in waste air to levels which meet the TLV-TWA standard, it is recommended as an absorbent solution forammonia removal from waste air.

  18. TREATMENT OF RADIOACTIVE WASTE SOLUTIONS CONTAINING CESIUM AND STRONTIUM BY CHEMICALLY MODIFIED ACTIVATED CARBON

    International Nuclear Information System (INIS)

    The aim of this study is to develop activated carbon prepared from peach stone shell as an adsorbent for Cs+ and Sr2+ ions from their aqueous waste solutions. In this respect, five samples of peach stone shell were investigated. The first four samples were prepared by immersing the samples in different concentrations of either ZnCl2 or KOH, individually, prior to heat treatment at 500oC. The fifth sample was prepared only by thermal treatment at 500oC.The physical and chemical characteristics of the prepared samples were carried out. A comparative study for the removal of Cs+ and Sr2+ ions from their aqueous waste solutions using the investigated samples have been carried out using batch experiments.The different parameters affecting adsorption process such as contact time and metal ion concentration were studied. The results obtained showed that the activated carbon prepared using ZnCl2 was more effective than the other investigated samples for adsorbing Cs+ and Sr2+ ions since the removal percentages reached 85% and 98% , respectively, while the activated carbon prepared using KOH was less effective for the removal of the same elements since the removal percentages reached 69% and 60%, respectively. In case of using physically activated carbon, the removal percentages reached 18% and 25% for Cs+ and Sr2+, respectively.From the obtained data, it can be concluded that the activated carbon prepared using ZnCl2 can be used as a good adsorbent for the removal of the investigated elements that may present in radioactive waste solutions before their discharge to the environment

  19. Chemical decontamination of radioactive waste

    International Nuclear Information System (INIS)

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

  20. Evaluation of alternatives for radium recovery of phosphogysum waste from chemical treatment of phosphatic ore

    International Nuclear Information System (INIS)

    The results from the research work undertaken to evaluate the economic recovery of the Itataia, Ceara phosphogypsum waste, obtained during the treatment of uranium bearing phosphatic ore are present. The implications involved in the waste storage taking into account different aspects of environmental safety, are discussed. (M.A.C.)

  1. Mixed and low-level waste treatment project: Appendix C, Health and safety criteria for the mixed and low-level waste treatment facility at the Idaho National Engineering Laboratory. Part 2, Chemical constituents

    Energy Technology Data Exchange (ETDEWEB)

    Neupauer, R.M.; Thurmond, S.M.

    1992-09-01

    This report contains health and safety information relating to the chemicals that have been identified in the mixed waste streams at the Waste Treatment Facility at the Idaho National Engineering Laboratory. Information is summarized in two summary sections--one for health considerations and one for safety considerations. Detailed health and safety information is presented in material safety data sheets (MSDSs) for each chemical.

  2. Automation of the chemical treatment plant of radioactive wastes at the RACSO Nuclear Center

    International Nuclear Information System (INIS)

    The RACSO Nuclear Center has a chemical treatment plant which has been designed and built for the low and medium activity radioactive residual treatment. Considering the Radiological Security standards and the optimization principle in order to reduce the doses of the operator personnel, the chemical treatment plant automation development was carried out

  3. Chemical modeling of acid-base properties of soluble biopolymers derived from municipal waste treatment materials.

    Science.gov (United States)

    Tabasso, Silvia; Berto, Silvia; Rosato, Roberta; Marinos, Janeth Alicia Tafur; Ginepro, Marco; Zelano, Vincenzo; Daniele, Pier Giuseppe; Montoneri, Enzo

    2015-01-01

    This work reports a study of the proton-binding capacity of biopolymers obtained from different materials supplied by a municipal biowaste treatment plant located in Northern Italy. One material was the anaerobic fermentation digestate of the urban wastes organic humid fraction. The others were the compost of home and public gardening residues and the compost of the mix of the above residues, digestate and sewage sludge. These materials were hydrolyzed under alkaline conditions to yield the biopolymers by saponification. The biopolymers were characterized by 13C NMR spectroscopy, elemental analysis and potentiometric titration. The titration data were elaborated to attain chemical models for interpretation of the proton-binding capacity of the biopolymers obtaining the acidic sites concentrations and their protonation constants. The results obtained with the models and by NMR spectroscopy were elaborated together in order to better characterize the nature of the macromolecules. The chemical nature of the biopolymers was found dependent upon the nature of the sourcing materials. PMID:25658795

  4. Chemical Modeling of Acid-Base Properties of Soluble Biopolymers Derived from Municipal Waste Treatment Materials

    Directory of Open Access Journals (Sweden)

    Silvia Tabasso

    2015-02-01

    Full Text Available This work reports a study of the proton-binding capacity of biopolymers obtained from different materials supplied by a municipal biowaste treatment plant located in Northern Italy. One material was the anaerobic fermentation digestate of the urban wastes organic humid fraction. The others were the compost of home and public gardening residues and the compost of the mix of the above residues, digestate and sewage sludge. These materials were hydrolyzed under alkaline conditions to yield the biopolymers by saponification. The biopolymers were characterized by 13C NMR spectroscopy, elemental analysis and potentiometric titration. The titration data were elaborated to attain chemical models for interpretation of the proton-binding capacity of the biopolymers obtaining the acidic sites concentrations and their protonation constants. The results obtained with the models and by NMR spectroscopy were elaborated together in order to better characterize the nature of the macromolecules. The chemical nature of the biopolymers was found dependent upon the nature of the sourcing materials.

  5. Chemical treatment of aqueous radioactive Cesium-137 waste using Ferri Chloride

    International Nuclear Information System (INIS)

    Ferric Chloride 6H2O was used for treatment of liquid radioactive wastes containing Cesium-137. Various concentration of ferric chloride 6H2O have been added into the waste at different pH and speed of stirrer. The treatment was based on the coagulans-flocculation and coprecipitation mechanisms. The best result of this experiment was achieved by adding 300 ppm of Ferric chloride 6 H2O into liquid waste on following condition the rate Stirrer was 250 rpm. At this condition, it was found that the separation efficiency and the decontamination factor were 83.32 % and 5.99. The activity of decreasing of aqueous radioactive Cesium-137 waste was 2.10 x 10-4 Ci/l to 3.50 x 10-5 Ci/l

  6. Solid waste electron beam treatment

    International Nuclear Information System (INIS)

    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)

  7. Chemical waste management in Hong Kong

    International Nuclear Information System (INIS)

    This paper reports that in Hong Kong, the control of chemical wastes is provided for in the Waste Disposal Ordinance. The enabling regulations of the Ordinance are presently being drafted and will be enforced in the near future. Presently, because of the lack of legislative control together with a general lack of knowledge on chemical wastes (such as mineral oils and fuel oils) and the unavailability of suitable treatment facilities, the majority of the chemical wastes generated are being discharged into the sewers or drains. In order that the control regulations can function effectively, it is decided that a Chemical Waste Treatment Center (CWTC) has to be provided by Government to ensure that the proper treatment facilities are available to the industry in the first place. As the majority of the chemical waste producers in Hong Kong are small generators, it is envisaged that most of these waste generators will have to rely on the CWTC for the proper treatment of their chemical wastes. The CWTC will also provide a waste collection service to collect and transport the chemical wastes from the industrial establishments to the CWTC. The waste generators are required to provide sufficient interim storage for their waste prior to their collection

  8. Chemical modeling of acid-base properties of soluble biopolymers derived from municipal waste treatment materials

    OpenAIRE

    Silvia Tabasso; Silvia Berto; Roberta Rosato; Janeth Alicia Tafur Marinos; Marco Ginepro; Vincenzo Zelano; Pier Giuseppe Daniele; Enzo Montoneri

    2015-01-01

    This work reports a study of the proton-binding capacity of biopolymers obtained from different materials supplied by a municipal biowaste treatment plant located in Northern Italy. One material was the anaerobic fermentation digestate of the urban wastes organic humid fraction. The others were the compost of home and public gardening residues and the compost of the mix of the above residues, digestate and sewage sludge. These materials were hydrolyzed under alkaline conditions to yield the b...

  9. Chemical characterization of emissions from a municipal solid waste treatment plant

    OpenAIRE

    Moreno Caballero, Ana Isabel; Arnaiz Arnaiz, Noelia; Font Montesinos, Rafael; Carratalá, Adoración

    2014-01-01

    Gaseous emissions are an important problem in municipal solid waste (MSW) treatment plants. The sources points of emissions considered in the present work are: fresh compost, mature compost, landfill leaks and leachate ponds. Hydrogen sulphide, ammonia and volatile organic compounds (VOCs) were analysed in the emissions from these sources. Hydrogen sulphide and ammonia were important contributors to the total emission volume. Landfill leaks are significant source points of emissions of H2S; t...

  10. Chemical treatment of secondary waste solutions resulting from wet oxidative degradation of spent ion-exchange resins

    International Nuclear Information System (INIS)

    The present experimental work has been carried out to evaluate the chemical treatment process of radioactive secondary waste solutions resulting from the wet oxidative degradation of simulated spent radioactive cation-exchange resins using hydrogen peroxide as oxidant. The present study aims mainly to evaluate the ability of ferrocyanide compound of nickel for selective fixation of radio-cesium from the secondary waste solution in presence of traces of soluble organic residues. Based on the data obtained, it was found that, using 5 x 10-3 of nickel ferrocyanide, at ph range from 1-9 and in the presence of traces of soluble organic carbon, more than 99% of the radiocesium initially found could be efficiently removed from the secondary radioactive waste solutions under consideration

  11. Chemical process for treatment of corrosive radioactive waste from the fabrication of nuclear fuel

    International Nuclear Information System (INIS)

    Experiments were carried out to decrease fluors concentration in corrosive radioactive liquid waste containing 19430 ppm of fluors by chemical method i.e. combination of coagulation, flocculation and sedimentation. Calcium chloride, aluminium sulfate, resin WWS 116, and mix of aluminium sulfate and resin WWS 116 were used as chemical coagulant on variation of concentration. The precipitates of fluors salt was separated from the solution, and than fluors concentration in solution is analyzed. The best result of optimum Fluors concentration in solution was achieved at 4.88 ppm by using of 1.3 mole/l calcium chloride coagulant at pH 8, the separation factor is 99.97%. (author)

  12. Physical-chemical treatment of wastes: a way to close turnover of elements in LSS.

    Science.gov (United States)

    Kudenko YuA; Gribovskaya, I V; Zolotukhin, I G

    2000-05-01

    "Man-plants-physical-chemical unit" system designed for space stations or terrestrial ecohabitats to close steady-state mineral, water and gas exchange is proposed. The physical-chemical unit is to mineralize all inedible plant wastes and physiological human wastes (feces, urine, gray water) by electromagnetically activated hydrogen peroxide in an oxidation reactor. The final product is a mineralized solution containing all elements balanced for plants' requirements. The solution has been successfully used in experiments to grow wheat, beans and radish. The solution was reusable: the evaporated moisture was replenished by the phytotron condensate. Sodium salination of plants was precluded by evaporating reactor-mineralized urine to sodium saturation concentration to crystallize out NaCl which can be used as food for the crew. The remaining mineralized product was brought back for nutrition of plants. The gas composition of the reactor comprises O2, N2, CO2, NH3, H2. At the reactor's output hydrogen and oxygen were catalyzed into water, NH3 was converted in a water trap into NH4 and used for nutrition of plants. A special accessory at the reactor's output may produce hydrogen peroxide from intrasystem water and gas which makes possible to close gas loops between LSS components. PMID:11543386

  13. Removal of radioactive contaminants from aqueous laboratory wastes by chemical treatment

    International Nuclear Information System (INIS)

    The following conclusions can be drawn from the studies reported. The presence of suspended matter (i.e., clay) in the spiked tapwater solution improved the plutonium removals; however, the addition of clinoptilolite to the plant raw feed did not provide any noticeable improvement for plutonium removal. The addition of powdered clinoptilolite to the regular treatment in the plant significantly improved the removal of 137Cs, but had little effect on plutonium or 90Sr removal. Magnesium sulfate-lime-TSP (trisodium phosphate) treatment in the plant performed adequately, but not as well as the regular ferric sulfate-lime-TSP treatment. However, magnesium appears to be an adequate alternate during occasions of non-typical influents. A large portion of the plutonium is associated with the suspended solids matter in the waste. Autoradiographs indicate that the plutonium is generally evenly distributed, with some occasional hot spots

  14. Efficiency of Chemical Treatments on Reduction of COD and Turbidity of Deinked Pulp Waste Water

    OpenAIRE

    Shademan Pourmousa; Somayeh Soltani Paraftabi

    2013-01-01

    The effect of poly aluminum chloride with cationic or anionic polymers in treatment of deinked waste water has been studied. The experiments were carried out in jar tests with poly aluminum chloride dosages range of 5-20 mg/l, cationic or anionic polymers dosages range of 1-3 mg/l, pH range of 7.2-8.2, rapid mixing at 100rpm for 2minute, followed by slow mixing at 40 rpm for 10minute and settling for 20minute. The effectiveness of poly aluminum chloride with cationic or anionic polymers were ...

  15. Pilot scale study of a chemical treatment process for decontamination of aqueous radioactive waste of pakistan research reactor-1

    International Nuclear Information System (INIS)

    Chemical treatment process for the low level liquid radioactive waste generated at PINSTECH was previously optimized on lab-scale making use of coprecipitation of hydrous oxides of iron in basic medium. Ferrous sulfate was used as coagulant. Batch wise application of this procedure on pilot scale has been tested on a 1200 L batch volume of typical PINSTECH liquid waste. Different parameters and unit operations have been evaluated. The required data for the construction of a small size treatment plant envisioned can be used for demonstration/teaching purpose as well as for the decontamination of the waste effluents of the Institute. The lab-scale process parameters were verified valid on pilot scale. It was observed that reagent doses can further be economized with out any deterioration of the Decontamination Factors (DF) achieved or of any other aspect of the process. This simple, cost- effective, DF-efficient and time-smart batch wise process could be coupled with an assortment of other treatment operations thus affording universal application. Observations recorded during this study are presented. (author)

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

    International Nuclear Information System (INIS)

    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 FeCI3 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

  17. On the chemical behaviour of technetium during treatment of high-level radioactive waste

    International Nuclear Information System (INIS)

    This work deals with 1. the behaviour of technetium during the vitrification of high-level radioactive waste, 2. the dissolution behaviour of technetium dioxide which is an important compound with regard to the geological disposal of high-level radioactive waste, 3. the leaching behaviour of glasses containing technetium. Incorporation and volatilization of technetium in the course of melting glass frits containing technetium was studied on a laboratory scale. The chemical state of the incorporated technetium was studied by means of X-ray microanalysis and EPR spectroscopy. The investigation of the dissolution behaviour of technetium dioxide in different aqueous systems (HCl, HNO3, NaOH, Na2CO3) has shown that under aerobic conditions TcO2 dissolves without a solubility equilibrium being established. Only heptavalent technetium in the form of pertechnetate was detected in the solutions. Under aerobic conditions, the dissolution rate of TcO2 is controlled by the oxidation potential of tetravalent to heptavalent technetium at the surface of the oxide. The dissolution rate depends on the surface properties and thus on the thermal pretreatment of the utilized oxide. Static leach experiments were performed on glasses containing technetium. In case of a borosilicate glass which contained heptavalent technetium, technetium was released by a diffusion controlled mechanism. Leaching a glass ceramic containing metallic technetium and technetium in oxidation states lower than 7+, a retention of technetium was observed after some time which was probably caused by a gel layer growing on the surface of the specimen. (orig./MM)

  18. Chemical and mineralogical modifications of simplified radioactive waste calcine during heat treatment

    International Nuclear Information System (INIS)

    understanding chemical reactions between the calcined waste and the glass precursor

  19. Chemical and mineralogical modifications of simplified radioactive waste calcine during heat treatment

    Science.gov (United States)

    Monteiro, A.; Schuller, S.; Toplis, M. J.; Podor, R.; Ravaux, J.; Clavier, N.; Brau, H. P.; Charpentier, T.; Angeli, F.; Leterrier, N.

    2014-05-01

    chemical reactions between the calcined waste and the glass precursor.

  20. Study on physico - chemical properties of Korean anthracite for utilization development - application to filtering materials for waste water treatment

    Energy Technology Data Exchange (ETDEWEB)

    Park, Hong Soo; Lee, Jae Ho; Park, Suk Whan [Korea Institute of Geology Mining and Materials, Taejon (Korea, Republic of)

    1996-12-01

    This research was initiated for the development of filtering materials those can be used in waste water treatment sites. The selected Jangseong coal for filtering material has low Hardgrove Grindability Index (HGI : 38.38) and crushed two granule size. One is 1-2 mm size (effective size : 0.77 mm, uniformity coefficient : 1.70) and the other is 2-4 mm size (2.04 mm, 1.37) First, we had application test to find out the possibility of 2-4 mm sample for using water filtering material instead of silica sand in Sandflo filter. The result were unsuitable for treatment efficiency and micron size granule. But it will be solution with control of granule size and washing of coal. For feasibility study, the small scale of filtration tester was built on the waste water treatment plant of Lotte-chilsung beverage Co. to use the precipitated water during filtration test processed by purifying system. Measurement items are filtration rate, temperature of waste water, Electric Conductivity (EC), pH, turbidity, Dissolved Oxygen (DO), Chemical Oxygen Demand (COD), Biochemical Oxygen Demand (BOD), Nitrogen Nitrate (NO{sub 3}-N), Organophosphorus and trace elements content (Zn, Al, Fe, Mg, K) of the supplied water and filtered water were carried out to find the filtration capacity of coal. The results indicated decreasing degree in turbidity (1-2 mm : 15.08 %, 2-4 mm : 11.58 %), COD (1-2 mm : 5.76 %, 2-4 mm : 5.49 %) and increasing degree in DO (1-2 mm : 11.25 %, 2-4 mm : 10 %). Trace elements removal degree of filtered waste water were about 30 % for Fe and 5 % for K. (author). 32 refs., tabs., figs.

  1. Waste management and chemical inventories

    Energy Technology Data Exchange (ETDEWEB)

    Gleckler, B.P.

    1995-06-01

    This section of the 1994 Hanford Site Environmental Report summarizes the classification and handling of waste at the Hanford Site. Waste produced at the Hanford Site is classified as either radioactive, nonradioactive, or mixed waste. Radioactive wastes are further categorized as transuranic, high-level, and low-level. Mixed waste may contain both radioactive and hazardous nonradioactive substances. This section describes waste management practices and chemical inventories at the site.

  2. Chemical modeling of waste sludges

    Energy Technology Data Exchange (ETDEWEB)

    Weber, C.F.; Beahm, E.C.

    1996-10-01

    The processing of waste from underground storage tanks at the Oak Ridge National Laboratory (ORNL) and other facilities will require an understanding of the chemical interactions of the waste with process chemicals. Two aspects of sludge treatment should be well delineated and predictable: (1) the distribution of chemical species between aqueous solutions and solids, and (2) potential problems due to chemical interactions that could result in process difficulties or safety concerns. It is likely that the treatment of waste tank sludge will begin with washing, followed by basic or acidic leaching. The dissolved materials will be in a solution that has a high ionic strength where activity coefficients are far from unity. Activity coefficients are needed in order to calculate solubilities. Several techniques are available for calculating these values, and each technique has its advantages and disadvantages. The techniques adopted and described here is the Pitzer method. Like any of the methods, prudent use of this approach requires that it be applied within concentration ranges where the experimental data were fit, and its use in large systems should be preceded by evaluating subsystems. While much attention must be given to the development of activity coefficients, other factors such as coprecipitation of species and Ostwald ripening must also be considered when one aims to interpret results of sludge tests or to predict results of treatment strategies. An understanding of sludge treatment processes begins with the sludge tests themselves and proceeds to a general interpretation with the aid of modeling. One could stop with only data from the sludge tests, in which case the table of data would become an implicit model. However, this would be a perilous approach in situations where processing difficulties could be costly or result in concerns for the environment or health and safety.

  3. Integrated chemical/biological treatment of paint stripper mixed waste: Metals toxicity and separation

    International Nuclear Information System (INIS)

    The DOE complex has generated vast quantities of complex heterogeneous mixed wastes. Paint stripper waste (PSW) is a complex waste that arose from decontamination and decommissioning activities. It contains paint stripper, cheesecloth, cellulose-based paints with Pb and Cr, and suspect Pu. Los Alamos National Laboratory has 150--200 barrels of PSW and other national laboratories such as Rocky Flats Plant have many more barrels of heterogeneous waste. Few technologies exist that can treat this complex waste. Our approach to solving this problem is the integration of two established technologies: biodegradation and metals chelation

  4. Chemical and mineralogical modifications of simplified radioactive waste calcine during heat treatment

    Energy Technology Data Exchange (ETDEWEB)

    Monteiro, A. [CEA, DEN, DTCD/SECM/LDMC Marcoule, BP 17171, F-30207 Bagnols-sur-Cèze cedex (France); Schuller, S., E-mail: sophie.schuller@cea.fr [CEA, DEN, DTCD/SECM/LDMC Marcoule, BP 17171, F-30207 Bagnols-sur-Cèze cedex (France); Toplis, M.J. [CNRS, Observatoire Midi Pyrénées, IRAP (UMR 5277), F-31400 Toulouse (France); Podor, R.; Ravaux, J.; Clavier, N.; Brau, H.P. [ICSM UMR 5257 CEA/CNRS/UMR/ENSCM Site de Marcoule, BP 17171, F-30207 Bagnols-sur-Cèze cedex (France); Charpentier, T. [UMR CEA/CNRS 3299, IRAMIS, SIS2M, LSDRM Saclay, F-91191 Gif-sur-Yvette cedex (France); Angeli, F. [CEA, DEN, DTCD/SECM/LCLT Marcoule, BP 17171, F-30207 Bagnols-sur-Cèze cedex (France); Leterrier, N. [CEA, DEN, DM2S/SFME/LSFT Saclay, F-91191 Gif-sur-Yvette cedex (France)

    2014-05-01

    influenced by the relative proportion of Al(NO{sub 3}){sub 3}⋅9H{sub 2}O in the calcine, larger amounts of Al leading to denitration at lower temperature. These results constitute the necessary background for understanding chemical reactions between the calcined waste and the glass precursor.

  5. Treatment of radioactive wastes

    International Nuclear Information System (INIS)

    This report is a review of some waste management activities including sources, system of collection and treatment of radioactive wastes. The report also includes methods and options used for treatment of liquid and solid radioactive wastes. (author). 26 refs., 5 figs., 6 tabs

  6. Thermal treatment of electronic waste in a fluidised bed and chemical digestion of solid products.

    Science.gov (United States)

    Woynarowska, Amelia; Żukowski, Witold; Żelazny, Sylwester

    2016-07-01

    The article presents the results of e-waste thermal treatment in a fluidised bed reactor and solid products digestion under acidic conditions. During the processes, measurements of carbon monoxide, carbon dioxide, volatile organic compounds, nitrogen oxides, sulphur dioxide, hydrogen chloride, hydrogen bromide, hydrogen cyanide, ammonia, phenol, aliphatic and aromatic hydrocarbons, hydrogen fluoride and phosgene were carried out. Several digestion tests of the solid residue in sulphuric acid (VI) at 25 °C-65 °C, for 55 min-24 h were conducted. In each case, the dilution method was used, i.e. preliminary digestion in concentrated sulphuric acid (VI) (95%) for 40 min, and then dilution to expected concentrations (30%-50%). Most preferred results were obtained using sulphuric acid (VI) with a target concentration of 40% at 65 °C, where the leaching degrees were 76.56% for copper, 71.67% for iron, 91.89% for zinc and 97.40% for tin. The time necessary to effectively carry out the digestion process was 220 min. PMID:27245176

  7. Chemical characterization of emissions from a municipal solid waste treatment plant.

    Science.gov (United States)

    Moreno, A I; Arnáiz, N; Font, R; Carratalá, A

    2014-11-01

    Gaseous emissions are an important problem in municipal solid waste (MSW) treatment plants. The sources points of emissions considered in the present work are: fresh compost, mature compost, landfill leaks and leachate ponds. Hydrogen sulphide, ammonia and volatile organic compounds (VOCs) were analysed in the emissions from these sources. Hydrogen sulphide and ammonia were important contributors to the total emission volume. Landfill leaks are significant source points of emissions of H2S; the average concentration of H2S in biogas from the landfill leaks is around 1700 ppmv. The fresh composting site was also an important contributor of H2S to the total emission volume; its concentration varied between 3.2 and 1.7 ppmv and a decrease with time was observed. The mature composting site showed a reduction of H2S concentration (biogas from landfill leaks varied from 160 to 640 ppmv). Regarding VOCs, the main compounds were: limonene, p-cymene, pinene, cyclohexane, reaching concentrations around 0.2-4.3 ppmv. H2S/NH3, limonene/p-cymene, limonene/cyclohexane ratios can be useful for analysing and identifying the emission sources. PMID:25106121

  8. Dyes Waste Treatments

    Directory of Open Access Journals (Sweden)

    Siew-Teng Ong

    2011-02-01

    Full Text Available Dyes waste represent one of the problematic groups of pollutants because their presence can be easily identified by the human eye and they are not easily biodegradable. This literature review paper highlights and provides an overview of dyes waste treatments for 3 years period, from 2008–2010. The noteworthy treatment processes for dyes waste include biological treatment, catalytic oxidation, filtration, sorption process and combination treatments.

  9. Final Report: Fiscal Year 1997 demonstration of omnivorous non-thermal mixed waste treatment: Direct chemical oxidation of organic solids and liquids using peroxydisulfate

    Energy Technology Data Exchange (ETDEWEB)

    Cooper, J.F.

    1998-01-01

    Direct Chemical Oxidation (DCO) is a non-thermal, ambient pressure, aqueous-based technology for the oxidative destruction of the organic components of hazardous or mixed waste streams. The process has been developed for applications in waste treatment, chemical demilitarization and decontamination at LLNL since 1992. The process uses solutions of the peroxydisulfate ion (typically sodium or ammonium salts) to completely mineralize the organics to carbon dioxide and water. The expended oxidant may be electrolytically regenerated to minimize secondary waste. The paper briefly describes: free radical and secondary oxidant formation; electrochemical regeneration; offgas stream; and throughput.

  10. Final Report: Fiscal Year 1997 demonstration of omnivorous non-thermal mixed waste treatment: Direct chemical oxidation of organic solids and liquids using peroxydisulfate

    International Nuclear Information System (INIS)

    Direct Chemical Oxidation (DCO) is a non-thermal, ambient pressure, aqueous-based technology for the oxidative destruction of the organic components of hazardous or mixed waste streams. The process has been developed for applications in waste treatment, chemical demilitarization and decontamination at LLNL since 1992. The process uses solutions of the peroxydisulfate ion (typically sodium or ammonium salts) to completely mineralize the organics to carbon dioxide and water. The expended oxidant may be electrolytically regenerated to minimize secondary waste. The paper briefly describes: free radical and secondary oxidant formation; electrochemical regeneration; offgas stream; and throughput

  11. Exploring the Reuse Potential of Chemical Sludge from Textile Wastewater Treatment Plants in India-A Hazardous Waste

    Directory of Open Access Journals (Sweden)

    Hema Patel

    2009-01-01

    Full Text Available Problem statement: This study was conducted to explore the reuse potential of the chemical sludge (considered as hazardous waste as per Indian Government Hazardous Waste Management Rules generated from combined effluent treatment in textile clusters. These textile clusters mainly cover the cotton dyeing and printing operations. Approach: Therefore, treatability studies of chemical sludge were conducted using solidification/stabilization treatment to examine the possibility of its reuse in construction materials. The sludge was characterised for its physico-chemical parameters and heavy metals. Standard blocks of dimensions 70.6×70.6×70.6 mm were prepared, in which chemical sludge was used as a partial replacement of cement by mixing 30-70 % of sludge in cement. After the experimental curing, the blocks were evaluated for physical engineering properties such as hardening time, block density, unconfined compressive strength. The chemical properties were determined in terms of concentrations of heavy metals in the TCLP leachate. Results: The hardening time ranged between 30-45 h. The compressive strength in the sludge cement blocks ranged from 2.63-22.54 N mm-2 after 14 days of water curing and 6.48-24.89 N mmm-2 after 28 days of water curing for 30, 40, 50, 60 and 70 % sludge replacement in cement. The block density varied between 1361. 3408-1813.8992 Kg m-3 after 14 days and 1386.3953-1842.3446 Kg m-3 after 28 days of water curing. The concentrations of heavy metals were negligible in the TCLP leachate and thus below USEPA regulatory limits. Conclusion/Recommendations: As far as structural applications is concerned, it is fulfilling the criteria of some of the classes (C to K as per the BIS standards of the bricks upto a strength of 25 N mm2. The use of sludge can definitely be explored for other structural and non-structural applications depending upon strength requirement. Other applications of textile sludge in the construction materials

  12. Thermal plasma waste treatment

    International Nuclear Information System (INIS)

    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)

  13. Application of Chemically Modified and Unmodified Waste Biological Sorbents in Treatment of Wastewater

    OpenAIRE

    John Kanayochukwu Nduka

    2012-01-01

    Protein wastes (feathers, goat hair) and cellulosic wastes (corn cob, coconut husks) were collected and washed with detergent solution, thoroughly rinsed and sun dried for 2 days before drying in an oven, and then ground. One-half of ground material was carbonized at a maximum temperature of 500°C after mixing with H2SO4. The carbonized parts were pulverized; both carbonized and uncarbonized sorbents were sieved into two particle sizes of 325 and 625 μm using mechanical sieve. Sorbents of a g...

  14. The physico-chemical treatment of laundry waste water; Tratamiento fisicoquimica de aguas residuales de lavanderias

    Energy Technology Data Exchange (ETDEWEB)

    Susial, P.; Jato, I. G.; Larranaga, I.

    2006-07-01

    Waste water from the washing of clot her is treated with aluminium sulphate + acrylamide to achieve coagulation/flocculation. The analytical data obtained in a jar-test using the FTU as the control parameter demonstrate the efficacy of the process, as reductions in the FTU approaching 100% and elimination rates of 80% in detergents and 85% in the COD were achieved. These results show that coagulation and flocculation are sufficient to treat laundry waste water, even though it contains a high pollutant load, since both organic and inorganic pollutants can be significantly reduced by such operations. (Author) 17 refs.

  15. Pilot plant SERSE: Description and results of the experimental tests under treatment of simulated chemical liquid waste

    International Nuclear Information System (INIS)

    The chemical processes for the selective separation of the actinides and long lived fission products from aged liquid wastes is described. The SERSE pilot plant is a cold facility which has been designed, by ENEA, for the engineering scale demonstration of the chemical separation processes. The experimental tests carried out in the plant are described and the results confirm the laboratory data. (author)

  16. Application of Chemically Modified and Unmodified Waste Biological Sorbents in Treatment of Wastewater

    Directory of Open Access Journals (Sweden)

    John Kanayochukwu Nduka

    2012-01-01

    Full Text Available Protein wastes (feathers, goat hair and cellulosic wastes (corn cob, coconut husks were collected and washed with detergent solution, thoroughly rinsed and sun dried for 2 days before drying in an oven, and then ground. One-half of ground material was carbonized at a maximum temperature of 500°C after mixing with H2SO4. The carbonized parts were pulverized; both carbonized and uncarbonized sorbents were sieved into two particle sizes of 325 and 625 μm using mechanical sieve. Sorbents of a given particle size were packed into glass column.Then, textile wastewater that had its physicochemical parameters previously determined was eluted into each glass column and a contact time of 60 and 120 mins was allowed before analysis. Results showed 48.15–99.98 percentage reduction of NO3−, EC, Cl−, BOD, COD, DO, TSS, and TDS, 34.67–99.93 percentage reduction of NO3−, EC, Cl−, BOD, COD, DO, TSS, and TDS, 52.83–97.95 percentage reduction of Pb2+, Ni2+, Cr3+ and Mn2+ and 34.59–94.87 percentage reduction of Pb2+, Ni2+, Cr3+ and Mn2+. Carbonization, small particle, size and longer contact time enhanced the sorption capabilities of the sorbents. These show that protein and cellulosic wastes can be used to detoxify wastewater.

  17. Chemical studies on the treatment of hazardous liquid wastes by Two-phase transfer

    International Nuclear Information System (INIS)

    Phosphate fertilizers produced from phosphate industries are one of the main sources of cadmium and other heavy metals in agricultural soils. Wastewater produced from phosphate industries and released in the water streams is highly acidic and contaminated with heavy metals which have severe environmental impacts. Phosphoric acid produced from phosphate ores by wet process contains small amounts of uranium together with some heavy metals. The presence of heavy metals represent a nuclear poison for using uranium as nuclear fuel. Therefore, the extraction of these elements from phosphoric acid produced by this process is necessary for the recovery of high purity uranium. The extraction of these elements from phosphate medium is of major importance where phosphate solution is a common species in radioactive waste solutions. The main trends to remove these elements are to use precipitation, ion exchange and liquid-liquid extraction. 9 tabs., 64 figs., 113 refs

  18. Patterns of waste generation, treatment and disposal in the chemical and allied industries in Ghana

    OpenAIRE

    Osei-Wusu Achaw

    2012-01-01

    Environmental pollution and degradation in urban Ghana has been on the increase as a result of the nations drive towards industrialization, a generally weak regulatory regime, and a lack of capacity to manage the environment. This situation is affecting the well-being and livelihood of affected communities. As part of an effort to address the issue, a thirteen (13) item questionnaire was designed and distributed to seventy (70) companies in the chemical and allied industry to solicit and anal...

  19. Method and techniques of radioactive waste treatment

    International Nuclear Information System (INIS)

    This study illustrates the characterization of radioactive wastes produced by the application of radioisotopes in industry and research. The treatment methods of such radioactive wastes, chemical co-precipitation and ion exchange depending on the technical state of radioactive waste management facility in Syria were described. The disposal of conditioned radioactive wastes, in a safe way, has been discussed including the disposal of the radioactive sources. The characterizations of the repository to stock conditioned radioactive wastes were mentioned. (author)

  20. Solid waste treatment technologies

    OpenAIRE

    Golomeova, Saska; Srebrenkoska, Vineta; Krsteva, Silvana; Spasova, Sanja

    2013-01-01

    Environmental pollution is the major problem associated with rapid industrialization, urbanization and rise in living standards of people. Increasing of the amount of solid waste and the pressure what it has on the environment, impose the need to introduce advanced approach to effectively managing of solid waste. This advanced approach includes technologies for solid waste treatment, that fall into the category of "Renewable". This paper put emphasis on technologies for material and energy u...

  1. Thermal treatment of organic radioactive waste

    International Nuclear Information System (INIS)

    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

  2. Lyophilization -Solid Waste Treatment

    Science.gov (United States)

    Litwiller, Eric; Flynn, Michael; Fisher, John; Reinhard, Martin

    2004-01-01

    This paper discusses the development of a solid waste treatment system that has been designed for a Mars transit exploration mission. The technology described is an energy-efficient lyophilization technique that is designed to recover water from spacecraft solid wastes. Candidate wastes include feces, concentrated brines from water processors, and other solid wastes that contain free water. The system is designed to operate as a stand-alone process or to be integrated into the International Space Station Waste Collection System. In the lyophilization process, water in an aqueous waste is frozen and then sublimed, separating the waste into a dried solid material and liquid water. The sublimed water is then condensed in a solid ice phase and then melted to generate a liquid product. In the subject system the waste solids are contained within a 0.2 micron bio-guard bag and after drying are removed from the system and stored in a secondary container. This technology is ideally suited to applications such as the Mars Reference Mission, where water recovery rates approaching 100% are desirable but production of CO2 is not. The system is designed to minimize power consumption through the use of thermoelectric heat pumps. The results of preliminary testing of a prototype system and testing of the final configuration are provided. A mathematical model of the system is also described.

  3. Strategic planning for waste management: Characterization of chemically and radioactively hazardous waste and treatment, storage, and disposal capabilities for diverse and varied multisite operations

    International Nuclear Information System (INIS)

    Information about current and projected waste generation as well as available treatment, storage, and disposal (TSD) capabilities and needs is crucial for effective, efficient, and safe waste management. This is especially true for large corporations that are responsible for multisite operations involving diverse and complex industrial processes. Such information is necessary not only for day-to-day operations, but also for strategic planning to ensure safe future performance. This paper reports on some methods developed and successfully applied to obtain requisite information and to assist waste management planning at the corporate level in a nationwide system of laboratories and industries. Waste generation and TSD capabilities at selected US Department of Energy (DOE) sites were studied. 1 ref., 2 tabs

  4. Assessing mixed waste treatment technologies

    International Nuclear Information System (INIS)

    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 m3 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

  5. Treatment, recovery, and disposal processes for radioactive wastes

    International Nuclear Information System (INIS)

    Radioactive wastes handling and disposal are discussed in over 200 processes here. Isolation means for these wastes must withstand attack, essentially indefinitely, from the radioactive material and the chemical and physical stresses of the natural environment. Contents: Immobilization Techniques; Storage Containers; Water Removal and Concentration Processes; Chemical Treatments; Heat Treatments; Recovery and Recycling Processes; Processing Radioactive Gases; Waste Treatment Apparatus and Equipment

  6. PERFORMANCE EVALUATION OF WASTE WATER TREATMENT PLANT

    OpenAIRE

    K. SUNDARA KUMAR; P. SUNDARA KUMAR,; Dr.M.J.Ratnakanth Babu

    2010-01-01

    The present study has been undertaken to evaluate performance efficiency of a waste water treatment plant. A sewage treatment plant operating on biological treatment method (Activated Sludge Process) with an average wastewater inflow of 23MLD bas been considered for case study. Waste water samples were collected at different stages of treatment units and analysed for the major water quality parameters, such as biological oxygen demand (BOD), chemical oxygen demand (COD), total suspended solid...

  7. Experiences with treatment of mixed waste

    International Nuclear Information System (INIS)

    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

  8. 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.

  9. The use of ionizing radiations in the treatment of liquid and solid waste; biological and physico-chemical effects and industrial study

    International Nuclear Information System (INIS)

    Short recycling of waste water and the use of liquid or dehydrated sludge as natural manure for agriculture, or animal supplement feed is of great economical and ecological interest. However, it requires strong disinfection. Treatment with ionizing radiation can be used as a complement to conventional methods in the treatment of liquid and solid wastes. An experiment conducted with a high-energy electron beam linear accellerator (10 MeV) is presented. Degradation of undesirable metabolites in wastes occurs at a dose of 50 krad. Undesirable seeds, present in sludge, are destroyed with a 200-krad dose. The same dose is sufficient for parasitic and bacterial disinfection (DL 90). Destruction of poliovirus (DL 90) is obtained at 400 krad. Higher doses (1000-2000 krad) produce mineralisation of toxic organic mercury or reduce some toxic chemical pollutants present in sludge and improve flocculation. Industrial study shows that waste treatment with high-energy electron beams is technically and economically feasible. The design for a treatment unit of 5 MCi cobalt-equivalent, with a capacity of 500 t/Mrad/24h is presented, with indicative cost calculation

  10. 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.

  11. Laundry liquid waste treatment

    International Nuclear Information System (INIS)

    Laundry liquid waste contains 99% of Co-60, Cs-137 and 1% of Mn-54, Cr-51 arising at decontamination workshops was treated using 3 stages of operation which are Reverse Osmosis (RO), Falling-Film Evaporation (FE) and Microwave - Oven Solidification (MO). The liquid waste from decontamination of clothes and surfaces which the activity is 2 pressure the reverse osmosis is occurred. The RO concentrate is passed through the steam heating at 140 C of FE process and finally the FE concentrate is automatically transferred to 25 lW 915 MHz of MO process. The concentrated wastes are dried, incinerated, solidified with glass powder and boric acid in 30 litre stainless steel drum. The solidified material is put in 200 litre concrete -lining drum for the concrete embedding and final storage. The condensate is sent to liquid waste facility after radioactive monitoring, for the further treatment or discharge to environment. After treatments, it is found that decontamination efficiencies are> 97% and the total volume reduction is 1:1,000 (RO 1:20, FE 1:5 and MO 1:10), which show the high effective and appreciative results

  12. Mixed Waste Treatment Project -- Scope and status

    International Nuclear Information System (INIS)

    Department of Energy (DOE) facilities currently store and generate significant quantities of mixed wastes - mixtures of materials containing both radioactive and hazardous chemical contamination. These wastes must be managed in compliance with DOE requirements and EPA Land Disposal Restrictions. To help meet these requirements for low-level mixed wastes, the DOE Office of Waste Operations has established The Mixed Waste Treatment Project (MWTP). The overall goal of the MWTP is demonstration of effective treatment of low-level mixed wastes in a full-scale prototype plant. The MWTP staff, supported by a technical committee comprised of waste operations representatives from Hanford, Idaho, Los Alamos, Oak Ridge, Rocky Flats and Savannah River have reviewed the three major DOE data bases, the Integrated Data Base, the National Report on Prohibited Wastes and the Waste Management Information System data base managed by HAZWRAP. Database upgrades to meet MWTP needs are being pursued by field visits to the major mixed waste generators. A reference flowsheet was developed for treatment of low level contact handled mixed wastes. Technology gaps identified by these analyses are being used by DOE Waste Operations, and the Office of Technology Development to define technology development needs. A brief analysis of options for deployment of capabilities to treat mixed wastes at DOE facilities nationwide has been conducted

  13. Electrochemical treatment of liquid wastes

    Energy Technology Data Exchange (ETDEWEB)

    Hobbs, D.T. [Savannah River Technology Center, Aiken, SC (United States)

    1997-10-01

    Under this task, electrochemical treatment processes are being evaluated and developed for the destruction of organic compounds and nitrates/nitrites and the removal of other hazardous species from liquid wastes stored throughout the DOE complex. This technology targets the (1) destruction of nitrates, nitrites and organic compounds; (2) removal of radionuclides; and (3) removal of RCRA metals. The development program consists of five major tasks: (1) evaluation of electrochemical reactors for the destruction and removal of hazardous waste components, (2) development and validation of engineering process models, (3) radioactive laboratory-scale tests, (4) demonstration of the technology in an engineering-scale reactor, and (5) analysis and evaluation of test data. The development program team is comprised of individuals from national laboratories, academic institutions, and private industry. Possible benefits of this technology include: (1) improved radionuclide separation as a result of the removal of organic complexants, (2) reduction in the concentrations of hazardous and radioactive species in the waste (e.g., removal of nitrate, mercury, chromium, cadmium, {sup 99}Tc, and {sup 106}Ru), (3) reduction in the size of the off-gas handling equipment for the vitrification of low-level waste (LLW) by reducing the source of NO{sub x} emissions, (4) recovery of chemicals of value (e.g. sodium hydroxide), and (5) reduction in the volume of waste requiring disposal.

  14. Electrochemical treatment of liquid wastes

    International Nuclear Information System (INIS)

    Under this task, electrochemical treatment processes are being evaluated and developed for the destruction of organic compounds and nitrates/nitrites and the removal of other hazardous species from liquid wastes stored throughout the DOE complex. This technology targets the (1) destruction of nitrates, nitrites and organic compounds; (2) removal of radionuclides; and (3) removal of RCRA metals. The development program consists of five major tasks: (1) evaluation of electrochemical reactors for the destruction and removal of hazardous waste components, (2) development and validation of engineering process models, (3) radioactive laboratory-scale tests, (4) demonstration of the technology in an engineering-scale reactor, and (5) analysis and evaluation of test data. The development program team is comprised of individuals from national laboratories, academic institutions, and private industry. Possible benefits of this technology include: (1) improved radionuclide separation as a result of the removal of organic complexants, (2) reduction in the concentrations of hazardous and radioactive species in the waste (e.g., removal of nitrate, mercury, chromium, cadmium, 99Tc, and 106Ru), (3) reduction in the size of the off-gas handling equipment for the vitrification of low-level waste (LLW) by reducing the source of NOx emissions, (4) recovery of chemicals of value (e.g. sodium hydroxide), and (5) reduction in the volume of waste requiring disposal

  15. Thermal and thermo-chemical pre-treatment of four waste residues and the effect on acetic acid production and methane synthesis.

    Science.gov (United States)

    Strong, P J; Gapes, D J

    2012-09-01

    In this study four diverse solid waste substrates (coal, Kraft pulp solids, chicken feathers and chicken processing waste) were thermally pre-treated (70, 140 and 200 °C), under an inert (nitrogen) or oxidative (oxygen) atmosphere, and then anaerobically digested. Membrane inlet mass spectrometry during the thermal and thermo-chemical reactions was successfully used to establish oxygen and carbon dioxide gas fluxes and product formation (acetic acid). There was significant solids hydrolysis pre-treatment at 200 °C under an oxidative atmosphere, as indicated by a decrease in the volatile suspended solids and an increase in dissolved organic carbon. Greater concentrations of volatile fatty acids were produced under oxidative conditions at higher temperatures. The methane yield more than tripled for feathers after pre-treatment at 140 °C (under both atmospheres), but decreased after oxidative pre-treatment at 200 °C, due to the destruction of available carbon by the thermo-chemical reaction. Methane yield more than doubled for the Kraft pulp solids with the 200 °C pre-treatment under oxidative conditions. This study illustrated the power of wet oxidation for solids destruction and its potential to improve methane yields generated during anaerobic digestion. PMID:22609530

  16. Technology for Treatment of Liquid Radioactive Waste Generated during Uranium and Plutonium Chemical and Metallurgical Manufacturing in FSUE PO Mayak - 13616

    International Nuclear Information System (INIS)

    Created technological scheme for treatment of liquid radioactive waste generated while uranium and plutonium chemical and metallurgical manufacturing consists of: - Liquid radioactive waste (LRW) purification from radionuclides and its transfer into category of manufacturing waste; - Concentration of suspensions containing alpha-nuclides and their further conversion to safe dry state (calcinate) and moving to long controlled storage. The following technologies are implemented in LRW treatment complex: - Settling and filtering technology for treatment of liquid intermediate-level waste (ILW) with volume about 1500m3/year and alpha-activity from 106 to 108 Bq/dm3 - Membrane and sorption technology for processing of low-level waste (LLW) of radioactive drain waters with volume about 150 000 m3/year and alpha-activity from 103 to 104 Bq/dm3. Settling and filtering technology includes two stages of ILW immobilization accompanied with primary settling of radionuclides on transition metal hydroxides with the following flushing and drying of the pulp generated; secondary deep after settling of radionuclides on transition metal hydroxides with the following solid phase concentration by the method of tangential flow ultrafiltration. Besides, the installation capacity on permeate is not less than 3 m3/h. Concentrates generated are sent to calcination on microwave drying (MW drying) unit. Membrane and sorption technology includes processing of averaged sewage flux by the method of tangential flow ultrafiltration with total capacity of installations on permeate not less than 18 m3/h and sorption extraction of uranium from permeate on anionite. According to radionuclide contamination level purified solution refers to general industrial waste. Concentrates generated during suspension filtering are evaporated in rotary film evaporator (RFE) in order to remove excess water, thereafter they are dried on infrared heating facility. Solid concentrate produced is sent for long

  17. AN EVALUATION OF APPLICABILITY OF PHYSICO-CHEMICAL THRTIARY TREATMENT OF DOMESTIC WASTE IN A REGION OF TEHRAN, IRAN

    Directory of Open Access Journals (Sweden)

    P. Samar

    1985-06-01

    Full Text Available The Purpose of this study was comparison of applicability of tertiary treatment of Tehran domestic sewage with organic and inorganic coagulants or a combination of them. The far test procedure was applied utilizing: alum, polyelectrolyte WT 2600, anionic Polyelectorlyte WT 3000, and nonionic polyelctrolyte WT 2690 as organic coagulants (products of Calgon. The combination of lime with each of the organic coagulants WT 2600 and WT 3000 was subsequently used in jar test analysis. The optimum pH and optimum dosage of each coagulant were determined, based on the removal of turbidity, COD, and suspended solids. The removal of various parameters including COD, and suspended solids, algal nutrients, metals, bacteria, alkalinity, turbidity, and color were assessed by applying of optimum dosage of each coagulant in an evaluation of final selection in physico- chemical treatment. Lime was considered the most suitable among the polyelectrolytes, but combination of lime and polyelectrolytes was comparatively ruled out.

  18. Gas treatment of Cr(VI)-contaminated sediment samples from the North 60`s pits of the chemical waste landfill

    Energy Technology Data Exchange (ETDEWEB)

    Thornton, E.C.; Amonette, J.E.

    1997-12-01

    Twenty sediment samples were collected at depths ranging from 5 to 100 ft (1.5 to 30 m) beneath a metal-contaminated plating-waste site and extensively characterized for Cr(VI) content and environmental availability. Three samples were selected for treatment with diluted gas mixtures with the objective of converting Cr(VI) to Cr(III), which is relatively nontoxic and immobile. These tests were designed to provide information needed to evaluate the potential application of gas injection as an in situ remediation technique. Gas treatment was performed in small columns (4.9-cm ID, 6.4- to 13.9-cm long) using 100 ppm ({mu}L L{sup -1}) H{sub 2}S or ethylene mixtures in N{sub 2}. Treatment progress during the tests involving H{sub 2}S was assessed by monitoring the breakthrough of H{sub 2}S. Evaluation of H{sub 2}S treatment efficacy included (1) water-leaching of treated and untreated columns for ten days, (2) repetitive extraction of treated and untreated subsamples by water, 0.01 M phosphate (pH 7) or 6 M HCl solutions, and (3) Cr K-edge X-ray absorption near-edge structure (XANES) spectroscopy of treated and untreated subsamples. Results of the water-leaching studies showed that the H{sub 2}S treatment decreased Cr(VI) levels in the column effluent by 90% to nearly 100%. Repetitive extractions by water and phosphate solutions echoed these results, and the extraction by HCl released only 35-40% as much Cr in the treated as in the untreated samples. Analysis by XANES spectroscopy showed that a substantial portion of the Cr in the samples remained as Cr(VI) after treatment, even though it was not available to the water and phosphate extracting solutions. These results suggest that this residual Cr(VI) is present in low solubility phases such as PbCrO{sub 4} or sequestered in unreacted grain interiors under impermeable coatings formed during H{sub 2}S treatment. However, this fraction is essentially immobile and thus unavailable to the environment.

  19. Gas treatment of Cr(VI)-contaminated sediment samples from the North 60's pits of the chemical waste landfill

    International Nuclear Information System (INIS)

    Twenty sediment samples were collected at depths ranging from 5 to 100 ft (1.5 to 30 m) beneath a metal-contaminated plating-waste site and extensively characterized for Cr(VI) content and environmental availability. Three samples were selected for treatment with diluted gas mixtures with the objective of converting Cr(VI) to Cr(III), which is relatively nontoxic and immobile. These tests were designed to provide information needed to evaluate the potential application of gas injection as an in situ remediation technique. Gas treatment was performed in small columns (4.9-cm ID, 6.4- to 13.9-cm long) using 100 ppm (μL L-1) H2S or ethylene mixtures in N2. Treatment progress during the tests involving H2S was assessed by monitoring the breakthrough of H2S. Evaluation of H2S treatment efficacy included (1) water-leaching of treated and untreated columns for ten days, (2) repetitive extraction of treated and untreated subsamples by water, 0.01 M phosphate (pH 7) or 6 M HCl solutions, and (3) Cr K-edge X-ray absorption near-edge structure (XANES) spectroscopy of treated and untreated subsamples. Results of the water-leaching studies showed that the H2S treatment decreased Cr(VI) levels in the column effluent by 90% to nearly 100%. Repetitive extractions by water and phosphate solutions echoed these results, and the extraction by HCl released only 35-40% as much Cr in the treated as in the untreated samples. Analysis by XANES spectroscopy showed that a substantial portion of the Cr in the samples remained as Cr(VI) after treatment, even though it was not available to the water and phosphate extracting solutions. These results suggest that this residual Cr(VI) is present in low solubility phases such as PbCrO4 or sequestered in unreacted grain interiors under impermeable coatings formed during H2S treatment. However, this fraction is essentially immobile and thus unavailable to the environment

  20. Le traitement des déchets polymères : la valorisation énergétique ou chimique Treatment of Polymer Wastes: Chemical Or Energy Upgrading

    Directory of Open Access Journals (Sweden)

    Dawans F.

    2006-11-01

    Full Text Available Une protection accrue de l'environnement requiert la mise en place de nouvelles techniques fiables et économiques de traitement des déchets polymères. Parmi les diverses méthodes envisagées pour la réutilisation ou l'élimination des polymères usagés, les recyclages énergétiques et chimiques peuvent apporter des solutions satisfaisantes et complémentaires au recyclage de la matière. Cet article fait le point sur l'état d'avancement des techniques de valorisation énergétique et chimique des rejets de polymères et il propose une analyse critique des traitements actuels. Increased environmental protection requires the installation of new treatment techniques for polymer wastes. Competitive industrial facilities are not available from the economic standpoint for recycling spent plastic and rubber wastes in the form of materials, especially when mixtures are involved. It is only by using other treatment method for the chemical or energy upgrading of polymers, as a supplement to the recycling of materials, that it should be possible to make a significant reduction in the amount of spent polymers currently being scrapped. The energy upgrading of wastes by incineration with energy recovery or by pyrolysis with the formation of fuels in an interesting approach for a great many countries. When no reuse is possible, the energy content of the material is upgraded before the subsequent scrapping of an ultimate residue that is reduced to its incompressible minimum after having been inerted. There are currently several technical solutions for incineration furnaces and the treatment of the fumes produced, which meet the more and more severe requirements concerning environmental protection. Incineration systems with energy recovery can recover about 8000 thermies per ton of unsorted plastics. They already have an important position, albeit a varying one, from one European country to another (Table 6. They should develop considerably further in

  1. Effects of heat treatment and formulation on the phase composition and chemical durability of the EBR-ll ceramic waste form.

    Energy Technology Data Exchange (ETDEWEB)

    Ebert, W. E.; Dietz, N. L.; Janney, D. E.

    2006-01-31

    High-level radioactive waste salts generated during the electrometallurgical treatment of spent sodium-bonded nuclear fuel from the Experimental Breeder Reactor-II will be immobilized in a ceramic waste form (CWF). Tests are being conducted to evaluate the suitability of the CWF for disposal in the planned federal high-level radioactive waste repository at Yucca Mountain. In this report, the results of laboratory tests and analyses conducted to address product consistency and thermal stability issues called out in waste acceptance requirements are presented. The tests measure the impacts of (1) variations in the amounts of salt and binder glass used to make the CWF and (2) heat treatments on the phase composition and chemical durability of the waste form. A series of CWF materials was made to span the ranges of salt and glass contents that could be used during processing: between 5.0 and 15 mass% salt loaded into the zeolite (the nominal salt loading is 10.7%, and the process control range is 10.6 to 11.2 mass%), and between 20 and 30 mass% binder glass mixed with the salt-loaded zeolite (the nominal glass content is 25% and the process control range is 20 to 30 mass%). In another series of tests, samples of two CWF products made with the nominal salt and glass contents were reheated to measure the impact on the phase composition and durability: long-term heat treatments were conducted at 400 and 500 C for durations of 1 week, 4 weeks, 3 months, 6 months, and 1 year; short-term heat treatments were conducted at 600, 700, 800, and 850 C for durations of 4, 28, 52, and 100 hours. All of the CWF products that were made with different amounts of salt, zeolite, and glass and all of the heat-treated CWF samples were analyzed with powder X-ray diffraction to measure changes in phase compositions and subjected to 7-day product consistency tests to measure changes in the chemical durability. The salt loading had the greatest impact on phase composition and durability. A

  2. Solar technology applications in chemical waste management

    International Nuclear Information System (INIS)

    Using solar energy to destroy waste chemicals and toxic materials has great appeal to environmentalists, industrialists and the public. Using free sunlight to resolve one of the industrial age's most troublesome problems is destruction must demonstrate that it competes favorably with current approaches in economic and environmental areas. This paper provides an environmental and economic analysis of solar applications in chemical waste management

  3. Introduction Of Treatment Of Waste Matter

    International Nuclear Information System (INIS)

    This book introduces treatment of waste matter with waste emission and composition change, treatment background of waste matter in the country, treatment of waste in city, structure of system of incineration process, human waste process, recycling technology system, industrial disposal with survey, selection of disposal system and recycling of industrial disposal, treatment of sewage on wastewater generation amount and the treatment, problem of sludge treatment, each process of sludge treatment, final disposal and disposal and process of radioactivity waste.

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

    International Nuclear Information System (INIS)

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

  5. Analysis of Chemical Technology Division waste streams

    International Nuclear Information System (INIS)

    This document is a summary of the sources, quantities, and characteristics of the wastes generated by the Chemical Technology Division (CTD) of the Oak Ridge National Laboratory. The major contributors of hazardous, mixed, and radioactive wastes in the CTD as of the writing of this document were the Chemical Development Section, the Isotopes Section, and the Process Development Section. The objectives of this report are to identify the sources and the summarize the quantities and characteristics of hazardous, mixed, gaseous, and solid and liquid radioactive wastes that are generated by the Chemical Technology Division (CTD) of the Oak Ridge National Laboratory (ORNL). This study was performed in support of the CTD waste-reduction program -- the goals of which are to reduce both the volume and hazard level of the waste generated by the division. Prior to the initiation of any specific waste-reduction projects, an understanding of the overall waste-generation system of CTD must be developed. Therefore, the general approach taken in this study is that of an overall CTD waste-systems analysis, which is a detailed presentation of the generation points and general characteristics of each waste stream in CTD. The goal of this analysis is to identify the primary waste generators in the division and determine the most beneficial areas to initiate waste-reduction projects. 4 refs., 4 figs., 13 tabs

  6. Solid Waste Treatment Technology

    Science.gov (United States)

    Hershaft, Alex

    1972-01-01

    Advances in research and commercial solid waste handling are offering many more processing choices. This survey discusses techniques of storage and removal, fragmentation and sorting, bulk reduction, conversion, reclamation, mining and mineral processing, and disposal. (BL)

  7. Presolidification treatment of decontamination wastes

    International Nuclear Information System (INIS)

    Unsatisfactory leaching performance of several solidified decontamination solutions indicated a need for presolidification treatments to reduce the water sensitivity of the active chemicals. Chemical treatments examined in this work include pH adjustment, precipitation and oxidation-reduction reactions. The reactions involved in these treatments are discussed. The most suitable presolidification treatment for each decontamination solution has been identified. Further research is needed to test the effectivenss of these treatments

  8. Chemical decontamination method for radioactive metal waste

    International Nuclear Information System (INIS)

    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

  9. Treatment of radioactive wastes from uranium concentrating

    International Nuclear Information System (INIS)

    Radioactive wastes from uranium and thorium ore processing pose potential environmental and public health problems because of their radioactivity and chemical composition. The radionuclides exist in these wastes are those resulting from the uranium 238, uranium 235 and thorium 232 decay series. The most important radionuclide in U 238 decay series are uranium 234, thorium 230, radium 226 and some short lived radionuclides such as radon-222. Radium 226 is the nuclide of principal concern from the standpoint of the assessment and control of the radiological hazard associated with the wastes. Thus determination of uranium, thorium and radium concentration in wastes resulting from nuclear fuel cycle is very important because of its potential hazard. Various analytical methods such as fluorimetry, neutron activation analysis, radon emanation, spectrophotometry and spectroscopy are used for determination of these radionuclides. Uranium and thorium are separated from interfering element by ion exchange chromatography and measured by spectrophotometry method using arsenazo III and thorin as indicator. Radium is separated from interfering elements and α-emitters by coprecipitation of radium barium sulphate and measured by counting α-particles with surface barrier detector. Regarding to physical and chemical characteristic of waste being investigated, decontamination factors and treatment methods, chemical precipitation and coprecipitation procedure were carried out in this research work. By adding barium chloride, radium is separated from liquid waste and optimum condition were determined. Precipitation with lime and sodium-hydroxide were also studied and good result were obtained. The results show that by neutralization of waste by lime and sodium hydroxide more than 99.9% of activity was removed from stream. Advantage and disadvantage of each methods were studied and finally, effluent resulted from treatment were discharged after analysis with γ-spectroscopy and

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

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    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.

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

    International Nuclear Information System (INIS)

    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

  12. Clarification and filtration of the floculated partuicles suspension from a chemical treatment of waste oil-in-water emulsions from a non-ferrous metalworking plant

    Directory of Open Access Journals (Sweden)

    Lazarević Vesna B.

    2011-01-01

    Full Text Available The effects of the coagulation/floculation conditions on clarification and filtration of the floculated particle suspension obtained by the chemical treatment of the waste oil-in-water emulsion (OWE from a non-ferrous metalworking plant were studied. The treatment involved the addition of aluminum(III sulfate and lime to the OWE. The main goal was to define the optimum conditions for clarification and filtration of the floculated particle suspension. The factors involved were amounts lime (i.e. pH and filter aid added the OWE on clarification and filtration rates. At pH>10, the clarification rate was increased and the final volume of the concentrated suspension (sludge was reduced, while filter aid affected negatively the clarification rate. The filtration rate was also increased when the coagulation was carried out at pH>10. The floculated particle suspension should be concentrated before filtration in order to decrease the filtration duration. The most efficient filter aid was Celite standard super-cel, its optimum initial concentration being found to be 2 g/dm3.

  13. Liquid waste treatment process - 59061

    International Nuclear Information System (INIS)

    Document available in abstract form only. Full text of publication follows: The law defined the responsibilities of the national center of nuclear energy in Morocco CNESTEN as the sole radioactive waste operating organization and designated CNESTEN as responsible for the management of radioactive waste at the national level in several social and economic sectors. The goals of the unit of radioactive waste management are: -reduce the volume of the radioactive waste product; -convert the radioactive waste into an appropriate waste for monitoring, storage and evacuation; -Recover if it's possible an element of value. The Moroccan products of radioactive liquid waste per year are 0.1 m3 of organic liquid and 35 m3 of liquid aqueous. The method adopted by CNESTEN was the evaporator for liquid aqueous and the solidification with the activated carbon for the organic liquid. An evaporation installation to treat 5 m3 of aqueous liquid in each campaign, the volume of the sludge obtained is 200 liters and 4800 liters of distillate water. Concerning the management system is plan to collect the liquid aqueous in tanks in the bottom of each nuclear installation. After characterization according to the technical specification of radioactive waste management nuclear installation, the waste is transported in an appropriate tank to the treatment building to be evaporated. After treatment the clean water is collect in a separate tank waiting its discharge if it complies with the requirements of release. The volume of sludge issued from evaporator is conditioning with mortar (40 liters) in 120 liters drum, the mixing operation is ensured by shingles introduced in the drum and the rotation of the drum is ensured by a mixer named 'turn drums'. The drum must respect the acceptance criteria before transferred to storage building. About the liquid organic waste was collected in the polyethylene move tank; this kind of waste is mixed to an absorbent product and conditioned like the sludge

  14. Hazardous chemical and radioactive wastes at Hanford

    International Nuclear Information System (INIS)

    The Hanford Site was established in 1944 to produce plutonium for defense. During the past four decades, a number of reactors, processing facilities, and waste management facilities were built at Hanford for plutonium production. Generally, Hanford's 100 Area was dedicated to reactor operation; the 200 Areas to fuel reprocessing, plutonium recovery, and waste management; and the 300 Area to fuel fabrication and research and development. Wastes generated from these operations included highly radioactive liquid wastes, which were discharged to single- and double-shell tanks; solid wastes, including both transuranic and low-level wastes, which were buried or discharged to caissons; and waste water containing low- to intermediate-level radioactivity, which was discharged to the soil column via near-surface liquid disposal units such as cribs, ponds, and retention basins. Virtually all of the wastes contained hazardous chemicals as well as radioactive constituents. This paper focuses on the hazardous chemical components of the radioactive mixed waste generated by plutonium production at Hanford. The processes, chemicals used, methods of disposition, fate in the environment, and actions being taken to clean up this legacy are described by location

  15. Experimental plant for the physical-chemical treatment of groundwater polluted by Municipal Solid Waste (MSW) leachate, with ammonia recovery

    OpenAIRE

    Massimo Raboni; Vincenzo Torretta; Paolo Viotti; Giordano Urbini

    2013-01-01

    The paper documents the results of the experimental treatment of groundwater (flow rate: 300 m3 h-1) polluted by the leachate of an old MSW landfill (7 million tonnes) in northern Italy. The process consists of a coagulation-flocculation pre-treatment at pH > 11, and subsequent ammonia stripping, after heating the water to 35-38 °C by means of the biogas produced by the landfill. The stripped ammonia was recovered by absorption with sulfuric acid, producing a 30% solution of ammonium sulfate,...

  16. Treatment and conditioning processes for low and medium activity waste

    International Nuclear Information System (INIS)

    This chapter reports on experimental studies of precipitation and membrane processes, exchange processes, particular techniques, and immobilization methods. Topics considered include the separation of actinides and fission products from medium activity waste (MAW) concentrate, the decontamination of low activity liquid wastes from fuel fabrication plants by ultrafiltration, active liquid treatment by a combination of precipitation and membrane processes, the treatment of liquid wastes by flocculation, the denitration and chemical precipitation of MAW concentrate, inorganic ion-exchangers prepared via a sol-gel process, liquid waste treatment by electrical processes, the incorporation of low and medium activity wastes in cement, and the conditioning of highly radioactive residues by utilizing a drum-dryer

  17. Methods and instruments for the ecological assessment of the treatment of solvent wastes in the chemical industry; Methoden und Instrumente zur oekologischen Bewertung der Abfall-Loesungsmittelbehandlung in der chemischen Industrie

    Energy Technology Data Exchange (ETDEWEB)

    Capello, Ch.

    2006-07-01

    This final report for the Swiss Federal Office of Energy (SFOE) presents the results of a project which looked at the treatment of solvent wastes in the chemical industry and its ecological impact. The development of a method based on the life-cycle-analysis (LCA) approach is described. The LCA methodology is to provide support for decision-making in the area of solvent waste disposal in the chemical industry. Various methods of disposal, such as distillation or incineration are looked at. The results of calculations using a software tool called 'ecosolvent' are presented and discussed. The 15 most important solvents and their quantities as used in the 6 facilities examined, are listed. The functioning of the ecosolvent software is discussed and illustrated in a flow-diagram. Along with detailed results, a few qualitative rules of thumb are quoted for the treatment of solvent wastes.

  18. Demonstration of omnivorous non-thermal mixed waste treatment: Direct chemical oxidation using peroxydisulfate. Progress report SF2-3-MW-35, October--December 1995

    International Nuclear Information System (INIS)

    Direct Chemical Oxidation is an emerging ''omnivorous'' waste destruction technique which uses one of the strongest known oxidants (ammonium peroxydisulfate) to convert organic solids or liquids to carbon dioxide and their mineral constituents. The process operates at ambient pressure and at moderate temperatures (80--100 C) where organic destruction is rapid without catalysts. The byproduct (ammonium sulfate) is benign and may be recycled using commercial electrolysis equipment. The authors have constructed and initially tested a bench-scale facility (batch prereactor and plug-flow reactor) which allows treatability tests on any solid or liquid organic waste surrogate, with off-gas analysis by mass spectroscopy. Shake-down tests of the plug flow reactor on model chemical ethylene glycol confirmed earlier predictive models. Pre-reactor tests on water-immiscible substances confirmed destruction of cotton rags (cellulose), kerosene, tributyl phosphate and triethylamine. The process is intended to provide an all-aqueous, ambient pressure destruction technique for difficult materials not suitable or fully accepted for conventional incineration. Such wastes include solid and liquid mixed wastes containing incinerator chars, halogenated and nitrogenated wastes, oils and greases, and chemical or biological warfare agents

  19. Modern methods for the treatment of heavily polluted waste water

    International Nuclear Information System (INIS)

    Biological processes are playing an increasingly important role alongside physical, chemical, and thermal processes in integrated process concepts for treatment of industrial waste water. The individual processes are complementary. Biological processes are particularly important in combination with membrane processes, adsorption, or oxidation in the treatment of seepage water from waste dumps. (orig.)

  20. AN EVALUATION OF APPLICABILITY OF PHYSICO-CHEMICAL THRTIARY TREATMENT OF DOMESTIC WASTE IN A REGION OF TEHRAN, IRAN

    OpenAIRE

    P. Samar; K. Imandel; F. Mesghali; Z. Javadi; G. Samar

    1985-01-01

    The Purpose of this study was comparison of applicability of tertiary treatment of Tehran domestic sewage with organic and inorganic coagulants or a combination of them. The far test procedure was applied utilizing: alum, polyelectrolyte WT 2600, anionic Polyelectorlyte WT 3000, and nonionic polyelctrolyte WT 2690 as organic coagulants (products of Calgon). The combination of lime with each of the organic coagulants WT 2600 and WT 3000 was subsequently used in jar test analysis. The optimum p...

  1. Offshore waste treatment guidelines

    International Nuclear Information System (INIS)

    These guidelines were prepared to aid offshore oil and gas operators in the management of waste materials related to petroleum drilling and production operations in offshore areas regulated by the Canada-Newfoundland and Labrador Offshore Petroleum Board (CNLOPB) and the Canada-Nova Scotia Offshore Petroleum Board (CNSOPB). A description of the relevant sections of the regulatory regime applicable to Canada's offshore oil and gas operations was included. Offshore operators are expected to take all reasonable measures to minimize the volumes of waste materials generated by their operations. The guidelines included recommendations for identifying, monitoring, and reporting discharges; performance expectations for specific discharges; requirements for greenhouse gas (GHG) and other air emissions; methods of characterizing and monitoring produced water, drilling muds, and desalination brine. Operational discharges associated with the installation and maintenance of subsea systems were also reviewed, and qualifications of analytical laboratories were presented. 24 refs., 2 appendices.

  2. Process evaluation for treatment of aluminium bearing declad waste

    International Nuclear Information System (INIS)

    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, 137Cs 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 137Cs and 90Sr removal by ion exchange, is used in this study

  3. Waste water treatment by flotation

    OpenAIRE

    Camelia Badulescu; Lorand Toth; Romulus Sarbu

    2005-01-01

    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, ...

  4. Hazard ranking systems for chemical wastes and chemical waste sites

    International Nuclear Information System (INIS)

    Hazardous materials and substances have always existed in the environment. Mankind has evolved to live with some degree of exposure to toxic materials. Until recently the risk has been from natural toxins or natural background radiation. While rapid technological advances over the past few decades have improved the lifestyle of our society, they have also dramatically increased the availability, volume and types of synthetic and natural hazardous materials. Many of their effects are as yet uncertain. Products and manufacturing by-products that no longer serve a useful purpose are deemed wastes. For some waste products land disposal will always be their ultimate fate. Hazardous substances are often included in the waste products. One needs to classify wastes by degree of hazard (risk). Risk (degree of probability of loss) is usually defined for risk assessment as probability of an occurrence times the consequences of the occurrence. Perhaps even more important than the definition of risk is the choice of a risk management strategy. The choice of strategy will be strongly influenced by the decision criteria used. Those decision criteria could be utility (the greatest happiness of the greatest number), rights or technology based or some combination of the three. It is necessary to make such choices about the definition of risks and criteria for management. It is clear that these are social (i.e., political) and value choices and science has little to say on this matter. This is another example of what Alvin Weinberg has named Transcience where the subject matter is scientific and technical but the choices are social, political and moral. This paper shall deal only with the scientific and technical aspects of the hazardous waste problem to create a hazardous substances classification system

  5. Experimental plant for the physical-chemical treatment of groundwater polluted by Municipal Solid Waste (MSW leachate, with ammonia recovery

    Directory of Open Access Journals (Sweden)

    Massimo Raboni

    2013-12-01

    Full Text Available The paper documents the results of the experimental treatment of groundwater (flow rate: 300 m3 h-1 polluted by the leachate of an old MSW landfill (7 million tonnes in northern Italy. The process consists of a coagulation-flocculation pre-treatment at pH > 11, and subsequent ammonia stripping, after heating the water to 35-38 °C by means of the biogas produced by the landfill. The stripped ammonia was recovered by absorption with sulfuric acid, producing a 30% solution of ammonium sulfate, which was reused as a base fertilizer. In addition, the paper reports important operational aspects related to the scaling of the stripping tower’s packing and its effect on pH and temperature profiles inside the towers caused by the closed loop, which recirculates the stripping air coming from the ammonia absorption towers with sulfuric acid. The average removal efficiency of ammonia reached 95.4% with an inlet mean concentration of 199.0 mg L-1.

  6. Treatment of textile wastes

    OpenAIRE

    Srebrenkoska, Vineta; Krsteva, Silvana; Golomeova, Saska

    2013-01-01

    The production of a textile requires several stages of mechanical processing such as spinning, weaving, knitting, and garment production, which seem to be insulated from the wet treatment processes like pretreatment, dyeing, printing, and finishing operations. Тhere is a strong interrelation between treatment processes in the dry state and consecutive wet treatments. Most of the processes and products have a negative impact on the environment. Laws and standards for environmental protection a...

  7. Waste Water Treatment Unit

    International Nuclear Information System (INIS)

    A wastewater treatment plant to treat both the sanitary and industrial effluent originated from process, utilities and off site units of the refinery is described. The purpose is to obtain at the end of the treatment plant, a water quality that is in compliance with contractual requirements and relevant environmental regulations. first treatment (pretreatment). Primary de-oiling, Equalization, Neutralization, Secondary de-oiling. Second treatment (Biological), The mechanism of BOD removal, Biological flocculation, Nutrient requirements, Nitrification, De-nitrification, Effect of temperature, Effect of ph, Toxicity

  8. The Use of Chemical Modification of Polymer Waste for Obtaining Polymer Flocculants

    Institute of Scientific and Technical Information of China (English)

    W.W.Sulkowski; K.Nowak; A.Sulkowska; A.Wolin; ska; S.Malanka; W.M.Baldur; D.Pentak

    2007-01-01

    1 Results Chemical modification of polymer plastic wastes to useful products can be one of the way of effective waste plastics management (chemical recycling). Chemical modification of polymers and polymer plastic wastes can yield products with suitable physical and chemical properties. In consequence they can be used as polyelectrolytes[1]. The variety of pollutants, universality of various water and sewage treatment technologies, introduction of new water quality improved technologies have caused a gr...

  9. Cyanide wastes treatment by bioremediation

    International Nuclear Information System (INIS)

    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)

  10. 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.

  11. Instructive of chemical residues waste administration

    International Nuclear Information System (INIS)

    An instructive is established for the waste management system of chemical residues generated at the Universidad de Costa Rica, ensuring the collection, separation, transportation, reuse, recycling and final disposal. The laboratory waste management system is conditioned to the volume and type of waste generated. The respective procedures are listed in data sheets according to the corresponding model: avoid, reduce, recycle, treat, delete. The materials are identified as: expired products, materials or damaged products, substances that have lost some of the required characteristics, waste from the regular activities of the lab, unused products that now no longer used because they are considered inadequate. The chemicals reagents or hazardous are transformed into small amounts of derivatives safe products, or less hazardous, to allow for removal or to pick up a spill of these without problem

  12. WASTE TREATMENT BUILDING SYSTEM DESCRIPTION DOCUMENT

    International Nuclear Information System (INIS)

    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

  13. 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

  14. Chemical decontamination method for radioactive metal waste

    International Nuclear Information System (INIS)

    When contaminants mainly composed of copper remained on the surface of stainless steel wastes sent from an electrolytic reduction as a first step are chemically decontaminated, metal wastes are discriminated to carbon steel wastes and stainless steel wastes. Then, the carbon steel wastes are applied only with the first step of immersing in a sulfuric acid solution, and stainless steel wastes are applied with a first step of immersing into a sulfuric acid solution for electrolytic reduction for a predetermined period of time and a second step of immersing into a liquid in which an oxidative metal salt is added to sulfuric acid. The decontamination liquid which is used for immersing the stainless steel wastes in the second step and the oxidation force of which is lowered is used as the sulfuric acid solution in the first step for the carbon steel wastes. In view of the above, the decontamination liquid of the second step can be utilized most effectively, enabling to greatly decrease the secondary wastes and to improve decontamination efficiency. (T.M.)

  15. Chemical compatibility of DWPF canistered waste forms

    International Nuclear Information System (INIS)

    The Waste Acceptance Preliminary Specifications (WAPS) require that the contents of the canistered waste form are compatible with one another and the stainless steel canister. The canistered waste form is a closed system comprised of a stainless steel vessel containing waste glass, air, and condensate. This system will experience a radiation field and an elevated temperature due to radionuclide decay. This report discusses possible chemical reactions, radiation interactions, and corrosive reactions within this system both under normal storage conditions and after exposure to temperatures up to the normal glass transition temperature, which for DWPF waste glass will be between 440 and 460 degrees C. Specific conclusions regarding reactions and corrosion are provided. This document is based on the assumption that the period of interim storage prior to packaging at the federal repository may be as long as 50 years

  16. Chemical studies on the synthesis and characterization of some ion- exchange materials and its use in the treatment of hazardous wastes

    International Nuclear Information System (INIS)

    Now inorganic ion exchange materials play an important role in analytical chemistry, based originally on their thermal and radiation resistance as well as their stability to chemical attack.Vanadate salts are one of the main categories of inorganic ion exchange materials widely used in separation and preconcentration of some toxic and hazardous elements from different waste media. Attempts in this study are focused on the preparation of two inorganic ion exchange materials ,Tin Vanadate (SnV) and Titanium Potassium Vanadate(TiKV) for treatment of hazardous waste.These material were characterized using X-ray spectra (XRD and XRF), IR, TGA-DTA and total elemental analysis studies. On the basis of distribution studies, the materials have been found that they are highly selective for Pb(II) and Cs(I)ions. Thermodynamic parameters (i.e. ΔG, ΔS and ΔH) have also been calculated for the adsorption of Pb2+, Cs+, Fe3+, Cd2+, Cu+2, Zn2+and Co2+ ions on Tin Vanadate (SnV) and Titanium Potassium Vanadate(TiKV) showing that the overall adsorption process is spontaneous and endothermic. The mechanism of diffusion of Fe3+, Co2+, Cu2+, Zn2+, Cd2+, Cs+and Pb2+ ions for Tin Vanadate (SnV) and Titanium Potassium Vanadate(TiKV) as cation exchangers were studied as a function of particle size, concentration of the exchanging ions, reaction temperatures and drying temperatures. The exchange rate was controlled by a particle diffusion mechanism as a limited batch technique and is confirmed from straight lines of B versus 1/r2 plots. The values of diffusion coefficients, activation energies and entropies of activation were calculated and their significance was discussed. The data obtained have been compared with that reported for other inorganic exchangers. Exchange isotherms for Cs+ ,Co2+and Cd2+ions were determined at 25, 45 and 65±1 degree C. These isotherms showed that Cs+ ,Co2+and Cd2+ are physically adsorbed. Finally, separations of the above mentioned cations on Tin Vanadate

  17. Plasma technology for waste treatment

    International Nuclear Information System (INIS)

    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

  18. Radiological, physical, and chemical characterization of transuranic wastes stored at the Idaho National Engineering Laboratory

    Energy Technology Data Exchange (ETDEWEB)

    Apel, M.L.; Becker, G.K.; Ragan, Z.K.; Frasure, J.; Raivo, B.D.; Gale, L.G.; Pace, D.P.

    1994-03-01

    This document provides radiological, physical and chemical characterization data for transuranic radioactive wastes and transuranic radioactive and hazardous (i.e., mixed) wastes stored at the Idaho National Engineering Laboratory and considered for treatment under the Private Sector Participation Initiative Program (PSPI). Waste characterization data are provided in the form of INEL Waste Profile Sheets. These documents provide, for each content code, information on waste identification, waste description, waste storage configuration, physical/chemical waste composition, radionuclide and associated alpha activity waste characterization data, and hazardous constituents present in the waste. Information is provided for 139 waste streams which represent an estimated total volume of 39,380{sup 3} corresponding to a total mass of approximately 19,000,000 kg. In addition, considerable information concerning alpha, beta, gamma, and neutron source term data specific to Rocky Flats Plant generated waste forms stored at the INEL are provided to assist in facility design specification.

  19. Radiological, physical, and chemical characterization of transuranic wastes stored at the Idaho National Engineering Laboratory

    International Nuclear Information System (INIS)

    This document provides radiological, physical and chemical characterization data for transuranic radioactive wastes and transuranic radioactive and hazardous (i.e., mixed) wastes stored at the Idaho National Engineering Laboratory and considered for treatment under the Private Sector Participation Initiative Program (PSPI). Waste characterization data are provided in the form of INEL Waste Profile Sheets. These documents provide, for each content code, information on waste identification, waste description, waste storage configuration, physical/chemical waste composition, radionuclide and associated alpha activity waste characterization data, and hazardous constituents present in the waste. Information is provided for 139 waste streams which represent an estimated total volume of 39,3803 corresponding to a total mass of approximately 19,000,000 kg. In addition, considerable information concerning alpha, beta, gamma, and neutron source term data specific to Rocky Flats Plant generated waste forms stored at the INEL are provided to assist in facility design specification

  20. Treatment of mixed waste coolant

    International Nuclear Information System (INIS)

    The primary processes used at Lawrence Livermore National Laboratory (LLNL) for treatment of radioactively contaminated machine coolants are industrial waste treatment and in situ carbon adsorption. These two processes simplify approaches to meeting the sanitary sewer discharge limits and subsequent Land Disposal Restriction criteria for hazardous and mixed wastes (40 CFR 268). Several relatively simple technologies are used in industrial water treatment. These technologies are considered Best Demonstrated Available Technologies, or BDAT, by the Environmental Protection Agency. The machine coolants are primarily aqueous and contain water soluble oil consisting of ethanol amine emulsifiers derived from fatty acids, both synthetic and natural. This emulsion carries away metal turnings from a part being machined on a lathe or other machining tool. When the coolant becomes spent, it contains chlorosolvents carried over from other cutting operations as well as a fair amount of tramp oil from machine bearings. This results in a multiphasic aqueous waste that requires treatment of metal and organic contaminants. During treatment, any dissolved metals are oxidized with hydrogen peroxide. Once oxidized, these metals are flocculated with ferric sulfate and precipitated with sodium hydroxide, and then the precipitate is filtered through diatomaceous earth. The emulsion is broken up by acidifying the coolant. Solvents and oils are adsorbed using powdered carbon. This carbon is easily separated from the remaining coolant by vacuum filtration

  1. Chemical Decontamination of Metallic Waste from Uranium Conversion Plant Dismantling

    International Nuclear Information System (INIS)

    Korea Atomic Energy Research Institute (KAERI) started a decommissioning program of the uranium conversion plant. Pre-work was carried as follows; installation of the access control facility, installation of a changing room and shower room, designation of an emergency exit way and indicating signs, installation of a radiation management facility, preparation of a storage area for tools and equipments, inspection and load test of crane, distribution and packaging of existing waste, and pre-decontamination of the equipment surface and the interior. First, decommissioning work was performed in kiln room, which will be used for temporary radioactive waste storage room. Kiln room housed hydro fluorination rotary kiln for production of uranium tetra-fluoride. The kiln is about 0.8 m in diameter and 5.5 m long. The total dismantled waste was 6,690 kg, 73 % of which was metallic waste and 27 % the others such as cable, asbestos, concrete, secondary waste, etc. And effluent treatment room and filtration room were dismantled for installation of decontamination equipment and lagoon sludge treatment equipment. There were tanks and square mixer in these rooms. The total dismantled waste was 17,250 kg, 67% of which was metallic waste and 33% the others. These dismantled metallic wastes consist of stainless and carbon steel. In this paper, the stainless steel plate and pipe were decontaminated by the chemical decontamination with ultrasonic

  2. Biological treatment of hazardous waste

    Energy Technology Data Exchange (ETDEWEB)

    Lewandowski, G.A.; Filippi, L.J. de [eds.

    1998-12-01

    This reference book is intended for individuals interested in or involved with the treatment of hazardous wastes using biological/biochemical processes. Composed of 13 chapters, it covers a wide variety of topics ranging from engineering design to hydrogeologic factors. The first four chapters are devoted to a description of several different types of bioreactors. Chapter 5 discusses the biofiltration of volatile organic compounds. Chapters 6 through 9 discuss specific biological, biochemical, physical, and engineering factors that affect bioremediation of hazardous wastes. Chapter 10 is a very good discussion of successful bioremediation of pentachlorophenol contamination under laboratory and field conditions, and excellent references are provided. The next chapter discusses the natural biodegradation of PCB-contaminated sediments in the Hudson River in New York state. Chapter 12 takes an excellent look at the bioremediation capability of anaerobic organisms. The final chapter discusses composting of hazardous waste.

  3. Radiobiological waste treatment-ashing treatment and immobilization with cement

    International Nuclear Information System (INIS)

    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 DH4A 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 DH4A 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, DH4A 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

  4. Evaluation of Secondary Streams in Mixed Waste Treatment

    International Nuclear Information System (INIS)

    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

  5. Technical area status report for chemical/physical treatment

    International Nuclear Information System (INIS)

    The Office of Environmental Restoration and Waste Management (EM) was established by the Department of Energy (DOE) to direct and coordinate waste management and site remediation programs and activities throughout the DOE Complex. The Mixed Waste Integrated Program (MWIP) was created by the DOE Office of Technology Development (OTD) to develop, deploy, and complete appropriate technologies for the treatment of an DOE low-level mixed waste (LLMW). The MWIP mission includes development of strategies related to enhanced waste form production, improvements to and testing of the EM-30 baseline flowsheet for mixed waste treatment, programmatic oversight for ongoing technical projects, and specific technical tasks related to the site specific Federal Facilities Compliance Agreement (FFCA). The MWIP has established five Technical Support Groups (TSGs) based on primary functional areas of the Mixed Waste Treatment Plant) identified by EM-30. These TSGs are: (1) Front-End Waste Handling, (2) Chemical/Physical Treatment, (3) Waste Destruction and Stabilization, (4) Second-stage Destruction and Offgas Treatment, and (5) Final Waste Forms. The focus of this document is the Chemical/Physical Treatment System (CPTS). The CPTS performs the required pretreatment and/or separations on the waste streams passing through the system for discharge to the environment or efficient downstream processing. Downstream processing can include all system components except Front-End Waste Handling. The primary separations to be considered by the CPTS are: (1) removal of suspended and dissolved solids from aqueous and liquid organic streams, (2) separation of water from organic liquids, (3) treatment of wet and dry solids, including separation into constituents as required, for subsequent thermal treatment and final form processing, (4) mercury removal and control, and (5) decontamination of equipment and waste classified as debris

  6. A Primer on Waste Water Treatment.

    Science.gov (United States)

    Department of the Interior, Washington, DC. Federal Water Pollution Control Administration.

    This information pamphlet is for teachers, students, or the general public concerned with the types of waste water treatment systems, the need for further treatment, and advanced methods of treating wastes. Present day pollution control methods utilizing primary and secondary waste treatment plants, lagoons, and septic tanks are described,…

  7. Physico-chemical wastewater treatment

    NARCIS (Netherlands)

    Mels, A.R.; Teerikangas, E.

    2002-01-01

    Wastewater reclamation strategies aimed at closing industrial water cycles and recovery of valuable components will in most cases require a combination of wastewater treatment unit operations. Biological unit operations are commonly applied as the core treatment. In addition, physico-chemical unit o

  8. Selection and Evaluation of Chemical Indicators for Waste Stream Identification

    Science.gov (United States)

    DeVita, W. M.; Hall, J.

    2015-12-01

    Human and animal wastes pose a threat to the quality of groundwater, surface water and drinking water. This is especially of concern for private and public water supplies in agricultural areas of Wisconsin where land spreading of livestock waste occurs on thin soils overlaying fractured bedrock. Current microbial source tracking (MST) methods for source identification requires the use of polymerase chain reaction (PCR) techniques. Due to cost, these tests are often not an option for homeowners, municipalities or state agencies with limited resources. The Water and Environmental Analysis Laboratory sought to develop chemical methods to provide lower cost processes to determine sources of fecal waste using fecal sterols, pharmaceuticals (human and veterinary) and human care/use products in ground and surface waters using solid phase extraction combined with triple quadrupole mass spectrometry. The two separate techniques allow for the detection of fecal sterol and other chemical markers in the sub part per billion-range. Fecal sterol ratios from published sources were used to evaluate drinking water samples and wastewater from onsite waste treatment systems and municipal wastewater treatment plants. Pharmaceuticals and personal care products indicative of human waste included: acetaminophen, caffeine, carbamazepine, cotinine, paraxanthine, sulfamethoxazole, and the artificial sweeteners; acesulfame, saccharin, and sucralose. The bovine antibiotic sulfamethazine was also targeted. Well water samples with suspected fecal contamination were analyzed for fecal sterols and PPCPs. Results were compared to traditional MST results from the Wisconsin State Laboratory of Hygiene. Chemical indicators were found in 6 of 11 drinking water samples, and 5 of 11 were in support of MST results. Lack of detection of chemical indicators in samples contaminated with fecal waste supports the need for confirmatory methods and advancement of chemical indicator detection technologies.

  9. Waste management and treatment or disguised disposal?

    International Nuclear Information System (INIS)

    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

  10. Chemical changes during vermicomposting of sago industry solid wastes.

    Science.gov (United States)

    Subramanian, Selvi; Sivarajan, M; Saravanapriya, S

    2010-07-15

    A laboratory study was undertaken to examine the temporal changes in physico-chemical properties during vermicomposting of sago industry waste. The sago industry waste was blended with cow dung, poultry manure at various proportions, kept for pre-treatment for 21 days and subsequently vermicomposted for a period of 45 days under shade. Earthworm species (Eisenia foetida) was introduced at the rate of 50 g/kg of waste. The substrate moisture content and temperature were monitored regularly. The vermicomposts were sampled at 0, 15, 30 and 45 days for the assessment of temporal changes in physico-chemical properties. The data revealed vermicomposting of sago wastes, cow dung and poultry manure mixed at equal proportion (1:1:1) produced a superior quality manure with desirable C:N ratio and higher nutritional status than composting. E. foetida is an earthworm suitable for composting organic wastes such as poultry manure with extreme pH and high temperature and sago waste with high organic carbon in a shorter period of time. This study suggests that the sago industry solid waste could be effectively converted into highly valuable manure that can be exploited to promote crop production. PMID:20359816

  11. Introducing Water-Treatment Subjects into Chemical Engineering Education.

    Science.gov (United States)

    Caceres, L.; And Others

    1992-01-01

    Proposes that inclusion of waste water treatment subjects within the chemical engineering curriculum can provide students with direct access to environmental issues from both a biotechnological and an ethical perspective. The descriptive details of water recycling at a copper plant and waste water stabilization ponds exemplify this approach from…

  12. Chemical treatment of liquors

    International Nuclear Information System (INIS)

    A liquor, which may contain heavy metal species, e.g. U or Pu, is passed along a pipeline provided with a cascade of fluidic mixing devices for adding a reagent or reagents. Pipeline sections are disposed downstream of mixing devices dimensioned so that the liquor and reagent(s) are afforded a residence time for reaction as they flow through it. The mixed liquor/reagent(s) are then fed into a settling vessel from which part of the contents is fed to a centrifugal separator to effect liquid/solid separation. A proportion of the solid separated is recycled back to the cascaded mixing pipeline to provide nuclei to enhance precipitation and/or increase concentration of a constituent, such as a floc-forming agent, used in the treatment of the liquor. (author)

  13. Microbiological treatment of radioactive wastes

    International Nuclear Information System (INIS)

    The ability of microorganisms which are ubiquitous throughout nature to bring about information of organic and inorganic compounds in radioactive wastes has been recognized. Unlike organic contaminants, metals cannot be destroyed, but must be either removed or converted to a stable form. Radionuclides and toxic metals in wastes may be present initially in soluble form or, after disposal may be converted to a soluble form by chemical or microbiological processes. The key microbiological reactions include (i) oxidation/reduction; (ii) change in pH and Eh which affects the valence state and solubility of the metal; (iii) production of sequestering agents; and (iv) bioaccumulation. All of these processes can mobilize or stabilize metals in the environment

  14. Mixed waste chemical compatibility with packaging components

    International Nuclear Information System (INIS)

    In this paper, a chemical compatibility testing program for packaging of mixed wastes at will be described. We will discuss the choice of four y-radiation doses, four time durations, four temperatures and four waste solutions to simulate the hazardous waste components of mixed wastes for testing materials compatibility of polymers. The selected simulant wastes are (1) an aqueous alkaline mixture of sodium nitrate and sodium nitrite; (2) a chlorinated hydrocarbon mixture; (3) a simulant liquid scintillation fluid; and (4) a mixture of ketones. A selection of 10 polymers with anticipated high resistance to one or more of these types of environments are proposed for testing as potential liner or seal materials. These polymers are butadiene acrylonitrile copolymer, cross-linked polyethylene, epichlorhyarin, ethylene-propylene rubber, fluorocarbon, glass-filled tetrafluoroethylene, high-density poly-ethylene, isobutylene-isoprene copolymer, polypropylene, and styrene-butadiene rubber. We will describe the elements of the testing plan along with a metric for establishing time resistance of the packaging materials to radiation and chemicals

  15. Chemical decontamination method for radioactive metal waste

    International Nuclear Information System (INIS)

    The present invention provides a chemical decontamination method for radioactive metal wastes, which are generated from radioactive material handling facilities and the surfaces of which are contaminated by radioactive materials. That is, it has a feature of applying acid dissolution simultaneously with mechanical grinding. The radioactive metal wastes are contained in a vessel such as a barrel together with abrasives in a sulfuric acid solution and rotated at several tens rotation per minute. By such procedures for the radioactive metal wastes, (1) cruds and passive membranes are mechanically removed, (2) exposed mother metal materials are uniformly brought into contact with sulfuric acid and further (3) the mother metal materials dissolve the cruds and the passive membranes also chemically by a reducing dissolution (so-called local cell effect). According to the method of the present invention, stainless steel metal wastes having cruds and passive membranes can rapidly and efficiently be decontaminated to a radiation level equal with that of ordinary wastes. (I.S.)

  16. USDOE activities in low-level radioactive waste treatment

    International Nuclear Information System (INIS)

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

  17. Donnan dialysis for the treatment of aqueous wastes

    International Nuclear Information System (INIS)

    Commercially available ion exchange membranes with high selectivity and chemical stability make attractive the use of Donnan dialysis as a separation process for the treatment of industrial liquid aqueous wastes. The concentration of metal ions in solution, by using a chemical gradient across a selective cationic membrane, can be the basis for new hybrid processes in which well-known chemical treatments and membrane separation are coupled. Donnan dialysis separations of two ions of different charge Sr(II) and Cr(III), by means of perfluorinated Nafion membranes in tubular form, are discussed by taking into account different hydrodynamic and chemical conditions in the feed and strip solutions. Results are compared with other hybrid processes for the treatment of low activity nuclear wastes (Sr-90) and conventional wastes (chromate and Cr(III)). (author)

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

    International Nuclear Information System (INIS)

    tank farms. In either case, testing is needed to evaluate if this stream is compatible with the evaporator and the other wastes in the tank farm. It should be noted that prior experience in evaporation of another melter off-gas stream, the Recycle Stream at the SRS Defense Waste Processing Facility, unexpectedly caused deleterious impacts on evaporator scaling and formation of aluminosilicate solids before controls were implemented. The compatibility of this stream with other wastes and components in the tank farms has not been fully investigated, whether it is sent for storage in AW-102 in preparation for evaporation in 242-A evaporator, or if it is pre-concentrated in an auxiliary evaporator. This stream is expected to be unusual because it will be very high in corrosive species that are volatile in the melter (chloride, fluoride, sulfur), will have high ammonia, and will contain carryover particulates of glass-former chemicals. These species have potential to cause corrosion, precipitation, flammable gases, and scale in the tank farm system. Testing is needed to demonstrate acceptable conditions and limits for these compounds in wastes sent to the tank farms. Alternate disposition of this LAW Recycle stream could beneficially impact WTP, and may also remove a sizeable fraction of the 99Tc from the source term at the IDF. The alternative radionuclide removal process envisioned for this stream parallels the Actinide Removal Process that has been successfully used at SRS for several years. In that process, Monosodium Titanate (MST) is added to the tank waste to adsorb 90Sr and actinides, and then the MST and radionuclides are removed by filtration. The process proposed for investigation for the Hanford WTP LAW Recycle stream would similarly add MST to remove 90Sr and actinides, along with other absorbents or precipitating agents for the remaining radionuclides. These include inorganic reducing agents for Tc, and zeolites for 137Cs. After treatment, disposition of the

  19. Treatment technology for organic radioactive waste

    Energy Technology Data Exchange (ETDEWEB)

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

    1999-12-01

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

  20. Electrochemical treatment of liquid wastes

    Energy Technology Data Exchange (ETDEWEB)

    Hobbs, D.

    1996-10-01

    Electrochemical treatment processes are being evaluated and developed for the destruction of organic compounds and nitrates/nitrites and the removal of other hazardous species from liquid wastes stored throughout the DOE complex. This activity consists of five major tasks: (1) evaluation of different electrochemical reactors for the destruction and removal of hazardous waste components, (2) development and validation of engineering process models, (3) radioactive laboratory-scale tests, (4) demonstration of the technology in an engineering-scale size reactor, and (5) analysis and evaluation of testing data. The development program team is comprised of individuals from federal, academic, and private industry. Work is being carried out in DOE, academic, and private industrial laboratories.

  1. Thermal waste treatment; Thermische Abfallbehandlung

    Energy Technology Data Exchange (ETDEWEB)

    Faulstich, M.; Urban, A.I.; Bilitewski, B. [eds.

    1998-09-01

    One effect of the enactment of the new Law on Recycling and Waste Management, in conjunction with the lowering of emission limit values, has been to bring thermal water treatment more and more into the focus of the discussion on optimal water utilisation. The present volume discusses the consequences of changing waste arisings and composition for various process combinations. [Deutsch] Durch das Inkrafttreten des neuen Kreislaufwirtschafts- und Abfallgesetzes und strengeren Emissionsgrenzwerten rueckt immer mehr die thermische Abfallbehandlung in den Vordergrund der Diskussionen um die optimale Abfallverwertung. Die Folgen der sich veraendernden Abfallmengen und -zusammensetzungen im Hinblick auf Anlagenauslastung, Feuerungstechnik, Rueckstaende und Kosten werden eroertert. Es werden verschiedene Verfahrenskombinationen vorgestellt und diskutiert. Verschiedene Moeglichkeiten der Klaerschlammbehandlung und der Einsatz der Reststoffe Asche und Schlacke in der Bauindustrie werden behandelt. (ABI)

  2. Electrochemical treatment of liquid wastes

    International Nuclear Information System (INIS)

    Electrochemical treatment processes are being evaluated and developed for the destruction of organic compounds and nitrates/nitrites and the removal of other hazardous species from liquid wastes stored throughout the DOE complex. This activity consists of five major tasks: (1) evaluation of different electrochemical reactors for the destruction and removal of hazardous waste components, (2) development and validation of engineering process models, (3) radioactive laboratory-scale tests, (4) demonstration of the technology in an engineering-scale size reactor, and (5) analysis and evaluation of testing data. The development program team is comprised of individuals from federal, academic, and private industry. Work is being carried out in DOE, academic, and private industrial laboratories

  3. Co-treatment of fruit and vegetable waste in sludge digesters: Chemical and spectroscopic investigation by fluorescence and Fourier transform infrared spectroscopy.

    Science.gov (United States)

    Provenzano, Maria Rosaria; Cavallo, Ornella; Malerba, Anna Daniela; Di Maria, Francesco; Cucina, Mirko; Massaccesi, Luisa; Gigliotti, Giovanni

    2016-04-01

    In a previous work co-digestion of food waste and sewage sludge was performed in a pilot apparatus reproducing operating conditions of an existing full scale digester and processing waste mixed sludge (WMS) and fruit and vegetable waste (FVW) at different organic loading rates. An analysis of the relationship among bio-methane generation, process stability and digestate phytotoxicity was conducted. In this paper we considered humification parameters and spectroscopic analysis. Humification parameters indicated a higher not humified fraction (NH) and a lower degree of humification (DH) of FVW with respect to WMS (NH=19.22 and 5.10%; DH=36.65 and 61.94% for FVW and WMS, respectively) associated with their different chemical compositions and with the stabilization process previously undergone by sludge. FVW additions seemed to be favourable from an agronomical point of view since a lower percentage of organic carbon was lost. Fourier transform infrared spectra suggested consumption of aliphatics associated with rising in bio-methane generation followed by accumulation of aliphatics and carboxylic acids when the biogas production dropped. The trend of peaks ratios can be used as an indicator of the process efficiency. Fluorescence intensity of peak B associated with tryptophan-like substances and peak D associated with humic-like substances observed on tridimensional Excitation Emission Matrix maps increased up to sample corresponding to the highest rate of biogas production. Overall spectroscopic results provided evidence of different chemical pathways of anaerobic digestion associated with increasing amount of FVW which led to different levels of biogas production. PMID:26946935

  4. Final Hazard Categorization for the Remediation of the 116-C-3 Chemical Waste Tanks

    Energy Technology Data Exchange (ETDEWEB)

    T. M. Blakley; W. D. Schofield

    2007-09-10

    This final hazard categorization (FHC) document examines the hazards, identifies appropriate controls to manage the hazards, and documents the commitments for the 116-C-3 Chemical Waste Tanks Remediation Project. The remediation activities analyzed in this FHC are based on recommended treatment and disposal alternatives described in the Engineering Evaluation for the Remediation to the 116-C-3 Chemical Waste Tanks (BHI 2005e).

  5. Treatment of chemical waste piassava for application in polymeric composites; Tratamento quimico do residuo de piacava para aplicacao em compositos polimericos

    Energy Technology Data Exchange (ETDEWEB)

    Miranda, C.S.; Fiuza, R.P.; Guimaraes, D.H.; Carvalho, G.G.P.; Carvalho, R.F.; Jose, N.M., E-mail: cleidienesm@gmail.co [Universidade Federal da Bahia (GECIM/UFBA), Salvador, BA (Brazil). Inst. de Quimica. Grupo de Energia e Ciencias dos Materiais

    2010-07-01

    Piassava fibers were investigated with the aim of adding new business value. The surface of the fibers were treated with NaOH and H{sub 2}SO{sub 4} for 1 h at room temperature. The samples were characterized by FTIR, TGA, DSC, chemical composition, XRD, SEM and tensile tests. The micrographs of the fibers showed that treatment with NaOH cleaned the fiber surface of a large amount of impurities and cause fibrillation. Chemical analysis, using the Van Soest method, showed that the palm fiber is a fiber rich in lignin, as evidenced by their brown color and with alkali treatment there was partial removal of hemicellulose and lignin, increasing the crystallinity index of the fiber, observed by XRD. The acid treatment caused no significant changes in the properties of the fiber. Therefore, the mercerisation was efficient in the fiber of palm fiber, improving their properties, enabling thus their use as reinforcement in polymer composites. (author)

  6. Development and demonstration of treatment technologies for the processing of US Department of Energy Mixed Waste

    International Nuclear Information System (INIS)

    Mixed waste is defined as ''waste contaminated with chemically hazardous and radioactive species.'' The Mixed Waste Integrated Program (MWIP) was established in response to the need for a unified, DOE complexwide solution to issues of mixed waste treatment that meets regulatory requirements. MWIP is developing treatment technologies that reduce risk, minimize life-cycle cost, and improve process performance as compared to existing technologies. Treatment for waste streams for which no current technology exists, and suitable waste forms for disposal, will be provided to improve operations of the DOE Office of Waste Management. MWIP is composed of six technical areas within a mixed-waste treatment system: (1) systems analysis, (2) materials handling, (3) chemical/physical separation, (4) waste destruction and stabilization, (5) off-gas treatment, and (6) final waste form stabilization. The status of the technical initiatives and the current research, development, and demonstration in each of these areas are described in this paper

  7. Current chemical recycling options for polyurethane waste

    Czech Academy of Sciences Publication Activity Database

    Beneš, Hynek; Kruliš, Zdeněk; Prokop, Jiří; Holler, Petr; Látalová, Petra

    Praha : Ústav makromolekulární chemie AV ČR, 2010. ML_3. ISBN 978-80-85009-62-0. [Workshop "Career in Polymers" /2./. 23.07.2010-24.07.2010, Praha] R&D Projects: GA MPO 2A-2TP1/135 Institutional research plan: CEZ:AV0Z40500505 Keywords : chemical recycling options * polyurethane waste * recycling Subject RIV: CD - Macromolecular Chemistry

  8. Technologies 1995: environment and wastes treatment

    International Nuclear Information System (INIS)

    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.)

  9. Development of salt waste treatment technology

    International Nuclear Information System (INIS)

    To develop a proper waste conditioning technology for salt wastes, alpha- contaminated organic wastes, and long-lived fission products, which are presumed to generate from the pyrochemical dry processing of spent fuel, researches on LiCl salt waste treatment (including salt fixation, ion exchange of radionuclides and salt pre-treatment technique), molten salt oxidation of organic alpha wastes and recovery of radioiodine have been performed. In a research on the waste LiCl salt treatment, the characterization on a salt-loaded zeolite sample, prepared by an immobilization of the molten LiCl salt waste with zeolite A, suggested that an optimum mixing ratio, r (=LiCl/zeolite) was 1.0. Pre-treatment of salt waste was performed via gelation reaction with additives of phosphate and sodium silicate. Characteristics of the gel product after drying and thermal treatment were tested and evaluated to establish the proper reaction conditions on the conversion of salt waste into durable waste forms. Molten salt oxidation (MSO) is selected as the most promising technology for the treatment of alpha-contaminated waste, and its lab-scale test and theoretical model study revealed its good effectiveness in the treatment of the problematic waste, such as halogenated organics including toxic and radioactive metals. The optimal conditions to effectively recover iodine from silver ion- exchanged adsorbent(AgX) was established and confirmed through experiment using radioiodine tracer. Fundamental data for conversion the recovered iodine to target material powder of NaI were obtained

  10. Hanford Tank Waste - Near Source Treatment of Low Activity Waste

    International Nuclear Information System (INIS)

    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

  11. Options for the treatment and solidification of organic radioactive wastes

    International Nuclear Information System (INIS)

    The nuclear fuel cycle generates a variety of low and intermediate level solid and liquid organic radioactive wastes. Suitable management includes interim storage, treatment and immobilization prior to disposal of the conditioned waste. This report deals with the treatment and conditioning of organic radioactive wastes for storage and disposal. The wastes considered in the report arise from nuclear fuel cycle operations, including fuel fabrication, reactor operation, fuel reprocessing, decontamination operations, and from fuel cycle research and development. Liquid organic wastes typically include lubricating and hydraulic fluids from reactor operation, solvents and diluents from fuel reprocessing, scintillation fluids from analytical laboratories, dry cleaning solvents and miscellaneous organic solvents from decontamination and decommissioning activities. Solid wastes consist of cellulosic materials, such as paper, rags and wood, and a variety of plastic and rubber items, such as polyvinyl chloride (PVC), polyethylene (PE), neoprene and natural rubber. These arise from reactor operation and maintenance and from glove box use in fuel fabrication and reprocessing. Most organic wastes contain only low levels of β/γ-activity and are substantially α-free. A lesser, but not inconsiderable, volume of organic waste is contaminated to higher levels with α-emitting transuranic (TRU) elements. Options for the treatment of organic wastes are influenced principally by the physical and chemical composition of each waste stream, whereas they may all be treated under similar conditions of radiological protection due to the absence of levels of β/γ-activity which would require shielding. Various options for conditioning the waste will depend on whether the waste is destined for storage or disposal; on the nuclide type and content; and on the activity levels in the immobilized waste, since these factors influence the type of repository to which the waste may be disposed. The

  12. DOE mixed waste treatment capacity analysis

    International Nuclear Information System (INIS)

    This initial DOE-wide analysis compares the reported national capacity for treatment of mixed wastes with the calculated need for treatment capacity based on both a full treatment of mixed low-level and transuranic wastes to the Land Disposal Restrictions and on treatment of transuranic wastes to the WIPP waste acceptance criteria. The status of treatment capacity is reported based on a fifty-element matrix of radiation-handling requirements and functional treatment technology categories. The report defines the classifications for the assessment, describes the models used for the calculations, provides results from the analysis, and includes appendices of the waste treatment facilities data and the waste stream data used in the analysis

  13. DOE mixed waste treatment capacity analysis

    Energy Technology Data Exchange (ETDEWEB)

    Ross, W.A.; Wehrman, R.R.; Young, J.R.; Shaver, S.R.

    1994-06-01

    This initial DOE-wide analysis compares the reported national capacity for treatment of mixed wastes with the calculated need for treatment capacity based on both a full treatment of mixed low-level and transuranic wastes to the Land Disposal Restrictions and on treatment of transuranic wastes to the WIPP waste acceptance criteria. The status of treatment capacity is reported based on a fifty-element matrix of radiation-handling requirements and functional treatment technology categories. The report defines the classifications for the assessment, describes the models used for the calculations, provides results from the analysis, and includes appendices of the waste treatment facilities data and the waste stream data used in the analysis.

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

    International Nuclear Information System (INIS)

    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

  15. Mixed waste treatment model: Basis and analysis

    International Nuclear Information System (INIS)

    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

  16. Nuclear waste treatment using Iranian natural zeolites

    International Nuclear Information System (INIS)

    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. 137Cs and 90Sr) is very important in using them

  17. TOPICAL REVIEW: Thermal plasma waste treatment

    Science.gov (United States)

    Heberlein, Joachim; Murphy, Anthony B.

    2008-03-01

    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.

  18. Final treatment of liquid radioactive wastes

    International Nuclear Information System (INIS)

    Final treatment of liquid radioactive wastes which are produced by 1st and 2nd 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

  19. Waste Water Management and Infectious Disease. Part II: Impact of Waste Water Treatment

    Science.gov (United States)

    Cooper, Robert C.

    1975-01-01

    The ability of various treatment processes, such as oxidation ponds, chemical coagulation and filtration, and the soil mantle, to remove the agents of infectious disease found in waste water is discussed. The literature concerning the efficiency of removal of these organisms by various treatment processes is reviewed. (BT)

  20. Development of treatment technologies of the processing of U.S. Department of Energy mixed waste

    International Nuclear Information System (INIS)

    Waste contaminated with chemically hazardous and radioactive species is defined as mixed waste. Significant technology development has been conducted for separate treatment of hazardous and radioactive waste, but technology development addressing mixed-waste treatment has been limited. In response to the need for a comprehensive and consistent approach to mixed-waste technology development, the Office of Technology Development of the US Department of Energy (DOE) has established the Mixed Waste Integrated Program. The program is identifying and evaluating treatment technologies to treat present and estimated future mixed wastes at DOE sites. The status of the technical initiatives in chemical/physical treatment, waste destruction/stabilization technology, off-gas treatment, and final waste form production/assessment is described in this paper

  1. In-Situ Chemical Precipitation of Radioactive Liquid Waste - 12492

    International Nuclear Information System (INIS)

    This paper presented in-situ chemical precipitation for radioactive liquid waste by using chemical agents. Results are reported on large-scale implementation on the removal of 137Cs, 134Cs and 60Co from liquid radioactive waste generating from Nuclear Research and Training Centre. Total amount of liquid radioactive waste was 35 m3 and main radionuclides were Cs-137, Cs- 134 and Co-60. Initial radioactivity concentration of the liquid waste was 2264, 17 and 9 Bq/liter for Cs-137, Cs-134 and Co-60 respectively. Potassium ferro cyanide was selected as chemical agent at high pH levels 8-10 according to laboratory tests. After the process, radioactive sludge precipitated at the bottom of the tank and decontaminated clean liquid was evaluated depending on discharge limits. By this precipitation method decontamination factors were determined as 60, 9 and 17 for Cs-137, Cs-134 and Co-60 respectively. At the bottom of the tank radioactive sludge amount was 0.98 m3. It was transferred by sludge pumps to cementation unit for solidification. By in situ chemical processing 97% of volume reduction was achieved. Using the optimal concentration of 0.75 M potassium ferro cyanide about 98% of the 137Cs can be removed at pH 8. The Potassium ferro cyanide precipitation method could be used successfully in large scale applications with nickel and ferrum agents for removal of Cs-137, Cs-134 and Co- 60. Although DF values of laboratory test were much higher than in-situ implementation, liquid radioactive waste was decontaminated successfully by using potassium ferro cyanide. Majority of liquid waste were discharged as clean liquid. %97.2 volumetric amount of liquid waste was cleaned and discharged at the original site. Reduced amount of sludge transportation in drums is more economical and safer method than liquid transportation. Although DF values could be different for each of applications related to main specifications of original liquid waste, this study shows that in-situ treatment

  2. Treatment of radioactive mixed wastes in commercial low-level wastes

    International Nuclear Information System (INIS)

    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

  3. Radioactive lightning rods waste treatment

    International Nuclear Information System (INIS)

    Full text: In this paper, we present alternative processes that could be adopted for the management of radioactive waste that arises from the replacement of lightning rods with attached Americium-241 sources. Lightning protectors, with Americium-241 sources attached to the air terminals, were manufactured in Brazil until 1989, when the regulatory authority overthrew the license for fabrication, commerce, and installation of radioactive lightning rods. It is estimated that, during the license period, about 75,000 such devices were set up in public, commercial and industrial buildings, including houses and schools. However, the policy of CNEN in regard to the replacement of the installed radioactive rods, has been to leave the decision to municipal governments under local building regulations, requiring only that the replaced rods be sent immediately to one of its research institutes to be treated as radioactive waste. As a consequence, the program of replacement proceeds in a low pace and until now only about twenty thousand rods have reached the waste treatment facilities The process of management that was adopted is based primarily on the assumption that the Am-241 sources will be disposed of as radioactive sealed sources, probably in a deep borehole repository. The process can be described broadly by the following steps: a) Receive and put the lightning rods in initial storage; b) Disassemble the rods and pull out the sources; c) Decontaminate and release the metal parts to metal recycling; d) Store the sources in intermediate storage; e) Package the sources in final disposal packages; and f) Send the sources for final disposal. Up to now, the disassembled devices gave rise to about 90,000 sources which are kept in storage while the design of the final disposal package is in progress. (author)

  4. The Management of Chemical Waste in a University Setting.

    Science.gov (United States)

    Coons, David Michael

    This thesis describes a study of the management of chemical waste at the State University of New York at Binghamton. The study revealed that the majority of chemical waste at the university is in the form of hazardous waste. It was hypothesized that the volume, related costs, and potential long-term liability associated with the disposal of…

  5. Organic waste treatment with organically modified clays

    International Nuclear Information System (INIS)

    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

  6. 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

  7. Estimation of Chemical Oxygen Demand in WasteWater using UV-VIS Spectroscopy

    OpenAIRE

    Alam, Tasnim

    2015-01-01

    The aim of this research is to build a portable system to perform real-time analysis ofwaste water samples. Thus, that can significantly improve existing waste water treatmenttechnology. In waste water treatment plant, an important parameter, chemical oxygen demandis needed to be measured. The amount of chemical oxygen demand determinesthe degree of water pollution by organic material. The conventional method for measuringchemical oxygen demand requires sample preparation and pre-treatment us...

  8. 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.

  9. Treatment of low- and intermediate-level liquid radioactive wastes

    International Nuclear Information System (INIS)

    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

  10. Innovative technologies for the treatment of hazardous and mixed wastes

    International Nuclear Information System (INIS)

    The treatment, storage, and disposal of hazardous and mixed wastes incur significant costs for Department of Energy (DOE) installations. These wastes must be managed under strict environmental controls and regulations to prevent the possibility of migration of hazardous materials to the biosphere. Through the Hazardous Waste Remedial Actions Program, the DOE is seeking to develop innovative ways of improving current treatment technologies to eliminate the hazardous components of wastes, reduce waste management costs, and minimize the volume requiring disposal as hazardous or mixed waste. Sponsored projects progress from research and development to field demonstration. Among the innovative technologies under development are supercritical water oxidation of hazardous chemicals, microwave-assisted destruction of chlorinated hydrocarbons, paramagnetic separation of metals from waste, detoxification and reclamation of waste acid, nitrate destruction through calcination, treatment/disposal of reactive metals, and methodologies for encapsulation. Technologies at a demonstration phase include detoxification of mixed waste sludge, microbial degradation of polychlorinated biphenyls in soil, and the remediation process for a hydrocarbon spill. 14 refs

  11. Solid and liquid radioactive waste treatment

    International Nuclear Information System (INIS)

    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)

  12. Novel integrated mechanical biological chemical treatment (MBCT) systems for the production of levulinic acid from fraction of municipal solid waste: A comprehensive techno-economic analysis.

    Science.gov (United States)

    Sadhukhan, Jhuma; Ng, Kok Siew; Martinez-Hernandez, Elias

    2016-09-01

    This paper, for the first time, reports integrated conceptual MBCT/biorefinery systems for unlocking the value of organics in municipal solid waste (MSW) through the production of levulinic acid (LA by 5wt%) that increases the economic margin by 110-150%. After mechanical separation recovering recyclables, metals (iron, aluminium, copper) and refuse derived fuel (RDF), lignocelluloses from remaining MSW are extracted by supercritical-water for chemical valorisation, comprising hydrolysis in 2wt% dilute H2SO4 catalyst producing LA, furfural, formic acid (FA), via C5/C6 sugar extraction, in plug flow (210-230°C, 25bar, 12s) and continuous stirred tank (195-215°C, 14bar, 20min) reactors; char separation and LA extraction/purification by methyl isobutyl ketone solvent; acid/solvent and by-product recovery. The by-product and pulping effluents are anaerobically digested into biogas and fertiliser. Produced biogas (6.4MWh/t), RDF (5.4MWh/t), char (4.5MWh/t) are combusted, heat recovered into steam generation in boiler (efficiency: 80%); on-site heat/steam demand is met; balance of steam is expanded into electricity in steam turbines (efficiency: 35%). PMID:27085988

  13. Treatment and conditioning of historical radioactive waste

    International Nuclear Information System (INIS)

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

  14. Grout treatment facility dangerous waste permit application

    International Nuclear Information System (INIS)

    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

  15. Treatment of radioactive wastes by incineration

    International Nuclear Information System (INIS)

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

  16. Recent approach in treatment of liquid radioactive waste: membrane methods

    International Nuclear Information System (INIS)

    Full text: The fuel cycle produces different types of radioactive waste. Radioactive waste is also generated during production and application of radioisotopes, as well as during processing of raw materials containing naturally occurring radioactive isotopes. All those wastes have to be treated and conditioned before safe storage or disposal to protect the human health and natural environment. The management of radioactive waste has to be reached with reasonable cost by implementing appropriate technologies. The processing requirements depend on the level of radioactivity and chemical and physical properties of the waste streams. Various methods are used to treat aqueous radioactive wastes, including evaporation, chemical precipitation and ion exchange, as well as less developed solvent extraction, biotechnological processes and membrane methods. Although membrane processes are still considered as novel technologies in the field of radioactive waste treatment, many applications in nuclear centres and laboratories around the world are reported. At the Department of Nuclear Methods of Process Engineering, Institute of Nuclear Chemistry and Technology, for many years membrane techniques are studied and considered as a possible application in radioactive wastes processing field. After some years of research reverse osmosis was applied at Institute of Atomic Energy (Department of Radioactive Waste Treatment) processing the radioactive wastes from all of Poland. The 3-stage RO plant supplements the existing waste processing system based on evaporator giving the possibility of initial concentration of liquid waste or final polishing of the condensate after evaporation. Intensive studies on ultrafiltration (UF) enhanced by sorption on different sorbents or complexation with chelating polymers are carried on. The ceramic membranes made from alumina, titania and zirconia are used in experiments. Such membranes show high chemical, temperature and radiation resistance. They

  17. Municipal waste - management and treatment

    International Nuclear Information System (INIS)

    Though per capita waste generation in Nepalese urban cities is not so high, the lack of proper waste management is considered one of the severe problems to be faced by urban people in future. With rapid urbanization, life style of people is changing their habits and consuming more materials and producing a large volume of waste in urban areas in Nepal. The nature and amount of waste generated in municipality is dependent of demography and geography. But most common aspect of municipal waste in Nepal is more than 60% of the waste biodegradable. Whatever the nature and amount of waste generated, the most common practice of managing municipal waste is to dispose in the riverside nearby or dumped elsewhere. The involvement of private sector in waste management is a new concept adopted by many municipalities in Nepal. One of the most progress approaches, 4R (reduces, reuse, recycle and refuse) principle is being practiced. The need of awareness progressive like segregation of wastes at collection point also being practiced in Nepal. Finally, Proper formulation of program and legislation and its application is one of the major challenges for local authorities in Nepal. (author)

  18. Chemical health risk assessment for hazardous and mixed waste management units at Lawrence Livermore National Laboratory

    International Nuclear Information System (INIS)

    The waste characterization for each treatment unit or process is based on treatment records from LLNL's computerized Hazardous Waste Management Inventory System (HWMIS). In 1990, these data were compiled into a single database comprising both hazardous waste and mixed waste data. Even though these data originate from the same source used in the previous HRA, the database was modified to set quantities and concentrations to a consistent set of units. This allowed an analysis of waste types by Hazardous Waste Management unit that was more accurate and did not rely upon many of the conservative assumptions used in the Phase II HRA waste characterization. Finally, the current waste characterizations are considered more representative of potential long-term wastes because they were developed by combining all wastes that could be treated in each unit, as opposed to the wastes treated only during 1988 to 1989. This final step more appropriately accounts for the variability in waste types likely to be seen by the Hazardous Waste Management Division. The quantities of each waste listed in the characterization tables represent the sum of all chemical quantities belonging to hazardous and mixed waste types potentially handled by each area

  19. Prospects of effective microorganisms technology in wastes treatment in Egypt.

    Science.gov (United States)

    Shalaby, Emad A

    2011-06-01

    Sludge dewatering and treatment may cost as much as the wastewater treatment. Usually large proportion of the pollutants in wastewater is organic. They are attacked by saprophytic microorganisms, i.e. organisms that feed upon dead organic matter. Activity of organisms causes decomposition of organic matter and destroys them, where the bacteria convert the organic matter or other constituents in the wastewater to new cells, water, gases and other products. Demolition activities, including renovation/remodeling works and complete or selective removal/demolishing of existing structures either by man-made processes or by natural disasters, create an extensive amount of wastes. These demolition wastes are characterized as heterogeneous mixtures of building materials that are usually contaminated with chemicals and dirt. In developing countries, it is estimated that demolition wastes comprise 20% to 30% of the total annual solid wastes. In Egypt, the daily quantity of construction and demolition (C&D) waste has been estimated as 10 000 tones. That is equivalent to one third of the total daily municipal solid wastes generated per day in Egypt. The zabbaliin have since expanded their activities and now take the waste they collect back to their garbage villages where it is sorted into recyclable components: paper, plastics, rags, glass, metal and food. The food waste is fed to pigs and the other items are sold to recycling centers. This paper summarizes the wastewater and solid wastes management in Egypt now and future. PMID:23569767

  20. Prospects of effective microorganisms technology in wastes treatment in Egypt

    Institute of Scientific and Technical Information of China (English)

    Emad A Shalaby

    2011-01-01

    Sludge dewatering and treatment may cost as much as the wastewater treatment. Usually large proportion of the pollutants in wastewater is organic. They are attacked by saprophytic microorganisms, i.e. organisms that feed upon dead organic matter. Activity of organisms causes decomposition of organic matter and destroys them, where the bacteria convert the organic matter or other constituents in the wastewater to new cells, water, gases and other products. Demolition activities, including renovation/remodeling works and complete or selective removal/demolishing of existing structures either by man-made processes or by natural disasters, create an extensive amount of wastes. These demolition wastes are characterized as heterogeneous mixtures of building materials that are usually contaminated with chemicals and dirt. In developing countries, it is estimated that demolition wastes comprise 20% to 30% of the total annual solid wastes. In Egypt, the daily quantity of construction and demolition (C&D) waste has been estimated as 10 000 tones. That is equivalent to one third of the total daily municipal solid wastes generated per day in Egypt. The zabbaliin have since expanded their activities and now take the waste they collect back to their garbage villages where it is sorted into recyclable components: paper, plastics, rags, glass, metal and food. The food waste is fed to pigs and the other items are sold to recycling centers. This paper summarizes the wastewater and solid wastes management in Egypt now and future.

  1. Biodegradation of Leather Waste by Enzymatic Treatment

    Institute of Scientific and Technical Information of China (English)

    2006-01-01

    The treatment of shavings, trimmings and splits of leather waste from tanneries has a potential to generate value-added products. In this study enzymatic treatment of leather waste was performed. This method utilizes alkaline protease produced by Bacillus subtilis in our laboratory by submerged fermentation. Optimum conditions of pH, time duration,temperature and concentration of enzyme were determined for maximum degradation of leather waste. The amount of degradation was measured by the release of amino acid hydroxyproline. Amino acid composition in the hydrolysate obtained by the enzyme hydrolysis was determined. This relative simple biotreatment of leather waste may provide a practical and economical solution.

  2. Treatment of low-level radioactive waste using Volcanic ash

    International Nuclear Information System (INIS)

    The effective application of volcanic ash, an indigenous adsorptive material abundant in the Mt. Pinatubo area, in the removal of radioiodine from radioactive waste streams was demonstrated. Factors such as availability, low cost and comparative retention capacity with respect to activated charcoal make volcanic ash an attractive alternative in the conditioning of radioactive waste containing radioiodine. Chemical precipitation was employed in the treatment of low level aqueous waste containing 137Cs. It was shown that there exists an optimum concentration of ferric ion that promotes maximum precipitation of caesium. It was further demonstrated that complete removal of caesium can be achieved with the addition of nickel hexacyanoferrate. (author). 5 refs, 3 figs

  3. Effects of waste treatment technique and quality of waste on bioaerosols in Finnish waste treatment plants

    Energy Technology Data Exchange (ETDEWEB)

    Tolvanen, O.

    2004-07-01

    The last fifteen years have seen immense changes in waste treatment in Finland. The number of landfill sites has been reduced and new waste treatment plants have been constructed; source separation of the various waste fractions has been become increasingly effective. At the same time, considerable attention has been paid to environmental factors such as odour problems. Another important factor at waste treatment plants is the working conditions of employees. Earlier, there were numerous problems with occupational hygiene in sewage treatment plants and landfills. The present study was undertaken to determine whether serious problems with bioaerosols still exist now that there are new waste treatment techniques and waste is sorted. The concentrations of dust, microbes and endotoxins were investigated at one windrow composting site in 1993-1994 and at eight waste treatment plants in 1998-2003. The best environment in regard to occupational hygiene was the combined drum and tunnel composting plant in Heinola. The most problematic area in the plant was the storage room (tunnel) for compost, but the concentrations of bioaerosols were low even there. At the composting plant in Hyvinkaeae, where the same kind of technique was in use, there were problems with bioaerosols in all working areas investigated. The same problems were encountered in dirty working areas in a drum composting plant in Oulu; in the control room number of bioaerosols was low. Conditions were worst in the dry waste treatment plant in Tampere, where viable microbes were a particular problem in the processing hall. As well, the concentrations of dust and endotoxin were occasionally increased to a level harmful to human health. The dry waste was most affected with microbes, while the treatment of wood waste caused problems with dust. In the other plants of the study, sorting and crushing of waste caused the highest concentrations of bioaerosols. The two most common air-borne fungi at every plant were

  4. Onsite Waste Water Treatment System

    Directory of Open Access Journals (Sweden)

    T. Subramani

    2014-06-01

    Full Text Available Onsite wastewater treatment systems (OWTSs have evolved from the pit privies used widely throughout history to installations capable of producing a disinfected effluent that is fit for human consumption. Although achieving such a level of effluent quality is seldom necessary, the ability of onsite systems to remove settles able solids, floatable grease and scum, nutrients, and pathogens. From wastewater discharges defines their importance in protecting human health and environmental resources. In the modern era, the typical onsite system has consisted primarily of a septic tank and a soil absorption field, also known as a subsurface wastewater infiltration system, or SWIS. In this manual, such systems are referred to as conventional systems. Septic tanks remove most settle able and floatable material and function as an anaerobic bioreactor that promotes partial digestion of retained organic matter. Septic tank effluent, which contains significant concentrations of pathogens and nutrients, has traditionally been discharged to soil, sand, or other media absorption fields (SWISs for further treatment through biological processes, adsorption, filtration, and infiltration into underlying soils. Conventional systems work well if they are installed in areas with appropriate soils and hydraulic capacities; designed to treat the incoming waste load to meet public health, ground water, and surface water performance standards; installed properly; and maintained to ensure long-term performance. These criteria, however, are often not met. Only about one-third of the land area in the United States has soils suited for conventional subsurface soil absorption fields. System densities in some areas exceed the capacity of even suitable soils to assimilate wastewater flows and retain and transform their contaminants. In addition, many systems are located too close to ground water or surface waters and others, particularly in rural areas with newly installed public

  5. 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)

  6. Life cycle assessment of electronic waste treatment

    International Nuclear Information System (INIS)

    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)

  7. Membrane bioreactor for waste gas treatment.

    OpenAIRE

    Reij, M W

    1997-01-01

    SummaryThis thesis describes the design and testing of a membrane bioreactor (MBR) for removal of organic pollutants from air. In such a bioreactor for biological gas treatment pollutants are degraded by micro-organisms. The membrane bioreactor is an alternative to other types of bioreactors for waste gas treatment, such as compost biofilters and bioscrubbers. Propene was used as a model pollutant to study the membrane bioreactor.A membrane bioreactor for waste gas treatment consists of a gas...

  8. Thermal treatment of waste contaminated with radioactive chemicals due to the accident at Fukushima Nuclear Power Stations. A review of recent research findings and introduction of some key literatures

    International Nuclear Information System (INIS)

    Many researches and challenges on thermal treatments such as incineration and melting for waste contaminated with radioactive fallout due to the explosions of Fukushima nuclear power stations have been reported. This paper reviews them not only in terms of Cs behavior and possibility to control the behavior but also in terms of appropriate maintenance of the thermal treatment plants. Various contaminated wastes from municipal solid wastes to biomass wastes discharged during decontamination works, but not from the on-site stations, are dealt with as the target wastes. Furthermore, the paper introduces some useful previous literatures associated with the recent findings and also suggests research subjects to be clarified in the future. (author)

  9. Management of low and intermediate level radioactive wastes with regard to their chemical toxicity

    International Nuclear Information System (INIS)

    A preliminary overview is provided of management options for low and intermediate level radioactive waste (LILW) with regard to its chemical toxicity. In particular, the following issues are identified and described associated with the management and safe disposal of chemically toxic materials in LILW: the origin and characteristics; the regulatory approaches; the pre-disposal management; the disposal; the safety assessment. Also included are: regulatory framework for chemically toxic low level wastes in the USA; pre-disposal processing options for LILW containing chemically toxic components; example treatment technologies for LILW containing chemically toxic components and safety assessment case studies for Germany, Belgium, France and Sweden

  10. Physical and chemical characteristics of candidate wastes for tailored ceramics

    International Nuclear Information System (INIS)

    Tailored Ceramics offer a potential alternative to glass as an immobilization form for nuclear waste disposal. The form is applicable to the wide variety of existing wastes and may be tailored to suit the diverse environments being considered as disposal sites. Consideration of any waste product form, however, require extensive knowledge of the waste to be incorporated. A varity of waste types are under consideration for incorporation into a Tailored Ceramic form. This report integrates and summarizes chemical and physical characteristics of the candidate wastes. Included here are data on Savannah River Purex Process waste; Hanford bismuth phosphate, uranium recovery, redox, Purex, evaporator and residual liquid wastes; Idaho Falls calcine; Nuclear Fuel Services Purex and Thorex wastes and miscellaneous waste including estimated waste stream compositions produced by possible future commercial fuel reprocessing

  11. 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)

  12. Technology for safe treatment of radioisotope organic wastes

    International Nuclear Information System (INIS)

    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 KH2PO4. 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)

  13. Chemical tailoring of steam to remediate underground mixed waste contaminants

    International Nuclear Information System (INIS)

    A method to simultaneously remediate mixed-waste underground contamination, such as organic liquids, metals, and radionuclides involves chemical tailoring of steam for underground injection. Gases or chemicals are injected into a high pressure steam flow being injected via one or more injection wells to contaminated soil located beyond a depth where excavation is possible. The injection of the steam with gases or chemicals mobilizes contaminants, such as metals and organics, as the steam pushes the waste through the ground toward an extraction well having subatmospheric pressure (vacuum). The steam and mobilized contaminants are drawn in a substantially horizontal direction to the extraction well and withdrawn to a treatment point above ground. The heat and boiling action of the front of the steam flow enhance the mobilizing effects of the chemical or gas additives. The method may also be utilized for immobilization of metals by using an additive in the steam which causes precipitation of the metals into clusters large enough to limit their future migration, while removing any organic contaminants

  14. Combination of chemical separation and data treatment for {sup 55}Fe, {sup 63}Ni, {sup 99}Tc, {sup 137}Cs and {sup 90}Sr/{sup 90}Y activity determination in radioactive waste by liquid scintillation

    Energy Technology Data Exchange (ETDEWEB)

    Mellado, J. [Departament de Quimica Analitica, Facultat de Quimica, Universitat de Barcelona, C/Marti Franques 1, 08028 Barcelona (Spain); Tarancon, A. [Departament de Quimica Analitica, Facultat de Quimica, Universitat de Barcelona, C/Marti Franques 1, 08028 Barcelona (Spain); Garcia, J.F. [Departament de Pintura, Facultat de Belles Arts, Universitat de Barcelona, C/Pau Gargallo 4, 08028 Barcelona (Spain)]. E-mail: jfgarcia@apolo.qui.ub.es; Rauret, G. [Departament de Quimica Analitica, Facultat de Quimica, Universitat de Barcelona, C/Marti Franques 1, 08028 Barcelona (Spain); Warwick, P. [Geoscience Advisory Unit, Southampton Oceanography Centre, Southampton SO14 3ZH (United Kingdom)

    2005-08-01

    Routine operations involving nuclear reactors and decommissioning activities require numerous chemical analyses. Most of the procedures developed for these chemical characterisations involve several separation steps to prepare the sample for measurement. Chemical treatments are time- and manpower-consuming, labour intensive and produce significant quantities of waste. In order to address this problem, we evaluate a data treatment procedure (multivariate calibration-PLS), which we propose as a substitute to some of these separation steps. Mixtures of beta emitter radionuclides of increasing complexity ({sup 90}Sr/{sup 90}Y-{sup 99}Tc, {sup 90}Sr/{sup 90}Y-{sup 99}Tc-{sup 63}Ni-{sup 137}Cs and {sup 90}Sr/{sup 90}Y-{sup 99}Tc-{sup 63}Ni-{sup 137}Cs-{sup 55}Fe) have been measured by liquid scintillation (LS) counting. The influences of quenching and level of activity was evaluated and the activity of unknown samples determined. Despite the spectra overlapping and low resolution of LS, relative errors in the activities quantification of unknown samples inside the range covered by the calibration matrix are lower than 15% whatever the number of radionuclides included in the solution was.

  15. Combination of chemical separation and data treatment for 55Fe, 63Ni, 99Tc, 137Cs and 90Sr/90Y activity determination in radioactive waste by liquid scintillation

    International Nuclear Information System (INIS)

    Routine operations involving nuclear reactors and decommissioning activities require numerous chemical analyses. Most of the procedures developed for these chemical characterisations involve several separation steps to prepare the sample for measurement. Chemical treatments are time- and manpower-consuming, labour intensive and produce significant quantities of waste. In order to address this problem, we evaluate a data treatment procedure (multivariate calibration-PLS), which we propose as a substitute to some of these separation steps. Mixtures of beta emitter radionuclides of increasing complexity (90Sr/90Y-99Tc, 90Sr/90Y-99Tc-63Ni-137Cs and 90Sr/90Y-99Tc-63Ni-137Cs-55Fe) have been measured by liquid scintillation (LS) counting. The influences of quenching and level of activity was evaluated and the activity of unknown samples determined. Despite the spectra overlapping and low resolution of LS, relative errors in the activities quantification of unknown samples inside the range covered by the calibration matrix are lower than 15% whatever the number of radionuclides included in the solution was

  16. Separation of radionuclides from chemical and electrochemical decontamination wastes

    International Nuclear Information System (INIS)

    A multistage process combining photocatalytic degradation of organic complexes and complexants followed by separation of the radionuclides by ion exchange was developed and tested for the treatment of aqueous waste from chemical or electrochemical decontamination of NPP primary circuit internals. In these solutions, both the oxalic and citric acids could be quantitatively degraded within 10-12 hours of irradiation by 254 nm UV radiation in the presence of TiO2 photocatalyst. For the group radionuclides separation, a standard cation exchanger was found to be preferable to any of the set of the tested inorganic-organic composite absorbers. (author)

  17. Electrochemical treatment of alkaline nuclear wastes

    International Nuclear Information System (INIS)

    Large quantities of highly radioactive waste have been generated throughout the Department of Energy complex over the past 50 years as a result of the production of special nuclear materials for defense and space programs. These wastes have been stored in underground tanks. Some of the tanks have developed cracks that have allowed waste to leak out of the primary tank. Many of the tanks are operating beyond their design life. Processes are being developed to remove the waste from the storage tanks and permanently dispose of it in engineered wasteforms. The bulk of the radioactivity will be concentrated into approximately 1% of the total waste volume and vitrified. The highly radioactive borosilicate glass wasteform will be placed in the federal repository. The remaining waste, which still contains low concentrations of radioactivity, will be incorporated into a low-level wasteform (e.g., cement, glass, ceramic, polymer, etc.) and placed in a near surface facility at the DOE site. Electrochemical-based processes are being evaluated to destroy organic compounds that impact radionuclide separations processes, to destroy or to remove hazardous species in the waste such as nitrates, nitrites, hazardous metals, and radionuclides that can impact wasteform production and characteristics, recovery chemicals of value such as sodium hydroxide (caustic) that can be recycled. Major benefits of such processes include the destruction or removal of hazardous species, waste volume reduction and the recovery of valuable chemicals contained in the waste

  18. Optimization of PWR waste water treatment

    International Nuclear Information System (INIS)

    The Waste Policy Amendments Act of 1985 has mandated specific volume limitations for waste generators and disposal sites. This, combined with increasing cost, has caused added emphasis to be placed on waste minimization and volume reduction. Since waste streams, as well as technical specifications for water release or re-use, differ from plant to plant, this effort to minimize and reduce waste must be site specific. Over the past several years, numerous water treatment technologies have become available and have resulted in reduced waste generation. This paper discusses the combination of various technologies Chem-Nuclear Systems, Inc. has applied to process Indian Point II's liquid waste streams, resulting in effective waste reduction program. Included in this discussion is the station's waste reduction program history, actions and results illustrated by the change from evaporation to state-of-the-art liquid waste processing. The paper demonstrates that the Indian Point experience has direct application to other PWRs in the areas of: (1) attempting to achieve the desired results through in-plant systems, (2) evaporator availability, (3) dealing with a waste stream which fluctuates over a broad spectrum and (4) changing from total waste recovery to discharge

  19. Blasting at a Superfund chemical waste site

    International Nuclear Information System (INIS)

    During the summer of 1989, Maine Drilling and Blasting of Gardiner, Maine was contracted by Cayer Corporation of Harvard, Massachusetts to drill and blast an interceptor trench at the Nyanza Chemical Superfund Site in Ashland, Massachusetts. The interceptor trench was to be 1,365 feet long and to be blasted out of granite. The trench was to be 12 feet wide at the bottom with 1/1 slopes, the deepest cut being 30 feet deep. A French drain 12 feet wide by 15 to 35 feet deep was blasted below the main trench on a 2% slope from its center to each end. A French drain is an excavation where the rock is blasted but not dug. The trench would be used as a perimeter road with any ground water flow going through the French drain flowing to both ends of the trench. Being a Superfund project turned a simple blasting project into a regulatory nightmare. The US Environmental Protection Agency performed all the chemical related functions on site. The US Army Corps of Engineers was overseeing all related excavation and construction on site, as was the Massachusetts Department of Environmental Quality Engineering, the local Hazardous Wastes Council, and the local Fire Department. All parties had some input with the blasting and all issues had to be addressed. The paper outlines the project, how it was designed and completed. Also included is an outline of the blast plan to be submitted for approval, an outline of the Safety/Hazardous Waste training and a description of all the problems which arose during the project by various regulatory agencies

  20. Treatment of NPP wastes using vitrification

    International Nuclear Information System (INIS)

    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/(cm2 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)

  1. Bioprocessing applications in the management of nuclear and chemical wastes

    International Nuclear Information System (INIS)

    The projected requirements for waste management and environmental restoration activities within the United States will probably cost tens of billions of dollars annually during the next two decades. Expenditures of this magnitude clearly have the potential to affect the international competitiveness of many US industries and the continued operation of many federal facilities. It is argued that the costs of implementing current technology will be too high unless the standards and schedules for compliance are relaxed. Since this is socially unacceptable, efforts to improve the efficiency of existing technologies and to develop new technologies should be pursued. A sizable research, development, and demonstration effort can be easily justified if the potential for reducing costs can be shown. Bioprocessing systems for the treatment of nuclear and chemically hazardous wastes offer such promise. 11 refs

  2. Bioprocessing applications in the management of nuclear and chemical wastes

    International Nuclear Information System (INIS)

    The US Department of Energy (DOE), the US Department of Defense (DOD), and other federal agencies already face profound challenges in finding strategies that manage budgets and priorities while bringing their sites and facilities into compliance with current statues and regulations and with agency policies and orders. While it is often agreed that current technology can be used to address most waste management and environmental restoration needs, it is also argued by many that the costs of implementing current technology will be too high unless the standards and schedules for compliance are relaxed. Since this is socially unacceptable, efforts to improve the efficiency of existing technologies and to develop new technologies should be pursued. A sizable research, development, and demonstration effort can be easily justified if the potential for reducing costs can be shown. Bioprocessing systems for the treatment of nuclear and chemically hazardous wastes offer such promise

  3. Pilot installation for the thermo-chemical characterisation of solid wastes.

    Science.gov (United States)

    Marculescu, C; Antonini, G; Badea, A; Apostol, T

    2007-01-01

    The increasing production and the large variety of wastes require operators of thermal treatment units to continuously adapt the installations or the functioning parameters to the different physical and chemical properties of the wastes. Usually, the treated waste is encountered in the form of heterogeneous mixtures. The classical tests such as thermogravimetry and calorimetric bomb operate component by component, separately. In addition to this, they can analyse only small quantities of waste at a time (a few grams). These common tests are necessary but insufficient in the global waste analysis in the view further thermal treatment. This paper presents an experimental installation, which was designed and built at the CNRS Science Division, Department of Industrial Methods, Compiègne University of Technology, France. It allows the determination of waste thermal and chemical properties by means of thermal treatment. Also, it is capable of continuously analysing significant quantities of waste (up to 50kg/h) as compared to the classical tests and it can work under various conditions: The installation reproduces the process conditions from incinerators or pyrolysis reactors. It also provides complete information on the kinetics of the waste thermal degradation and on the pollutant emissions. Using different mixtures of components present in the municipal solid waste and also in the reconstituted MSW samples, we defined a series of criteria for characterising waste behaviour during the stages of the main treatment process such as: feeding, devolatilisation/oxidation, advancement, solid residue evacuation, and pollutants emission. PMID:16617012

  4. An overview of in situ waste treatment technologies

    International Nuclear Information System (INIS)

    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

  5. Thyroid disruption in male goldfish (Carassius auratus) exposed to leachate from a municipal waste treatment plant: Assessment combining chemical analysis and in vivo bioassay.

    Science.gov (United States)

    Gong, Yufeng; Tian, Hua; Dong, Yifei; Zhang, Xiaona; Wang, Jun; Wang, Wei; Ru, Shaoguo

    2016-06-01

    Several classes of thyroid-disrupting chemicals (TDCs) have been found in refuse leachate, but the potential impacts of leachate on the thyroid cascade of aquatic organisms are yet not known. In this study, we chemically analyzed frequently reported TDCs, as well as conducted a bioassay, to evaluate the potential thyroid-disrupting effects of leachate. We used radioimmunoassay to determine the effects of leachate exposure on plasma 3,3',5-triiodo-l-thyronine (T3), 3,3',5,5'-l-thyroxine (T4), and thyroid-stimulating hormone (TSH) levels in adult male goldfish (Carassius auratus). We also investigated the impacts of leachate treatment on hepatic and gonadal deiodinases [types I (D1), II (D2), and III (D3)] and gonadal thyroid receptor (TRα-1 and TRβ) mRNA expressions by using real-time polymerase chain reaction. The results indicated the presence of five TDCs (bisphenol A, 4-t-octylphenol, di-n-butyl phthalate, di-n-octyl phthalate, and diethylhexyl phthalate); their mean concentrations in the leachate were 18.11, 2.76, 4.86, 0.21, and 9.16μg/L, respectively. Leachate exposure induced plasma T3 and TSH levels in male fish, without influencing the plasma T4 levels. The highly elevated D2 mRNA levels in the liver were speculated to be the primary reason for the induction of plasma T3 levels. Disruption of thyroid functions by leachate was also suggested by the up-regulation of D1 and D2 as well as TRα-1 mRNA levels in the gonads. Prominent thyroid disruptions despite the very low TDC concentrations in the exposure media used in the bioassay strongly indicated the existence of unidentified TDCs in the leachate. Our study indicated the necessity of conducting in vivo bioassays to detect thyroid dysfunctions caused by leachate. PMID:26950620

  6. Treatment of complex electroplating waste by 'zero discharge' technique

    International Nuclear Information System (INIS)

    Surface treatment processes generate lot of liquid waste, which contains toxic substances and are potentially harmful to the living beings. It is extremely difficult to treat the pollutants where processes and frequencies are not fixed. In Chemical Treatment Facility of RRCAT, surface treatment processes are user dependent and makes the electroplating waste very complicated. Initially the waste was treated by simple chemical transformation technique in which heavy metal ions are converted to hydroxide precipitates. Non metallic ions that contribute much to the plating waste could not be treated by this process. To remove maximum possible pollutants, many experiments were conducted on the laboratory scale. Based on those results, a pilot ion exchange plant of various resins was introduced in the process to achieve disposal quality effluent. Anionic load of Phosphate, Nitrate and fluoride caused frequent anionic bed exhaustions and polymeric network damaging. To avoid this phenomenon a new setup was designed. This pre treatment has the capacity to treat 500 litres per hour connected to a platter with clarifier followed by high pressure carbon and pebbles filters. Analysis of these ions was carried out on the advanced ion chromatography system and is found free of toxic metals, phosphate and fluoride. This effluent can be reused by adding a reverse osmosis system followed by ion exchange system to produce good quality de mineralized water needed for surface treatment activities. In this paper we describe the existing status of effluent treatment facility and future plans for achieving 'zero discharge'. (author)

  7. Management, treatment and final disposal of solid hazardous hospital wastes

    International Nuclear Information System (INIS)

    Medical Waste is characterized by its high risk to human health and the environment. The main risk is biological, due to the large amount of biologically contaminated materials present in such waste. However, this does not mean that the chemical and radioactive wastes are less harmful just because they represent a smaller part of the total waste. Hazardous wastes from hospitals can be divided in 3 main categories: Solid Hazardous Hospital Wastes (S.H.H.W.), Liquid Hazardous Hospital Wastes (L.H.H.W.) and Gaseous Hazardous Hospital Wastes (G.H.H.W.) Most gaseous and liquid hazardous wastes are discharged to the environment without treatment. Since this inappropriate disposal practice, however, is not visible to society, there is no societal reaction to such problem. On the contrary, hazardous solid wastes (S.H.H.W.) are visible to society and create worries in the population. As a result, social and political pressures arise, asking for solutions to the disposal problems of such wastes. In response to such pressures and legislation approved by Costa Rica on waste handling and disposal, the Caja Costarricense de Seguro Social developed a plan for the handling, treatment, and disposal of hazardous solid wastes at the hospitals and clinics of its system. The objective of the program is to reduce the risk to society of such wastes. In this thesis a cost-effectiveness analysis was conducted to determine the minimum cost at which it is possible to reach a maximum level of reduction in hazardous wastes, transferring to the environment the least possible volume of solid hazardous wastes, and therefore, reducing risk to a minimum. It was found that at the National Children's Hospital the internal handling of hazard solid wastes is conducted with a high level of effectiveness. However, once out of the hospital area, the handling is not effective, because hazardous and common wastes are all mixed together creating a larger amount of S.H.H.W. and reducing the final efficiency

  8. Radiation treatment of toxic chemicals

    International Nuclear Information System (INIS)

    Polychlorinated biphenyls (PCBs) were commercially produced from 1920s as complex mixtures containing multiple isomers for a variety of applications. They are very toxic, chemically stable and resist microbial, photochemical, chemical, and thermal degradation. The public, legal, and scientific concerns about PCBs arose from research indicating they were environmental contaminants that had a potential to adversely impact the environment, and, therefore, were undesirable as commercial products. Eventually, most producers reduced or stopped production of PCBs in the 1970s. Stockholm convention on POPs (Persistent Organic Pollutants), which was effective on May 2004 and 151 nations including Korea were joined on June 2005, asked to dispose of PCBs by 2028 with environmental friendly methods. Korean government also has declared to conduct by 2015. According to the Environmental law of Korea, over 2 ppm of PCBs has to be decomposed by legal methods of incineration and thermal destruction. But those are inapplicable owing to the environmental groups. KAERI(Korea Atomic Energy Research Institute) has recently developed a remarkable technology for radiation treatment of toxic chemicals including chlorides using an electron beam accelerator. Electron beam accelerator of 2.5 MeV energy and 100 kW power capacity was used to decompose of PCBs having been used as a commercial transformer oil for more than 30 years. The oil were irradiated with ∼ 0.1 percent of TEA (Triethyl Amin) to make chloride ion aparted off from the PCBs into precipitate at the conditions of normal temperature and pressure. The concentrations of PCBs were measured by GC (Gas Chromatography) with ECD (Electron Capture Detector) following the KS (Korean Standard) test procedure. Electron beam should be a useful tool for environmental conservation. Residual concentrations of PCBs after irradiation were depended on the absorption dose of electron beam energy. Advantages comparing to other methods such as

  9. BASIS FOR DETERMINATION OF CHEMICAL STABILITY and COMPATIBILITY OF SOLID WASTE CHEMICAL COMPATIBILITY TECHNICAL BASIS

    International Nuclear Information System (INIS)

    Solid wastes must be managed to prevent inadvertent reactions, explosion and degradation of waste containers per the ''Washington State Department of Ecology Dangerous Waste Regulations'' (WAC 173-303). An understanding of chemical compatibility principles and a consistent approach for implementing compatibility requirements is essential for complying with the regulations. This document explains the technical basis for ensuring chemical compatibility for solid wastes that are stored on site at on-site TSD facilities and for solid waste that will go to off-site TSD facilities. The document applies directly to the following aspects of chemical compatibility: (1) Ensuring that hazardous waste is not chemically reactive or unstable such that it cannot be safely transported or stored; (2) Ensuring that lab packs (i.e., drums containing multiple inner containers of differing types of hazardous waste) are packaged such that incompatible chemicals are not placed into the same drum; (3) Selecting containers and liners that are compatible with the waste they contain. This document does not cover individual TSD requirements, or specific offsite TSD requirements. This document does not cover chemical compatibility and segregation requirements for shipping wastes on-site or off-site. This document does not cover radiological hazards associated with radioactive waste or mixed wastes. Evaluation of compatibility for comingling and treating solid waste is beyond the scope of this document. In addition, heat generation and gas generation as they apply to the Hanford waste acceptance criteria are not covered in this document

  10. Results of Hazardous and Mixed Waste Excavation from the Chemical Waste Landfill

    International Nuclear Information System (INIS)

    This paper describes the results of the excavation of a 1.9-acre hazardous and mixed waste landfill operated for 23 years at Sandia National Laboratories, Albuquerque, New Mexico. Excavation of the landfill was completed in 2 1/2 years without a single serious accident or injury. Approximately 50,000 cubic yards of soil contaminated with volatile and semi-volatile organics, metals, polychlorinated biphenyl compounds, and radioactive constituents was removed. In addition, over 400 cubic yards of buried debris was removed, including bulk debris, unknown chemicals, compressed gas cylinders, thermal and chemical batteries, explosive and ordnance debris, pyrophoric materials and biohazardous waste. Removal of these wastes included negotiation of multiple regulations and guidances encompassed in the Resource Conservation and Recovery Act (RCRA), the Toxic Substances Control Act (TSCA), and risk assessment methodology. RCRA concepts that were addressed include the area of contamination, permit modification, emergency treatment provision, and listed waste designation. These regulatory decisions enabled the project to overcome logistical and programmatic needs such as increased operational area, the ability to implement process improvements while maintaining a record of decisions and approvals

  11. Radioactivities at megalopolis waste water treatment plants

    International Nuclear Information System (INIS)

    In waste water treatment plants, the nuclides originated from nuclear medicine are generally detected. In the Tokyo Metropolis, the sludges in five waste water treatment plants were investigated, where the same nuclides were detected, though the concentration was different. The radioactivity was far lower than the permissible concentration level for waste water. In the aspect of environmental protection, the radioactivity contained in the resultant sludges is important. Such sludges are mostly treated by incineration. In this case, the nuclide released to the atmosphere is mainly 131I. This quantity is only slight presently. However, if the quantity of RIs used should increase largely, it will be necessary to monitor the radioactivity in the waste treatment plants. The most suitable place for the monitoring is the process of sludge treatment, preferably with Ge semiconductor detectors. (Mori, K.)

  12. Treatment of Radioactive Gaseous Waste

    International Nuclear Information System (INIS)

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

  13. Radiological, physical, and chemical characterization of low-level alpha contaminated wastes stored at the Idaho National Engineering Laboratory

    International Nuclear Information System (INIS)

    This document provides radiological, physical, and chemical characterization data for low-level alpha-contaminated radioactive and low-level alpha-contaminated radioactive and hazardous (i.e., mixed) wastes stored at the Idaho National Engineering Laboratory and considered for treatment under the Private Sector Participation Initiative Program. Waste characterization data are provided in the form of INEL Waste Profile Sheets. These documents provide, for each content code, information on waste identification, waste description, waste storage configuration, physical/chemical waste composition, radionuclide and associated alpha activity waste characterization data, and hazardous constituents present in the waste. Information is provided for 97 waste streams which represent an estimated total volume of 25,450 m 3 corresponding to a total mass of approximately 12,000,000 kg. In addition, considerable information concerning alpha, beta, gamma, and neutron source term data specific to Rocky Flats-generated waste forms stored at the INEL are provided to assist in facility design specification

  14. Radiological, physical, and chemical characterization of low-level alpha contaminated wastes stored at the Idaho National Engineering Laboratory

    Energy Technology Data Exchange (ETDEWEB)

    Apel, M.L.; Becker, G.K.; Ragan, Z.K.; Frasure, J.; Raivo, B.D.; Gale, L.G.; Pace, D.P.

    1994-03-01

    This document provides radiological, physical, and chemical characterization data for low-level alpha-contaminated radioactive and low-level alpha-contaminated radioactive and hazardous (i.e., mixed) wastes stored at the Idaho National Engineering Laboratory and considered for treatment under the Private Sector Participation Initiative Program. Waste characterization data are provided in the form of INEL Waste Profile Sheets. These documents provide, for each content code, information on waste identification, waste description, waste storage configuration, physical/chemical waste composition, radionuclide and associated alpha activity waste characterization data, and hazardous constituents present in the waste. Information is provided for 97 waste streams which represent an estimated total volume of 25,450 m 3 corresponding to a total mass of approximately 12,000,000 kg. In addition, considerable information concerning alpha, beta, gamma, and neutron source term data specific to Rocky Flats-generated waste forms stored at the INEL are provided to assist in facility design specification.

  15. 76 FR 34200 - Land Disposal Restrictions: Revision of the Treatment Standards for Carbamate Wastes

    Science.gov (United States)

    2011-06-13

    ... Standards for Carbamate Wastes AGENCY: Environmental Protection Agency. ACTION: Proposed rule. SUMMARY: The...) treatment standards for hazardous wastes from the production of carbamates and carbamate commercial chemical... carbamate wastes must be treated to meet numeric concentration limits before they can be land...

  16. 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.

  17. Impact of decontamination on LWR radioactive waste treatment systems

    International Nuclear Information System (INIS)

    Only at N-Reactor is there a means to accommodate radwaste produced during decontamination. The Dresden system is expected to be ready to accommodate such solutions by the summer of 1979. Solidification of the processed decontamination waste may be a significant problem. There is doubt that the materials in current radwaste treatment systems can handle chemicals from a concentrated process. The total storage volume, for concentrated decontamination, is not sufficient in existing radwaste treatment systems. Greater attention should be placed on designing reactors and radwaste treatment systems for decontamination. A means of handling waste material resulting from leaks in the primary system during the decontamination must be developed. On-site storage of solidified decontamination wastes may be a viable option, but license amendments will be necessary

  18. Pilot studies to achieve waste minimization and enhance radioactive liquid waste treatment at the Los Alamos National Laboratory Radioactive Liquid Waste Treatment Facility

    International Nuclear Information System (INIS)

    The Radioactive and Industrial Wastewater Science Group manages and operates the Radioactive Liquid Waste Treatment Facility (RLWTF) at the Los Alamos National Laboratory (LANL). The RLWTF treats low-level radioactive liquid waste generated by research and analytical facilities at approximately 35 technical areas throughout the 43-square-mile site. The RLWTF treats an average of 5.8 million gallons (21.8-million liters) of liquid waste annually. Clarifloculation and filtration is the primary treatment technology used by the RLWTF. This technology has been used since the RLWTF became operable in 1963. Last year the RLWTF achieved an average of 99.7% removal of gross alpha activity in the waste stream. The treatment process requires the addition of chemicals for the flocculation and subsequent precipitation of radionuclides. The resultant sludge generated during this process is solidified in drums and stored or disposed of at LANL

  19. Development of treatment technologies for the processing of US Department of Energy mixed waste

    International Nuclear Information System (INIS)

    Waste contaminated with chemically hazardous and radioactive species is defined as mixed waste. Significant technology development has been conducted for separate treatment of hazardous and radioactive waste, but technology development addressing mixed-waste treatment has been limited. Management of mixed waste requires treatment which must meet the standards established by the US Environmental Protection Agency for the specific hazardous constituents while also providing adequate control of the radionuclides. Technology has not been developed, demonstrated, or tested to produce a low-risk final waste form specifically for mixed waste. Throughout the US Department of Energy (DOE) complex, mixed waste is a problem because definitive treatment standards have not been established and few disposal facilities are available. Treatment capability and capacity are also limited. Site-specific solutions to the management of mixed waste have been initiated; however, site-specific programs result in duplication of technology development between various sites. Significant progress is being made in developing technology for mixed waste under the Mixed Waste Integrated Program. The status of the technical initiatives in chemical/physical treatment, destruction/stabilization technology, off-gas treatment, and final waste form production/assessment is described in this paper

  20. Chemical Characteristics of Compost and Humic Acid from Sago Waste (Metroxylon sagu)

    OpenAIRE

    Auldry C. Petrus; Osumanu H. Ahmed; Ab M.N. Muhamad; Hassan M. Nasir; Make Jiwan; Michael G. Banta

    2009-01-01

    Problem statement: Agriculture waste such as Sago Waste (SW) has a potential to cause pollution either on land or in water. In order to reduce this problem, a study was conducted to investigate the effect of three different treatments on the chemical characteristics of compost and humic acid from SW. Approach: The study had three treatments which were: T1: SW (80%) + chicken feed (5%) + chicken dung slurry (5%) + molasses (5%) + urea (5%), T2: SW (80%) + chicken feed (10%) + chicken dung slur...

  1. New treatment methods of radioactive wastes

    International Nuclear Information System (INIS)

    Techniques of Radioactive waste treatment continues to make advances in year by year. First of all we would explain the new plant constructed by Studsvik of America in Tenn. U.S.A. This plant consist of pyrolysis and hydro-reforming process. These combination technique are capable for incineration and decompose the inflammable material such as ion-exchange resin. ZWILAG is the central control facility of Radioactive wastes in Switzerland. This facility has wastes storage halls and incineration plant which operated by plasma torch. This system is the first plant in the would. Radon Science Research Center of Russia has been developed many kinds of technique in radwaste treatment. Powdered metal fuel is very unique material for incineration of ionexchange resin. Magnetic stirrer is applied for cement solidification. Ebara designed special equipment for nuclear accident such as movable radioactive measurement car and radioactive liquid waste treatment installed on car are explained. (author)

  2. Sustainable treatment of municipal waste water

    DEFF Research Database (Denmark)

    Hansen, Peter Augusto; Larsen, Henrik Fred

    develop and implement a methodology to compare and prioritize these technologies and optimizations based on a holistic approach. This will be achieved through the use of life cycle assessment (LCA) along with cost/efficiency analysis with focus on the effects of nutrients, pathogens and micropollutants (i.......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....

  3. Treatment of solid waste containing 226Ra

    International Nuclear Information System (INIS)

    This work is directed to the treatment of radioactive solid waste containing mainly radium (226Ra) produced from oil and gas production industries in Egypt. The treatment process has been carried out by suspending the clay fraction content in the solid waste in suitable leaching solutions. These compremise aqueous saline solution and aqueous saline solutions containing certain additives, namely, Washing Powder (W.P.), Shell and Span 20 surfactants. Treatment with saline solution containing either W.P. or Shell surfactants, showed an enhancement in the removal of 226Ra compared to that with saline solution alone or containing Span 20. Factors affect the treatment process have been investigated and discussed. The removal percentage of 226Ra was found to depend on the clay fines content in the solid waste. Further sequential treatment schemes have been tested and optimized

  4. Treatment of mixed wastes by thermal plasma discharges

    International Nuclear Information System (INIS)

    The present study has as purpose to apply the technology of thermal plasma in the destruction of certain type of waste generated in the ININ. As first instance, origin, classification and disposition of the radioactive waste generated in the ININ is identified. Once identified the waste, the waste to treat is determined based on: the easiness of treating him with plasma, classification and importance. Later on, a substance or compound settles down (sample model) that serves as indicative of the waste for its physical-chemical characteristics, this is made because in the Thermal Plasma Applications Laboratory is not had the license to work with radioactive material. The sample model and the material to form the vitreous matrix are characterized before and after the treatment in order to evaluating their degradation and vitrification. During the treatment by means of the thermal plasma, the appropriate conditions are determined for the degradation and vitrification of the waste. Also, it is carried out an energy balance in the system to know the capacity to fuse the material depending the transfer of existent heat between the plasma and the material to treat. Obtaining favorable results, it thought about to climb in the project and by this way to help to solve one of the environmental problems in Mexico, as they are it the mixed wastes. (Author)

  5. Measurements and models for hazardous chemical and mixed wastes. 1998 annual progress report

    International Nuclear Information System (INIS)

    'Aqueous waste of various chemical compositions constitutes a significant fraction of the total waste produced by industry in the US. A large quantity of the waste generated by the US chemical process industry is waste water. In addition, the majority of the waste inventory at DoE sites previously used for nuclear weapons production is aqueous waste. Large quantities of additional aqueous waste are expected to be generated during the clean-up of those sites. In order to effectively treat, safely handle, and properly dispose of these wastes, accurate and comprehensive knowledge of basic thermophysical property information is paramount. This knowledge will lead to huge savings by aiding in the design and optimization of treatment and disposal processes. The main objectives of this project are: Develop and validate models that accurately predict the phase equilibria and thermodynamic properties of hazardous aqueous systems necessary for the safe handling and successful design of separation and treatment processes for hazardous chemical and mixed wastes. Accurately measure the phase equilibria and thermodynamic properties of a representative system (water + acetone + isopropyl alcohol + sodium nitrate) over the applicable ranges of temperature, pressure, and composition to provide the pure component, binary, ternary, and quaternary experimental data required for model development. As of May, 1998, nine months into the first year of a three year project, the authors have made significant progress in the database development, have begun testing the models, and have been performance testing the apparatus on the pure components.'

  6. Methods Used in Urban Waste Treatment

    OpenAIRE

    I. OROIAN; PROOROCU M.; Antonia ODAGIU; I. BRASOVEAN

    2010-01-01

    The paper presents the main options aiming the treatment of urban waste consisting mainly of the household andthose resulting from industrial activities, acordin to the present EU legislation. The aspects of the two major types ofwaste treatment, mechanical biological treatment and incineration respectively are described. Distinction is madebetween mechanical and biological treatment of aerobic and anaerobic issues being addressed and biological dryingprocess. The result of these processes is...

  7. Guidelines for generators of hazardous chemical waste at LBL and guidelines for generators of radioactive and mixed waste at LBL

    International Nuclear Information System (INIS)

    The purpose of this document is to provide the acceptance criteria for the transfer of hazardous chemical waste to LBL's Hazardous Waste Handling Facility (HWHF). Hazardous chemical waste is a necessary byproduct of LBL's research and technical support activities. This waste must be handled properly if LBL is to operate safely and provide adequate protection to staff and the environment. These guidelines describe how you, as a generator of hazardous chemical waste, can meet LBL's acceptance criteria for hazardous chemical waste

  8. Hazardous waste treatment and environmental remediation research

    International Nuclear Information System (INIS)

    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

  9. Hazardous waste treatment and environmental remediation research

    Energy Technology Data Exchange (ETDEWEB)

    1989-09-29

    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.

  10. Physical and chemical methods for the characterization of hazardous wastes

    Science.gov (United States)

    Francis, C. W.; Maskarinec, M. P.; Lee, D. W.

    Numerous test methods have been proposed and developed to evaluate the hazards associated with handling and disposal of wastes in landfills. The major concern is the leaching of toxic constituents from the wastes. The fate of hazardous constituents in landfilled wastes is highly dependent on the physical and chemical characteristics of the waste. Thus, the primary objective in the selection of waste characterization procedures should be focused on those methods that gauge the fate of the waste's hazardous constituents in a specific landfill environment. Waste characterization in the United States has centered around the characteristics of ignitability, corrosivity, reactivity, and toxicity. The strategy employed in the development of most regulatory waste characterization procedures has been a pass or fail approach, usually tied to some form of a mismanagement scenario for that waste. For example, USEPA has chosen the disposal of a waste in a municipal waste landfill as a mismanagement scenario for the development of the waste leaching tests to determine the toxicity characteristic. Many wastes, such as large-volume utility wastes or mining wastes, are not disposed of in municipal waste landfills. As a consequence, more effort is needed in the development of waste leaching tests that determine the long-term leaching characteristics of that waste in the landfill environment in which the waste is to be disposed. Waste leaching models also need to be developed and tested as to their ability to simulate actual disposal environments. These models need to be compared with laboratory leaching tests, and, if practical, coupled with groundwater transport models.

  11. 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...

  12. New technologies for treatment of various wastes and an integrated waste treatment system for PWRs

    International Nuclear Information System (INIS)

    Several unique technologies for the treatment of various wastes generated by PWR nuclear power plants are discussed. An integrated treatment system consisting of Slag Cement Solidification, High Temperature Incineration and Cement Grout Stabilization is proposed in this study. (author)

  13. Biological treatment of concentrated hazardous, toxic, and radionuclide mixed wastes without dilution

    OpenAIRE

    Stringfellow, William T.; Komada, Tatsuyuki; Chang, Li-Yang

    2004-01-01

    Approximately 10 percent of all radioactive wastes produced in the U. S. are mixed with hazardous or toxic chemicals and therefore can not be placed in secure land disposal facilities. Mixed wastes containing hazardous organic chemicals are often incinerated, but volatile radioactive elements are released directly into the biosphere. Some mixed wastes do not currently have any identified disposal option and are stored locally awaiting new developments. Biological treatment has been propo...

  14. Chemical pretreatment of Savannah River Site nuclear waste for disposal

    International Nuclear Information System (INIS)

    This work describes two processes, Extended Sludge Processing and In-Tank Precipitation, which have been developed and demonstrated at full-scale to pretreat the Savannah River Site High-Level Waste for permanent disposal. These processes will be carried out in waste storage tanks which have been modified for chemical processing. These processes will concentrate the radioactivity into a small volume for vitrification. The bulk of the waste will be sufficiently decontaminated such that it can be disposed of as a low-level waste. The decontaminated waste will be incorporated into a cement wasteform in the Saltstone Facility

  15. 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.

  16. Seminar on waste treatment and disposal

    International Nuclear Information System (INIS)

    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

  17. Thermal treatment of municipal waste: An overview

    International Nuclear Information System (INIS)

    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)

  18. Radioactive Bench-scale Steam Reformer Demonstration of a Monolithic Steam Reformed Mineralized Waste Form for Hanford Waste Treatment Plant Secondary Waste - 12306

    International Nuclear Information System (INIS)

    Hanford currently has 212,000 m3 (56 million gallons) of highly radioactive mixed waste stored in the Hanford tank farm. This waste will be processed to produce both high-level and low-level activity fractions, both of which are to be vitrified. Supplemental treatment options have been under evaluation for treating portions of the low-activity waste, as well as the liquid secondary waste from the low-activity waste vitrification process. One technology under consideration has been the THORR fluidized bed steam reforming process offered by THOR Treatment Technologies, LLC (TTT). As a follow-on effort to TTT's 2008 pilot plant FBSR non-radioactive demonstration for treating low-activity waste and waste treatment plant secondary waste, TTT, in conjunction with Savannah River National Laboratory, has completed a bench scale evaluation of this same technology on a chemically adjusted radioactive surrogate of Hanford's waste treatment plant secondary waste stream. This test generated a granular product that was subsequently formed into monoliths, using a geo-polymer as the binding agent, that were subjected to compressibility testing, the Product Consistency Test and other leachability tests, and chemical composition analyses. This testing has demonstrated that the mineralized waste form, produced by co-processing waste with kaolin clay using the TTT process, is as durable as low-activity waste glass. Testing has shown the resulting monolith waste form is durable, leach resistant, and chemically stable, and has the added benefit of capturing and retaining the majority of Tc-99, I-129, and other target species at high levels. (authors)

  19. Closed Fuel Cycle Waste Treatment Strategy

    Energy Technology Data Exchange (ETDEWEB)

    Vienna, J. D. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Collins, E. D. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Crum, J. V. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Ebert, W. L. [Argonne National Lab. (ANL), Argonne, IL (United States); Frank, S. M. [Idaho National Lab. (INL), Idaho Falls, ID (United States); Garn, T. G. [Idaho National Lab. (INL), Idaho Falls, ID (United States); Gombert, D. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Jones, R. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL); Jubin, R. T. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Maio, V. C. [Idaho National Lab. (INL), Idaho Falls, ID (United States); Marra, J. C. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL); Matyas, J. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Nenoff, T. M. [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Riley, B. J. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Sevigny, G. J. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Soelberg, N. R. [Idaho National Lab. (INL), Idaho Falls, ID (United States); Strachan, D. M. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Thallapally, P. K. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Westsik, J. H. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States)

    2015-02-01

    This study is aimed at evaluating the existing waste management approaches for nuclear fuel cycle facilities in comparison to the objectives of implementing an advanced fuel cycle in the U.S. under current legal, regulatory, and logistical constructs. The study begins with the Global Nuclear Energy Partnership (GNEP) Integrated Waste Management Strategy (IWMS) (Gombert et al. 2008) as a general strategy and associated Waste Treatment Baseline Study (WTBS) (Gombert et al. 2007). The tenets of the IWMS are equally valid to the current waste management study. However, the flowsheet details have changed significantly from those considered under GNEP. In addition, significant additional waste management technology development has occurred since the GNEP waste management studies were performed. This study updates the information found in the WTBS, summarizes the results of more recent technology development efforts, and describes waste management approaches as they apply to a representative full recycle reprocessing flowsheet. Many of the waste management technologies discussed also apply to other potential flowsheets that involve reprocessing. These applications are occasionally discussed where the data are more readily available. The report summarizes the waste arising from aqueous reprocessing of a typical light-water reactor (LWR) fuel to separate actinides for use in fabricating metal sodium fast reactor (SFR) fuel and from electrochemical reprocessing of the metal SFR fuel to separate actinides for recycle back into the SFR in the form of metal fuel. The primary streams considered and the recommended waste forms include; Tritium in low-water cement in high integrity containers (HICs); Iodine-129: As a reference case, a glass composite material (GCM) formed by the encapsulation of the silver Mordenite (AgZ) getter material in a low-temperature glass is assumed. A number of alternatives with distinct advantages are also considered including a fused silica waste form

  20. Develop of a model to minimize and to treat waste coming from the chemical laboratories

    International Nuclear Information System (INIS)

    They were investigated and proposed alternative of minimization and treatment of waste organic type coming from chemical laboratories, considering as alternative the disposition for the drainage, the chemical treatment of the waste, the disposition in sanitary fillers, the creation of a cellar to recycle material, the incineration, the distillation and the possibility to establish an agreement with the company Cements INCSA to discard the materials in the oven to cements of this enterprise. the methodology had as first stage the summary of information about the production of residuals for Investigation Center or Academic Unit. For this they were considered the laboratories of investigation of the CICA, CELEQ, CIPRONA, LAYAFA, and the laboratories of teaching of the sections of Organic Chemistry, Inorganic Chemistry, Physicochemical, Pharmacognosy, Drugs Analysis, Physicopharmacy, Histology and Physiology. Additionally, you considers the office of purveyor of the Microbiology School. Subsequently one carries out an analysis of costs to determine which waste constituted most of the waste generated by the University, as for cost and volume. Then, they were carried out classifications of the materials according to chemical approaches, classification of the NFPA and for data of combustion heats. Once carried out this classification and established the current situation of the laboratories considered as for handling and treatment of waste, they proceeded to evaluate and select treatment options and disposition of waste considering advantages and disadvantages as for implementation possibility and cost stops this way a minimization model and treatment that it can be implemented in the University to settle down

  1. Grout treatment facility dangerous waste permit application

    International Nuclear Information System (INIS)

    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 liquid waste with cementitious dry materials. The resulting grout is cast within underground vaults. This report on the GTF contains information on the following: Vault design, run-on/run-off control design, and asphalt compatibility with 90-degree celsius double-shell slurry feed

  2. Economic and environmental optimization of waste treatment

    International Nuclear Information System (INIS)

    Highlights: • Optimizing waste treatment by incorporating LCA methodology. • Applying different objectives (minimizing costs or GHG emissions). • Prioritizing multiple objectives given different weights. • Optimum depends on objective and assumed displaced electricity production. - Abstract: This article presents the new systems engineering optimization model, OptiWaste, which incorporates a life cycle assessment (LCA) methodology and captures important characteristics of waste management systems. As part of the optimization, the model identifies the most attractive waste management options. The model renders it possible to apply different optimization objectives such as minimizing costs or greenhouse gas emissions or to prioritize several objectives given different weights. A simple illustrative case is analysed, covering alternative treatments of one tonne of residual household waste: incineration of the full amount or sorting out organic waste for biogas production for either combined heat and power generation or as fuel in vehicles. The case study illustrates that the optimal solution depends on the objective and assumptions regarding the background system – illustrated with different assumptions regarding displaced electricity production. The article shows that it is feasible to combine LCA methodology with optimization. Furthermore, it highlights the need for including the integrated waste and energy system into the model

  3. Economic and environmental optimization of waste treatment

    Energy Technology Data Exchange (ETDEWEB)

    Münster, M. [System Analysis Department, DTU Management Engineering, Technical University of Denmark, Frederiksborgvej 399, 4000 Roskilde (Denmark); Ravn, H. [RAM-løse edb, Æblevangen 55, 2765 Smørum (Denmark); Hedegaard, K.; Juul, N. [System Analysis Department, DTU Management Engineering, Technical University of Denmark, Frederiksborgvej 399, 4000 Roskilde (Denmark); Ljunggren Söderman, M. [IVL Swedish Environmental Research Institute, Box 53021, SE-40014 Gothenburg (Sweden); Chalmers University of Technology, SE-412 96 Gothenburg (Sweden)

    2015-04-15

    Highlights: • Optimizing waste treatment by incorporating LCA methodology. • Applying different objectives (minimizing costs or GHG emissions). • Prioritizing multiple objectives given different weights. • Optimum depends on objective and assumed displaced electricity production. - Abstract: This article presents the new systems engineering optimization model, OptiWaste, which incorporates a life cycle assessment (LCA) methodology and captures important characteristics of waste management systems. As part of the optimization, the model identifies the most attractive waste management options. The model renders it possible to apply different optimization objectives such as minimizing costs or greenhouse gas emissions or to prioritize several objectives given different weights. A simple illustrative case is analysed, covering alternative treatments of one tonne of residual household waste: incineration of the full amount or sorting out organic waste for biogas production for either combined heat and power generation or as fuel in vehicles. The case study illustrates that the optimal solution depends on the objective and assumptions regarding the background system – illustrated with different assumptions regarding displaced electricity production. The article shows that it is feasible to combine LCA methodology with optimization. Furthermore, it highlights the need for including the integrated waste and energy system into the model.

  4. Offgas treatment for radioactive waste incinerators

    International Nuclear Information System (INIS)

    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

  5. Waste characterization for the F/H Effluent Treatment Facility in support of waste certification

    International Nuclear Information System (INIS)

    The Waste Acceptance Criteria (WAC) procedures define the rules concerning packages of solid Low Level Waste (LLW) that are sent to the E-area vaults (EAV). The WACs tabulate the quantities of 22 radionuclides that require manifesting in waste packages destined for each type of vault. These quantities are called the Package Administrative Criteria (PAC). If a waste package exceeds the PAC for any radionuclide in a given vault, then specific permission is needed to send to that vault. To avoid reporting insignificant quantities of the 22 listed radionuclides, the WAC defines the Minimum Reportable Quantity (MRQ) of each radionuclide as 1/1000th of the PAC. If a waste package contains less than the MRQ of a particular radionuclide, then the package's manifest will list that radionuclide as zero. At least one radionuclide has to be reported, even if all are below the MRQ. The WAC requires that the waste no be ''hazardous'' as defined by SCDHEC/EPA regulations and also lists several miscellaneous physical/chemical requirements for the packages. This report evaluates the solid wastes generated within the F/H Effluent Treatment Facility (ETF) for potential impacts on waste certification

  6. 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.

  7. Thermochemical treatment of radioactive waste by using powder metal fuels

    International Nuclear Information System (INIS)

    Full text: A thermochemical approach was suggested for treating and conditioning specific streams of radioactive wastes for example spent ion exchange resins, mixed, organic or chlorine-containing radioactive waste as well as in order to decontaminate heavily contaminated surfaces. Conventional treatment methods of such waste encounters serious problems concerning complete destruction of organic molecules and possible emissions of radionuclides, heavy metals and chemically hazardous species or in case of contaminated materials - complete removal of contamination from surface. The thermochemical treatment of radioactive waste uses powdered metal fuels (PMF) that are specifically formulated for the waste composition and react chemically with the waste components. Thermochemical treatment technologies use the energy of chemical reactions in the mixture of waste with PMF to sustain both decomposition and synthesis processes as well as processes of isomorphic substitutions of hazardous elements into stable mineral forms. The composition of the PMF is designed in such a way as to minimise the release of hazardous components and radionuclides in the off gas and to confine the contaminants in the mineral or glass like final products. The thermochemical procedures allow decomposition of organic matter and capturing hazardous radionuclides and chemical species simultaneously. Thermochemical treatment technologies are very efficient, easy to apply, they have low capital investment and can be used both at large and small facilities. An advantage of thermochemical technologies is their autonomy. Thus these technologies can be successfully applied in order to treat small amount of waste without usage of complex and expensive equipment. They can be used also in emergency situations. Currently the thermochemical treatment technologies were developed and demonstrated to be feasible as follows: 1. Decontamination of surfaces; 2. Processing of organic waste; 3. Vitrification of dusty

  8. Method for fractional solid-waste sampling and chemical analysis

    DEFF Research Database (Denmark)

    Riber, Christian; Rodushkin, I.; Spliid, Henrik;

    2007-01-01

    Chemical characterization of solid waste is a demanding task due to the heterogeneity of the waste. This article describes how 45 material fractions hand-sorted from Danish household waste were subsampled and prepared for chemical analysis of 61 substances. All material fractions were subject to...... repeated particle-size reduction, mixing, and mass reduction until a sufficiently small but representative sample was obtained for digestion prior to chemical analysis. The waste-fraction samples were digested according to their properties for maximum recognition of all the studied substances. By combining...... four subsampling methods and five digestion methods, paying attention to the heterogeneity and the material characteristics of the waste fractions, it was possible to determine 61 substances with low detection limits, reasonable variance, and high accuracy. For most of the substances of environmental...

  9. Hanford Waste Treatment Complex Foundation for Success

    International Nuclear Information System (INIS)

    The mission of the U.S. Department of Energy (DOE) Office of River Protection (ORP) River Protection Project (RPP) is to build and operate a Waste Treatment Complex to complete the cleanup of the Hanford Site's highly radioactive tank waste. As directed by Congress in Section 3139 of the Strom Thurmond National Defense Authorization Act for Fiscal Year 1999, DOE established ORP at the Hanford Site in eastern Washington State to manage RPP (formerly the Tank Waste Remediation System). This is DOE's largest and most complex environmental cleanup project. ORP is responsible for safe storage, retrieval, treatment, and disposal of 53 million gallons of highly toxic, high-level radioactive waste stored in 177 underground tanks located within seven miles of the Columbia River. One hundred forty-nine of these tanks have a single steel liner inside the concrete tanks and are decades beyond their design life. Sixty-seven have leaked an estimated one million gallons of waste into the soil. Some of this waste has reached the groundwater, threatening the Columbia River. It is urgent that this waste be vitrified (turned to glass) and stored or disposed of in a more secure location before more leaks occur and before tanks and infrastructure deteriorate to the point where the cost and schedule for cleanup becomes prohibitive. This cleanup must occur in an environmentally sound, safe, and cost-efficient manner. The cleanup also must comply with the comprehensive cleanup and compliance agreement among DOE, the U.S. Environmental Protection Agency, and the Washington State Department of Ecology, signed on May 15, 1989. The Hanford Federal Facility Agreement and Consent Order, or Tri-Party Agreement, is an agreement for achieving compliance with the Comprehensive Environmental Response Compensation and Liability Act of 1980 remedial action provisions and with the Resource Conservation and Recover Act of 1976 treatment, storage, and disposal unit regulations and corrective action

  10. Chemical composition of material fractions in Danish household waste

    DEFF Research Database (Denmark)

    Riber, Christian; Petersen, Claus; Christensen, Thomas Højlund

    2009-01-01

    The chemical composition of Danish household waste was determined by two approaches: a direct method where the chemical composition (61 substances) of 48 material fractions was determined after hand sorting of about 20 tonnes of waste collected from 2200 households; and an indirect method where...... batches of 80-1200 tonnes of unsorted household waste was incinerated and the content of the waste determined from the content of the outputs from the incinerator. The indirect method is believed to better represent the small but highly contaminated material fractions (e,g., batteries) than the direct...... method, because of the larger quantities included and the more homogenous material to sample from. Differences between the direct and the direct methods led to corrections in the of heavy metal concentration of a few fractions. The majority of the energy content of the waste originates from organic waste...

  11. Equipment for radioactive waste treatment

    International Nuclear Information System (INIS)

    The equipment is used for the concentration, calcination, possibly denitration of high, medium and low level radioactive wastes. It is provided with a heated body and driving mechanism. In the heated body there is a horizontal or oblique shaft with a system of vanes, possibly with a screw. On one side of the heated body there is an opening for drop and vapour extraction. A lead screen may be placed in this area, opposite to it a shielding and between them a deactivation slot. The advantage of the discovery is in that the shaft including the bearings are placed outside of the working part of the equipment. (M.D.)

  12. Grout treatment facility dangerous waste permit application

    International Nuclear Information System (INIS)

    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

  13. Inorganic anion exchangers for the treatment of radioactive wastes

    International Nuclear Information System (INIS)

    Inorganic anion exchangers are evaluated for Tc, I and S isotope removal from aqueous nuclear waste streams. Chemical, thermal, and radiation stabilities were examined. Selected exchangers were examined in detail for their selectivities, kinetics and mechanism of the sorption process (especially in NO3-, OH- and BO3- environments). Cement encapsulation and leaching experiments were made on the exchangers showing most promise for 'radwaste' treatment. (author)

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

    International Nuclear Information System (INIS)

    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

  15. WASTE TREATMENT BUILDING VENTILATION SYSTEM DESCRIPTION DOCUMENT

    Energy Technology Data Exchange (ETDEWEB)

    P.A. Kumar

    2000-06-22

    The Waste Treatment Building Ventilation System provides heating, ventilation, and air conditioning (HVAC) for the contaminated, potentially contaminated, and uncontaminated areas of the Monitored Geologic Repository's (MGR) Waste Treatment Building (WTB). In the uncontaminated areas, the non-confinement area ventilation system maintains the proper environmental conditions for equipment operation and personnel comfort. In the contaminated and potentially contaminated areas, in addition to maintaining the proper environmental conditions for personnel comfort and equipment operation, the contamination confinement area ventilation system directs potentially contaminated air away from personnel in the WTB and confines the contamination within high-efficiency particulate air (HEPA) filtration units. The contamination confinement area ventilation system creates airflow paths and pressure zones to minimize the potential for spreading contamination with the building. The contamination confinement ventilation system also protects the environment and the public by limiting airborne releases of radioactive or other hazardous contaminants from the WTB. The Waste Treatment Building Ventilation System confines the radioactive and hazardous material within the building such that the release rates comply with regulatory limits, The system design, operations, and maintenance activities incorporate ALARA (as low as is reasonably achievable) principles to maintain personnel radiation doses to all occupational workers below regulatory limits and as low as is reasonably achievable. The system provides status of important system parameters and equipment operation, and provides audible and/or visual indication of off-normal conditions and equipment failures. The Waste Treatment Building Ventilation System interfaces with the Waste Treatment Building System by being located in the WTB, and by maintaining specific pressure, temperature, and humidity environments within the building

  16. INTEGRATED WASTE MANAGEMENT - CONTRIBUTION TO SUSTAINABLE DEVELOPMENT IN CHEMICAL INDUSTRY

    OpenAIRE

    Hansotto Drotloff

    2012-01-01

    Facing a more and more globalized economy and growing population worldwide,chemical industry in Germany has identified sustainable development as a key factor ofeconomic success. An integrated resource management must include waste besidesmaterials and energy. This requires that waste is understood as a potential value and notas a burden. In the present paper, strategies of modern waste management in syntheticresins production will be discussed. The aim of this paper is to demonstrate how the...

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

    International Nuclear Information System (INIS)

    To centralize treatment, storage, and staging areas for hazardous wastes, Los Alamos National Laboratory has designed a 12,000-ft2 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

  18. CHEMICAL AND BIOLOGICAL CHARACTERIZATION OF LEACHATES FROM COAL SOLID WASTES

    Science.gov (United States)

    The report gives results of the chemical and mineralogical characterization of coal solid wastes. The wastes included three Lurgi gasification ashes, mineral residues from the SRC-1 and H-Coal liquefaction processes, two chars, two coal-cleaning residues, and a fly-ash-and-water-...

  19. Waste water treatment in Bukkerup (VB)

    DEFF Research Database (Denmark)

    Thomsen, Rikke; Overgaard, Morten; Jørgensen, Michael Søgaard

    1999-01-01

    In connection to the new waste water plan of Tølløse municipal the technical and environmental board has suggested that Bukkerup get a sewer system which brings the waste water to the treatment plant for Tysinge. All though the residents would like to list alternative suggestions which improve the...... local water environment but is still competitive.In this report the alternatives are listed, e.i. root system plants, sand filters and mini treatment plants.The conclusion is that root system plants and a combination of root system plants and sand filters are better that the sewer system....

  20. Chemical characterization of SRP waste tank sludges and supernates

    International Nuclear Information System (INIS)

    Most high-level liquid wastes at the Savannah River Plant (SRP) are byproducts from plutonium and enriched uranium recovery processes. The high-level liquid wastes generated by these separations processes are stored in large, underground, carbon-steel tanks. The liquid wastes consist of: supernate (an aqueous solution containing sodium, nitrate, nitrite, hydroxyl, and aluminate ions), sludge (a gelatinous material containing insoluble components of the waste, such as ferric and aluminum hydroxides, and mercuric and manganese oxides), and salt cake (crystals, such as sodium nitrate, formed by evaporation of water from supernate). Analyses of SRP wastes by laser-Raman spectrometry, atomic absorption spectrometry, spark-source mass spectrometry, neutron activation analysis, colorimetry, ion chromatography, and various other wet-chemical and radiochemical methods are discussed. These analyses are useful in studies of waste tank corrosion and of forms for long-term waste storage

  1. Chemical species of plutonium in Hanford radioactive tank waste

    Energy Technology Data Exchange (ETDEWEB)

    Barney, G.S.

    1997-10-22

    Large quantities of radioactive wastes have been generated at the Hanford Site over its operating life. The wastes with the highest activities are stored underground in 177 large (mostly one million gallon volume) concrete tanks with steel liners. The wastes contain processing chemicals, cladding chemicals, fission products, and actinides that were neutralized to a basic pH before addition to the tanks to prevent corrosion of the steel liners. Because the mission of the Hanford Site was to provide plutonium for defense purposes, the amount of plutonium lost to the wastes was relatively small. The best estimate of the amount of plutonium lost to all the waste tanks is about 500 kg. Given uncertainties in the measurements, some estimates are as high as 1,000 kg (Roetman et al. 1994). The wastes generally consist of (1) a sludge layer generated by precipitation of dissolved metals from aqueous wastes solutions during neutralization with sodium hydroxide, (2) a salt cake layer formed by crystallization of salts after evaporation of the supernate solution, and (3) an aqueous supernate solution that exists as a separate layer or as liquid contained in cavities between sludge or salt cake particles. The identity of chemical species of plutonium in these wastes will allow a better understanding of the behavior of the plutonium during storage in tanks, retrieval of the wastes, and processing of the wastes. Plutonium chemistry in the wastes is important to criticality and environmental concerns, and in processing the wastes for final disposal. Plutonium has been found to exist mainly in the sludge layers of the tanks along with other precipitated metal hydrous oxides. This is expected due to its low solubility in basic aqueous solutions. Tank supernate solutions do not contain high concentrations of plutonium even though some tanks contain high concentrations of complexing agents. The solutions also contain significant concentrations of hydroxide which competes with other

  2. Chemical species of plutonium in Hanford radioactive tank waste

    International Nuclear Information System (INIS)

    Large quantities of radioactive wastes have been generated at the Hanford Site over its operating life. The wastes with the highest activities are stored underground in 177 large (mostly one million gallon volume) concrete tanks with steel liners. The wastes contain processing chemicals, cladding chemicals, fission products, and actinides that were neutralized to a basic pH before addition to the tanks to prevent corrosion of the steel liners. Because the mission of the Hanford Site was to provide plutonium for defense purposes, the amount of plutonium lost to the wastes was relatively small. The best estimate of the amount of plutonium lost to all the waste tanks is about 500 kg. Given uncertainties in the measurements, some estimates are as high as 1,000 kg (Roetman et al. 1994). The wastes generally consist of (1) a sludge layer generated by precipitation of dissolved metals from aqueous wastes solutions during neutralization with sodium hydroxide, (2) a salt cake layer formed by crystallization of salts after evaporation of the supernate solution, and (3) an aqueous supernate solution that exists as a separate layer or as liquid contained in cavities between sludge or salt cake particles. The identity of chemical species of plutonium in these wastes will allow a better understanding of the behavior of the plutonium during storage in tanks, retrieval of the wastes, and processing of the wastes. Plutonium chemistry in the wastes is important to criticality and environmental concerns, and in processing the wastes for final disposal. Plutonium has been found to exist mainly in the sludge layers of the tanks along with other precipitated metal hydrous oxides. This is expected due to its low solubility in basic aqueous solutions. Tank supernate solutions do not contain high concentrations of plutonium even though some tanks contain high concentrations of complexing agents. The solutions also contain significant concentrations of hydroxide which competes with other

  3. Plasma technology for treatment of waste

    International Nuclear Information System (INIS)

    Meeting goals for waste cleanup will require new technology with improved environmental attractiveness and reduced cost. Plasma technology appears promising because of the high degree of controllability; capability to process waste without the adverse effects of combustion; and a very wide temperature range of operation. At the Plasma Fusion Center at the Massachusetts Institute of Technology, a range of plasma technologies are being investigated. 'Hot' thermal plasmas produced by DC arc technology are being examined for treatment of solid waste. In conjunction with this activity, new diagnostics are being developed for monitoring arc furnace operating parameters and gaseous emissions. Electron-beam generated plasma technology is being investigated as a means of producing non-thermal 'cold' plasmas for selective processing of dilute concentrations of gaseous waste. (author). 4 figs., 5 refs

  4. Economic and environmental optimization of waste treatment

    DEFF Research Database (Denmark)

    Münster, Marie; Ravn, Hans; Hedegaard, Karsten;

    2015-01-01

    This article presents the new systems engineering optimization model, OptiWaste, which incorporates a life cycle assessment (LCA) methodology and captures important characteristics of waste management systems. As part of the optimization, the model identifies the most attractive waste management...... with different assumptions regarding displaced electricity production. The article shows that it is feasible to combine LCA methodology with optimization. Furthermore, it highlights the need for including the integrated waste and energy system into the model. © 2014 Elsevier Ltd. All rights reserved....... options. The model renders it possible to apply different optimization objectives such as minimizing costs or greenhouse gas emissions or to prioritize several objectives given different weights. A simple illustrative case is analysed, covering alternative treatments of one tonne of residual household...

  5. Physical and chemical characterization of waste wood derived biochars.

    Science.gov (United States)

    Yargicoglu, Erin N; Sadasivam, Bala Yamini; Reddy, Krishna R; Spokas, Kurt

    2015-02-01

    Biochar, a solid byproduct generated during waste biomass pyrolysis or gasification in the absence (or near-absence) of oxygen, has recently garnered interest for both agricultural and environmental management purposes owing to its unique physicochemical properties. Favorable properties of biochar include its high surface area and porosity, and ability to adsorb a variety of compounds, including nutrients, organic contaminants, and some gases. Physical and chemical properties of biochars are dictated by the feedstock and production processes (pyrolysis or gasification temperature, conversion technology and pre- and post-treatment processes, if any), which vary widely across commercially produced biochars. In this study, several commercially available biochars derived from waste wood are characterized for physical and chemical properties that can signify their relevant environmental applications. Parameters characterized include: physical properties (particle size distribution, specific gravity, density, porosity, surface area), hydraulic properties (hydraulic conductivity and water holding capacity), and chemical and electrochemical properties (organic matter and organic carbon contents, pH, oxidation-reduction potential and electrical conductivity, zeta potential, carbon, nitrogen and hydrogen (CHN) elemental composition, polycyclic aromatic hydrocarbons (PAHs), heavy metals, and leachable PAHs and heavy metals). A wide range of fixed carbon (0-47.8%), volatile matter (28-74.1%), and ash contents (1.5-65.7%) were observed among tested biochars. A high variability in surface area (0.1-155.1g/m(2)) and PAH and heavy metal contents of the solid phase among commercially available biochars was also observed (0.7-83 mg kg(-1)), underscoring the importance of pre-screening biochars prior to application. Production conditions appear to dictate PAH content--with the highest PAHs observed in biochar produced via fast pyrolysis and lowest among the gasification

  6. Efeito dos tratamentos físicos e químicos no resíduo de lixadeira do algodão Effects of physical and chemical treatments in cotton textile mill waste

    Directory of Open Access Journals (Sweden)

    Juliana dos Santos

    2004-08-01

    Full Text Available O experimento foi conduzido no Departamento de Zootecnia (UFLA e no Laboratório de Alimentos (UNIFENAS, com o objetivo de avaliar o valor nutritivo do resíduo de lixadeira do algodão pela composição bromatológica (PB, FDN, FDA e pela degradabilidade da MS e da FDN. Os tratamentos foram: T1 - in natura (IN; T2 - pressão e vapor (127ºC/1,5 kgf/cm²/35min; PV; T3 - 4% hidróxido de sódio (por 24 horas; NaOH; T4 - 3% uréia (por 28 dias; U; T5 - 4% NaOH + 3% uréia (NaOH/U; T6 - PV + 4% NaOH (PV/NaOH; T7 - PV + 3% uréia (PV/U. Pelos resultados referentes à composição química, conclui-se que os tratamentos associados foram mais eficientes em aumentar o valor nutritivo do resíduo, sendo o tratamento NaOH/U o que apresentou os melhores resultados para PB, FDN e FDA. Os maiores valores para a degradabilidade efetiva da MS foram verificados para o resíduo tratado com PV, U, NaOH/U, PV/NaOH, PV/U, que também apresentaram maior fração solúvel e menor fração insolúvel potencialmente degradável (b. Os tratamentos U, PV/NaOH e PV/U apresentaram as maiores de degradabilidade efetiva da FDN e maior fração solúvel. Os tratamentos associados aumentaram a degradabilidade e o valor nutritivo do resíduo de lixadeira do algodão.The experiment was carried out at the Department of Animal Science of the Universidade Federal de Lavras and at the Food Laboratory at the Universidade José do Rosário Vellano (UNIFENAS, with the objective to evaluate the nutritive value of cotton textile mill waste using chemical composition (DM, CP, NDF, ADF and ruminal degradability of the dry matter and NDF. The treatments were: T1 - in natura residue (IN; T2 - residue submitted to the pressure and steam treated (127ºC/1,5 kgf/cm²/35"; PS; T3 - 4% sodium hydroxide treated residue (four 24 hours; NaOH; T4 - 3% urea treated residue (for 28 days; U; T5 - 4% NaOH +3% urea treated residue (NaOH/U; T6 - pressure and steam + 4% NaOH treated residue (PS/NaOH; T7

  7. Alternative Waste Forms for Electro-Chemical Salt Waste

    Energy Technology Data Exchange (ETDEWEB)

    Crum, Jarrod V.; Sundaram, S. K.; Riley, Brian J.; Matyas, Josef; Arreguin, Shelly A.; Vienna, John D.

    2009-10-28

    This study was undertaken to examine alternate crystalline (ceramic/mineral) and glass waste forms for immobilizing spent salt from the Advanced Fuel Cycle Initiative (AFCI) electrochemical separations process. The AFCI is a program sponsored by U.S. Department of Energy (DOE) to develop and demonstrate a process for recycling spent nuclear fuel (SNF). The electrochemical process is a molten salt process for the reprocessing of spent nuclear fuel in an electrorefiner and generates spent salt that is contaminated with alkali, alkaline earths, and lanthanide fission products (FP) that must either be cleaned of fission products or eventually replaced with new salt to maintain separations efficiency. Currently, these spent salts are mixed with zeolite to form sodalite in a glass-bonded waste form. The focus of this study was to investigate alternate waste forms to immobilize spent salt. On a mole basis, the spent salt is dominated by alkali and Cl with minor amounts of alkaline earth and lanthanides. In the study reported here, we made an effort to explore glass systems that are more compatible with Cl and have not been previously considered for use as waste forms. In addition, alternate methods were explored with the hope of finding a way to produce a sodalite that is more accepting of as many FP present in the spent salt as possible. This study was done to investigate two different options: (1) alternate glass families that incorporate increased concentrations of Cl; and (2) alternate methods to produce a mineral waste form.

  8. ENGINEERING BULLETIN: CHEMICAL OXIDATION TREATMENT

    Science.gov (United States)

    Oxidation destroys hazardous contaminants by chemically converting them to nonhazardous or less toxic compounds that are ideally more stable, less mobile, and/or inert. However, under some conditions, other hazardous compounds may be formed. The oxidizing agents most commonly use...

  9. Radioactive waste treatment technology at Czech nuclear power plants

    International Nuclear Information System (INIS)

    This presentation describes the main technologies for the treatment and conditioning of radioactive wastes at Czech nuclear power plants. The main technologies are bituminisation for liquid radioactive wastes and supercompaction for solid radioactive wastes. (author)

  10. Methods Used in Urban Waste Treatment

    Directory of Open Access Journals (Sweden)

    OROIAN I.

    2010-12-01

    Full Text Available The paper presents the main options aiming the treatment of urban waste consisting mainly of the household andthose resulting from industrial activities, acordin to the present EU legislation. The aspects of the two major types ofwaste treatment, mechanical biological treatment and incineration respectively are described. Distinction is madebetween mechanical and biological treatment of aerobic and anaerobic issues being addressed and biological dryingprocess. The result of these processes is reflected in obtaining products that can be used as soil improvers. With regardto incineration, the basic components of industrial installations for the purpose, and usability of products resulting fromtheir processing, most often, various types of solid fuel are presented. The paper also highlights the importance of thesetreatments in efficient waste management planning.

  11. Evaluation of nanofiltration membranes for treatment of liquid radioactive waste

    International Nuclear Information System (INIS)

    The physicochemical behavior of two nanofiltration membranes for treatment of a low-level radioactive liquid waste (carbonated water) was investigated through static, dynamic and concentration tests. This waste was produced during conversion of uranium hexafluoride (UF6) to uranium dioxide (UO2) in the cycle of nuclear fuel. This waste contains about 7.0 mg L-1 of uranium and cannot be discarded to the environment without an adequate treatment. In static tests membrane samples were immersed in the waste for 24 to 5000 h. Their transport properties (hydraulic permeability, permeate flux, sulfate and chloride ions rejection) were evaluated before and after immersion in the waste using a permeation flux front system under 0.5 MPa. The selective layer (polyamide) was characterized by zeta potential, contact angle, scanning electron microscopy for field emission, atomic force microscopy, infrared spectroscopy, x-ray fluorescence and thermogravimetric analysis before and after static tests. In dynamic tests the waste was permeated under 0.5 MPa, and the membranes showed rejection to uranium above 85% were obtained. The short-term static tests (24-72 h) showed that the selective layer and surface charge of the membranes were not chemical changed, according infrared spectra data. After 5000 h a coating layer was released from the membranes, poly(vinyl alcohol), PVA. After this loss the rejection for uranium decreased. Permeation and concentration of the waste were carried out in permeation flux tangential system under 1.5 MPa. The rejection of uranium was around 90% for permeation tests. In concentration tests the permeated was collected continuously until about 80% reduction of the feed volume. The rejection of uranium was of the 97%. The nanofiltration membranes tested were efficient to concentrate the uranium from the waste. (author)

  12. DWTF [decontamination and waste treatment facilities] assessment

    International Nuclear Information System (INIS)

    The purpose of this study has been to evaluate the adequacy of present and proposed decontamination and waste treatment facilities (DWTF) at LLNL, to determine the cost effectiveness for proposed improvements, and possible alternatives for accomplishing these improvements. To the extent possible, we have also looked at some of the proposed environmental compliance and cleanup (ECC) projects

  13. Controlled air incineration of hazardous chemical and mixed waste at Los Alamos

    International Nuclear Information System (INIS)

    The Los Alamos National Laboratory (LANL) Controlled Air Incineration (CAI) system, originally developed for transuranic (TRU) waste volume reduction studies, is currently being qualified for hazardous chemical and mixed waste treatment under provisions of the Resource Conservation and Recovery Act (RCRA). The objective is to obtain a permanent RCRA Part B permit for thermal disposal of hazardous and mixed wastes generated by LANL. Constructed in the mid-1970s as a demonstration project for incineration of TRU solid wastes, the CAI process was substantially modified and tested in 1980-1983 for acceptance of both liquid and solid hazardous chemicals. Successful demonstration of TRU solid waste processing objectives in 1979 and later chemical waste incineration studies have been documented in several publications. In 1984, the LANL CAI became the first US Dept. of Energy (DOE) incinerator to be permitted for polychlorinated biphenyl disposal under the Toxic Substances Control Act. Following establishment of Environmental Protection Agency (EPA) jurisdiction over DOE chemical waste management in 1984, LANL sought and was granted interim status for the CAI and applied for a trial burn permit in the overall laboratory RCRA Part B application. A trial burn and final report have been completed; results have been submitted to EPA and the New Mexico Environmental Improvement Division. This paper provides an overview of trial burn planning and results together with the operational status of LANL's CAI

  14. Health Aspects of the Disposal of Waste Chemicals.

    Science.gov (United States)

    Grisham, Joe W., Ed.

    Intended to be a source of information on the nature and significance of health effects related to chemical disposal, this document is the final report of the Executive Scientific Panel on Health Aspects of the Disposal of Waste Chemicals. The panel, which was organized by the Universities Associated for Research and Education in Pathology…

  15. Classification of toxic chemical-waste streams from nuclear reactors

    International Nuclear Information System (INIS)

    The radiological and chemical constituents from light water reactors are identified, the methodology for comparing the hazards of various chemicals quantitatively with those of radioactive materials is presented, and the possible management basis of low-level waste (LLW) is considered

  16. Grout treatment facility dangerous waste permit application

    International Nuclear Information System (INIS)

    The long-term performance of the grout disposal system for Phosphate/Sulfate Waste (PSW) was analyzed. PSW is a low-level liquid generated by activities associated with N Reactor operations. The waste will be mixed with dry solids and permanently disposed of as a cementitious grout in sub-surface concrete vaults at Hanford's 200-East Area. Two categories of scenarios were analyzed that could cause humans to be exposed to radionuclides and chemicals from the grouted waste: contaminated groundwater and direct intrusion. In the groundwater scenario, contaminants are released from the buried grout monoliths, then eventually transported via the groundwater to the Columbia River. As modeled, the contaminants are assumed to leach out of the monoliths at a constant rate over a 10,000-year period. The other category of exposure involves intruders who inadvertently contact the waste directly, either by drilling, excavating, or gardening. Long-term impacts that could result from disposal of PSW grout were expressed in terms of incremental increases of (1) chemical concentrations in the groundwater and surface waters, and (2) radiation doses. None of the calculated impacts exceeded the corresponding regulatory limits set by Washington State, Department of Energy, or the Nuclear Regulatory Commission

  17. Applicability of federal and state hazardous waste regulatory programs to waste chemical weapons and chemical warfare agents.; TOPICAL

    International Nuclear Information System (INIS)

    This report reviews federal and state hazardous waste regulatory programs that govern the management of chemical weapons or chemical warfare agents. It addresses state programs in the eight states with chemical weapon storage facilities managed by the U.S. Army: Alabama, Arkansas, Colorado, Indiana, Kentucky, Maryland, Oregon, and Utah. It also includes discussions on 32 additional states or jurisdictions with known or suspected chemical weapons or chemical warfare agent presence (e.g., disposal sites containing chemical agent identification sets): Alaska, Arizona, California, Florida, Georgia, Hawaii, Idaho, Illinois, Iowa, Kansas, Louisiana, Massachusetts, Michigan, Mississippi, Missouri, Nebraska, Nevada, New Jersey, New Mexico, New York, North Carolina, Ohio, Pennsylvania, South Carolina, South Dakota, Tennessee, Texas, the U.S. Virgin Islands, Virginia, Washington, Washington, D.C., and Wyoming. Resource Conservation and Recovery Act (RCRA) hazardous waste programs are reviewed to determine whether chemical weapons or chemical warfare agents are listed hazardous wastes or otherwise defined or identified as hazardous wastes. Because the U.S. Environmental Protection Agency (EPA) military munitions rule specifically addresses the management of chemical munitions, this report also indicates whether a state has adopted the rule and whether the resulting state regulations have been authorized by EPA. Many states have adopted parts or all of the EPA munitions rule but have not yet received authorization from EPA to implement the rule. In these cases, the states may enforce the adopted munitions rule provisions under state law, but these provisions are not federally enforceable

  18. Chemical and mechanical performance properties for various final waste forms -- PSPI scoping study

    Energy Technology Data Exchange (ETDEWEB)

    Farnsworth, R.K.; Larsen, E.D.; Sears, J.W.; Eddy, T.L.; Anderson, G.L.

    1996-09-01

    The US DOE is obtaining data on the performance properties of the various final waste forms that may be chosen as primary treatment products for the alpha-contaminated low-level and transuranic waste at the INEL`s Transuranic Storage Area. This report collects and compares selected properties that are key indicators of mechanical and chemical durability for Portland cement concrete, concrete formed under elevated temperature and pressure, sulfur polymer cement, borosilicate glass, and various forms of alumino-silicate glass, including in situ vitrification glass and various compositions of iron-enriched basalt (IEB) and iron-enriched basalt IV (IEB4). Compressive strength and impact resistance properties were used as performance indicators in comparative evaluation of the mechanical durability of each waste form, while various leachability data were used in comparative evaluation of each waste form`s chemical durability. The vitrified waste forms were generally more durable than the non-vitrified waste forms, with the iron-enriched alumino-silicate glasses and glass/ceramics exhibiting the most favorable chemical and mechanical durabilities. It appears that the addition of zirconia and titania to IEB (forming IEB4) increases the leach resistance of the lanthanides. The large compositional ranges for IEB and IEB4 more easily accommodate the compositions of the waste stored at the INEL than does the composition of borosilicate glass. It appears, however, that the large potential variation in IEB and IEB4 compositions resulting from differing waste feed compositions can impact waste form durability. Further work is needed to determine the range of waste stream feed compositions and rates of waste form cooling that will result in acceptable and optimized IEB or IEB4 waste form performance. 43 refs.

  19. Grout treatment facility dangerous waste permit application

    International Nuclear Information System (INIS)

    This section briefly describes the Hanford Site, provides a general description of the site operations and administration, provides an overview of the contents of this Grout Treatment Facility (GTF) Permit Application, and gives a list of acronyms and abbreviations used in the document. The decision was made to use the checklist as a locator reference instead of using the checklist section numbers as paragraph section numbers because several different types of waste management units, some of which are not addressed in the checklists, are part of the GTF. The GTF is a waste management unit within the Hanford Site facility. In May 1988, permit application was filed that identified the GTF as an existing facility. The GTF mixes dry cementitious solids with liquid mixed wastes (containing both dangerous and radioactive constituents) produced by Hanford Site operations. In addition to the design and operating features of the GTF that are intended to meet the requirements of dangerous waste regulations, many additional design and operating features are necessary to comply with radioactive waste management practices. The GTF design features and practices are intended to keep operational exposure to radionuclides and dangerous substances ''as low as reasonably achievable'' (ALARA) and to provide a disposal system that protects the environment for at least 10,000 yr. In some instances, ALARA practices present difficulties when complying with requirements of dangerous waste regulations

  20. Grout Treatment Facility dangerous waste permit application

    International Nuclear Information System (INIS)

    This section briefly describes the Hanford Site, provides a general description of the site operations and administration, provides an overview of the contents of this Grout Treatment Facility (GTF) Permit Application, and gives a list of acronyms and abbreviations used in the document. The decision was made to use the checklist as a locator reference instead of using the checklist section numbers as paragraph section numbers because several different types of waste management units, some of which are not addressed in the checklists, are part of the GTF. The GTF is a waste management unit within the Hanford Site facility. In May 1988, a permit application was filed that identified the GTF as an existing facility. The GTF mixes dry cementitious solids with liquid wastes (containing both dangerous and radioactive constituents) produced by Hanford Site operations. In addition to the design and operating features of the GTF that are intended to meet the requirements of dangerous waste regulations, many additional design and operating features are necessary to comply with radioactive waste management practices. The GTF design features and practices are intended to keep operational exposure to radionuclides and dangerous substances ''as low as reasonably achievable'' (ALARA) and to provide a disposal system that protects the environment for at least 10,000 yr. In some instances, ALARA practices present difficulties when complying with requirements of dangerous waste regulations. This volume contains 14 Appendices. Topics include Engineering Drawings, Maps, Roads, Toxicity Testing, and Pilot-Scale Testing

  1. Biological treatment of cokery waste water. Phase 2

    International Nuclear Information System (INIS)

    In order to develop a biotechnological process for the treatment of cokery waste water a two stage bioreactor system of each 800 l volume was designed, built up and proven for its efficiency by treating process water of two different origins. A third type of cokery waste water was treated in a lab scale bioreactor. The bacterial culture used for the process consists of a basic population for the degradation of phenol and cresols. Additionally several special strains isolated for their ability to degrade polymethylated phenols, quinoline and thiocyanate were supplemented to obtain an effective mineralization of these compounds. The successful integration of these bacterial specialists could be confirmed by detection of the respective metabolic activities (e.g. pathway-specific enzyme) in the activated sludge. -In addition to chemical analyses of the waste waters before and after biological treatment a toxicological method based on bacterial bio-luminescence inhibition was applied to characterize the clean up. - The results obtained for the DMT-process reveal that independently from the constitution of the waste water a hydraulic retention time of 6 hours for phenol degradation and 12 hours for thiocyanate degradation is necessary. So thiocyanate degradation is the rate limiting step in the process. The degree of DOC removal resulted in 80 to 90%. The degradation capacities vary from 0,3 to 2,7 kg DOC/m3 d depending on the type of waste water used for the treatment. In each case biological treatment of the waste water led to a strong reduction of water toxicity. - A feasibility study, based on the results obtained from pilot plant operation, revealed specific costs of 3 DM per kg DOC removal for a commercial plant with a capacity of 10 m3/h. (orig.). 13 refs., 13 tabs., 58 figs

  2. Treatment of liquid radioactive waste: Evaporation

    International Nuclear Information System (INIS)

    About 10.000 m3 of low active liquid waste (LLW) arise in the Nuclear Research Center Karlsruhe. Chemical contents of this liquid waste are generally not declared. Resulting from experiments carried out in the Center during the early sixties, the evaporator facility was built in 1968 for decontamination of LLW. The evaporators use vapor compression and concentrate recirculation in the evaporator sump by pumps. Since 1971 the medium active liquid waste (MLW) from the Karlsruhe Reprocessing Plant (WAK) was decontaminated in this evaporator facility, too. By this time the amount of low liquid waste (LLW) had been decontaminated without mentionable interruptions. Afterwards a lot of interruptions of operations occurred, mainly due to leakages of pumps, valves and pipes. There was also a very high radiation level for the operating personnel. As a consequence of this experience a new evaporator facility for decontamination of medium active liquid waste was built in 1974. This facility started operation in 1976. The evaporator has natural circulation and is heated by steam through a heat exchanger. (orig./RW)

  3. Treatment of gaseous wastes in vitrification plants for fission products

    International Nuclear Information System (INIS)

    In order to solidify highly active fission product solutions from reprocessing of nuclear fuels, a discontinuous as well as continuous vitrification process has been developed and the appropriate plants been put into operation in Marcoule, France. The waste gases formed in the part processes of vitrification, evaporation, calcination and melting, are described according to their origin, chemical composition and their technical, chemical, radioactive or toxic effects and the effectivity of the equipment used in both methods to purify the waste gas are demonstrated. The behaviour and treatment of the volatile ruthenium, fluorine and mercury, as well as volatile components in the molten glass which are released when filling into storage containers (Cs 137, Ce 144, Ru 106) are particularly dealt with. In a bad case, decontamination factors of 1010 are reached. (RB)

  4. RETRIEVAL & TREATMENT OF HANFORD TANK WASTE

    Energy Technology Data Exchange (ETDEWEB)

    EACKER, J.A.; SPEARS, J.A.; STURGES, M.H.; MAUSS, B.M.

    2006-01-20

    The Hanford Tank Farms contain 53 million gal of radioactive waste accumulated during over 50 years of operations. The waste is stored in 177 single-shell and double-shell tanks in the Hanford 200 Areas. The single-shell tanks were put into operation from the early 1940s through the 1960s with wastes received from several generations of processing facilities for the recovery of plutonium and uranium, and from laboratories and other ancillary facilities. The overall hanford Tank Farm system represents one of the largest nuclear legacies in the world driving towards completion of retrieval and treatment in 2028 and the associated closure activity completion by 2035. Remote operations, significant radiation/contamination levels, limited access, and old facilities are just some of the challenges faced by retrieval and treatment systems. These systems also need to be able to successfully remove 99% or more of the waste, and support waste treatment, and tank closure. The Tank Farm retrieval program has ramped up dramatically in the past three years with design, fabrication, installation, testing, and operations ongoing on over 20 of the 149 single-shell tanks. A variety of technologies are currently being pursued to retrieve different waste types, applications, and to help establish a baseline for recovery/operational efficiencies. The paper/presentation describes the current status of retrieval system design, fabrication, installation, testing, readiness, and operations, including: (1) Saltcake removal progress in Tanks S-102, S-109, and S-112 using saltcake dissolution, modified sluicing, and high pressure water lancing techniques; (2) Sludge vacuum retrieval experience from Tanks C-201, C-202, C-203, and C-204; (3) Modified sluicing experience in Tank C-103; (4) Progress on design and installation of the mobile retrieval system for sludge in potentially leaking single-shell tanks, particularly Tank C-101; and (5) Ongoing installation of various systems in the next

  5. New techniques for waste water treatment of waste treatment centers and landfills

    Energy Technology Data Exchange (ETDEWEB)

    Kaartinen, T.; Eskola, P.; Vestola, E.; Merta, E.; Mroueh, U.-M.

    2009-10-15

    In this research project new techno-economically feasible and eco-efficient techniques for waste water treatment of waste treatment centers and landfills have been developed. In this publication water quality on existing Finnish waste treatment centers and landfills has been reviewed. Examples of segregated water treatment solutions at waste treatment centers and landfills in Finland and abroad have been introduced. Experimental research concentrated on treatment of heavy metal contaminated waters. Studied techniques were biological sulphate reduction and reactive by-product materials as filter media. Both techniques yielded promising results in the treatment of heavy metal bearing waters. Next step of the research should be more precise study on the boundary conditions of the chosen techniques. Good basis for scaling up the treatment techniques from laboratory to pilot-scale plants exists after this research project. In addition an excel-based site-specifically applicable procedure for comparing water management alternatives of waste treatment centers and landfills has been developed. Applying the procedure comparisons on e.g. economy of viable water management options can be made. (orig.)

  6. Physical chemical properties of sludges of a chemical treatment of boilers feed water and ways of their utilization

    Directory of Open Access Journals (Sweden)

    T. Krasnenko

    2013-03-01

    Full Text Available Water is a necessary process for TPP power plant operation. To the power station, in the production of electricity and heat as a result of the preparation of large amounts of water to compensate for losses associated with the release of process steam for production, produce large quantities of waste water treatment - water treatment chemical sludge (WTCS.

  7. Electrical processes for liquid waste treatment

    International Nuclear Information System (INIS)

    This report describes the development of electrical techniques for the treatment of liquid waste streams. Part I is concerned with solid/liquid separation and the demonstration of the electrokinetic thickening of flocs at inorganic membranes suitable for intermediate-level wastes and electrochemical cleaning of stainless steel microfilters and graphite ultrafilters. Part II describes work on the development of electrochemical ion exchange, particularly the use of inorganic absorption media and polarity reversal to enhance system selectivity. Work on the adsorption and desorption of plutonium in acid nitrate solution at various electrode materials is also included. (author)

  8. Grout Treatment Facility dangerous waste permit application

    International Nuclear Information System (INIS)

    The Grout Treatment Facility (GTF) is an existing treatment, storage, and/or disposal (TSD) unit located in the 200 East Area and the adjacent 600 Area of the Hanford Site. The GTF mixes dry cementitious solids with liquid mixed waste (containing both dangerous and radioactive constituents) produced by Hanford Site operations. The GTF consists of the following: The 241-AP-02D and 241-AP-04D waste pump pits and transfer piping; Dry Materials Facility (DMF); Grout Disposal Facility (GDF), consisting of the disposal vault and support and monitoring equipment; and Grout Processing Facility (GPF) and Westinghouse Hanford Company on the draft Hanford Facility Dangerous Waste Permit and may not be read to conflict with those comments. The Grout Treatment Facility Dangerous Waste Permit Application consists of both a Part A and a Part B permit application. An explanation of the Part A revisions associated with this TSD unit, including the current revision, is provided at the beginning of the Part A section. The Part B consists of 15 chapters addressing the organization and content of the Part B checklist prepared by the Washington State Department of Ecology (Ecology 1987). For ease of reference, the checklist section numbers, in brackets, follow chapter headings and subheadings

  9. Treatment of low alpha activity liquid wastes

    International Nuclear Information System (INIS)

    The nuclear industry considers so big safety problems that the purifying treatment of liquid wastes must always provide for a complete recycle of the liquid strems from the production processes as regard this problem. ''Enea-Comb-Ifec'' people from saluggia, already previously engages with verifying and setting-up ''Sol-Gel'' process for the recover of uranium-plutonium solutions coming from irradiated fuel reprocessing, started an experimental work, with the assistance of ''Cnr-Irsa'' from Rome, on the applicability of the biological treatment to the purification of liquid wastes coming from the production process itself. The present technical report gives, besides a short description of the ''Sol-Gel'' process, the first results, only relating to the biological stage of the whole proposed purifyng treatment, included the final results of the experimental work, object of a contract between ''Enea-Ifec'' and ''Snam progetti'' from Fano

  10. Chemical cleaning of porous stainless steel cross-flow filter elements for nuclear waste applications

    International Nuclear Information System (INIS)

    The Waste Treatment and Immobilization Plant (WTP) currently under construction for treatment of High-Level Waste (HLW) at the Hanford Site will rely on cross-flow ultrafiltration to provide solids-liquid separation as a core part of the treatment process. To optimize process throughput, periodic chemical cleaning of the porous stainless steel filter elements has been incorporated into the design of the plant. It is currently specified that chemical cleaning with nitric acid will occur after significant irreversible membrane fouling is observed. Irreversible fouling is defined as fouling that cannot be removed by backpulsing the filter. PNNL has investigated chemical cleaning processes as part of integrated tests with HLW simulants and with actual Hanford tank wastes. To quantify the effectiveness of chemical cleaning, the residual membrane resistance after cleaning was compared against the initial membrane resistance for each test in a series of long-term fouling tests. The impact of the small amount of residual resistance in these tests could not be separated from other parameters and the historical benchmark of >1 GPM/ft2 for clean water flux was determined to be an adequate metric for chemical cleaning. Using the results from these tests, a process optimization strategy is presented suggesting that for the simulant material under test, the value of chemical cleaning may be suspect. The period of enhanced filtration may not be enough to offset the down time required for chemical cleaning, without respect to the other associated costs.

  11. Chemical cleaning of porous stainless steel cross-flow filter elements for nuclear waste applications

    Energy Technology Data Exchange (ETDEWEB)

    Billing, Justin M.; Daniel, Richard C.; Hallen, Richard T.; Schonewill, Philip P.; Shimskey, Rick W.; Peterson, Reid A.

    2011-05-10

    The Waste Treatment and Immobilization Plant (WTP) currently under construction for treatment of High-Level Waste (HLW) at the Hanford Site will rely on cross-flow ultrafiltration to provide solids-liquid separation as a core part of the treatment process. To optimize process throughput, periodic chemical cleaning of the porous stainless steel filter elements has been incorporated into the design of the plant. It is currently specified that chemical cleaning with nitric acid will occur after significant irreversible membrane fouling is observed. Irreversible fouling is defined as fouling that cannot be removed by backpulsing the filter. PNNL has investigated chemical cleaning processes as part of integrated tests with HLW simulants and with actual Hanford tank wastes. To quantify the effectiveness of chemical cleaning, the residual membrane resistance after cleaning was compared against the initial membrane resistance for each test in a series of long-term fouling tests. The impact of the small amount of residual resistance in these tests could not be separated from other parameters and the historical benchmark of >1 GPM/ft2 for clean water flux was determined to be an adequate metric for chemical cleaning. Using the results from these tests, a process optimization strategy is presented suggesting that for the simulant material under test, the value of chemical cleaning may be suspect. The period of enhanced filtration may not be enough to offset the down time required for chemical cleaning, without respect to the other associated costs.

  12. Chemical analysis of simulated high level waste glasses to support stage III sulfate solubility modeling

    International Nuclear Information System (INIS)

    The U.S. Department of Energy (DOE), Office of Environmental Management (EM) is sponsoring an international, collaborative project to develop a fundamental model for sulfate solubility in nuclear waste glass. The solubility of sulfate has a significant impact on the achievable waste loading for nuclear waste forms within the DOE complex. These wastes can contain relatively high concentrations of sulfate, which has low solubility in borosilicate glass. This is a significant issue for low-activity waste (LAW) glass and is projected to have a major impact on the Hanford Tank Waste Treatment and Immobilization Plant (WTP). Sulfate solubility has also been a limiting factor for recent high level waste (HLW) sludge processed at the Savannah River Site (SRS) Defense Waste Processing Facility (DWPF). The low solubility of sulfate in glass, along with melter and off-gas corrosion constraints, dictate that the waste be blended with lower sulfate concentration waste sources or washed to remove sulfate prior to vitrification. The development of enhanced borosilicate glass compositions with improved sulfate solubility will allow for higher waste loadings and accelerate mission completion.The objective of the current scope being pursued by SHU is to mature the sulfate solubility model to the point where it can be used to guide glass composition development for DWPF and WTP, allowing for enhanced waste loadings and waste throughput at these facilities. A series of targeted glass compositions was selected to resolve data gaps in the model and is identified as Stage III. SHU fabricated these glasses and sent samples to SRNL for chemical composition analysis. SHU will use the resulting data to enhance the sulfate solubility model and resolve any deficiencies. In this report, SRNL provides chemical analyses for the Stage III, simulated HLW glasses fabricated by SHU in support of the sulfate solubility model development.

  13. Chemical analysis of simulated high level waste glasses to support stage III sulfate solubility modeling

    Energy Technology Data Exchange (ETDEWEB)

    Fox, K. M. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL)

    2016-03-17

    The U.S. Department of Energy (DOE), Office of Environmental Management (EM) is sponsoring an international, collaborative project to develop a fundamental model for sulfate solubility in nuclear waste glass. The solubility of sulfate has a significant impact on the achievable waste loading for nuclear waste forms within the DOE complex. These wastes can contain relatively high concentrations of sulfate, which has low solubility in borosilicate glass. This is a significant issue for low-activity waste (LAW) glass and is projected to have a major impact on the Hanford Tank Waste Treatment and Immobilization Plant (WTP). Sulfate solubility has also been a limiting factor for recent high level waste (HLW) sludge processed at the Savannah River Site (SRS) Defense Waste Processing Facility (DWPF). The low solubility of sulfate in glass, along with melter and off-gas corrosion constraints, dictate that the waste be blended with lower sulfate concentration waste sources or washed to remove sulfate prior to vitrification. The development of enhanced borosilicate glass compositions with improved sulfate solubility will allow for higher waste loadings and accelerate mission completion.The objective of the current scope being pursued by SHU is to mature the sulfate solubility model to the point where it can be used to guide glass composition development for DWPF and WTP, allowing for enhanced waste loadings and waste throughput at these facilities. A series of targeted glass compositions was selected to resolve data gaps in the model and is identified as Stage III. SHU fabricated these glasses and sent samples to SRNL for chemical composition analysis. SHU will use the resulting data to enhance the sulfate solubility model and resolve any deficiencies. In this report, SRNL provides chemical analyses for the Stage III, simulated HLW glasses fabricated by SHU in support of the sulfate solubility model development.

  14. Stabilization Using Phosphate Bonded Ceramics. Salt Containing Mixed Waste Treatment. Mixed Waste Focus Area. OST Reference #117

    Energy Technology Data Exchange (ETDEWEB)

    None, None

    1999-09-01

    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.

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

    International Nuclear Information System (INIS)

    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.

  16. Technical area status report for chemical/physical treatment

    International Nuclear Information System (INIS)

    These Appendices describe various technologies that may be applicable to the Mixed Waste Treatment Plant (MWTP) Chemical/Physical Treatment System (CPTS). These technologies were identified by the CPTS Technical Support Group (TSG) as potentially applicable to a variety of separation, volume reduction, and decontamination requirements. The purpose was to identify all available and developing technologies, and their characteristics, for subsequent evaluation for specific requirements identified for the CPTS. However, the technologies described herein are not necessarily all inclusive, nor are they necessarily all applicable

  17. Guidelines for generators of hazardous chemical waste at LBL and Guidelines for generators of radioactive and mixed waste at LBL

    Energy Technology Data Exchange (ETDEWEB)

    1991-07-01

    The purpose of this document is to provide the acceptance criteria for the transfer of hazardous chemical, radioactive, and mixed waste to Lawrence Berkeley Laboratory's (LBL) Hazardous Waste Handling Facility (HWHF). These guidelines describe how a generator of wastes can meet LBL's acceptance criteria for hazardous chemical, radioactive, and mixed waste. 9 figs.

  18. Guidelines for generators of hazardous chemical waste at LBL and Guidelines for generators of radioactive and mixed waste at LBL

    International Nuclear Information System (INIS)

    The purpose of this document is to provide the acceptance criteria for the transfer of hazardous chemical, radioactive, and mixed waste to Lawrence Berkeley Laboratory's (LBL) Hazardous Waste Handling Facility (HWHF). These guidelines describe how a generator of wastes can meet LBL's acceptance criteria for hazardous chemical, radioactive, and mixed waste. 9 figs

  19. Treatment of some radioactive wastes by using new chelating membranes

    International Nuclear Information System (INIS)

    The preparation of chelating membranes containing nitrile and carboxylic acid as functional groups was investigated. The modification of such membranes by chemical treatments to produce significant changes in their properties was studied. This modification results in a higher rate of exchange and higher capacity. The applicability of such modified membranes in the removal of Co-60 and Cs-137 from their wastes were tested. The dependence of these radioactive nuclides uptake on the time and degree of grafting for H CI-, NH2OH-and KOH-treated membranes was investigated. It was found that the adsorption rate and capacity were higher for KOH-treated membrane than those for the NH2OH and H CI treated ones. The prepared grafted membranes have a good affinity towards the adsorption or chelation with Co-60 and Cs-137. This result may make such prepared materials acceptable for practicable use in some radioactive waste treatments and recovery

  20. Hazardous Waste/Mixed Waste Treatment Building Safety Information Document (SID)

    International Nuclear Information System (INIS)

    This Safety Information Document (SID) provides a description and analysis of operations for the Hazardous Waste/Mixed Waste Disposal Facility Treatment Building (the Treatment Building). The Treatment Building has been classified as a moderate hazard facility, and the level of analysis performed and the methodology used are based on that classification. Preliminary design of the Treatment Building has identified the need for two separate buildings for waste treatment processes. The term Treatment Building applies to all these facilities. The evaluation of safety for the Treatment Building is accomplished in part by the identification of hazards associated with the facility and the analysis of the facility's response to postulated events involving those hazards. The events are analyzed in terms of the facility features that minimize the causes of such events, the quantitative determination of the consequences, and the ability of the facility to cope with each event should it occur. The SID presents the methodology, assumptions, and results of the systematic evaluation of hazards associated with operation of the Treatment Building. The SID also addresses the spectrum of postulated credible events, involving those hazards, that could occur. Facility features important to safety are identified and discussed in the SID. The SID identifies hazards and reports the analysis of the spectrum of credible postulated events that can result in the following consequences: Personnel exposure to radiation; Radioactive material release to the environment; Personnel exposure to hazardous chemicals; Hazardous chemical release to the environment; Events leading to an onsite/offsite fatality; and Significant damage to government property. The SID addresses the consequences to the onsite and offsite populations resulting from postulated credible events and the safety features in place to control and mitigate the consequences

  1. Hazardous Waste/Mixed Waste Treatment Building Safety Information Document (SID)

    Energy Technology Data Exchange (ETDEWEB)

    Fatell, L.B.; Woolsey, G.B.

    1993-04-15

    This Safety Information Document (SID) provides a description and analysis of operations for the Hazardous Waste/Mixed Waste Disposal Facility Treatment Building (the Treatment Building). The Treatment Building has been classified as a moderate hazard facility, and the level of analysis performed and the methodology used are based on that classification. Preliminary design of the Treatment Building has identified the need for two separate buildings for waste treatment processes. The term Treatment Building applies to all these facilities. The evaluation of safety for the Treatment Building is accomplished in part by the identification of hazards associated with the facility and the analysis of the facility`s response to postulated events involving those hazards. The events are analyzed in terms of the facility features that minimize the causes of such events, the quantitative determination of the consequences, and the ability of the facility to cope with each event should it occur. The SID presents the methodology, assumptions, and results of the systematic evaluation of hazards associated with operation of the Treatment Building. The SID also addresses the spectrum of postulated credible events, involving those hazards, that could occur. Facility features important to safety are identified and discussed in the SID. The SID identifies hazards and reports the analysis of the spectrum of credible postulated events that can result in the following consequences: Personnel exposure to radiation; Radioactive material release to the environment; Personnel exposure to hazardous chemicals; Hazardous chemical release to the environment; Events leading to an onsite/offsite fatality; and Significant damage to government property. The SID addresses the consequences to the onsite and offsite populations resulting from postulated credible events and the safety features in place to control and mitigate the consequences.

  2. Bulky waste quantities and treatment methods in Denmark

    DEFF Research Database (Denmark)

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

    2012-01-01

    Bulky waste is a significant and increasing waste stream in Denmark. However, only little research has been done on its composition and treatment. In the present study, data about collection methods, waste quantities and treatment methods for bulky waste were obtained from two municipalities. 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...

  3. Handling and treatment of radioactive aqueous wastes

    International Nuclear Information System (INIS)

    This report aims to provide essential guidance to developing Member States without a nuclear power programme regarding selection, design and operation of cost effective treatment processes for radioactive aqueous liquids arising as effluents from small research institutions, hospitals and industries. The restricted quantities and low activity associated with the relevant wastes will generally permit contact-handling and avoid the need for shielding requirements. The selection of liquid waste treatment involves: Characterization of arising with the possibility of segregation; Discharge requirements for decontaminated liquors, both radioactive and non-radioactive; Available technologies and costs; Conditioning of the concentrates resulting from the treatment; Storage and disposal of the conditioned concentrates. The report will serve as a technical manual providing reference material and direct step-by-step know-how to staff in radioisotope user establishments and research centres in the developing Member States without nuclear power generation. Therefore, emphasis is limited to the simpler treatment facilities, which will be included with only the robust, well-established waste management processes carefully chosen as appropriate to developing countries. 20 refs, 12 figs, 7 tabs

  4. Commercial waste treatment program annual progress report for FY 1983

    International Nuclear Information System (INIS)

    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

  5. Nuclear Waste Treatment Program: Annual report for FY 1986

    International Nuclear Information System (INIS)

    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

  6. Safety in the Chemical Laboratory--Chemical Management: A Method for Waste Reduction.

    Science.gov (United States)

    Pine, Stanley H.

    1984-01-01

    Discusses methods for reducing or eliminating waste disposal problems in the chemistry laboratory, considering both economic and environmental aspects of the problems. Proposes inventory control, shared use, solvent recycling, zero effluent, and various means of disposing of chemicals. (JM)

  7. Carbowaste: treatment and disposal of irradiated graphite and other carbonaceous waste

    International Nuclear Information System (INIS)

    The European Project on 'Treatment and Disposal of Irradiated Graphite and other Carbonaceous Waste (CARBOWASTE)' addressed the retrieval, characterization, treatment, reuse and disposal of irradiated graphite with the following main results: - I-graphite waste features significantly depend on the specific manufacture process, on the operational conditions in the nuclear reactor (neutron dose, atmosphere, temperature etc.) and on radiolytic oxidation leading to partial releases of activation products and precursors during operation. - The neutron activation process generates significant recoil energies breaking pre-existing chemical bonds resulting in dislocations of activation products and new chemical compounds. - Most activation products exist in different chemical forms and at different locations. - I-graphite can be partly purified by thermal and chemical treatment processes leaving more leach-resistant waste products. - Leach tests and preliminary performance analyses show that i-graphite can be safely disposed of in a wide range of disposal systems, after appropriate treatment and/or conditioning. (authors)

  8. Chemical Dewatering Technique of waste Polymer Drilling Fluid

    Institute of Scientific and Technical Information of China (English)

    Li Gang; Zhu Muo

    1997-01-01

    @@ On the basis of the compositional analysis of waste polymer drilling fluid, we adopt chemical dewatering technique and thoroughly break down the colloid system of the drilling fluid. Having changed the surface properties of the clay particles and made the waste mud flocculate, the floc lost mud making ability and the phemeonenon of the floc returning mud is completely dispelled when it is buried. The recovered water can be reused in the mud system.

  9. Physical and chemical evaluation of furniture waste briquettes.

    Science.gov (United States)

    Moreno, Ana Isabel; Font, Rafael; Conesa, Juan A

    2016-03-01

    Furniture waste is mainly composed of wood and upholstery foam (mostly polyurethane foam). Both of these have a high calorific value, therefore, energy recovery would be an appropriate process to manage these wastes. Nevertheless, the drawback is that the energy content of these wastes is limited due to their low density mainly that of upholstery foam. Densification of separate foam presents difficulties due to its elastic character. The significance of this work lies in obtaining densified material by co-densification of furniture wood waste and polyurethane foam waste. Densification of furniture wood and the co-densification of furniture wood waste with polyurethane foam have been studied. On the one hand, the parameters that have an effect on the quality of the furniture waste briquettes have been analysed, i.e., moisture content, compaction pressure, presence of lignin, etc. The maximum weight percentage of polyurethane foam that can be added with furniture wood waste to obtain durable briquettes and the optimal moisture were determined. On the other hand, some parameters were analysed in order to evaluate the possible effect on the combustion. The chemical composition of waste wood was compared with untreated wood biomass; the higher nitrogen content and the concentration of some metals were the most important differences, with a significant difference of Ti content. PMID:26856442

  10. Radioactive liquid waste treatment plant in KEK

    International Nuclear Information System (INIS)

    The outline and flow diagram of the low level (-5 μCi/cm3) radioactive liquid waste treatment plant in the National Laboratory for High Energy Physics are presented. The detailed description of the individual facilities or equipments is given. The decontamination factors (DF) for the flocculation system and evaporation-condensation system have been obtained experimentally using stable Sr(NO3)2. (author)

  11. The DMC process for radioactive waste treatment

    International Nuclear Information System (INIS)

    This paper describes AEA Technology's patented Direct Membrane Cleaning (DMC) technology for enhancing the filtration of finely divided solids from aqueous streams. Electrolytically generated, microscopic gas bubbles at the membrane surface remove the superficial fouling layer, enching the permeation rate of the membrane. DMC technology has been demonstrated for ultrafilters and microfilters; several applications are summarized, including radioactive waste treatment and non-nuclear applications

  12. Solid waste disposal in the soil: effects on the physical, chemical, and organic properties of soil

    Directory of Open Access Journals (Sweden)

    Vanessa Regina Lasaro Mangieri

    2015-04-01

    Full Text Available Currently, there is growing concern over the final destination of the solid waste generated by society. Landfills should not be considered the endpoint for substances contained or generated in solid waste. The sustainable use of natural resources, especially soil and water, has become relevant, given the increase in anthropogenic activities. Agricultural use is an alternative to solid waste (leachate, biosolid disposal, considering the hypothesis that the agricultural use of waste is promising for reducing waste treatment costs, promoting nutrient reuse and improving the physical and chemical conditions of soil. Thus, this literature review, based on previously published data, seeks to confirm or disprove the hypothesis regarding the promising use of solid waste in agriculture to decrease the environmental liability that challenges public administrators in the development of efficient management. The text below addresses the following subtopics after the introduction: current solid waste disposal and environmental issues, the use of solid waste in agriculture, and the effect on the physical and chemical properties of soil and on organic matter, ending with final considerations.

  13. The role of chemical reaction in waste-form performance

    International Nuclear Information System (INIS)

    The dissolution rate of waste solids in a geologic repository is a complex function of waste form geometry, chemical raction rate, exterior flow field, and chemical environment. We present here an analysis to determine the stady-state mass transfer rate, over the entire range of flow conditions relevant to geologic disposal of nuclear waste. The equations for steady-state mass transfer with a chemical-reaction-rate boundary condition are solved by three different mathematical techniques which supplement each other. This theory is illustrated with laboratory leach data for borosilicate-glass and a spherical spent-fuel waste form under typical repository conditions. For borosilicate glass waste in the temperature range of 57/degree/C to 250/degree/C, dissolution rate in a repository is determined for a wide range of chemical reaction rates and for Peclet numbers from zero to well over 100, far beyond any Peclet values expected in a repository. Spent-fuel dissolution in a repository is also investigated, based on the limited leach data now available. 10 refs., 4 figs., 1 tab

  14. Waste dissolution with chemical reaction, diffusion and advection

    International Nuclear Information System (INIS)

    This paper extends the mass-transfer analysis to include the effect of advective transport in predicting the steady-state dissolution rate, with a chemical-reaction-rate boundary condition at the surface of a waste form of arbitrary shape. This new theory provides an analytic means of predicting the ground-water velocities at which dissolution rate in a geologic environment will be governed entirely to the chemical reaction rate. As an illustration, we consider the steady-state potential flow of ground water in porous rock surrounding a spherical waste solid. 3 refs., 2 figs

  15. Manufacturing waste disposal practices of the chemical propulsion industry

    Science.gov (United States)

    Goldberg, Benjamin E.; Adams, Daniel E.; Schutzenhofer, Scott A.

    1995-01-01

    The waste production, mitigation and disposal practices of the United States chemical propulsion industry have been investigated, delineated, and comparatively assessed to the U.S. industrial base. Special emphasis has been placed on examination of ozone depleting chemicals (ODC's). The research examines present and anticipated future practices and problems encountered in the manufacture of solid and liquid propulsion systems. Information collected includes current environmental laws and regulations that guide the industry practices, processes in which ODC's are or have been used, quantities of waste produced, funding required to maintain environmentally compliant practices, and preventive efforts.

  16. HUMIC ACID-LIKE MATTER ISOLATED FROM GREEN URBAN WASTES. PART II: PERFORMANCE IN CHEMICAL AND ENVIRONMENTAL TECHNOLOGIES

    Directory of Open Access Journals (Sweden)

    Enzo Montoneri

    2008-02-01

    Full Text Available Novel uses of the organic fraction of municipal solid wastes for diversified technological applications are reported. A humic acid-like substance (cHAL2 isolated from green urban wastes was tested as a chemical auxiliary for fabric cleaning and dyeing, and as a catalyst for the photodegradation of dyes. The results illustrate the fact that biomass wastes can be an interesting source of products for the chemical market. Process and product development in this direction are likely to offer high economic and environmental benefits in a modern, more sustainable waste treatment strategy.

  17. Fuel reprocessing and waste treatment at Karlsruhe Nuclear Research Centre

    International Nuclear Information System (INIS)

    The rapid development of nuclear energy in the Federal Republic of Germany has caused fuel reprocessing, waste solidification and final disposal to assume key functions in the country's atomic energy programme. An important basis for planning and construction of a large 1400t U/a reprocessing plant, scheduled for start-up around 1986, is the R and D work of the Karlsruhe Nuclear Research Centre and the experience gained from operating the pilot reprocessing plant WAK at the same site, reported in this paper. During the first five years of operation, since September 1971, the WAK plant, with a nominal capacity of 35 tU/a, has successfully demonstrated the feasibility of the Purex technology for reprocessing high-burnup LWR fuels. Substantial improvements have been achieved in fuel-handling techniques, head-end treatment, performance of high-activity extraction equipment, waste decrease by internal recycle, and iodine retention. Operating and maintenance experience has allowed continuing reduction of radiation doses to plant personnel to a level as low as 13% of the maximum permissible limits. Future work will include retention of 85Kr from dissolver off-gases and reprocessing of mixed-oxide fuels from the FRG's plutonium-recycle programme. The object of development work on fuel reprocessing technology is to minimize radioactive wastes and environment releases, and to increase operational safety and reliability. Based on experience gained by reprocessing campaigns with LWR fuels up to 37,000MWd/t and FBR fuel up to 61,000MWd/t in the MILLI facility, and by ''cold'' runs on the pilot-plant scale, progress is reported on (1) improved procedures for off-gas treatment and purification; (2) dissolution and solvent extraction of high-burnup fuels; and (3) application of ''salt-free'' procedures in U/Pu separation, Pu reoxidation and purification, absorbing construction material for criticality control. Based on this experience, the chemical flowsheet for a 5t/d LWR fuel

  18. 40 CFR 266.235 - What waste treatment does the storage and treatment conditional exemption allow?

    Science.gov (United States)

    2010-07-01

    ... 40 Protection of Environment 26 2010-07-01 2010-07-01 false What waste treatment does the storage... HAZARDOUS WASTES AND SPECIFIC TYPES OF HAZARDOUS WASTE MANAGEMENT FACILITIES Conditional Exemption for Low-Level Mixed Waste Storage, Treatment, Transportation and Disposal. Treatment § 266.235 What...

  19. The micro-electrolysis technique in waste water treatment

    International Nuclear Information System (INIS)

    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

  20. National Institutes of Health: Mixed waste minimization and treatment

    International Nuclear Information System (INIS)

    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

  1. Mixed and low-level waste treatment project: Appendix C, Health and safety criteria for the mixed and low-level waste treatment facility at the Idaho National Engineering Laboratory

    Energy Technology Data Exchange (ETDEWEB)

    Neupauer, R.M.; Thurmond, S.M.

    1992-09-01

    This report contains health and safety information relating to the chemicals that have been identified in the mixed waste streams at the Waste Treatment Facility at the Idaho National Engineering Laboratory. Information is summarized in two summary sections--one for health considerations and one for safety considerations. Detailed health and safety information is presented in material safety data sheets (MSDSs) for each chemical.

  2. Mixed and low-level waste treatment project: Appendix C, Health and safety criteria for the mixed and low-level waste treatment facility at the Idaho National Engineering Laboratory

    International Nuclear Information System (INIS)

    This report contains health and safety information relating to the chemicals that have been identified in the mixed waste streams at the Waste Treatment Facility at the Idaho National Engineering Laboratory. Information is summarized in two summary sections--one for health considerations and one for safety considerations. Detailed health and safety information is presented in material safety data sheets (MSDSs) for each chemical

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

    International Nuclear Information System (INIS)

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

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

    International Nuclear Information System (INIS)

    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

  5. Characterisation and Evaluation of Wastes for Treatment in the Batch Pyrolysis Plant in Studsvik, Sweden - 13586

    Energy Technology Data Exchange (ETDEWEB)

    Lindberg, Maria; Oesterberg, Carl; Vernersson, Thomas [Studsvik Nuclear AB, Studsvik Nuclear AB, 611 82 Nykoeping (Sweden)

    2013-07-01

    The new batch pyrolysis plant in Studsvik is built primarily for treatment of uranium containing dry active waste, 'DAW'. Several other waste types have been identified that are considered or assumed suitable for treatment in the pyrolysis plant because of the possibility to carefully control the atmosphere and temperature of the thermal treatment. These waste types must be characterised and an evaluation must be made with a BAT perspective. Studsvik have performed or plan to perform lab scale pyrolysis tests on a number of different waste types. These include: - Pyrophoric materials (uranium shavings), - Uranium chemicals that must be oxidised prior to being deposited in repository, - Sludges and oil soaks (this category includes NORM-materials), - Ion exchange resins (both 'free' and solidified/stabilised), - Bitumen solidified waste. Methodology and assessment criteria for various waste types, together with results obtained for the lab scale tests that have been performed, are described. (authors)

  6. Natural radiation, nuclear wastes and chemical pollutants

    International Nuclear Information System (INIS)

    Doses from natural radiation to the population in the Nordic Countries are summarized and man made modifications of the natural radiation environment are discussed. An account is given of the radiological consequences of energy conservation by reduced ventilation. Risks from possible future releases of radioactivity from final repositories of spent nuclear fuel are compared to the risks from present natural radioactivity in the environment. The possibilities for comparison between chemical and radiological risks are discussed. (author) 13 refs

  7. Chemical recycling of mixed waste plastics by selective pyrolysis

    Energy Technology Data Exchange (ETDEWEB)

    Tatsumoto, K.; Meglen, R.; Evans, R. [National Renewable Energy Laboratory, Golden, CO (United States)

    1995-05-01

    The goal of this work is to use selective pyrolysis to produce high-value chemicals from waste plastics mixtures. Selectivity is achieved by exploiting differences in reaction rates, catalysis, and coreactants. Target wastes are molecular mixtures such as; blends or composites, or mixtures from manufactured products such as; carpets and post-consumer mixed-plastic wastes. The experimental approach has been to use small-scale experiments using molecular beam mass spectrometry (MBMS), which provides rapid analysis of reaction products and permits rapid screening of process parameters. Rapid screening experiments permit exploration of many potential waste stream applications for the selective pyrolysis process. After initial screening, small-scale, fixed-bed and fluidized-bed reactors are used to provide products for conventional chemical analysis, to determine material balances, and to test the concept under conditions that will be used at a larger scale. Computer assisted data interpretation and intelligent chemical processing are used to extract process-relevant information from these experiments. An important element of this project employs technoeconomic assessments and market analyses of durables, the availability of other wastes, and end-product uses to identify target applications that have the potential for economic success.

  8. Fly Ash Treatment Technology in Modern Waste Incineration Plant

    Czech Academy of Sciences Publication Activity Database

    Šyc, Michal; Keppert, M.; Pohořelý, Michael; Novák, P.; Punčochář, Miroslav; Fišerová, Eva; Pekárek, Vladimír

    Milwaukee: UWM Centre for By-Products Utilization, 2010 - (Zachar, J.; Claisse, J.; Naik, T.; Ganjian, E.), s. 405-412 ISBN 978-1-4507-1490-7. [International Conference on Sustainable Construction Materials and Technologies /2./. Ancona (IT), 28.06.2010-30.06.2010] R&D Projects: GA MŠk 2B08048 Grant ostatní: NTF(NO) A/CZ0046/1/0027 Institutional research plan: CEZ:AV0Z40720504 Keywords : fly ash * waste incineration * treatment Subject RIV: CI - Industrial Chemistry, Chemical Engineering

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

    International Nuclear Information System (INIS)

    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

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

    Energy Technology Data Exchange (ETDEWEB)

    McKee, R.W.; Swanson, J.L.; Daling, P.M.; Clark, L.L.; Craig, R.A.; Nesbitt, J.F.; McCarthy, D.; Franklin, A.L.; Hazelton, R.F.; Lundgren, R.A.

    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.

  11. What to do with your chemical waste ?

    CERN Multimedia

    Roland Magnier/SC

    2004-01-01

    For any type and quantity of chemical waste, please contact phone number 16 0879 or 16 3315 for the collection and safe elimination. The quality and the safety of our environment is our own responsibility. Let's do it. Roland Magnier/SC-GS

  12. Canonical correlations between chemical and energetic characteristics of lignocellulosic wastes

    Directory of Open Access Journals (Sweden)

    Thiago de Paula Protásio

    2012-09-01

    Full Text Available Canonical correlation analysis is a statistical multivariate procedure that allows analyzing linear correlation that may exist between two groups or sets of variables (X and Y. This paper aimed to provide canonical correlation analysis between a group comprised of lignin and total extractives contents and higher heating value (HHV with a group of elemental components (carbon, hydrogen, nitrogen and sulfur for lignocellulosic wastes. The following wastes were used: eucalyptus shavings; pine shavings; red cedar shavings; sugar cane bagasse; residual bamboo cellulose pulp; coffee husk and parchment; maize harvesting wastes; and rice husk. Only the first canonical function was significant, but it presented a low canonical R². High carbon, hydrogen and sulfur contents and low nitrogen contents seem to be related to high total extractives contents of the lignocellulosic wastes. The preliminary results found in this paper indicate that the canonical correlations were not efficient to explain the correlations between the chemical elemental components and lignin contents and higher heating values.

  13. Mixed waste treatment using the ChemChar thermolytic detoxification technique

    Energy Technology Data Exchange (ETDEWEB)

    Kuchynka, D. [Mirage Systems, Sunnyvale, CA (United States)

    1995-10-01

    The diversity of mixed waste matrices contained at Department of Energy sites that require treatment preclude a single, universal treatment technology capable of handling sludges, solids, heterogeneous debris, aqueous and organic liquids and soils. This report describes the ChemChar thermolytic detoxification process. The process is a thermal, chemically reductive technology that converts the organic portion of mixed wastes to a synthesis gas, while simultaneously absorbing volatile inorganics on a carbon-based char.

  14. Waste Water Treatment And Data Book Of Method Of Water Quality Analysis

    International Nuclear Information System (INIS)

    This book indicates the method of water quality analysis and waste water treatment with collecting water quality data of advanced country and WHO, which introduces poisonous substance in industrial waste water such as heavy metal, ammonia, chlorine ion, PCB, chloroform, residual chlorine and manganese, reports about influence of those materials on human health, lists on method of analysis the poisonous substance, research way like working order and precautions on treatment and method of chemical process and use.

  15. STUDY ON APPLICATION OF AERATION BIOLOGICAL FLUID TANK TECHNOLGY IN NH4+—N WASTE WATER TREATMENT

    Institute of Scientific and Technical Information of China (English)

    CHENYi; LUJian-guo

    2003-01-01

    This paper introduces an application of "Aeration biological fluid tank"technology (ABFT) for the treatment of waste water containing NH4+-N and high concentrated chemicals.Highlights were focused on the effects of dissolved oxygen,pH,temperature and retention time on waste water bilogical treatment in order to find out a new approach in treatment of waste time on containing high concentrated NH4+-N.

  16. Treatment of off-gas from radioactive waste incinerators

    International Nuclear Information System (INIS)

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

  17. Using Advanced Mixed Waste Treatment Technology To Meet Accelerated Cleanup Program Milestones

    International Nuclear Information System (INIS)

    Some DOE Complex facilities are entering the late stages of facility closure. As waste management operations are completed at these sites, remaining inventories of legacy mixed wastes must be finally disposed. These wastes have unique physical, chemical and radiological properties that have made their management troublesome, and hence why they have remained on site until this late stage of closure. Some of these wastes have had no approved or practical treatment alternative until just recently. Results are provided from using advanced mixed waste treatment technology to perform two treatment campaigns on these legacy wastes. Combinations of macro-encapsulation, vacuum thermal desorption (VTD), and chemical stabilization, with off-site incineration of the organic condensate, provided a complete solution to the problem wastes. One program included approximately 1,900 drums of material from the Fernald Environmental Management Project. Another included approximately 1,200 drums of material from the Accelerated Cleanup Program at the Oak Ridge Reservation. Both of these campaigns were conducted under tight time schedules and demanding specifications, and were performed in a matter of only a few months each. Coordinated rapid waste shipment, flexible permitting and waste acceptance criteria, adequate waste receiving and storage capacity, versatile feed preparation and sorting capability, robust treatment technology with a broad feed specification, and highly reliable operations were all valuable components to successful accomplishment of the project requirements. Descriptions of the waste are provided; material that was difficult or impossible to treat in earlier phases of site closure. These problem wastes included: 1) the combination of special nuclear materials mixed with high organic chemical content and/or mercury, 2) high toxic metal content mixed with high organic chemical content, and 3) very high organic chemical content mixed with debris, solids and sludge

  18. The management of radioactive waste treatment facility

    International Nuclear Information System (INIS)

    The radioactive wastes generated at Korea Atomic Energy Research Institute (KAERI) in 1994 are about 56 m3 of liquid waste and 323 drums of solid waste. Liquid waste were treated by the evaporation process, the bituminization process, and the solar evaporation process. The solid wastes were treated in 1994 are about 87 m3 of liquid waste and 81 drums of solid waste, respectively. 2 tabs., 26 figs., 12 refs. (Author) .new

  19. Effective solidification/stabilisation of mercury-contaminated wastes using zeolites and chemically bonded phosphate ceramics.

    Science.gov (United States)

    Zhang, Shaoqing; Zhang, Xinyan; Xiong, Ya; Wang, Guoping; Zheng, Na

    2015-02-01

    In this study, two kinds of zeolites materials (natural zeolite and thiol-functionalised zeolite) were added to the chemically bonded phosphate ceramic processes to treat mercury-contaminated wastes. Strong promotion effects of zeolites (natural zeolite and thiol-functionalised zeolite) on the stability of mercury in the wastes were obtained and these technologies showed promising advantages toward the traditional Portland cement process, i.e. using Portland cement as a solidification agent and natural or thiol-functionalised zeolite as a stabilisation agent. Not only is a high stabilisation efficiency (lowered the Toxicity Characteristic Leaching Procedure Hg by above 10%) obtained, but also a lower dosage of solidification (for thiol-functionalised zeolite as stabilisation agent, 0.5 g g(-1) and 0.7 g g(-1) for chemically bonded phosphate ceramic and Portland cement, respectively) and stabilisation agents (for natural zeolite as stabilisation agent, 0.35 g g(-1) and 0.4 g g(-1) for chemically bonded phosphate ceramic and Portland cement, respectively) were used compared with the Portland cement process. Treated by thiol-functionalised zeolite and chemically bonded phosphate ceramic under optimum parameters, the waste containing 1500 mg Hg kg(-1) passed the Toxicity Characteristic Leaching Procedure test. Moreover, stabilisation/solidification technology using natural zeolite and chemically bonded phosphate ceramic also passed the Toxicity Characteristic Leaching Procedure test (the mercury waste containing 625 mg Hg kg(-1)). Moreover, the presence of chloride and phosphate did not have a negative effect on the chemically bonded phosphate ceramic/thiol-functionalised zeolite treatment process; thus, showing potential for future application in treatment of 'difficult-to-manage' mercury-contaminated wastes or landfill disposal with high phosphate and chloride content. PMID:25568090

  20. Karlsruhe Database for Radioactive Wastes (KADABRA) - Accounting and Management System for Radioactive Waste Treatment - 12275

    International Nuclear Information System (INIS)

    The data management system KADABRA was designed according to the purposes of the Cen-tral Decontamination Department (HDB) of the Wiederaufarbeitungsanlage Karlsruhe Rueckbau- und Entsorgungs-GmbH (WAK GmbH), which is specialized in the treatment and conditioning of radioactive waste. The layout considers the major treatment processes of the HDB as well as regulatory and legal requirements. KADABRA is designed as an SAG ADABAS application on IBM system Z mainframe. The main function of the system is the data management of all processes related to treatment, transfer and storage of radioactive material within HDB. KADABRA records the relevant data concerning radioactive residues, interim products and waste products as well as the production parameters relevant for final disposal. Analytical data from the laboratory and non destructive assay systems, that describe the chemical and radiological properties of residues, production batches, interim products as well as final waste products, can be linked to the respective dataset for documentation and declaration. The system enables the operator to trace the radioactive material through processing and storage. Information on the actual sta-tus of the material as well as radiological data and storage position can be gained immediately on request. A variety of programs accessed to the database allow the generation of individual reports on periodic or special request. KADABRA offers a high security standard and is constantly adapted to the recent requirements of the organization. (authors)

  1. Waste water treatment of hydrometallurgical mill in mine No. 754

    International Nuclear Information System (INIS)

    The author briefly introduces some measures to waste water treatment of hydrometallurgical mill of Uranium Mine No. 754. It is shown in practice that making rational use of waste water is advantageous to production, reducing qcost and lightening environment pollution

  2. Demonstration of packaging of Fernald Silo I waste in chemically bonded phosphate ceramic

    International Nuclear Information System (INIS)

    This paper summarizes our experience in bench-scale packaging of Fernald Silo I waste in chemically bonded phosphate ceramics. The waste was received from the Fernald Environmental Management Project (FEMP), and its treatability was studied in our laboratory. This waste contained As5+, Ba, Cr6+, Ni, Pb, Se4+, and Zn as the hazardous contaminants. In addition, the total specific activity of all the radioactive isotopes in the waste was 3.85 microCi/g, of which that of radium alone was 0.477 microCi/g. This indicated that radon (a daughter product of the radium) in the waste could present a serious handling problem during this study. For this reason, the waste was handled and stored in a flowing-air glovebox. We made waste form samples with an actual waste loading of 66.05 wt.% and subjected them to the Environmental Protection Agency (EPA) Toxicity Characteristic Leaching Procedure (TCLP). The results showed excellent stabilization of all contaminants. Actual levels detected in the leachate were well below the EPA's most stringent Universal Treatment Standards and in almost all cases were one order of magnitude below this limit. Radioactivity in the leachate was also very low. Alpha activity was 25 ± 2.5 pCi/mL, while beta activity was 9.81 ± 0.98 pCi/mL. This very low activity was attributed to the efficient stabilization of radium as insoluble radium phosphate in the waste form, thus prohibiting its leaching. This study indicates that the chemically bonded phosphate ceramic process may be a very suitable way to package Silo I waste for transportation and storage or disposal

  3. Thermal plasma treatment of cell-phone waste : preliminary result

    Energy Technology Data Exchange (ETDEWEB)

    Ruj, B. [Central Mechanical Engineering Research Inst., Durgapur (India). Thermal Engineering Group; Chang, J.S.; Li, O.L. [McMaster Univ., Hamilton, ON (Canada). Dept. of Engineering Physics; Pietsch, G. [RWTH Aachen Univ., Aachen (Germany)

    2010-07-01

    The cell phone is an indispensable service facilitator, however, the disposal and recycling of cell phones is a major problem. While the potential life span of a mobile phone, excluding batteries, is over 10 years, most of the users upgrade their phones approximately four times during this period. Cell phone waste is significantly more hazardous than many other municipal wastes as it contains thousands of components made of toxic chemicals and metals like lead, cadmium, chromium, mercury, polyvinyl chlorides (PVC), brominated flame retardants, beryllium, antimony and phthalates. Cell phones also use many expensive rare metals. Since cell phones are made up of plastics, metals, ceramics, and trace other substances, primitive recycling or disposal of cell phone waste to landfills and incinerators creates irreversible environmental damage by polluting water and soil, and contaminating air. In order to minimize releases into the environment and threat to human health, the disposal of cell phones needs to be managed in an environmentally friendly way. This paper discussed a safer method of reducing the generation of syngas and hydrocarbons and metal recovery through the treatment of cell phone wastes by a thermal plasma. The presentation discussed the experiment, with particular reference to sample preparation; experimental set-up; and results four samples with different experimental conditions. It was concluded that the plasma treatment of cell phone waste in reduced condition generates gaseous components such as hydrogen, carbon monoxide, and hydrocarbons which are combustible. Therefore, this system is an energy recovery system that contributes to resource conservation and reduction of climate change gases. 5 refs., 2 tabs., 2 figs.

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

    International Nuclear Information System (INIS)

    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

  5. 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.

  6. Study of commercial chemical additives for cementation of radioactive waste

    International Nuclear Information System (INIS)

    In this research it has been studied the effects of chemical additives (admixtures) in the cementation process of radioactive wastes, which are used to improve the properties of waste cementation process, both of the paste and of the solidified product. However there are a large variety of these materials that are frequently changed or taken out of the market, then it is essential to know the commercially available materials and their effects. The tests were carried out with a solution simulating the evaporator concentrate waste coming from PWR nuclear reactors. It was cemented using two formulations, A and B, incorporating higher or lower amount of waste, respectively. It was added chemical admixtures from two manufacturers (S and H), which were: accelerators, set retarders and superplasticizers. The experiments were organized by a factorial design 23. The measured parameters were the viscosity, the setting time, the paste and product density and the compressive strength. In this study we performed comparative analyzes of the results of compressive strength at age of 28 and 90 days and between the densities of the samples at the same ages. The compressive strength test at age of 28 days is considered a parameter essential issues related to security handling, transport and storage of cemented waste product. The results showed that the addition of accelerators improved the compressive strength of the cemented product, but presented lower values density products. (authors)

  7. Operation of the radioactive waste treatment facility

    International Nuclear Information System (INIS)

    The radioactive wasted generated at Korea Atomic Energy Research Institute (KAERI) in 1996 are about 118m3 of liquid waste and 204 drums of solid waste. Liquid waste were treated by the evaporation process, the bituminization process, and the solar evaporation process. In 1996, 100.5m3 of liquid waste was treated. (author). 84 tabs., 103 figs

  8. Operation of the radioactive waste treatment facility

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Kil Jeong; Ahn, Seom Jin; Lee, Kang Moo; Lee, Young Hee; Sohn, Jong Sik; Bae, Sang Min; Kang, Kwon Ho; Lim, Kil Sung; Sohn, Young Joon; Kim, Tae Kook; Jeong, Kyung Hwan; Wi, Geum San; Park, Seung Chul; Park, Young Woong; Yoon, Bong Keun

    1996-12-01

    The radioactive wasted generated at Korea Atomic Energy Research Institute (KAERI) in 1996 are about 118m{sup 3} of liquid waste and 204 drums of solid waste. Liquid waste were treated by the evaporation process, the bituminization process, and the solar evaporation process. In 1996, 100.5m{sup 3} of liquid waste was treated. (author). 84 tabs., 103 figs.

  9. Degradation of hazardous chemicals in liquid radioactive wastes from biomedical research using a mixed microbial population

    International Nuclear Information System (INIS)

    As the costs associated with treatment of mixed wastes by conventional methods increase, new technologies will be investigated as alternatives. This study examines the potential of using a selected mixed population of microorganisms to treat hazardous chemical compounds in liquid low level radioactive wastes from biomedical research procedures. Microorganisms were isolated from various waste samples and enriched against compounds known to occur in the wastes. Individual isolates were tested for their ability to degrade methanol, ethanol, phenol, toluene, phthalates, acetonitrile, chloroform, and trichloroacetic acid. Following these tests, the organisms were combined in a media with a mixture of the different compounds. Three compounds: methanol, acetonitrile, and pseudocumene, were combined at 500 microliter/liter each. Degradation of each compound was shown to occur (75% or greater) under batch conditions with the mixed population. Actual wastes were tested by adding an aliquot to the media, determining the biomass increase, and monitoring the disappearance of the compounds. The compounds in actual waste were degraded, but at different rates than the batch cultures that did not have waste added. The potential of using bioprocessing methods for treating mixed wastes from biomedical research is discussed

  10. Degradation of hazardous chemicals in liquid radioactive wastes from biomedical research using a mixed microbial population

    Energy Technology Data Exchange (ETDEWEB)

    Wolfram, J.H.; Radtke, M.; Wey, J.E.; Rogers, R.D. [Lockheed Martin Idaho Technology Co., Idaho Falls, ID (United States). Idaho National Engineering and Environmental Lab.; Rau, E.H. [National Inst. of Health, Bethesda, MD (United States). Div. of Safety

    1997-10-01

    As the costs associated with treatment of mixed wastes by conventional methods increase, new technologies will be investigated as alternatives. This study examines the potential of using a selected mixed population of microorganisms to treat hazardous chemical compounds in liquid low level radioactive wastes from biomedical research procedures. Microorganisms were isolated from various waste samples and enriched against compounds known to occur in the wastes. Individual isolates were tested for their ability to degrade methanol, ethanol, phenol, toluene, phthalates, acetonitrile, chloroform, and trichloroacetic acid. Following these tests, the organisms were combined in a media with a mixture of the different compounds. Three compounds: methanol, acetonitrile, and pseudocumene, were combined at 500 microliter/liter each. Degradation of each compound was shown to occur (75% or greater) under batch conditions with the mixed population. Actual wastes were tested by adding an aliquot to the media, determining the biomass increase, and monitoring the disappearance of the compounds. The compounds in actual waste were degraded, but at different rates than the batch cultures that did not have waste added. The potential of using bioprocessing methods for treating mixed wastes from biomedical research is discussed.

  11. 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)

    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

  12. Development of biological treatment of high concentration sodium nitrate waste liquid

    International Nuclear Information System (INIS)

    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)

  13. 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.

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

    International Nuclear Information System (INIS)

    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

  15. The influence of preliminary aerobic treatment on the efficacy of waste stabilisation under leachate recirculation conditions

    Directory of Open Access Journals (Sweden)

    Monika Suchowska-Kisielewicz

    2014-12-01

    Full Text Available This article presents the changes in the chemical composition of leachate and the concentrations and quantity of methane production in each individual decomposition phases, determined for untreated and after aerobic treatment of waste stabilised in anaerobic reactors with and without leachate recirculation. The research results demonstrate that leachate recirculation intensifies the decomposition of both aerobically treated and untreated waste. The methane production in the reactor with untreated, stabilised waste with recirculation was 28% higher; and in the reactor with aerobically treated waste, the methane production was 24% higher than in the reactors without recirculation. An important finding of the study is that aerobic treatment of waste prior to landfilling effectively reduces the quantity of pollutant emissions in leachate and biogas from waste and increases the availability for methane micro-organisms of organic substrates from difficult-to-decompose organic substances.

  16. Chemical durability of soda-lime-aluminosilicate glass for radioactive waste vitrification

    International Nuclear Information System (INIS)

    Vitrification has been identified as one of the most viable waste treatment alternatives for nuclear waste disposal. Currently, the most popular glass compositions being selected for vitrification are the borosilicate family of glasses. Another popular type that has been around in glass industry is the soda-lime-silicate variety, which has often been characterized as the least durable and a poor candidate for radioactive waste vitrification. By replacing the boron constituent with a cheaper substitute, such as silica, the cost of vitrification processing can be reduced. At the same time, addition of network intermediates such as Al2O3 to the glass composition increases the environmental durability of the glass. The objective of this study is to examine the ability of the soda-lime-aluminosilicate glass as an alternative vitrification tool for the disposal of radioactive waste and to investigate the sensitivity of product chemical durability to variations in composition

  17. Biological treatment of concentrated hazardous, toxic, and radionuclide mixed wastes without dilution

    International Nuclear Information System (INIS)

    Approximately 10 percent of all radioactive wastes produced in the U. S. are mixed with hazardous or toxic chemicals and therefore can not be placed in secure land disposal facilities. Mixed wastes containing hazardous organic chemicals are often incinerated, but volatile radioactive elements are released directly into the biosphere. Some mixed wastes do not currently have any identified disposal option and are stored locally awaiting new developments. Biological treatment has been proposed as a potentially safer alternative to incineration for the treatment of hazardous organic mixed wastes, since biological treatment would not release volatile radioisotopes and the residual low-level radioactive waste would no longer be restricted from land disposal. Prior studies have shown that toxicity associated with acetonitrile is a significant limiting factor for the application of biotreatment to mixed wastes and excessive dilution was required to avoid inhibition of biological treatment. In this study, we demonstrate that a novel reactor configuration, where the concentrated toxic waste is drip-fed into a complete-mix bioreactor containing a pre-concentrated active microbial population, can be used to treat a surrogate acetonitrile mixed waste stream without excessive dilution. Using a drip-feed bioreactor, we were able to treat a 90,000 mg/L acetonitrile solution to less than 0.1 mg/L final concentration using a dilution factor of only 3.4. It was determined that the acetonitrile degradation reaction was inhibited at a pH above 7.2 and that the reactor could be modeled using conventional kinetic and mass balance approaches. Using a drip-feed reactor configuration addresses a major limiting factor (toxic inhibition) for the biological treatment of toxic, hazardous, or radioactive mixed wastes and suggests that drip-feed bioreactors could be used to treat other concentrated toxic waste streams, such as chemical warfare materiel

  18. Biological treatment of concentrated hazardous, toxic, andradionuclide mixed wastes without dilution

    Energy Technology Data Exchange (ETDEWEB)

    Stringfellow, William T.; Komada, Tatsuyuki; Chang, Li-Yang

    2004-06-15

    Approximately 10 percent of all radioactive wastes produced in the U. S. are mixed with hazardous or toxic chemicals and therefore can not be placed in secure land disposal facilities. Mixed wastes containing hazardous organic chemicals are often incinerated, but volatile radioactive elements are released directly into the biosphere. Some mixed wastes do not currently have any identified disposal option and are stored locally awaiting new developments. Biological treatment has been proposed as a potentially safer alternative to incineration for the treatment of hazardous organic mixed wastes, since biological treatment would not release volatile radioisotopes and the residual low-level radioactive waste would no longer be restricted from land disposal. Prior studies have shown that toxicity associated with acetonitrile is a significant limiting factor for the application of biotreatment to mixed wastes and excessive dilution was required to avoid inhibition of biological treatment. In this study, we demonstrate that a novel reactor configuration, where the concentrated toxic waste is drip-fed into a complete-mix bioreactor containing a pre-concentrated active microbial population, can be used to treat a surrogate acetonitrile mixed waste stream without excessive dilution. Using a drip-feed bioreactor, we were able to treat a 90,000 mg/L acetonitrile solution to less than 0.1 mg/L final concentration using a dilution factor of only 3.4. It was determined that the acetonitrile degradation reaction was inhibited at a pH above 7.2 and that the reactor could be modeled using conventional kinetic and mass balance approaches. Using a drip-feed reactor configuration addresses a major limiting factor (toxic inhibition) for the biological treatment of toxic, hazardous, or radioactive mixed wastes and suggests that drip-feed bioreactors could be used to treat other concentrated toxic waste streams, such as chemical warfare materiel.

  19. University program in hazardous chemical and radioactive waste management

    International Nuclear Information System (INIS)

    The three main functions of a university program are education, training, and research. At Vanderbilt University, there is a Solid and Hazardous Waste option in the Master of Science in Engineering Program. The two main foci are treatment of wastes and environmental transport and transformation of the wastes. Courses in Hazardous Waste Engineering and Radioactive Waste Disposal present a synoptic view of the field, including legal, economic, and institutional aspects as well as the requisite technical content. The training is accomplished for some of the students through the aegis of an internship program sponsored by the US Department of Energy. In the summer between the two academic years of the program, the study works at a facility where decontamination and/or decommissioning and/or remedial actions are taking place. Progress in understanding the movement, transformation, and fate of hazardous materials in the environment is so rapid that it will not be possible to be current in the field without participating in that discovery. Therefore, their students are studying these processes and contributing to new knowledge. Some recent examples are the study of safety factors implicit in assuming a saturated zone below a hazardous waste landfill when an unsaturated zone exists, application of probabilistic risk assessment to three National Priority List sites in Tennessee, and the explanation of why certain organics precede pH, conductivity and nitrates through a clay liner at a hazardous waste disposal site

  20. Mixed wastes treatment in Atucha I

    International Nuclear Information System (INIS)

    Full text: During decontamination works of the fueling machine of Atucha I nuclear power plant (AINPP), a liquid waste with special characteristics was generated, which needed the development of a treatment method. The waste consisted of an emulsion designed for the cleaning of mechanical components and was formed by an organic solvent dispersed in water with aid of an emulsifier additive. After several cleaning operations, the emulsion contained an important quantity of lubricants and radioactive dirt. The treatment had the objective of recycling a toxic waste such as the organic solvent and reducing the volume of the residual mass. Laboratory tests were made tending to the emulsion separation in their components. Ionic force and ionic mobility were modified for join the emulsion micelles and produce their coalescence. Different salts and working temperatures were tried and it was stated that the combination of 1% of Na2SO4 added and 40 degree C temperature were the optimum taking into account the available equipment in AINPP and cost considerations. The process was carried out in batch mode and 3 residual streams were obtained, an aqueous one which was sent to Residual Water System of AINPP, an organic liquid consisting of decontaminated hydrocarbons, useful for other cleaning tasks and finally a solid one, sited in the in-between interface of the other two liquids, consisting of insoluble soaps used as lubricant thickness, containing the principal proportion of radioactivity. As a result of this process we have achieved a volume reduction higher than 90%, the recycling of the organic solvent and concentration of radioactivity in a solid greasy mass with low water solubility. (author)

  1. Chemical Disposition of Plutonium in Hanford Site Tank Wastes

    International Nuclear Information System (INIS)

    This report examines the chemical disposition of plutonium (Pu) in Hanford Site tank wastes, by itself and in its observed and potential interactions with the neutron absorbers aluminum (Al), cadmium (Cd), chromium (Cr), iron (Fe), manganese (Mn), nickel (Ni), and sodium (Na). Consideration also is given to the interactions of plutonium with uranium (U). No consideration of the disposition of uranium itself as an element with fissile isotopes is considered except tangentially with respect to its interaction as an absorber for plutonium. The report begins with a brief review of Hanford Site plutonium processes, examining the various means used to recover plutonium from irradiated fuel and from scrap, and also examines the intermediate processing of plutonium to prepare useful chemical forms. The paper provides an overview of Hanford tank defined-waste-type compositions and some calculations of the ratios of plutonium to absorber elements in these waste types and in individual waste analyses. These assessments are based on Hanford tank waste inventory data derived from separately published, expert assessments of tank disposal records, process flowsheets, and chemical/radiochemical analyses. This work also investigates the distribution and expected speciation of plutonium in tank waste solution and solid phases. For the solid phases, both pure plutonium compounds and plutonium interactions with absorber elements are considered. These assessments of plutonium chemistry are based largely on analyses of idealized or simulated tank waste or strongly alkaline systems. The very limited information available on plutonium behavior, disposition, and speciation in genuine tank waste also is discussed. The assessments show that plutonium coprecipitates strongly with chromium, iron, manganese and uranium absorbers. Plutonium's chemical interactions with aluminum, nickel, and sodium are minimal to non-existent. Credit for neutronic interaction of plutonium with these

  2. Use of the ultrasound in waste treatment

    International Nuclear Information System (INIS)

    Wastewaters from the chemical industry may contain highly toxic organic compounds. This compounds cannot be degraded by the biological conventional treatment. For this reason, the use of ultrasounds, as a non conventional technique, offers a great potential in the degradation of refractory compounds, in the improvement of the biological degradation and in the disintegration of sludge. The aim of this work is to offer the elementary necessary knowledge to understand the principles of the use of the ultrasound in wastewater treatment as well as to show the results of the most recent works in this field

  3. Radioactive waste treatment techniques of Fugen Nuclear Power Station

    International Nuclear Information System (INIS)

    Hollow fiber membrane filters for liquid radioactive waste treatment system and a dry cleaning equipment for laundry system were installed in the prototype heavy water reactor 'Fugen' on August 1989 in order to enhance the performance of the liquid waste treatment system and reduce the quantity of discharged radioactivity. A solid waste incinerator for volume reduction of low level burnable solid waste was also installed in Fugen on October 1989. And these equipments have been operated successfully. This paper reports details of the radioactive waste treatment systems and techniques of Fugen including above equipments. (author)

  4. Thermochemical treatment of radioactive waste by using powder metal fuels

    International Nuclear Information System (INIS)

    A thermochemical approach was suggested for treating and conditioning specific streams of radioactive wastes as well as for decontamination of highly contaminated surfaces. The thermochemical treatment of radioactive wastes uses powder metal fuels or reactant mixtures that are specifically formulated for the waste composition and react exothermically with the waste components. As a result of this treatment, the release of hazardous components and radionuclides in the off-gas minimizes and contaminants are confined in the mineral or glass-like end product. An advantage of thermochemical treatment is its autonomy that allows successfully treating some wastes without usage of complex and expensive equipment. (author)

  5. Optimization of thermo-chemical hydrolysis of kitchen wastes.

    Science.gov (United States)

    Vavouraki, Aikaterini Ioannis; Angelis, Evangelos Michael; Kornaros, Michael

    2013-03-01

    Municipal Solid Wastes (MSWs) in Greece consist mainly of fermentable organic material such as food scraps (∼50%) and paper residuals (∼20%). The aim of this work was to study the thermo-chemical pretreatment of the kitchen waste (KW) fraction of MSW focusing on biotechnological exploitation of pretreated wastes for biofuel production. A representative sample of municipal food residues was derived by combining weighted amounts of each individual type of residue recognized in daily samples obtained from the University of Patras' students restaurant located at the Students Residence Hall (Greece). Chemical pretreatment experiments of the representative KW sample were performed using several types of chemical solutions (i.e. H2SO4, HCl, NaOH, H2SO3) of different solute concentration (0.7%, 1.5%, 3%) at three temperatures (50, 75, 120°C) and a range of residence times (30-120min). Optimized results proved that chemical pretreatment of KW, using either 1.12% HCl for 94min or 1.17% HCl for 86min (at 100°C), increased soluble sugars concentration by 120% compared to untreated KW. The increase of soluble sugars was mainly attributed to the mono-sugars glucose and fructose. PMID:22883686

  6. Combined Chemical Activation and Fenton Degradation to Convert Waste Polyethylene into High-Value Fine Chemicals.

    Science.gov (United States)

    Chow, Cheuk-Fai; Wong, Wing-Leung; Ho, Keith Yat-Fung; Chan, Chung-Sum; Gong, Cheng-Bin

    2016-07-01

    Plastic waste is a valuable organic resource. However, proper technologies to recover usable materials from plastic are still very rare. Although the conversion/cracking/degradation of certain plastics into chemicals has drawn much attention, effective and selective cracking of the major waste plastic polyethylene is extremely difficult, with degradation of C-C/C-H bonds identified as the bottleneck. Pyrolysis, for example, is a nonselective degradation method used to crack plastics, but it requires a very high energy input. To solve the current plastic pollution crisis, more effective technologies are needed for converting plastic waste into useful substances that can be fed into the energy cycle or used to produce fine chemicals for industry. In this study, we demonstrate a new and effective chemical approach by using the Fenton reaction to convert polyethylene plastic waste into carboxylic acids under ambient conditions. Understanding the fundamentals of this new chemical process provides a possible protocol to solve global plastic-waste problems. PMID:27168079

  7. Management of the radioactive waste treatment facility

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Kil Jeong; An, Sum Jin; Lee, Kang Mu; Jeong, Kyeong Hwan; Lee, Young Hee; Sohn, Jong Sik; Bae, Sang Min; Kang, Kwon Ho; Yim, Kil Sung; Ui, Keum San; Kim, Tae Kuk; Sohn, Young Jun; You, Young Keol; Park, Young Yoong; Yoon, Bong Keun [Korea Atomic Energy Research Institute, Taejon (Korea, Republic of)

    1993-12-01

    The radioactive wastes generated in Korea Atomic Energy Research Institute (KAERI) in 1993 are about 107 m{sup 3} of liquid waste and 169 drums of solid waste. Liquid waste is treated by the evaporation process, the bituminization process, and the solar evaporation process. The solid waste is treated by the compaction process and the cementation process. The radioactive wastes treated in 1993 are about 194 m{sup 3} of liquid waste and 31 drums of solid waste, respectively. 28 tabs., 12 figs. (Author) .new.

  8. Waste management and enzymatic treatment of Municipal Solid Waste

    DEFF Research Database (Denmark)

    Jensen, Jacob Wagner

    content), 2) low ash and xenobiotic content, 3) high gas yield, 4) volume (produced), 5) dependable distribution and 6) low competition with other end-user technologies. MSW is a complex substrate comprising both degradable and non-degradable material being metal, plastic, glass, building waste etc...... simulating Danish household waste in composition and weight, 2) evaluating the performance of best enzyme candidates on original waste with and without additional additives, 3) measuring the biogas potential of liquefied waste and comparing the results with the biogas potential of untreated waste...

  9. Effect of thermal, chemical and thermo-chemical pre-treatments to enhance methane production

    Energy Technology Data Exchange (ETDEWEB)

    Rafique, Rashad; Nizami, Abdul-Sattar; Murphy, Jerry D.; Kiely, Gerard [Department of Civil and Environmental Engineering, University College Cork (Ireland); Poulsen, Tjalfe Gorm [Department of Biotechnology, Chemistry and Environmental Engineering, Aalborg University (Denmark); Asam, Zaki-ul-Zaman [Department of Civil Engineering, National University of Ireland Galway (Ireland)

    2010-12-15

    The rise in oil price triggered the exploration and enhancement of various renewable energy sources. Producing biogas from organic waste is not only providing a clean sustainable indigenous fuel to the number of on-farm digesters in Europe, but also reducing the ecological and environmental deterioration. The lignocellulosic substrates are not completely biodegraded in anaerobic digesters operating at commercial scale due to their complex physical and chemical structure, which result in meager energy recovery in terms of methane yield. The focus of this study is to investigate the effect of pre-treatments: thermal, thermo-chemical and chemical pre-treatments on the biogas and methane potential of dewatered pig manure. A laboratory scale batch digester is used for these pre-treatments at different temperature range (25 C-150 C). Results showed that thermo-chemical pretreatment has high effect on biogas and methane potential in the temperature range (25-100 C). Maximum enhancement is observed at 70 C with increase of 78% biogas and 60% methane production. Thermal pretreatment also showed enhancement in the temperature range (50-10 C), with maximum enhancement at 100 C having 28% biogas and 25% methane increase. (author)

  10. Treatment of Bone Waste Using Thermal Plasma Technology

    Institute of Scientific and Technical Information of China (English)

    KI Ho Beom; KIM Woo Hyung; KIM Bong Soo; K00 Hyung Joon; LI Mingwei; CHAE Jae Ou

    2007-01-01

    Daily meat consumption produces a lot of bone waste, and dumped bone waste without treatment would result in environmental hazards. Conventional treatment methods of waste bones have some disadvantages. Herein, an investigation of bone waste treated using thermal plasma technology is presented. A high-temperature plasma torch operated at 25.2 kW was used to treat bone waste for seven minutes. The bone waste was finally changed into vitric matter and lost 2/3 of its weight after the treatment. The process was highly efficient, economical, convenient, and fuel-free. This method could be used as an alternative for disposal of bone waste, small infectious animals, hazardous hospital waste, etc.

  11. Waste treatment at the La Hague and Marcoule sites

    International Nuclear Information System (INIS)

    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

  12. 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.

  13. Chemical durability of Savannah River Plant waste glass as a function of waste loading

    International Nuclear Information System (INIS)

    The leachability of Savannah River Plant (SRP) waste forms was assessed for glass containing up to 50 wt % simulated waste oxides. Leach tests included standard MCC-1 static tests and pH-buffered solution experiments. An integrated approach combining leachate solution analysis with both bulk and surface analyses was used to study waste glass corrosion as a function of waste loading. Leachate solutions were analyzed by inductively coupled plasma spectroscopy and atomic absorption. Bulk and surface analyses were performed using optical microscopy, wide angle x-ray diffraction, scanning electron microscopy, x-ray energy spectroscopy, and electron microprobe analysis. Scouting tests on key processing and product parameters, such as viscosity, electrical resistivity, and density were also performed. Results of this study show that the durability of SRP waste glass improves due to the presence of the waste, for waste loadings up to 50 wt % because of the formation of protective surface layers. In addition, the data indicate that the practical limit of waste loading will be determined not by chemical durability of the product, but by processing considerations

  14. Chemical Disposition of Plutonium in Hanford Site Tank Wastes

    Energy Technology Data Exchange (ETDEWEB)

    Delegard, Calvin H. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Jones, Susan A. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States)

    2015-05-07

    This report examines the chemical disposition of plutonium (Pu) in Hanford Site tank wastes, by itself and in its observed and potential interactions with the neutron absorbers aluminum (Al), cadmium (Cd), chromium (Cr), iron (Fe), manganese (Mn), nickel (Ni), and sodium (Na). Consideration also is given to the interactions of plutonium with uranium (U). No consideration of the disposition of uranium itself as an element with fissile isotopes is considered except tangentially with respect to its interaction as an absorber for plutonium. The report begins with a brief review of Hanford Site plutonium processes, examining the various means used to recover plutonium from irradiated fuel and from scrap, and also examines the intermediate processing of plutonium to prepare useful chemical forms. The paper provides an overview of Hanford tank defined-waste–type compositions and some calculations of the ratios of plutonium to absorber elements in these waste types and in individual waste analyses. These assessments are based on Hanford tank waste inventory data derived from separately published, expert assessments of tank disposal records, process flowsheets, and chemical/radiochemical analyses. This work also investigates the distribution and expected speciation of plutonium in tank waste solution and solid phases. For the solid phases, both pure plutonium compounds and plutonium interactions with absorber elements are considered. These assessments of plutonium chemistry are based largely on analyses of idealized or simulated tank waste or strongly alkaline systems. The very limited information available on plutonium behavior, disposition, and speciation in genuine tank waste also is discussed. The assessments show that plutonium coprecipitates strongly with chromium, iron, manganese and uranium absorbers. Plutonium’s chemical interactions with aluminum, nickel, and sodium are minimal to non-existent. Credit for neutronic interaction of plutonium with these absorbers

  15. Implementation of the Urban Waste Water Treatment Directive in Norway - An Evaluation of the Norwegian Approach regarding Wastewater Treatment

    OpenAIRE

    Källqvist, T.; Molvær, J.; Oug, E.; Berge, D.; Tjomsland, T.; Stene-Johansen, S.

    2002-01-01

    This report discusses the effects and benefits of full implementation of the Urban Waste Water Treatment Directive in Norway. The Norwegian policy for wastewater treatment has targeted phosphorus removal as the primary measure to reduce adverse effects of discharge of wastewater to freshwater and marine recipients. Chemical precipitation is therefore used at more than 70% of the wastewater treatment plants. This technique is very efficient in reducing the phosphorus concentration and in addit...

  16. Mixed waste characterization, treatment, and disposal focus area. Technology summary

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1995-06-01

    This paper presents details about the technology development programs of the Department of Energy. In this document, waste characterization, thermal treatment processes, non-thermal treatment processes, effluent monitors and controls, development of on-site innovative technologies, and DOE business opportunities are applied to environmental restoration. The focus areas for research are: contaminant plume containment and remediation; mixed waste characterization, treatment, and disposal; high-level waste tank remediation; landfill stabilization; and decontamination and decommissioning.

  17. Mixed waste characterization, treatment, and disposal focus area. Technology summary

    International Nuclear Information System (INIS)

    This paper presents details about the technology development programs of the Department of Energy. In this document, waste characterization, thermal treatment processes, non-thermal treatment processes, effluent monitors and controls, development of on-site innovative technologies, and DOE business opportunities are applied to environmental restoration. The focus areas for research are: contaminant plume containment and remediation; mixed waste characterization, treatment, and disposal; high-level waste tank remediation; landfill stabilization; and decontamination and decommissioning

  18. Chemical pathways for the formation of ammonia in Hanford wastes

    International Nuclear Information System (INIS)

    This report reviews chemical reactions leading to the formation of ammonia in Hanford wastes. The general features of the chemistry of the organic compounds in the Hanford wastes are briefly outlined. The radiolytic and thermal free radical reactions that are responsible for the initiation and propagation of the oxidative degradation reactions of the nitrogen-containing complexants, trisodium HEDTA and tetrasodium EDTA, are outlined. In addition, the roles played by three different ionic reaction pathways for the oxidation of the same compounds and their degradation products are described as a prelude to the discussion of the formation of ammonia. The reaction pathways postulated for its formation are based on tank observations, laboratory studies with simulated and actual wastes, and the review of the scientific literature. Ammonia derives from the reduction of nitrite ion (most important), from the conversion of organic nitrogen in the complexants and their degradation products, and from radiolytic reactions of nitrous oxide and nitrogen (least important)

  19. Chemical pathways for the formation of ammonia in Hanford wastes

    Energy Technology Data Exchange (ETDEWEB)

    Stock, L.M.; Pederson, L.R.

    1997-12-01

    This report reviews chemical reactions leading to the formation of ammonia in Hanford wastes. The general features of the chemistry of the organic compounds in the Hanford wastes are briefly outlined. The radiolytic and thermal free radical reactions that are responsible for the initiation and propagation of the oxidative degradation reactions of the nitrogen-containing complexants, trisodium HEDTA and tetrasodium EDTA, are outlined. In addition, the roles played by three different ionic reaction pathways for the oxidation of the same compounds and their degradation products are described as a prelude to the discussion of the formation of ammonia. The reaction pathways postulated for its formation are based on tank observations, laboratory studies with simulated and actual wastes, and the review of the scientific literature. Ammonia derives from the reduction of nitrite ion (most important), from the conversion of organic nitrogen in the complexants and their degradation products, and from radiolytic reactions of nitrous oxide and nitrogen (least important).

  20. Design of Biochemical Oxidation Process Engineering Unit for Treatment of Organic Radioactive Liquid Waste

    International Nuclear Information System (INIS)

    Organic radioactive liquid waste from nuclear industry consist of detergent waste from nuclear laundry, 30% TBP-kerosene solvent waste from purification or recovery of uranium from process failure of nuclear fuel fabrication, and solvent waste containing D2EHPA, TOPO, and kerosene from purification of phosphoric acid. The waste is dangerous and toxic matter having low pH, high COD and BOD, and also low radioactivity. Biochemical oxidation process is the effective method for detoxification of organic waste and decontamination of radionuclide by bio sorption. The result process are sludges and non radioactive supernatant. The existing treatment facilities radioactive waste in Serpong can not use for treatment of that’s organics waste. Dio chemical oxidation process engineering unit for continuous treatment of organic radioactive liquid waste on the capacity of 1.6 L/h has been designed and constructed the equipment of process unit consist of storage tank of 100 L capacity for nutrition solution, 2 storage tanks of 100 L capacity per each for liquid waste, reactor oxidation of 120 L, settling tank of 50 L capacity storage tank of 55 L capacity for sludge, storage tank of 50 capacity for supernatant. Solution on the reactor R-01 are added by bacteria, nutrition and aeration using two difference aerators until biochemical oxidation occurs. The sludge from reactor of R-01 are recirculated to the settling tank of R-02 and on the its reverse operation biological sludge will be settled, and supernatant will be overflow. (author)

  1. Mixed and Low-Level Waste Treatment Facility project

    International Nuclear Information System (INIS)

    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

  2. RECOVERY OF CHITIN AND CHITOSAN FROM SHRIMP WASTE BY CHEMICAL AND MICROBIAL METHODS

    Directory of Open Access Journals (Sweden)

    A. Khanafari, R. Marandi, Sh. Sanatei

    2008-01-01

    Full Text Available Shrimp waste is the most important chitin source for commercial use. In this study chitin and chitosan were extracted from Penaeus semisulcatus waste collected from a shrimp processing landing center situated at Persian Gulf in south of Iran by chemical and microbial methods. Chitin and chitosan were extracted by alkali-acid treatment and the yields were 510 and 410mg/g, respectively. Demineralization is an important step in the chitin purification process from shrimp waste. Chemical extraction method included the use of NaOH solution and acetic acid. In microbial extraction, organic acids (lactic acid produced by probiotic bacteria was used to demineralize microbial deproteinized shrimp shells. The study showed that the effectiveness of using lactic acid bacteria especially added Fe (NO33 as extra nitrogen source for demineralization of shrimp shells than chemical method (1750 against 810mg/g. Chitin and chitosan extracted from shrimp waste by chemical and microbial methods was crystalline powder, non-harmful and odorless, white and off-white, respectively. The moisture content was calculated as 63.8%. The amount of Ca, Fe, Cu and Mn present in the shells was 168, 35.58, 38.28 and 6.72mg/L, obtained by atomic absorption spectroscopy, respectively. The amount of calcium in the shells was 25 times higher than manganese. The results suggested Lactobacillus plantarum (PTTC 1058 is an attractive source of recovery for chitin and chitosan.

  3. Waste Issues Associated with the Safe Movement of Hazardous Chemicals

    International Nuclear Information System (INIS)

    Moving hazardous chemicals presents the risk of exposure for workers engaged in the activity and others that might be in the immediate area. Adverse affects are specific to the chemicals and can range from minor skin, eye, or mucous membrane irritation, to burns, respiratory distress, nervous system dysfunction, or even death. A case study is presented where in the interest of waste minimization; original shipping packaging was removed from a glass bottle of nitric acid, while moving corrosive liquid through a security protocol into a Radiological Control Area (RCA). During the transfer, the glass bottle broke. The resulting release of nitric acid possibly exposed 12 employees with one employee being admitted overnight at a hospital for observation. This is a clear example of administrative controls to reduce the generation of suspect radioactive waste being implemented at the expense of employee health. As a result of this event, material handling procedures that assure the safe movement of hazardous chemicals through a security protocol into a radiological control area were developed. Specifically, hazardous material must be transferred using original shipping containers and packaging. While this represents the potential to increase the generation of suspect radioactive waste in a radiological controlled area, arguments are presented that justify this change. Security protocols for accidental releases are also discussed. In summary, the 12th rule of ''Green Chemistry'' (Inherently Safer Chemistry for Accident Prevention) should be followed: the form of a substance used in a chemical process (Movement of Hazardous Chemicals) should be chosen to minimize the potential for chemical accidents, including releases

  4. Simultaneous treatment of low-level miscellaneous solid waste by thermal plasma

    International Nuclear Information System (INIS)

    Volume reduction is a cost saving method for the final disposal of radioactive waste. On one hand, arc plasma heating can provide sufficient heat independent of the chemical and physical properties of waste, therefore enabling stable heating at high treatment rates. CRIEPI (central research institute of electric power industry) focused on the advantages of arc plasma heating, and has clarified that arc plasma heating can be used in a simultaneous melting treatment process for low-level miscellaneous mixed solid waste, generated from nuclear power plants for volume reduction, and in the stabilization of radionuclides. (authors)

  5. Simultaneous treatment of low-level miscellaneous solid waste by thermal plasma

    Energy Technology Data Exchange (ETDEWEB)

    Amakawa, T.; Adachi, K.; Yasui, S. [Central Research Institute of Electric Power Industry, Kanagawa (Japan)

    2001-07-01

    Volume reduction is a cost saving method for the final disposal of radioactive waste. On one hand, arc plasma heating can provide sufficient heat independent of the chemical and physical properties of waste, therefore enabling stable heating at high treatment rates. CRIEPI (central research institute of electric power industry) focused on the advantages of arc plasma heating, and has clarified that arc plasma heating can be used in a simultaneous melting treatment process for low-level miscellaneous mixed solid waste, generated from nuclear power plants for volume reduction, and in the stabilization of radionuclides. (authors)

  6. High level nuclear waste treatment in the Defense Waste Processing Facility: Overview and integrated flowsheet model

    International Nuclear Information System (INIS)

    Design and construction of the world's largest vitrification facility for high level nuclear waste has been nearly completed at the US Department of Energy's Savannah River Site. Equipment testing and calibration are currently being performed in preparation for the nonradioactive Chemical Runs in the late 1991. In 1993, the Defense Waste Processing Facility (DWPF) will begin producing 100 kg/hr of radioactive waste glass at 28 wt% waste oxide loading. This paper describes all phases of waste processing operations in DWPF and waste tank farms using the integrated flowsheet modeling approach. Particular emphases are given to recent developments in the DWPF processes and design

  7. Development and status of the AL Mixed Waste Treatment Plan or I love that mobile unit of mine

    International Nuclear Information System (INIS)

    Nine Department of Energy (DOE) sites reporting to the Albuquerque Office (AL) have mixed waste that is chemically hazardous and radioactive. The hazardous waste regulations require the chemical portion of mixed waste to be to be treated to certain standards. The total volume of low-level mixed waste at the nine sites is equivalent to 7,000 drums, with individual site volumes ranging from 1 gallon of waste at the Pinellas Plant to 4,500 drums at Los Alamos National Laboratory. Nearly all the sites have a diversity of wastes requiring a diversity of treatment processes. Treatment capacity does not exist for much of this waste, and it would be expensive for each site to build the diversity of treatment processes needed to treat its own wastes. DOE-AL assembled a team that developed the AL Mixed Waste Treatment Plan that uses the resources of the nine sites to treat the waste at the sites. Work on the plan started in October 1993, and the plan was finalized in March 1994. The plan uses commercial treatment, treatability studies, and mobile treatment units. The plan specifies treatment technologies that will be built as mobile treatment units to be moved from site to site. Mobile units include bench-top units for very small volumes and treatability studies, drum-size units that treat one drum per day, and skid-size units that handle multiple drum volumes. After the tools needed to treat the wastes were determined, the sites were assigned to provide part of the treatment capacity using their own resources and expertise. The sites are making progress on treatability studies, commercial treatment, and mobile treatment design and fabrication. To date, this is the only plan for treating waste that brings the resources of several DOE sites together to treat mixed waste. It is the only program actively planning to use mobile treatment coordinated between DOE sites

  8. The development of radioactive waste treatment technology(IV)

    International Nuclear Information System (INIS)

    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)

  9. Region 9 NPDES Facilities 2012- Waste Water Treatment Plants

    Data.gov (United States)

    U.S. Environmental Protection Agency — Point geospatial dataset representing locations of NPDES Waste Water Treatment Plant Facilities. NPDES (National Pollution Discharge Elimination System) is an EPA...

  10. Region 9 NPDES Facilities - Waste Water Treatment Plants

    Data.gov (United States)

    U.S. Environmental Protection Agency — Point geospatial dataset representing locations of NPDES Waste Water Treatment Plant Facilities. NPDES (National Pollution Discharge Elimination System) is an EPA...

  11. State waste discharge permit application, 200-E chemical drain field

    Energy Technology Data Exchange (ETDEWEB)

    1994-06-01

    As part of the Hanford Federal Facility Agreement and Consent Order negotiations (Ecology et al. 1994), the US Department of Energy, Richland Operations Office, the US Environmental Protection Agency, and the Washington State Department of Ecology agreed that liquid effluent discharges to the ground on the Hanford Site which affect groundwater or have the potential to affect ground would be subject to permitting under the structure of Chapter 173-216 (or 173-218 where applicable) of the Washington Administrative Code, the State Waste Discharge Permit Program. As a result of this decision, the Washington State Department of Ecology and the US Department of Energy, Richland Operations Office entered into Consent Order No. DE 91NM-177, (Ecology and DOE-RL 1991). The Consent Order No. DE 91NM-177 requires a series of permitting activities for liquid effluent discharges. This document presents the State Waste Discharge Permit (SWDP) application for the 200-E Chemical Drain Field. Waste water from the 272-E Building enters the process sewer line directly through a floor drain, while waste water from the 2703-E Building is collected in two floor drains, (north and south) that act as sumps and are discharged periodically. The 272-E and 2703-E Buildings constitute the only discharges to the process sewer line and the 200-E Chemical Drain Field.

  12. State waste discharge permit application, 200-E chemical drain field

    International Nuclear Information System (INIS)

    As part of the Hanford Federal Facility Agreement and Consent Order negotiations (Ecology et al. 1994), the US Department of Energy, Richland Operations Office, the US Environmental Protection Agency, and the Washington State Department of Ecology agreed that liquid effluent discharges to the ground on the Hanford Site which affect groundwater or have the potential to affect ground would be subject to permitting under the structure of Chapter 173-216 (or 173-218 where applicable) of the Washington Administrative Code, the State Waste Discharge Permit Program. As a result of this decision, the Washington State Department of Ecology and the US Department of Energy, Richland Operations Office entered into Consent Order No. DE 91NM-177, (Ecology and DOE-RL 1991). The Consent Order No. DE 91NM-177 requires a series of permitting activities for liquid effluent discharges. This document presents the State Waste Discharge Permit (SWDP) application for the 200-E Chemical Drain Field. Waste water from the 272-E Building enters the process sewer line directly through a floor drain, while waste water from the 2703-E Building is collected in two floor drains, (north and south) that act as sumps and are discharged periodically. The 272-E and 2703-E Buildings constitute the only discharges to the process sewer line and the 200-E Chemical Drain Field

  13. Global Nuclear Energy Partnership Waste Treatment Baseline

    Energy Technology Data Exchange (ETDEWEB)

    Gombert, Dirk; Ebert, William; Marra, James; Jubin, Robert; Vienna, John [Idaho National laboratory, 2525 Fremont Ave., Idaho Falls, ID 83402 (United States)

    2008-07-01

    The Global Nuclear Energy Partnership (GNEP) program is designed to demonstrate that a proliferation-resistant and sustainable integrated nuclear fuel cycle can be commercialized and used internationally. Alternative stabilization concepts for byproducts and waste streams generated by fuel recycling processes were evaluated and a baseline set of waste forms was recommended for the safe disposition of waste streams. Specific waste forms are recommended based on the demonstrated or expected commercial practicability and technical maturity of the processes needed to make the waste forms, and expected performance of the waste form materials when disposed. Significant issues remain in developing technologies to process some of the wastes into the recommended waste forms, and a detailed analysis of technology readiness may lead to the choice of a different waste form than what is recommended herein. Evolving regulations could also affect the selection of waste forms. (authors)

  14. Global Nuclear Energy Partnership Waste Treatment Baseline

    Energy Technology Data Exchange (ETDEWEB)

    Dirk Gombert; William Ebert; James Marra; Robert Jubin; John Vienna

    2008-05-01

    The Global Nuclear Energy Partnership program (GNEP) is designed to demonstrate a proliferation-resistant and sustainable integrated nuclear fuel cycle that can be commercialized and used internationally. Alternative stabilization concepts for byproducts and waste streams generated by fuel recycling processes were evaluated and a baseline of waste forms was recommended for the safe disposition of waste streams. Waste forms are recommended based on the demonstrated or expected commercial practicability and technical maturity of the processes needed to make the waste forms, and performance of the waste form materials when disposed. Significant issues remain in developing technologies to process some of the wastes into the recommended waste forms, and a detailed analysis of technology readiness and availability may lead to the choice of a different waste form than what is recommended herein. Evolving regulations could also affect the selection of waste forms.

  15. Global Nuclear Energy Partnership Waste Treatment Baseline

    International Nuclear Information System (INIS)

    The Global Nuclear Energy Partnership (GNEP) program is designed to demonstrate that a proliferation-resistant and sustainable integrated nuclear fuel cycle can be commercialized and used internationally. Alternative stabilization concepts for byproducts and waste streams generated by fuel recycling processes were evaluated and a baseline set of waste forms was recommended for the safe disposition of waste streams. Specific waste forms are recommended based on the demonstrated or expected commercial practicability and technical maturity of the processes needed to make the waste forms, and expected performance of the waste form materials when disposed. Significant issues remain in developing technologies to process some of the wastes into the recommended waste forms, and a detailed analysis of technology readiness may lead to the choice of a different waste form than what is recommended herein. Evolving regulations could also affect the selection of waste forms. (authors)

  16. Treatment of radioactive liquid waste by sorption on natural zeolite in Turkey

    International Nuclear Information System (INIS)

    Liquid radioactive waste has been generated from the use of radioactive materials in industrial applications, research and medicine in Turkey. Natural zeolites (clinoptilolite) have been studied for the removal of several key radionuclides (137Cs, 60Co, 90Sr and 110mAg) from liquid radioactive waste. The aim of the present study is to investigate effectiveness of zeolite treatment on decontamination factor (DF) in a combined process (chemical precipitation and adsorption) at the laboratory tests and scale up to the waste treatment plant. In this study, sorption and precipitation techniques were adapted to decontamination of liquid low level waste (LLW). Effective decontamination was achieved when sorbents are used during the chemical precipitation. Natural zeolite samples were taken from different zeolite formations in Turkey. Comparison of the ion-exchange properties of zeolite minerals from different formations shows that Gordes clinoptilolite was the most suitable natural sorbent for radionuclides under dynamic treatment conditions and as an additive for chemical precipitation process. Clinoptilolite were shown to have a high selectivity for 137Cs and 110mAg as sorbent. In the absence of potassium ions, native clinoptilolite removed 60Co and 90Sr very effectively from the liquid waste. In the end of this liquid waste treatment, decontamination factor was provided as 430 by using 0.5 mm clinoptilolite at 30 deg. C

  17. Chemical states of molybdenum in radioactive waste glass

    International Nuclear Information System (INIS)

    In order to confirm an expectation that the chemical state of molybdenum in glass reflects the phase separation tendency of the yellow solid from the melt of borosilicate glass, simulated waste glasses were prepared, and ESCA analysis was performed using a commercially available electron spectrometer (PHI550 E) with an excitation source consisting of Mg Kα-ray. The effects of the concentration of Mo and FE2O3 and the melting atmosphere (oxidizing or reducing) in which the samples were prepared on the chemical state of Mo and the solubility of MoO3 were examined. From the observation of Mo spectra, it was shown that Mo in waste glass had several valencies, e.g., Mo(3), Mo(4), Mo(5) and Mo(6), while Mo in the yellow solid separated from the melts exhibited hexa-valent state, the peak intensity of higher valencies increased relatively with the increase of MoO3 concentration, but the chemical state of Mo did not change remarkably around the solubility limit of MoO3, the melting atmosphere influenced on the Mo state in the waste glass, the peak intensity of Mo(6) increased relatively with the increasing Fe2O3 concentration, and Mo in devitrified glass exhibited hexa-valent state. (Yoshitake, I.)

  18. LAND TREATMENT FIELD STUDIES. VOLUME 6. INORGANIC PICKLING LIQUOR WASTE

    Science.gov (United States)

    This report presents the results of field measurements and observations of a land treatment site for the management of an inorganic pickling liquor waste. The waste is spread on the site as a 20% solids sludge. Sulfate and iron are known to be major waste constituents. The organi...

  19. Safety analysis report-building 3544 process waste treatment plant

    Energy Technology Data Exchange (ETDEWEB)

    Braatz, R.J.; Robinson, R.A.

    1976-06-01

    A new Process Waste Treatment Plant was constructed at ORNL. The wastes are processed through a precipitation-clarification step and then through an ion exchange step to remove the low-level activity in the waste before discharge into White Oak Creek. There are no unusual hazards associated with the operation of the plant. (auth)

  20. Research and development of radioactive waste treatment methods

    International Nuclear Information System (INIS)

    The Nuclear Research Institute (NRI) uses the reactor for research, training, isotope production and activation analyses. NRI generates about 150 m3 of liquid and 5 m3 of solid wastes every year. The researched methods applied to treatment of radwastes are coagulation-precipitation and two steps ion-exchange for liquid waste and compaction for solid waste are described. (author)

  1. Operational experience at radioactive waste treatment plant, after 15 years

    International Nuclear Information System (INIS)

    Available in abstract form only. Full text of publication follows: The experience of the radioactive waste treatment plant (PTDR) in Chile, which centralizes all activities related to pre-disposal activities in the radioactive waste management, in the country is presented. It is the solely waste treatment plant in the country, where radioactive waste are received from all nuclear and radioactive waste generators facilities located in the country. Radioactive waste in Chile proceeds from radioisotope application at industrial, health, universities research, and from two nuclear research centers. Lately, there have been included the radioactive wastes discovered in metal recycling facilities, which sometimes make big amounts. Radioactive Waste Treatment Plant was planned in 1990; adoption of decision and started operation in 1992. At that time, a facility to store waste packages as conditioned waste in cementitious matrices in standardized 200 l drums was built (43 m3 total capacity) for a storage period estimated in 15 years. The methodology and procedures developed has been transferred to Latin American and El Caribe professionals, through demonstration training courses held in this Waste Treatment Plant which recognized as Demonstration facilities to prepare people in the processing of radioactive waste from nuclear applications, previous to disposal. These procedures were the first one developed following international recommendations and complying requirements to immobilize the radioactive material to avoid the external intrusion of thirds, and requirements of dose radiation according to transport regulations for radioactive material. (authors)

  2. 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.

  3. Rheological properties of kaolin and chemically simulated waste

    International Nuclear Information System (INIS)

    The Savannah River Laboratory is conducting tests to determine the best operating conditions of pumps used to transfer insoluble radioactive sludges from old to new waste tanks. Because it is not feasible to conduct these tests with real or chemically simulated sludges, kaolin clay is being used as a stand-in for the solid waste. The rheology tests described herein were conducted to determine whether the properties of kaolin were sufficiently similar to those of real sludge to permit meaningful pump tests. The rheology study showed that kaolin can be substituted for real waste to accurately determine pump performance. Once adequately sheared, kaolin properties were found to remain constant. Test results determined that kaolin should not be allowed to settle more than two weeks between pump tests. Water or supernate from the waste tanks can be used to dilute sludge on an equal volume basis because they identically affect the rheological properties of sludge. It was further found that the fluid properties of kaolin and waste are insensitive to temperature

  4. Method of waste stabilization with dewatered chemically bonded phosphate ceramics

    Science.gov (United States)

    Wagh, Arun; Maloney, Martin D.

    2010-06-29

    A method of stabilizing a waste in a chemically bonded phosphate ceramic (CBPC). The method consists of preparing a slurry including the waste, water, an oxide binder, and a phosphate binder. The slurry is then allowed to cure to a solid, hydrated CBPC matrix. Next, bound water within the solid, hydrated CBPC matrix is removed. Typically, the bound water is removed by applying heat to the cured CBPC matrix. Preferably, the quantity of heat applied to the cured CBPC matrix is sufficient to drive off water bound within the hydrated CBPC matrix, but not to volatalize other non-water components of the matrix, such as metals and radioactive components. Typically, a temperature range of between 100.degree. C.-200.degree. C. will be sufficient. In another embodiment of the invention wherein the waste and water have been mixed prior to the preparation of the slurry, a select amount of water may be evaporated from the waste and water mixture prior to preparation of the slurry. Another aspect of the invention is a direct anyhydrous CBPC fabrication method wherein water is removed from the slurry by heating and mixing the slurry while allowing the slurry to cure. Additional aspects of the invention are ceramic matrix waste forms prepared by the methods disclosed above.

  5. Recycling and treatment of plastic waste

    International Nuclear Information System (INIS)

    Radiation technology, using gamma or electron beams, develops its benefits at highest yield if macromolecular systems are treated. This is valid equally if build-up processes (polymerization, crosslinking) or degradative processes (chain scission, depolymerization) are initiated by radiation. Radiation-induced degradation is applied to convert polytetrafluoroethylene (Teflon) scrap into powder and low-molecular-weight products used in the production of other perfluoro compounds. The Teflon powder is blended with other materials for use as lubricant, and the perfluorocarboxylic derivatives are employed as surfactants. Radiation treatment of polymers could play a build-up role in the recycling of polymer wastes. The non-selective energy transfer from gamma or electron sources to polymer systems produces many kinds of reactive centers such as free radicals, oxydized and peroxydized active groups, on which further reactions may occur. In presence of monomer-like or oligomer-like reactive additives graft-copolymerization may take place, compatibilizing in this way the originally incompatible polymer components. Such a compatibilization is the key solution to recycling commingled plastic waste or producing composite materials of fibrous natural polymers and synthetic thermoplastics

  6. Hanford Site waste treatment/storage/disposal integration

    International Nuclear Information System (INIS)

    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

  7. Development and demonstration of treatment technologies for the processing of US Department of Energy mixed waste

    International Nuclear Information System (INIS)

    Mixed waste is defined as waste contaminated with chemically hazardous (governed by the Resource Conservation and Recovery Act) and radioactive species [governed by US Department of Energy (DOE) orders]. The Mixed Waste Integrated Program (MWIP) is responding to the need for DOE mixed waste treatment technologies that meet these dual regulatory requirements. MWIP is developing emerging and innovative treatment technologies to determine process feasibility. Technology demonstrations will be used to determine whether processes are superior to existing technologies in reducing risk, minimizing life-cycle cost, and improving process performance. The Program also provides a forum for stakeholder and customer involvement in the technology development process. MWIP is composed of six technical areas that support a mixed-waste treatment system: (1) systems analysis, (2) materials handling, (3) chemical/physical separation, (4) waste destruction and stabilization, (5) off-gas treatment, and (6) final waste form stabilization. The status of the technical initiatives and the current research, development, and demonstration in each of these areas is described in this paper

  8. Department of Energy treatment capabilities for greater-than-Class C low-level radioactive waste

    International Nuclear Information System (INIS)

    This report provides brief profiles for 26 low-level and high-level waste treatment capabilities available at the Idaho National Engineering Laboratory (INEL), Lawrence Livermore National Laboratory (LLNL), Los Alamos National Laboratory (LANL), Oak Ridge National Laboratory (ORNL), Pacific Northwest Laboratory (PNL), Rocky Flats Plant (RFP), Savannah River Site (SRS), and West Valley Demonstration Plant (WVDP). Six of the treatments have potential use for greater-than-Class C low-level waste (GTCC LLW). They include: (a) the glass ceramic process and (b) the Waste Experimental Reduction Facility incinerator at INEL; (c) the Super Compaction and Repackaging Facility and (d) microwave melting solidification at RFP; (e) the vitrification plant at SRS; and (f) the vitrification plant at WVDP. No individual treatment has the capability to treat all GTCC LLW streams. It is recommended that complete physical and chemical characterizations be performed for each GTCC waste stream, to permit using multiple treatments for GTCC LLW

  9. Treatment of low level radioactive waste by plasma technology

    International Nuclear Information System (INIS)

    Into the interest of the waste producers and future generation a high volume reduction factor (VRF) of the waste is desired in order to minimize the volume and overall costs of storage and waste disposal. Not only the VRF is of importance but also the growing requirements for improved quality of the final waste form. Therefore the plasma technology can also be used to recondition previous conditioned waste packages that don't meet any longer the present acceptance criteria for final disposal. This paper describes further the principles of plasma, the different waste feed systems, off gas treatment, operational experience and future plasma plants

  10. Chemical health risk assessment for hazardous and mixed waste management units at Lawrence Livermore National Laboratory

    International Nuclear Information System (INIS)

    The Lawrence Livermore National Laboratory (LLNL) operates three Hazardous Waste Management Facilities with 24 associated waste management units for the treatment and storage of hazardous and mixed wastes. These wastes are generated by research programs and support operations. The storage and treatment units are presently operated under interim status in accordance with the requirements of the US Envirorunental Protection Agency (US EPA) and the Department of Toxic Substances Control (DTSC), a division of the California Envirorunental Protection Agency (Cal/EPA). As required by the California Hazardous Waste Control Act and the Resource Conservation and Recovery Act (RCRA), LLNL ha s applied for a Part B permit to continue operating the storage and waste treatment facilities. As part of this permitting process, LLNL is required to conduct a health risk assessment (HRA) to examine the potential health impacts to the surrounding community from continued storage and treatment of hazardous and mixed wastes. analysis document presents the results of this risk assessment. An analysis of maximum credible chemical accidents is also included in Section 7.0. This HRA was prepared in accordance with procedures set forth by the California Air Pollution Control Officers Association (CAPCOA) ''Air Toxics Assessment Manual,'' CAPCOA guidelines for preparing risk assessments under the Air Toxic ''Hot Spots'' Act (AB 2588) and requirements of the US EPA. By following these procedures, this risk assessment presents a conservative analysis of a hypothetical Maximally Exposed Individual (MEI) using many worst-case assumptions that will not apply to an actual individual. As such, the risk estimates presented should be regarded as a worst-case estimate of any actual risk that may be present

  11. Thermal treatment of high-caloric waste in fluidized bed incineration plants in Austria

    International Nuclear Information System (INIS)

    The importance of thermal treatment of waste and residues in Austria is expected to rise due to the current changes of the legal situation in waste management. Assessing the rank order of different thermal treatment processes for waste management it has been shown that - especially caused by the rising importance of the mechanical treatment step in the mechanical-biological residual waste treatment and the subsequent necessity of the thermal treatment of a high-caloric preprocessed waste stream - the importance of the fluidized bed technology will increase. The main advantages are the high existing capacities as well as the flexibility of this technology in regard of fuel properties and further on the fact of the lacking influence of the ash towards the quality of a product. This is true although the thermal treatment in fluidized bed incinerators requires some processing of the waste. This doctoral thesis also contains a thorough physical and chemical characterization of various waste fuels - especially those which have been used during full scale incineration experiments. This characterization includes a comparison with fossil fuel. The practical part contains the documentation and balancing of full scale incineration experiments. A comparison of a reference experiment with experiments when waste fuel has been thermally utilized showed that a significant increase of emissions to the atmosphere has not been observed. Based on the incineration experiments conclusions in regard of waste fuels as well as different categories of thermal treatment plants are being stated. Finally, a recommendation of the assignation of various waste streams to different categories of thermal treatment plants is being made. (author)

  12. 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).

  13. Mixed-waste treatment -- What about the residuals?

    International Nuclear Information System (INIS)

    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

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

    International Nuclear Information System (INIS)

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

  15. The treatment of Medical Waste – technologies, location and origin

    OpenAIRE

    Krstev, Boris; Krstev, Aleksandar; Danevski, Tome; Jovanovski, Vlatko; Lazarov, Aleksandar

    2012-01-01

    The medical waste categorization belongs to the group of hazardous waste. The management and the treatment in most cases are invalid. The resolving of these wastes should be effectively and economically and requires special functional systems or scenario. It’s a challenge for the countries in the development, similar to our country. The establishment of the system like the integrated management of medical wastes has occurred and looked for clear information and education for people. Also, the...

  16. The hazardous medical wastetreatment technologies, location and origin

    OpenAIRE

    Alili, Agron; Krstev, Boris; Krstev, Aleksandar; Stamenov, Goran; Stoilov, Zoran

    2015-01-01

    The medical waste categorization belongs to the group of hazardous waste. The management and the treatment in most cases are invalid. The resolving of these wastes should be effectively and economically and requires special functional systems or scenario. It’s a challenge for the countries in the development, similar to our country. The establishment of the system like the integrated management of medical wastes has occurred and looked for clear information and education for people. Also, the...

  17. Idaho Chemical Processing Plant Spent Fuel and Waste Management Technology Development Program Plan

    International Nuclear Information System (INIS)

    The Department of Energy (DOE) has received spent nuclear fuel (SNF) at the Idaho Chemical Processing Plant (ICPP) for interim storage and reprocessing since 1953. Reprocessing of SNF has resulted in an existing inventory of 1.5 million gallons of radioactive sodium-bearing liquid waste and 3800 cubic meters (m3) of calcine, in addition to the 768 metric tons (MT) of SNF and various other fuel materials in inventory. To date, the major activity of the ICPP has been the reprocessing of SNF to recover fissile uranium; however, recent changes in world events have diminished the demand to recover and recycle this material. As a result, DOE has discontinued reprocessing SNF for uranium recovery, making the need to properly manage and dispose of these and future materials a high priority. In accordance with the Nuclear Waste Policy Act (NWPA) of 1982, as amended, disposal of SNF and high-level waste (HLW) is planned for a geological repository. Preparation of SNF, HLW, and other radioactive wastes for disposal may include mechanical, physical, and/or chemical processes. This plan outlines the program strategy of the ICPP Spent Fuel and Waste Management Technology Development Program (SF ampersand WMTDP) to develop and demonstrate the technology required to ensure that SNF and radioactive waste will properly stored and prepared for final disposal. Program elements in support of acceptable interim storage and waste minimization include: developing and implementing improved radioactive waste treatment technologies; identifying and implementing enhanced decontamination and decommissioning techniques; developing radioactive scrap metal (RSM) recycle capabilities; and developing and implementing improved technologies for the interim storage of SNF

  18. Idaho Chemical Processing Plant Spent Fuel and Waste Management Technology Development Program Plan

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1993-09-01

    The Department of Energy (DOE) has received spent nuclear fuel (SNF) at the Idaho Chemical Processing Plant (ICPP) for interim storage and reprocessing since 1953. Reprocessing of SNF has resulted in an existing inventory of 1.5 million gallons of radioactive sodium-bearing liquid waste and 3800 cubic meters (m{sup 3}) of calcine, in addition to the 768 metric tons (MT) of SNF and various other fuel materials in inventory. To date, the major activity of the ICPP has been the reprocessing of SNF to recover fissile uranium; however, recent changes in world events have diminished the demand to recover and recycle this material. As a result, DOE has discontinued reprocessing SNF for uranium recovery, making the need to properly manage and dispose of these and future materials a high priority. In accordance with the Nuclear Waste Policy Act (NWPA) of 1982, as amended, disposal of SNF and high-level waste (HLW) is planned for a geological repository. Preparation of SNF, HLW, and other radioactive wastes for disposal may include mechanical, physical, and/or chemical processes. This plan outlines the program strategy of the ICPP Spent Fuel and Waste Management Technology Development Program (SF&WMTDP) to develop and demonstrate the technology required to ensure that SNF and radioactive waste will properly stored and prepared for final disposal. Program elements in support of acceptable interim storage and waste minimization include: developing and implementing improved radioactive waste treatment technologies; identifying and implementing enhanced decontamination and decommissioning techniques; developing radioactive scrap metal (RSM) recycle capabilities; and developing and implementing improved technologies for the interim storage of SNF.

  19. Guidelines for generators of hazardous chemical waste at LBL and guidelines for generators of radioactive and mixed waste at LBL

    International Nuclear Information System (INIS)

    In part one of this document the Governing Documents and Definitions sections provide general guidelines and regulations applying to the handling of hazardous chemical wastes. The remaining sections provide details on how you can prepare your waste properly for transport and disposal. They are correlated with the steps you must take to properly prepare your waste for pickup. The purpose of the second part of this document is to provide the acceptance criteria for the transfer of radioactive and mixed waste to LBL's Hazardous Waste Handling Facility (HWHF). These guidelines describe how you, as a generator of radioactive or mixed waste, can meet LBL's acceptance criteria for radioactive and mixed waste

  20. Toxicity evaluation of leachate of solid waste after biological and photocatalitical treatment

    OpenAIRE

    Ronaldo Teixeira Pelegrini; José Euclides Stipp Paterniani; Núbia Natália de Brito Pelegrini; Simoni Micheti Geraldo; Juliana Graciani Carniato

    2007-01-01

    The final disposition of urban solid wastes is a practice that still causes serious environmental impacts generating several pollutant subproducts, such as the landfill leachate. The toxicity tests are used in the pollution control with the scope of finding the permissive concentrations of a chemical agent for the development survival of particular alive organisms. This work aims the toxicity evaluation study in leachate samples of in natura solid wastes, after biological treatment through sl...

  1. Radiological characterization of waste products at a catalan drinking water treatment plant

    OpenAIRE

    Camacho García, Antonia; Montaña Gurrera, Montserrat; Serrano Carreño, M. Isabel; Blázquez Pérez, Sonia M.; Montes, Sergio; Ganzer Martí, Marta; Devesa, Ricard; Duch Guillen, María Amor

    2014-01-01

    Conventional Drinking Water Treatment Plants (DWTPs) have a fairly standard sequence of processes which essentially consist of solid separation using either physical processes such as settling and filtration, or chemical processes such as coagulation and disinfection. Consequently, large quantities of solid wastes (sludge, filtration media, exhausted ion exchange resin and astewaters) are generated every year by DWTPs. These solid wastes may contain all kinds of pollutants, some with signi...

  2. Challenges when performing economic optimization of waste treatment: A review

    DEFF Research Database (Denmark)

    Juul, Nina; Münster, Marie; Ravn, H.;

    2013-01-01

    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...

  3. OPTIMIZATION OF THE CONDITIONS REQUIRED FOR CHEMICAL AND BIOLOGICAL MODIFICATION OF THE YEAST WASTE FROM BEER MANUFACTURING TO PRODUCE ADHESIVE COMPOSITIONS

    OpenAIRE

    Davud Kadimaliev,; Vladimir Telyatnik,; Victor Revin,; Alexander Parshin,; Surhay Allahverdi,; Gokhan Gunduz; Elena Kezina,; Nejla Asık

    2012-01-01

    During the production of beer large amounts of yeast waste are generated. This paper considers the possible making of environmentally friendly adhesive compositions from such wastes. Chemical treatment of yeast wastes increases their adhesive characteristics. Chemical cross-linking with glutaric aldehyde and biological cross-linking by enzyme transglutaminase improves the moisture resistance of the adhesive compositions. In terms of their physical and mechanical parameters they are not inferi...

  4. Treatment of hazardous organic wastes using silent discharge plasmas

    International Nuclear Information System (INIS)

    During the past two decades, interest in applying non-equilibrium plasmas to the removal of hazardous chemicals from gaseous media has been growing, in particular from heightened concerns over the pollution of our environment and a growing body of environmental regulations. At the Los Alamos National Laboratory, we are currently engaged in a project to develop non-equilibrium plasma technology for hazardous waste treatment. Our present focus is on dielectric-barrier discharges, which are historically called silent electrical discharges. This type of plasma is also named a silent discharge plasma (SDP). We have chosen this method due to its potential for high energy efficiency, its scientific and technological maturity, and its scalability. The SDP process has been demonstrated to be reliable and economical for the industrial-scale synthesis of ozone, where municipal water treatment plants frequently require the on-site generation of thousands of kilograins per day (Eliasson ampersand Kogelschatz). The related methods of corona processing are presently the focus of work at other institutions, particularly for flue gas processing. Both SDP and corona processes are characterized by the production of large quantities of highly reactive free radicals, especially atomic oxygen O(3P) and the hydroxyl OH, in the gaseous medium and their subsequent reaction with contaminants. Our primary objective is to convert hazardous or toxic chemicals into non-hazardous compounds or into materials which are more amenable to treatment. In the ideal case, the hazardous wastes are destructively oxidized to simpler, non-hazardous compounds plus CO2 and H2O. Sometimes the reaction products are still potentially hazardous, but are easily treated by conventional methods to yield non-hazardous products

  5. Progress on Radioactive Waste Treatment Facilities Construction

    Institute of Scientific and Technical Information of China (English)

    2011-01-01

    In 2011, five projects were undertaken by radioactive waste projects management department, which are "Cold Commissioning of the Pilot Project on Radioactive Waste Retrieval and Conditioning (abbreviation 'Pilot Project')", "Radioactive Ventilation Project Construction (abbreviation 'Ventilation

  6. Treatment methods for the waste from the pyrometallurgical treatment of SNF abroad

    International Nuclear Information System (INIS)

    The treatment methods for the waste from the pyrometallurgical treatment of SNF abroad were re- viewed in this paper. The pyrometallurgical treatment process generates two kinds of high-level waste--a metallic and a salt-home waste. The metallic waste was melted to form ingot that was the metal waste form. For the salt-home waste, three methods were potential, immobilization in ceramic matrix, phosphate precipitation, vitrification after the converting the chloride cations to oxides. China's research is yet at an early stage of development, so we should make reference to the experiences gained by those countries. (authors)

  7. Methods in the treatment of sodium wastes

    International Nuclear Information System (INIS)

    In the domain of sodium waste processing, we have followed a logical route that has enabled us to propose a global method with respect to sodium wastes. This approach has led to: The choice of only those sodium processes using water; The development of sodium purification methods; The development of methods for cutting metallic wastes soiled by or filled with sodium; The transformation of the resulting sodium hydroxide into ultimate solid wastes for surface storage. (author)

  8. 40 CFR 35.925-15 - Treatment of industrial wastes.

    Science.gov (United States)

    2010-07-01

    ... 40 Protection of Environment 1 2010-07-01 2010-07-01 false Treatment of industrial wastes. 35.925... § 35.925-15 Treatment of industrial wastes. That the allowable project costs do not include (a) costs of interceptor or collector lines constructed exclusively, or almost exclusively, to serve...

  9. Conceptual project of waste treatment plant of CDTN

    International Nuclear Information System (INIS)

    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.)

  10. Barriers in process of treatment with radioactive wastes

    International Nuclear Information System (INIS)

    In this leaflet the scheme of the barriers used in process of treatment of radioactive wastes in Bohunice Radwaste Treatment Centre (BSC RAO) are presented. Transport, sorting, compacting, preparation of final product as well as transport and disposal of radioactive wastes as final product are described

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

    International Nuclear Information System (INIS)

    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

  12. 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.

  13. Thermophilic slurry-phase treatment of petroleum hydrocarbon waste sludges

    International Nuclear Information System (INIS)

    Chemoheterotrophic thermophilic bacteria were used to achieve enhanced hydrocarbon degradation during slurry-phase treatment of oily waste sludges from petroleum refinery operations. Aerobic and anaerobic bacterial cultures were examined under thermophilic conditions to assess the effects of mode of metabolism on the potential for petroleum hydrocarbon degradation. The study determined that both aerobic and anaerobic thermophilic bacteria are capable of growth on petroleum hydrocarbons. Thermophilic methanogenesis is feasible during the degradation of hydrocarbons when a strict anaerobic condition is achieved in a slurry bioreactor. Aerobic thermophilic bacteria achieved the largest apparent reduction in chemical oxygen demand, freon extractable oil, total and volatile solid,s and polycyclic aromatic hydrocarbons (PAHs) when treating oily waste sludges. The observed shift with time in the molecular weight distribution of hydrocarbon material was more pronounced under aerobic metabolic conditions than under strict anaerobic conditions. The changes in the hydrocarbon molecular weight distribution, infrared spectra, and PAH concentrations during slurry-phase treatment indicate that the aerobic thermophilic bioslurry achieved a higher degree of hydrocarbon degradation than the anaerobic thermophilic bioslurry during the same time period

  14. Full scale treatment of phenolic coke coking waste water under unsteady conditions

    Energy Technology Data Exchange (ETDEWEB)

    Suschka, Jan [Institute for Ecology of Industrial Areas, Katowice (Poland); Morel, Jacek; Mierzwinski, Stanislaw; Januszek, Ryszard [Coke Plant Przyjazn, Dabrowa Gornicza (Poland)

    1993-12-31

    Phenolic waste water from the largest coke coking plant in Poland is treated at a full technical scale. From the very beginning it became evident that very high qualitative variations in short and long periods were to be expected. For this purpose, the biological treatment plant based on activated sludge is protected through preliminary physical-chemical treatment and the results are secured by a final chemical stage of treatment. Nevertheless, improvements in the performance of the treatment plant have been found necessary to introduce. In this work, the experience gained over the last five years is described and developed improvements were presented. 3 refs., 9 figs., 1 tab.

  15. Challenges when performing economic optimization of waste treatment: A review

    International Nuclear Information System (INIS)

    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

  16. Avaliação das técnicas de precipitação química e encapsulamento no tratamento e destinação conjunta de resíduos líquidos contendo cromo e vidrarias de laboratório Evaluation of chemical precipitation and encapsulation techniques in the treatment and joint disposal of liquid wastes containing chromium and laboratory glassware

    Directory of Open Access Journals (Sweden)

    Juliana Graciela Giovannini

    2008-01-01

    Full Text Available In this paper, we present procedures for the treatment and final disposal of residual solutions containing chromium, in order to evaluate the effectiveness of chemical precipitation of the metal and the potential of the glass encapsulation technique, using broken laboratory glassware. The results demonstrated that pH-values convenient for chemical precipitation are between 10 - 11. With regard to Cr(OH3 encapsulation, the leaching and solubilization tests allowed to classify the waste as non-dangerous and non-inert. Finally, it is pointed out that the adoption of waste management practices in universities should be encouraged, helping to train professionals skilled in good laboratory practices.

  17. Different indices to express biodegradability in organic solid wastes. Application to full scale waste treatment plants

    OpenAIRE

    Ponsá Salas, Sergio

    2010-01-01

    Biodegradable waste receives especial attention in the European Legislation (Revised Framework Directive 2008/98/CE) and this has been also reflected in Spanish Legislation in the Plan Nacional Integrado de Residuos 20082015 (PNIR), due to the high importance that this municipal solid waste fraction has on the waste treatment environmental impact when it is not treated correctly and the possibility of recycling the biodegradable waste, to finally obtain compost or/and biogas that means green ...

  18. Waste Water Treatment of Dye Contamination

    Directory of Open Access Journals (Sweden)

    Pattana Boonyaprapa

    2009-01-01

    Full Text Available The objectives of this research were to study tie-dye process data and wastewater characteristics from 60 entrepreneurs, and to study the colour density treatment in pilot scale by using upflow anaerobic filters. From 60 filled-out questionnaires, it was found that all tie-dye entrepreneurs used reactive dyes by a hot method. Ninety-eight percent of the tie-dye enterpreneurs produced wastewater at the rate of not more than 1500 liters per day. All of them lacked tie-dye wastewater treatment systems. Eighty-five percent of tie-dye entrepreneurs agreed that there must be wastewater treatment before release into the environment. From group discussions, it was found that the entrepreneurs realized the wastewater problem and wanted to carry out environment friendly tie-dyeing. Our study demonstrated that the average value of the colour density, chemical oxygen demand (COD, total dissolved solids (TDS and pH of the wastewater characteristics were 170 SU (space units, 1584 mg/l, 2487 mg/l and 8, respectively. For the upflow anaerobic filter, 5 sets of experiments, with 24 hours retention time, were designed, with 0, 1, 2, 3 and 4 % of cow’s feces ferment, respectively (sets 1st-5th. The result showed decreasing colour densities from 170 SU to 160 SU (dark colour, 60 SU (very light colour, 12 SU (no colour, 10 SU (no colour and 10 SU (no colour, respectively. We conclude that the upflow anaerobic filter, containing 2% cow’s feces ferment is an efficient way to reduce colour density of the wastewater. Mixing cow’s feces ferment with tie-dye wastewater increased COD and TDS in wastewater. Mean COD was increased by residual organic matter from 1584 mg/l (before treatment to (after-treatment, sets 2nd- 5th 1600 mg/l, 1680 mg/l, 1710 mg/l and 1750 mg/l, respectively. COD aftertreatment was higher than the industrial effluence standard (400 mg/l. Further treatment COD might include wetland procedures. TDS was increased by some residual organic matter

  19. 300 Area waste acid treatment system closure plan

    International Nuclear Information System (INIS)

    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

  20. 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.

  1. Technology needs for treatment of DOE's low-level mixed wastes

    International Nuclear Information System (INIS)

    The US Department of Energy (DOE) stores and generates significant amounts of low-level mixed wastes (LLMW) consisting of radioactive materials mixed with hazardous chemical substances. Many of these wastes are regulated under the US Environmental Protection Agency (EPA) Land Disposal Restrictions and must be treated and disposed in compliance with applicable state and federal requirements. In general, treatment requirements include elimination of organic hazardous constituents and stabilization of inorganic hazardous constituents. Final waste forms must meet both EPA leach testing and DOE disposal acceptance criteria. The DOE currently does not have an adequate capability to meet these treatment objectives. The Mixed Waste Treatment Project has been established by the DOE to define needed LLMW treatment capabilities as a basis for either a prototype plant design or an existing facility modifications. Existing DOE mixed waste data bases were analyzed to identify the range of waste quantities and types and to define broad treatment categories needed to bring these wastes into compliance. Using these treatment categories as a starting point, we constructed a baseline flow sheet defining process steps from receipt through final form. From this baseline flow sheet, we developed functional and operational requirements (F ampersand ORs) for each process train. An initial set of near-term technologies was identified for each process step, and alternative near- and long-term options were listed. Based on these analyses, we identified technology gaps and improvement needs in the areas of characterization, waste handling, segregation and sorting, size reduction, decontamination, materials recycle, primary and secondary treatment for RCRA compliance, offgas treatment, and final waste forms

  2. Technology needs for treatment of DOE's low-level mixed wastes

    International Nuclear Information System (INIS)

    The US Department of Energy (DOE) stores and generates significant amounts of low-level mixed wastes (LLMW) consisting of radioactive materials mixed with hazardous chemical substances. Many of these wastes are regulated under the US Environmental Protection Agency (BPA) Land Disposal Restrictions and must be treated and disposed in compliance with applicable state and federal requirements. In general treatment requirements include elimination of organic hazardous constituents and stabilization of inorganic hazardous constituents. Final waste forms must meet both EPA leach testing and DOE disposal acceptance criteria. The DOE currently does not have an adequate capability to meet these treatment objectives. The Mixed Waste Treatment Project has been established by the DOE to define needed LLMW treatment capabilities as a basis for either a prototype plant design or an existing facility modification. Existing DOE mixed waste data bases were analyzed to identify the range of waste quantities and types and to define broad treatment categories needed to bring these wastes into compliance. Using these treatment categories as a starting point, we constructed a baseline flow sheet defining process steps from receipt through final form. From this baseline flow sheet, we developed functional and operational requirements (F and ORs) for each process train. An initial set of near-term technologies was identified for each process step, and alternative near- and long-term options were listed. Based on these analyses, we identified technology gaps and improvement needs in the areas of characterization, waste handling, segregation and sorting, size reduction, decontamination, materials recycle, primary and secondary treatment for RCRA compliance, offgas treatment, and final waste forms. (author)

  3. Pyrochlore as nuclear waste form. Actinide uptake and chemical stability

    International Nuclear Information System (INIS)

    Radioactive waste is generated by many different technical and scientific applications. For the past decades, different waste disposal strategies have been considered. Several questions on the waste disposal strategy remain unanswered, particularly regarding the long-term radiotoxicity of minor actinides (Am, Cm, Np), plutonium and uranium. These radionuclides mainly arise from high level nuclear waste (HLW), specific waste streams or dismantled nuclear weapons. Although many countries have opted for the direct disposal of spent fuel, from a scientific and technical point of view it is imperative to pursue alternative waste management strategies. Apart from the vitrification, especially for trivalent actinides and Pu, crystalline ceramic waste forms are considered. In contrast to glasses, crystalline waste forms, which are chemically and physically highly stable, allow the retention of radionuclides on well-defined lattice positions within the crystal structure. Besides polyphase ceramics such as SYNROC, single phase ceramics are considered as tailor made host phases to embed a specific radionuclide or a specific group. Among oxidic single phase ceramics pyrochlores are known to have a high potential for this application. This work examines ZrO2 based pyrochlores as potential nuclear waste forms, which are known to show a high aqueous stability and a high tolerance towards radiation damage. This work contributes to (1) understand the phase stability field of pyrochlore and consequences of non-stoichiometry which leads to pyrochlores with mixed cationic sites. Mixed cationic occupancies are likely to occur in actinide-bearing pyrochlores. (2) The structural uptake of radionuclides themselves was studied. (3) The chemical stability and the effect of phase transition from pyrochlore to defect fluorite were probed. This phase transition is important, as it is the result of radiation damage in ZrO2 based pyrochlores. ZrO2 - Nd2O3 pellets with pyrochlore and defect

  4. Pyrochlore as nuclear waste form. Actinide uptake and chemical stability

    Energy Technology Data Exchange (ETDEWEB)

    Finkeldei, Sarah Charlotte

    2015-07-01

    Radioactive waste is generated by many different technical and scientific applications. For the past decades, different waste disposal strategies have been considered. Several questions on the waste disposal strategy remain unanswered, particularly regarding the long-term radiotoxicity of minor actinides (Am, Cm, Np), plutonium and uranium. These radionuclides mainly arise from high level nuclear waste (HLW), specific waste streams or dismantled nuclear weapons. Although many countries have opted for the direct disposal of spent fuel, from a scientific and technical point of view it is imperative to pursue alternative waste management strategies. Apart from the vitrification, especially for trivalent actinides and Pu, crystalline ceramic waste forms are considered. In contrast to glasses, crystalline waste forms, which are chemically and physically highly stable, allow the retention of radionuclides on well-defined lattice positions within the crystal structure. Besides polyphase ceramics such as SYNROC, single phase ceramics are considered as tailor made host phases to embed a specific radionuclide or a specific group. Among oxidic single phase ceramics pyrochlores are known to have a high potential for this application. This work examines ZrO{sub 2} based pyrochlores as potential nuclear waste forms, which are known to show a high aqueous stability and a high tolerance towards radiation damage. This work contributes to (1) understand the phase stability field of pyrochlore and consequences of non-stoichiometry which leads to pyrochlores with mixed cationic sites. Mixed cationic occupancies are likely to occur in actinide-bearing pyrochlores. (2) The structural uptake of radionuclides themselves was studied. (3) The chemical stability and the effect of phase transition from pyrochlore to defect fluorite were probed. This phase transition is important, as it is the result of radiation damage in ZrO{sub 2} based pyrochlores. ZrO{sub 2} - Nd{sub 2}O{sub 3} pellets

  5. Survey of carbonization facilities for municipal solid waste treatment in Japan.

    Science.gov (United States)

    Hwang, In-Hee; Kawamoto, Katsuya

    2010-07-01

    The operations of carbonization facilities for municipal solid waste treatment in Japan were examined. Input waste, system processes, material flows, quality of char and its utilization, fuel and chemical consumption, control of facility emissions, and trouble areas in facility operation were investigated and analyzed. Although carbonization is a technically available thermochemical conversion method for municipal solid waste treatment, problems of energy efficiency and char utilization must be solved for carbonization to be competitive. Possible solutions include (1) optimizing the composition of input waste, treatment scale, organization of unit processes, operational methods, and quality and yield of char on the basis of analysis and feedback of long-term operating data of present operating facilities and (2) securing stable char demands by linking with local industries such as thermal electric power companies, iron manufacturing plants, and cement production plants. PMID:20149627

  6. Chemical and biological studies on producing high quality biscuits with irradiated tomato wastes

    International Nuclear Information System (INIS)

    The present investigation has been carried out to produce high quality biscuits for treatment of some special diseases. In this study, the total tomato processing wastes were used as new source of protein in which the most predominate elements were found to be phosphorus, potassium and magnesium. Phenyl alanine was found to be the first limiting amino acid, while lysine was the second limiting amino acid. It was found to contain about 30.66% fiber and 28.1% protein. The total tomato processing wastes remain unutilized and they not only add to the disposal problem, but also aggravate environmental pollution. Tomato wastes were irradiated in two doses (1.5 and 2.5 KGy) for preservation. Biscuits were made with supplementation of 5, 10 and 15% tomato wastes. All samples of biscuits were examined for chemical composition and organoleptic evaluation. Biological assay was carried out on rats fed biscuits containing 15% irradiated and non-irradiated tomato wastes. The weight gain, serum cholesterol and triglycerides were determined. Internal organs were also followed. The results obtained showed that 15% tomato wastes biscuit had the highest content of lysine, isoleucine and fiber (6.36, 2.72 and 24.80, respectively) and also scored a good grade. Weight gain, cholesterol and triglycerides were reduced comparable to control and there was no effect of irradiation on the rats internal organs

  7. Evaluation of alternative treatments for spent fuel rod consolidation wastes and other miscellaneous commercial transuranic wastes

    International Nuclear Information System (INIS)

    Eight alternative treatments (and four subalternatives) are considered for both existing commercial transuranic wastes and future wastes from spent fuel consolidation. Waste treatment is assumed to occur at a hypothetical central treatment facility (a Monitored Retrieval Storage facility was used as a reference). Disposal in a geologic repository is also assumed. The cost, process characteristics, and waste form characteristics are evaluated for each waste treatment alternative. The evaluation indicates that selection of a high-volume-reduction alternative can save almost $1 billion in life-cycle costs for the management of transuranic and high-activity wastes from 70,000 MTU of spent fuel compared to the reference MRS process. The supercompaction, arc pyrolysis and melting, and maximum volume reduction alternatives are recommended for further consideration; the latter two are recommended for further testing and demonstration

  8. Treatment of liquid radioactive waste by membranes techniques - Needs and future trends

    International Nuclear Information System (INIS)

    The nuclear industry generates a broad spectrum of low and intermediate level liquid radioactive wastes (LRWs). The treatment methods used for liquid radioactive waste are related to the conventional processes used for the treatment of the industrial wastewater, like chemical treatment, adsorption, filtration and ionic exchange. The use of such of techniques is limited due to their decreased capacity to remove the radioactive contaminants, the increased operational costs (e.g. evaporation) or the yielding potential for significant quantities of secondary solid waste. After development of suitable membrane materials and their long-term verification in conventional water purification fields, the membrane processes have been adopted by the nuclear industry as a viable alternative for the treatment of LRWs. The most utilized processes in the field of water and wastewater treatment are those utilizing pressure gradient as the process driving force. These processes include reverse osmosis, nanofiltration, ultrafiltration and microfiltration, allowing the selective removing both dissolved and particulate contaminants. (authors)

  9. Waste remediation using in situ magnetically assisted chemical separation

    International Nuclear Information System (INIS)

    The magnetically assisted chemical separation process (MACS) combines the selective and efficient separation afforded by chemical sorption with the magnetic recovery of ferromagnetic particles. This process is being developed for treating the underground storage tanks at Hanford. These waste streams contain cesium, strontium, and transuranics (TRU) that must be removed before this waste can be disposed of as grout. The separation process uses magnetic particles coated with either (1) a selective ion exchange material or an organic extractant containing solvent (for cesium and strontium removal) or (2) solvents for selective separation of TRU elements (e.g., TRUEX process). These coatings, by their chemical nature, selectively separate the contaminants onto the particles, which can then be recovered from the tank using a magnet. Once the particles are removed, the contaminants can either be left on the loaded particles and added to the glass feed slurry or stripped into a small volume of solution so that the extracting particles can be reused. The status of chemistry and separation process is discussed in this paper

  10. Hydrophysical, chemical and microbial properties of imported green waste composts

    Directory of Open Access Journals (Sweden)

    SAIFELDIN A.F. EL-NAGERABI

    2014-05-01

    Full Text Available El-Nagerabi SAF, Elshafie AE, Alburashdi H. 2014. Hydrophysical, chemical and microbial properties of imported green waste composts. Nusantara Bioscience 6: 13-18.To study the hydrophysical, chemical and microbial properties of the imported green waste composts (GWCs and their suitability as an alternative to agrochemicals, four types of GWCs (Florabella, Mikskaar, Potgrond, and Shamrock were selected. All composts showed normal physical properties, except weed seeds in Shamrock. The germination indexes comparable to the standard (90% were 100% for Mikskaar followed by Florabella (97%, Potgrond (95%, and Shamrock (92%. Variations in physico-chemical properties were shown as acidic pH 5.1-6.5 (standard 5-8, electrical conductivity (EC 0.8-1.8 mScm-1 (standard 0.0-4.0 mScm-1, moisture content (MC 54-70.5% (standard 35-60% and water holding capacity (WHC% 400-800%. The chemical properties were expressed as ammonia concentrations 2871-6565 mg kg-1 (standard <500 mg kg-1, organic matter 53.3-66.2% (standard 35%. The concentrations of heavy metals (Zn, Ni, Pb, Hg, As, Cd, and Cr were lower than the recommended levels. The bacterial colony forming unit per gram compost ranged between 330-2870 cfu/g, the most probable number (MPN for coliform bacteria was 23-460 cfu/g, whereas the fungal cfu were 30-1800 cfu/g. Aspergillus niger was the predominant fungus recovered from all compost samples (100%, followed by A. fumigatus (75%, whereas A. sparsus, A. versicolor and yeasts (50%, and the remaining species of the genus Acremonium sp., A. flavus, A. restrictus, Cladosporium spp., and Penicillium spp. recovered from 25% of the samples. Generally, these composts revealed normal hydrophysical properties with obvious variation in moisture contents and elevated chemicals and microbial contamination. Therefore, there is an urgent need for quality control measurements and restrict abide to legislations and quarantine regulations.

  11. Tertiary Treatment for Textile Waste Water-A Review

    OpenAIRE

    Manali Desai*1, Mehali Mehta2

    2014-01-01

    Tertiary treatment is the Industrial waste water treatment process which removes stubborn contaminants that have not been removed in secondary treatment. Effluent becomes even cleaner by Tertiary treatment through the use of stronger and more advanced treatment systems. The present work is an attempt to review all possible tertiary treatment methods for removal of dyestuff from textile effluent. Conventional method for treatment of textile effluent has own certain limitations ...

  12. Economic optimization of waste treatment and energy production in Denmark

    DEFF Research Database (Denmark)

    Münster, Marie; Ravn, Hans; Hedegaard, Karsten;

    2013-01-01

    This article presents an optimization model that incorporates LCA methodology and captures important characteristics of waste management systems. The most attractive waste management options are in the model identified as part the optimization. The model renders it possible to apply different...... shows that it is feasible to combine LCA approaches with optimization and highlights the need for including the integrated waste and energy system into the model....... optimization objectives such as minimizing costs or greenhouse gas emissions or to prioritise several objectives given different weights. An illustrative case is analyzed, covering alternative treatments of 1 tonne residual household waste: incineration of the full amount or sorting out organic waste...

  13. Techniques of treatment or conditioning for waste arising from 131I production

    International Nuclear Information System (INIS)

    Distillation, evaporation/crystallization, direct immobilization and some chemical like precipitation and reduction were studied as techniques of treatment or conditioning for waste arising from 131I production. The description of all techniques studied, as well as evaluation and discussion of the results are presented. (author)

  14. Chemical recycling of municipal waste slag by using phase separation

    OpenAIRE

    Nanba, Tokuro; Kuroda, Yutaro; Sakida, Shinichi; Benino, Yasuhiko

    2009-01-01

    A chemical recycling method by using phase separation was applied to municipal waste slags. Glasses were prepared from incineration ash and ash-melted slag, where B(2)O(3) was added to promote phase separation. The glasses were heat-treated at temperatures higher than their glass transition temperatures, and they were soaked in hydrochloric acid, leaching CaO, Fe(2)O(3), K(2)O, and S. Transparent and colorless solids containing ca. 80 mass% of SiO(2) were successfully obtained as residues. It...

  15. Supercritical Water Process for the Chemical Recycling of Waste Plastics

    Science.gov (United States)

    Goto, Motonobu

    2010-11-01

    The development of chemical recycling of waste plastics by decomposition reactions in sub- and supercritical water is reviewed. Decomposition reactions proceed rapidly and selectively using supercritical fluids compared to conventional processes. Condensation polymerization plastics such as PET, nylon, and polyurethane, are relatively easily depolymerized to their monomers in supercritical water. The monomer components are recovered in high yield. Addition polymerization plastics such as phenol resin, epoxy resin, and polyethylene, are also decomposed to monomer components with or without catalysts. Recycling process of fiber reinforced plastics has been studied. Pilot scale or commercial scale plants have been developed and are operating with sub- and supercritical fluids.

  16. Biofilm treatment of soil for waste containment and remediation

    Energy Technology Data Exchange (ETDEWEB)

    Turner, J.P.; Dennis, M.L.; Osman, Y.A.; Chase, J.; Bulla, L.A. [Univ. of Wyoming, Laramie, WY (United States)

    1997-12-31

    This paper examines the potential for creating low-permeability reactive barriers for waste treatment and containment by treating soils with Beijerinckia indica, a bacterium which produces an exopolysaccharide film. The biofilm adheres to soil particles and causes a decrease in soil hydraulic conductivity. In addition, B. Indica biodegrades a variety of polycyclic aromatic hydrocarbons and chemical carcinogens. The combination of low soil hydraulic conductivity and biodegradation capabilities creates the potential for constructing reactive biofilm barriers from soil and bacteria. A laboratory study was conducted to evaluate the effects of B. Indica on the hydraulic conductivity of a silty sand. Soil specimens were molded with a bacterial and nutrient solution, compacted at optimum moisture content, permeated with a nutrient solution, and tested for k{sub sat} using a flexible-wall permeameter. Saturated hydraulic conductivity (k{sub sat}) was reduced from 1 x 10{sup -5} cm/sec to 2 x 10{sup -8} cm/sec: by biofilm treatment. Permeation with saline, acidic, and basic solutions following formation of a biofilm was found to have negligible effect on the reduced k{sub sat}, for up to three pore volumes of flow. Applications of biofilm treatment for creating low-permeability reactive barriers are discussed, including compacted liners for bottom barriers and caps and creation of vertical barriers by in situ treatment.

  17. Biofilm treatment of soil for waste containment and remediation

    International Nuclear Information System (INIS)

    This paper examines the potential for creating low-permeability reactive barriers for waste treatment and containment by treating soils with Beijerinckia indica, a bacterium which produces an exopolysaccharide film. The biofilm adheres to soil particles and causes a decrease in soil hydraulic conductivity. In addition, B. Indica biodegrades a variety of polycyclic aromatic hydrocarbons and chemical carcinogens. The combination of low soil hydraulic conductivity and biodegradation capabilities creates the potential for constructing reactive biofilm barriers from soil and bacteria. A laboratory study was conducted to evaluate the effects of B. Indica on the hydraulic conductivity of a silty sand. Soil specimens were molded with a bacterial and nutrient solution, compacted at optimum moisture content, permeated with a nutrient solution, and tested for ksat using a flexible-wall permeameter. Saturated hydraulic conductivity (ksat) was reduced from 1 x 10-5 cm/sec to 2 x 10-8 cm/sec: by biofilm treatment. Permeation with saline, acidic, and basic solutions following formation of a biofilm was found to have negligible effect on the reduced ksat, for up to three pore volumes of flow. Applications of biofilm treatment for creating low-permeability reactive barriers are discussed, including compacted liners for bottom barriers and caps and creation of vertical barriers by in situ treatment

  18. Overview of microbial technologies for the treatment of hazardous and radioactive wastes

    International Nuclear Information System (INIS)

    Improved technologies for the management of radioactive and/or hazardous wastes are needed prior to their release to the environment, or retrospectively, for remediation of contaminated sites. The paramount role of microorganisms in the global cycling of carbon and other elements has long been recognized. The diverse metabolic activities of microorganisms, and in particularly their ability to interact with complex organic and inorganic substances, are now being exploited in the treatment of hazardous and/or radioactive wastes. Novel microbial technologies are being evaluated for their ability to reduce the danger posed by these wastes in the contexts of both waste management and environmental restoration. Microbial waste treatment technologies may be employed to achieve the destruction, detoxification, or immobilization of a waste component, or to reduce the volume of the waste. These treatments are carried out via biodegradation, biotransformation, or biosorption. Design of a specific process requires a thorough understanding of both treatment goals and treatment mechanisms. Either standard or novel organisms (including environmental isolates) may be useful, depending on the particular application. Genetic engineering represents another valuable approach to the development of improved organisms. Microbial treatment processes may be designed to employ microbial cultures within bioreactors or in situ. The practical utility of such processes may be affected by operating conditions and other considerations such as toxicity of the waste stream. The microbial technologies must be competitive with established, nonbiological technologies and must overcome certain psychological resistances. The development and implementation of new microbial waste treatment technologies can be achieved through the coupling of applied microbiological expertise with chemical engineering and/or environmental engineering skills

  19. EPA/DOE joint efforts on mixed waste treatment

    International Nuclear Information System (INIS)

    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

  20. 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)

    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 137Cs, 129I, 99Tc, Cl, F, and SO4 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. The

  1. 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

  2. Treatment of active laboratory liquid wastes by ultrafiltration

    International Nuclear Information System (INIS)

    A new treatment of active laboratory liquid wastes has been started in UP3 since mid 95. This facility is a part of the new liquid waste management performed by COGEMA in order to minimize the volume of final residues to be disposed of. After the introduction, part II of this paper outlines the main principles of the new waste management. The treatment of active laboratory liquid wastes, based on actinide precipitation and ultrafiltration is then described in more details in part III and part IV. Finally, some operating results after the first year of operation of the new facility are given in part V. (author)

  3. Overview of treatment and conditioning of low-level wastes

    International Nuclear Information System (INIS)

    The consideration of alternative technologies in low-level waste management is assumed to be partly a response to current demands for lower risk in waste disposal. One of the determinants of risk in waste disposal is the set of characteristics of the materials placed into disposal cells, i.e., the products of treatment and conditioning operations. The treatment and conditioning operations that have been applied to waste streams are briefly examined. Three operations are the most important determinants of the stability that will contribute to reducing risk at the disposal cell: compaction, high-integrity containers, and solidification. The status of these three operations is reviewed

  4. Microbiological treatment of oil mill waste waters

    Directory of Open Access Journals (Sweden)

    Ranalli, A.

    1992-02-01

    Full Text Available Experiments of the biological treatment of the oil mill waste waters, deriving from continuous system, have been carried out with selected mutant ferments, adapted to rather forced toxic conditions. The commercial microbio formulations SNKD, LLMO and PSBIO have been utilized; the last two are liquid suspensions, constituted by living micro-organisms that, in contrast to those frozen or lyophilized, do not need be revitalized before their use and became completely active in short time. The experiments with the SNKD biological preparation were carried out both on filtered oil mill outflows (type A with an initial COD of approximately 43 g/l and on waste water dephenolized by Caro-acid (type B with a COD equal to 30 g/l. The experiments with LLMO and PSBIO complexes were conduced both on oil mill outflows filtered and diluted (ratio 1:0.5 with an initial COD equal to 44 g/l (type C, and on waste water that were filtered and preventatively subjected to a cryogenic treatment (type D, with an initial COD of approximately 22 g/l. The residual COD with the microbio formulation SNKD, was about 15 g/l (type A and 5 g/l (type B; with the PSBIO It was about 7 g/l (type C and 1.5 g/l (type D; with the microbio formulation LLMO it resulted in 6 g/l (type C and 1.3 g/l (type D.

    Han sido efectuadas pruebas de tratamiento biológico de alpechines, provenientes de sistemas continuos, con fermentos seleccionados adaptados a condiciones de toxicidad muy elevadas. Han sido utilizadas las formulaciones microbianas SNKD, LLMO y PSBIO; las dos últimas son suspensiones líquidas, constituidas por microorganismos vivos, los cuales a diferencia de los liofilizados o congelados, no deben ser revitalizados antes del uso; estos tienen una fase «lag» más breve y entran antes en completa actividad. Las pruebas con la preparación biológica SNKD han sido efectuadas en los alpechines filtrados (tipo A con DQO inicial alrededor de 43 g/l, y también con alpech

  5. Ariab acidic min-influenced water: a waste to waste treatment

    International Nuclear Information System (INIS)

    Six samples of acidic mine-influenced water (AMIW) from Ariab area, Red Sea Hills, northeastern part of Sudan, were analyzed for some waste water parameters. The investigation showed that, the pH ranged between 1.30 to 1.88, sulphate content between 40200 to 235300 mg/1, total iron 9879 to 103969 mg/1, copper, 280.0 to 1112.5 mg/1, zinc, 1825 to 3345 mg/1, manganese, 210.0 to 570.0 mg /1 in addition to high contents of cobalt and cadmium which are known for their negative impact on the environment. Khartoum Refinery Sour Water (KRSW) sample was analyzed for some pollutants, the analysis showed that it is alkaline industrial waste having a pH of 10.10, alkalinity of 26381 mg/1 as CaC3/1, Chemical Oxygen Demand (COD) of 29400 mg/1 as O2. It was found to be relatively free of heavy and environmentally hazardous elements such as Fe, Co, Ca, Cd, Cu, Zn, Mn, Pb and Mg. A waste to waste treatment was carried to Ariab AMIW with KRSW, satisfactory results were obtained in reduction of the parameters studied in the treated effluent. The pH of AMIW was raised to about 8.50, and the element contents of Fe, Co, Ca, Cd, Cu, Zn, Mn, Pb were either completely removed or reduced to levels that meet the allowed limits of the industrial effluent disposal threshold. Sulphate content, however, decreased due to dilution, but still above the specified limits of the effluent disposal. (Author)

  6. Treatment of concentrated waste for storage

    International Nuclear Information System (INIS)

    The french experience in bituminization of radioactive wastes is described through the successive items, an outline on the industrial realizations is followed by the inventories of the coatable wastes, the constraints to be respected for embedding and quality of bitumen to be used. The technological aspect is described with the example of brennilis, characteristics and properties of coated wastes are given in conclusion. (orig./RW)

  7. Liquid Radioactive Wastes Treatment: A Review

    OpenAIRE

    Yung-Tse Hung; R. O. Abdel Rahman; Ibrahium, H.A.

    2011-01-01

    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 applie...

  8. Designing chemical soil characterization programs for mixed waste sites

    International Nuclear Information System (INIS)

    The Weldon Spring Site Remedial Action Project is a remedial action effort funded by the U.S. Department of Energy. The Weldon Spring Site, a former uranium processing facility, is located in east-central Missouri on a portion of a former ordnance works facility which produced trinitrotoluene during World War II. As a result of both uranium and ordnance production, the soils have become both radiologically and chemically contaminated. As a part of site characterization efforts in support of the environmental documentation process, a chemical soil characterization program was developed. This program consisted of biased and unbiased sampling program which maximized areal coverage, provided a statistically sound data base and maintained cost effectiveness. This paper discusses how the general rationale and processes used at the Weldon Spring Site can be applied to other mixed and hazardous waste sites

  9. Information related to low-level mixed waste inventory, characteristics, generation, and facility assessment for treatment, storage, and disposal alternatives considered in the U.S. Department of Energy Waste Management programmatic environmental impact statement

    International Nuclear Information System (INIS)

    This report was prepared to support the analysis of risks and costs associated with the proposed treatment of low-level mixed waste (LLMW) under management of the U.S. Department of Energy (DOE). The various waste management alternatives for treatment of LLMW have been defined in the DOE's Office of Waste Management Programmatic Environmental Impact Statement. This technical memorandum estimates the waste material throughput expected at each proposed LLMW treatment facility and analyzes potential radiological and chemical releases at each DOE site resulting from treatment of these wastes. Models have been developed to generate site-dependent radiological profiles and waste-stream-dependent chemical profiles for these wastes. Current site-dependent inventories and estimates for future generation of LLMW have been obtained from DOE's 1994 Mixed Waste Inventory Report (MWIR-2). Using treatment procedures developed by the Mixed Waste Treatment Project, the MWIR-2 database was analyzed to provide waste throughput and emission estimates for each of the different waste types assessed in this report. Uncertainties in the estimates at each site are discussed for waste material throughputs and radiological and chemical releases

  10. Information related to low-level mixed waste inventory, characteristics, generation, and facility assessment for treatment, storage, and disposal alternatives considered in the U.S. Department of Energy Waste Management Programmatic Environmental Impact Statement

    International Nuclear Information System (INIS)

    This report was prepared to support the analysis of risks and costs associated with the proposed treatment of low-level mixed waste (LLMW) under management of the US Department of Energy (DOE). The various waste management alternatives for treatment of LLMW have been defined in the DOE's Office of Waste Management Programmatic Environmental Impact Statement. This technical memorandum estimates the waste material throughput expected at each proposed LLMW treatment facility and analyzes potential radiological and chemical releases at each DOE site resulting from treatment of these wastes. Models have been developed to generate site-dependent radiological profiles and waste-stream-dependent chemical profiles for these wastes. Current site-dependent inventories and estimates for future generation of LLMW have been obtained from DOE's 1994 Mixed Waste Inventory Report (MWIR-2). Using treatment procedures developed by the Mixed Waste Treatment Project, the MWIR-2 database was analyzed to provide waste throughput and emission estimates for each of the different waste types assessed in this report. Uncertainties in the estimates at each site are discussed for waste material throughputs and radiological and chemical releases

  11. Guide Of Treatment On Noxious Waste Of Experiment

    International Nuclear Information System (INIS)

    This book deals with environmental safe management and smooth driving of facilities, which indicates purpose of this guide, responsibility of environmental safe management, division of collect of starting point treatment, batch processing system, treatment of noxious waste of experiment, regulation of harmful waste such as medicine, corrosivity liquid, and treatment of cleaning solution of chrome-sulfuric acid, and regulation of Kyungpook National University Department Environmental Engineering Research Center, environmental protection law and the other related law.

  12. Treatment and final disposal of nuclear waste

    International Nuclear Information System (INIS)

    The present background report to RD and D-programme 93 'Detailed R and D-programme 1993-1998' gives a detailed description of the state-of-the-art and future plans for safety assessments and supportive research. The technical development that is required for the construction of the encapsulation station and the deep repository for demonstration deposition is described. The report describes the need for performance and safety assessments occasioned by the above plans for activities. Against the background of the time schedule for safety reports etc., an account is given of the state-of-the-art, goals and planned work during the period with regard to the engineered barriers of spent nuclear fuel, canister material and buffer and backfill material. State-of-the-art, goals and planned work within the geosciences for groundwater movements, bedrock stability and geohydrological and rock mechanical calculation models are presented as well as the situation within the chemistry programme, with separate sections on groundwater and geochemistry, radionuclide chemistry and validation of processes in transport model and radionuclide migration. The study of such natural conditions as constitute analogues in certain respects to important chemical sorption and transport processes in a deep repository is presented. The state of knowledge concerning radionuclide transport in the biosphere and modelling of the same, as well as resulting doese to man, are described. R and D efforts associated with the development of technology that is required for repository construction, excavation of tunnels, deposition of waste and possibly necessary retrieval of canisters, as well as backfilling and sealing of the repository are presented

  13. Westinghouse Cementation Facility of Solid Waste Treatment System - 13503

    International Nuclear Information System (INIS)

    During NPP operation, several waste streams are generated, caused by different technical and physical processes. Besides others, liquid waste represents one of the major types of waste. Depending on national regulation for storage and disposal of radioactive waste, solidification can be one specific requirement. To accommodate the global request for waste treatment systems Westinghouse developed several specific treatment processes for the different types of waste. In the period of 2006 to 2008 Westinghouse awarded several contracts for the design and delivery of waste treatment systems related to the latest CPR-1000 nuclear power plants. One of these contracts contains the delivery of four Cementation Facilities for waste treatment, s.c. 'Follow on Cementations' dedicated to three locations, HongYanHe, NingDe and YangJiang, of new CPR-1000 nuclear power stations in the People's Republic of China. Previously, Westinghouse delivered a similar cementation facility to the CPR-1000 plant LingAo II, in Daya Bay, PR China. This plant already passed the hot functioning tests successfully in June 2012 and is now ready and released for regular operation. The 'Follow on plants' are designed to package three 'typical' kind of radioactive waste: evaporator concentrates, spent resins and filter cartridges. The purpose of this paper is to provide an overview on the Westinghouse experience to design and execution of cementation facilities. (authors)

  14. Nuclear waste treatment program. Annual report for FY 1985

    International Nuclear Information System (INIS)

    Two of the US Department of Energy's (DOE) nuclear waste management-related goals are: (1) to ensure that waste management is not an obstacle to the further deployment of light-water reactors (LWR) and the closure of the nuclear fuel cycle and (2) 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 Terminal Waste Disposal and Remedial Action of DOE established what is now called the Nuclear Waste Treatment Program (NWTP) at the Pacific Northwest Laboratory (PNL) during the second half of FY 1982. To support DOE's attainment of its goals, the NWTP is to provide (1) documented technology necessary for the design and operation of nuclear waste treatment facilities by commercial enterprises as part of a licensed waste management system and (2) 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 1985 toward meeting these two objectives. The detailed presentation is organized according to the task structure of the program

  15. Nuclear waste treatment program: Annual report for FY 1987

    International Nuclear Information System (INIS)

    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

  16. Mixed Waste Treatment Project: Computer simulations of integrated flowsheets

    International Nuclear Information System (INIS)

    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

  17. Nuclear Waste Treatment Program. Annual report for FY 1984

    International Nuclear Information System (INIS)

    Two of the US Department of Energy's (DOE) nuclear waste management-related goals are: (1) to ensure that waste management is not an obstacle to the further deployment of light-water reactors (LWR) and nuclear fuel cycle closure and (2) to fulfill its institutional responsibility for providing safe storage and disposal of existing and future nuclear wastes. As part of its approach to achieving those goals, the Office of Terminal Waste Disposal and Remedial Action of DOE established what is now called the Nuclear Waste Treatment Program (NWTP) at the Pacific Northwest Laboratory (PNL) during the second half of FY 1982. To support DOE's attainment of its goals, the NWTP has two objectives: (1) to provide documented technology necessary for the design and operation of nuclear waste treatment facilities by commercial enterprises as part of a licensed waste management system and (2) to provide 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 1984 toward meeting the two objectives. 31 figs., 4 tabs

  18. TREATMENT OF METAL-LADEN HAZARDOUS WASTES WITH ADVANCED CLEAN COAL TECHNOLOGY BY-PRODUCTS

    Energy Technology Data Exchange (ETDEWEB)

    James T. Cobb, Jr.

    2003-09-12

    Metal-laden wastes can be stabilized and solidified using advanced clean coal technology by-products (CCTBs)--fluid bed combustor ash and spray drier solids. These utility-generated treatment chemicals are available for purchase through brokers, and commercial applications of this process are being practiced by treaters of metal-laden hazardous waste. A complex of regulations governs this industry, and sensitivities to this complex has discouraged public documentation of treatment of metal-laden hazardous wastes with CCTBs. This report provides a comprehensive public documentation of laboratory studies that show the efficacy of the stabilization and solidification of metal-laden hazardous wastes--such as lead-contaminated soils and sandblast residues--through treatment with CCTBs. It then describes the extensive efforts that were made to obtain the permits allowing a commercial hazardous waste treater to utilize CCTBs as treatment chemicals and to install the equipment required to do so. It concludes with the effect of this lengthy process on the ability of the treatment company to realize the practical, physical outcome of this effort, leading to premature termination of the project.

  19. Electrical processes for liquid waste treatment

    International Nuclear Information System (INIS)

    Three electrical processes are being developed at pilot plant scale for the treatment of active liquid wastes. The extra reaction variable of applied potential not only simplifies automatic control but through enhanced performance also reduces plant size and operating costs. Direct electrical membrane cleaning (DMC) provides an alternative to crossflow as a way of controlling filtration membrane fouling. The periodic in situ electrolytic generation of microscopic gas bubbles at conductive micro- or ultrafiltration membrane surfaces by short current pulses (1-2 s at 0.1 A/cm2) removes solid deposits without the need to interrupt filtration. The resulting high permeation rates and lower crossflows minimize plant wear, as well as significantly reducing plant size and pumping energy. While DMC can concentrate feeds to > or approx. 5%, filtration fluxes decline much beyond this. Electro-osmotic dewatering is attractive for further concentration of these or gravity settled feeds to 30-40% so that they can be immobilized by cement powder addition. An electric field is applied across a microporous non-conducting membrane (organic or inorganic) instead of pressure to achieve rapid permeation rates (0.3-1.5 m/h) and high solids (and hence activity) retention for only a small energy consumption (1.5-7% of that required for evaporation). Electrochemical ion exchange controls the absorption and elution behaviour of ion exchange media incorporated in an electrode structure by an externally applied potential. High decontamination factors (∼2000) are achieved even up to almost complete utilization of exchanger capacity (∼75%). Polarity reversal elutes the ions into water to give a concentrated product (>0.25M) suitable for vitrification, for a low energy expenditure (0.3% of that required for evaporation). The system performance remains unchanged even after 2000 cycles and 10 MGy irradiation. Enhanced selectivity is possible through absorber choice and potential control

  20. Chemical pathways for the formation of ammonia in Hanford wastes

    International Nuclear Information System (INIS)

    This report reviews chemical reactions leading to the formation of ammonia in Hanford wastes. The general features of the chemistry of the organic compounds in the Hanford wastes are briefly outlined. The radiolytic and thermal free radical reactions that are responsible for the initiation and propagation of the oxidative degradation reactions of the nitrogen-containing complexants, trisodium HEDTA and tetrasodium EDTA, are outlined. In addition, the roles played by three different ionic reaction pathways for the oxidation of the same compounds and their degradation products are described as a prelude to the discussion of the formation of ammonia. The reaction pathways postulated for its formation are based on tank observations, laboratory studies with simulated and actual wastes, and the review of the scientific literature. Ammonia derives from the reduction of nitrite ion (most important), from the conversion of organic nitrogen in the complexants and their degradation products, and from radiolytic reactions of nitrous oxide and nitrogen (least important). Reduction of nitrite ions is believed to be the most important source of ammonia. Whether by radiolytic or thermal routes, nitrite reduction reactions proceed through nitrogen dioxide, nitric oxide, the nitrosyl anion, and the hyponitrite anion. Nitrite ion is also converted into hydroxylamine, another important intermediate on the pathway to form ammonia. These reaction pathways additionally result in the formation of nitrous oxide and molecular nitrogen, whereas hydrogen formation is produced in a separate reaction sequence