calcined wastes: Topics by WorldWideScience.org

Effect of calcination and physico-chemical properties of red mud

Liquid radioactive raffinates from nuclear fuel reprocessing at the Idaho National Engineering and Environmental Laboratory were solidified, or calcines, in a fluidized bed reactor at approximately 500 C to form a dry granular material. This calcine has been provisionally stored near-surface in concrete-encased stainless steel bins at the Idaho Nuclear Technology Engineering Center. Research addressing the permanent immobilization of radioactive waste has been ongoing. One option is to separate the radioactive constituents from the calcine, thereby reducing the radioactive waste volume to be ultimately stored at a national nuclear waste repository. Nitric acid dissolution of the calcine is a key front-end unit operation in the separations option. In order to design calcine dissolution equipment, quantification of ...

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Calcination of Fluorinel-sodium waste blends using sugar as a feed additive (formerly WINCO-11879)

Physico-chemical studies were carried out on a sample of red mud collected from NALCO, Orissa, after calcination up to 1,200 C at an interval of 100 C. The observed change in properties like surface area, particle size, bulk density and mineral phases etc., can be profitably used while finding an appropriate application of this polluting waste from alumina plants.

1996-10-01

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Connecting section and associated systems concept for the spray calciner/in-can melter process

Methods were studied for using sugar as a feed additive for converting the sodium-bearing wastes stored at the Idaho Chemical Processing Plant into granular, free flowing solids by fluidized-bed calcination at 500{degrees}C. All methods studied blended sodium-bearing wastes with Fluorinel wastes but differed in the types of sugar (sucrose or dextrose) that were added to the blend. The most promising sugar additive was determined to be sucrose, since it is converted more completely to inorganic carbon than is dextrose. The effect of the feed aluminum-to-alkali metal mole ratio on calcination of these blends with sugar was also investigated. Increasing the aluminum-to-alkali metal ratio from 0.6 to 1.0 decreased the calcine product-to-fines ratio from 3.0 to 1.0 and the attrition index from 80 to 15%. Further increasing the ratio to 1.25 had no effect.

1992-06-01

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Design and performance of a 100-kg/h, direct calcine-fed electric-melter system for nuclear-waste vitrification

For a number of years, researchers at the Pacific Northwest Laboratory have been developing processes and equipment for converting high-level liquid wastes to solid forms. One of these processes is the Spray Calciner/In-Can Melter system. To immobilize high-level liquid wastes, this system must be operated remotely, and the calcine must be reliably conveyed from the calciner to the melting furnace. A concept for such a remote conveyance system was developed at the Pacific Northwest Laboratory, and equipment was tested under full-scale, nonradioactive conditions. This concept and the design of demonstration equipment are described, and the results of equipment operation during experimental runs of 7 d are presented. The design includes a connecting section and its associated systems - a canister sypport and alignment concept and a weight-monitoring system for the melting furnace. ...

1981-06-01

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Review of high-level waste form properties. [146 bibliographies

This report describes the physical characteristics of a ceramic-lined, joule-heated glass melter that is directly connected to the discharge of a spray calciner and is currently being used to study the vitrification of simulated nuclear-waste slurries. Melter performance characteristics and subsequent design improvements are described. The melter contains 0.24 m/sup 3/ of glass with a glass surface area of 0.76 m/sup 2/, and is heated by the flow of an alternating current (ranging from 600 to 1200 amps) between two Inconel-690 slab-type electrodes immersed in the glass at either end of the melter tank. The melter was maintained at operating temperature (900 to 1260/sup 0/C) for 15 months, and produced 62,000 kg of glass. The maximum sustained operating period was 122 h, during which glass was produced at the rate of 70 kg/h.

1980-11-01

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Development of a pozzolanic pigment from red mud

This report is a review of waste form options for the immobilization of high-level-liquid wastes from the nuclear fuel cycle. This review covers the status of international research and development on waste forms as of May 1979. Although the emphasis in this report is on waste form properties, process parameters are discussed where they may affect final waste form properties. A summary table is provided listing properties of various nuclear waste form options. It is concluded that proposed waste forms have properties falling within a relatively narrow range. In regard to crystalline versus glass waste forms, the conclusion is that either glass of crystalline materials can be shown to have some advantage when a single property is considered; however, at this date no single waste form offers optimum ...

1980-12-01

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Comparison of sodium zirconium phosphate and Synroc matrices for immobilization of high-level waste

Red mud is a waste generated by the aluminum industry, and its disposal is a major problem for this industry. Very rich in iron, it can be used as cheap pigment for colored concrete. The red coloration can be enhanced by calcination in the range of 600 to 800 C. Such operation also transforms the aluminum hydroxides (goethite and boehmite) and clays minerals into pozzolanic admixtures that are able to consume the calcium hydroxide produced by cement hydration. Thus, it is possible to develop a new admixture for concrete: a pozzolanic pigment. The pozzolanic properties of calcined red mud were investigated by monitoring lime consumption of different mixtures of OPC and red mud. The main products of hydration were C-S-H and mono-carboaluminate (C{sub 4}A{bar C}H{sub 11}). A uniform and durable colored concrete was obtained using white cement interground with 11% of burnt red mud.

1997-10-01

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Development of a pelleted waste form for high-level alumina wastes

The aims of the present work were to investigate possible compatibility between sodium zirconium phosphate (NZP) and Synroc titanate phases, to prepare NZP-based waste forms by hot-pressing rather than sintering, and to investigate the incorporation in NZP of (a) Cs/Sr as simulated heat-generating nuclides; (b) simulated actinides; and (c) simulated Purex waste. The NZP samples were prepared by methods similar to those used for Synroc. The precursor NZP phase was formed from tetrabutyl zirconate Zr(OC{sub 4}H{sub 9}){sub 4}, sodium nitrate, and 85% orthophosphoric acid. Simulated waste nitrate solutions were then mixed with the liquid precursor. After stir drying of the precursor, calcination was carried out at 700{degree}C to remove nitrates and organics.

1996-12-31

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Investigation of corrosion experienced in a spray calciner/ceramic melter vitrification system

A formulation to pelletize simulated high-level ICPP alumina waste calcine was developed. The pellets are formed on a 41-cm-diameter disc pelletizer using 5% bentonite, 2% metakaolin, and 5 wt % calcium hydroxide as a solid binder and a solution of 7M phosphoric acid and 4M nitric acid as a liquid binder. After drying and heat treatment at 800/sup 0/C for 2 hours, the average crush strength of the pellets is 3.9 MPa and the pellets have a leach resistance of 10/sup -3/ g/cm/sup 2//day, based on Soxhlet leaching for 48 h at 95/sup 0/C with distilled water.

1980-09-01

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CHEMICAL TECHNOLOGY DIVISION. UNIT OPERATIONS SECTION MONTHLY PROGRESS REPORT, FEBRURARY 1963

After periodic testing of a large-scale spray calciner/ceramic melter vitrification system over a 2-yr period, sufficient corrosion was noted on various parts of the vitrification system to warrant its disassembly and inspection. A majority of the 316 SS sintered metal filters on the spray calciner were damaged by chemical corrosion and/or high temperature oxidation. Inconel-601 portions of the melter lid were attacked by chlorides and sulfates which volatilized from the molten glass. The refractory blocks, making up the walls of the melter, were attacked by the waste glass. This attack was occurring when operating temperatures were >1200/sup 0/C. The melter floor was protected by a sludge layer and showed no corrosion. Corrosion to the Inconel-690 electrodes was minimal, and no corrosion was noted in the offgas treatment system downstream of the sintered metal filters. It is believed that most of the melter corrosion ...

1980-08-01

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Recycling of red mud waste for use as a catalyst for eliminating volatile organic compounds; Recyclage d'un dechet, une boue rouge, comme catalyseur pour l'elimination des composes organiques volatils

Development of a shear and leach complex for UO/sub 2/-SS clad fuel was continued with major emphasis on the operation of a rotary drum leacher. Flooding data for nozzle plate pulse columns at high A/O ratios are reported. Engineering tests of dissolution of Zr--6% U alloy with HF in molten salt demonstrated a dissolution rate of 0.8 to 1.5 mg/cm/sup 2//min. Subsequent fluorination with 100% F/sub 2/ proceeded at half times of 40 to 135 min. The results of a high level waste calcination (run R-72) made with formaldehyde treated simulated Purex waste are reported. (auth)

1963-10-01

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Aqueous waste management for minor actinides and lanthanides separation process

Red mud is a waste product of the aluminium refining industry. It is composed of aluminium hydroxide and iron oxide. This study examined the feasibility of using red mud as a catalyst to eliminate volatile organic compounds in atmospheric pollutants. Volatile organic compounds can be eliminated by thermal oxidation between 600 and 1100 degrees C. However, the oxidation of volatile organic compounds can also be accomplished at lower temperatures (200 to 450 degrees C) if a catalyst is present. Currently, the low temperature destruction of volatile organic compounds is not widespread because of the difficulty in deactivating the catalyst. In this study, red mud was calcined in air at 500 degrees C. Under such conditions, the red mud converts to aluminium oxide and iron oxide. These 2 oxides are active and are carbon dioxide selective in the oxidation of volatile organic compounds. The study showed that red mud can be used as a catalyst for the ...

2005-08-01

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Evaluation of red mud as pozzolanic material in replacement of cement for production of mortars; Avaliacao da lama vermelha como material pozolanico em substituicao ao cimento para producao de argamassas

The French strategy of high level radioactive aqueous waste management is an incorporation in glassy fission products containers. Therefore, nitric acid soluble organic reagents needed for minor actinides and lanthanides selective separation from fission product solutions have to be sufficiently removed to reach carbon concentrations compatible with calcinator working. Thus, the ability of reagents to be oxidized under concentration conditions with or without denitration becomes a criteria of selection and have been studied. Further, if not working, other operations like hot hydrogen peroxide oxidation, catalyzed or not, are investigated. Reagents involved in this work are mainly complexing products (N-(2-Hydroxyethyl) Ethylene-diamine-tri-acetic Acid), pH keeping reagents (carboxylic acids like citric, glycolic, tartaric and lactic acid) and alkaline species (Tetramethylammonium hydroxide). Behaviour of acetic acid, which is often the main ...

2004-07-01

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Evaluation of red mud as pozzolanic material in replacement of cement for production of mortars

Red mud is a by-product of the alkaline extraction of aluminum from the bauxite and represents a renewed environmental problem due the significant annual throughput by the plants. In the present work, the pozzolanic properties of Brazilian red mud fired at 600, 700, 800 and 900 deg C were investigated by monitoring lime consumption using DTA analysis and Brazilian standard methodology NBR 5772 (1992). Products and kinetics of hydration were determined in cement pastes produced with 5 and 15% red mud using x-ray diffraction and DTA analysis. Compressive strength and capillary absorption tests were realized on mortars constituted by 5, 10 and 15% red mud in replacement of cement. When calcined at 600 deg C, the red mud develops good pozzolanic properties, and the compressive strength of mortars produced with this waste meet values in accordance with regulatory standard. These results shown than red mud can be used, in partial replacement of ...

2010-07-01

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Direct denitration and recycling of PFBR MOX liquid waste from dissolution test using microwave heating method

Red mud is a by-product of the alkaline extraction of aluminum from the bauxite and represents a renewed environmental problem due the significant annual throughput by the plants. In the present work, the pozzolanic properties of Brazilian red mud fired at 600, 700, 800 and 900 deg C were investigated by monitoring lime consumption using DTA analysis and Brazilian standard methodology NBR 5772 (1992). Products and kinetics of hydration were determined in cement pastes produced with 5 and 15% red mud using x-ray diffraction and DTA analysis. Compressive strength and capillary absorption tests were realized on mortars constituted by 5, 10 and 15% red mud in replacement of cement. When calcined at 600 deg C, the red mud develops good pozzolanic properties, and the compressive strength of mortars produced with this waste meet values in accordance with regulatory standard. These results shown than red mud can be used, in partial replacement of ...

2010-11-21

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WASTE TREATMENT AND DISPOSAL PROGRESS REPORT FOR JUNE AND JULY 1962

Full text: Dissolution test (DT) is one of the important specifications of PFBR MOX fuel. It is a macro homogeneity test used to ascertain that the dissolution of spent fuel will be easier during reprocessing. The DT specification limit for PFBR MOX fuel is ? 1.0 wt.% residue of the whole pellet when it is dissolved in HNO3 under reflux conditions. For this test, sintered MOX pellet is dissolved in reflux condition in 60 ml of 12M HNO3 for 10 hours. This test is carried out for each batch and during complete MOX campaign a lot of MOX waste in liquid form is being generated. This liquid waste is in clean form and U and Pu is required to be recovered from the clean waste. Different methods like direct denitration, precipitation and solvent extraction are available but either the product is not of good quality for pelletization or secondary liquid wastes are generated. Microwave denitration is a faster and ...

2010-11-24

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CHEMICAL TECHNOLOGY DIVISION, UNIT OPERATIONS SECTION MONTHLY PROGRESS REPORT, JULY 1960

9 9 simulated Purex waste oxides was investigated as a function of Na/sub 2/O, CaO and P/sub 2/O/sub 5/ content. All compositions lost some sulfate at 50 to 100 deg C above the softening point. In generai the volatility decreased with increase of either Na/ sub 2/O or CaO relative to P/sub 2/O/sub 5/, but no simple correlation Was indicated. Softening temperatures were lowered by inc ease in Na/sub 2/O vs CaO. Ceramic solids were obtained but no true glasses. Attempts to produce glasses by addition of varying combinations of Al/sub 2/O/sub 3/, PbO, BaO, and B/sub 2/O/ sub 3/ to simulated Pure x waste plus phosphite were unsuccessful. The use of 0.005 M Na/sub 2/C/O/sub 3/ to precipitate calcium from wastes containing up to 3 ppm of phosphate was demonstrated in four pilot plant runs and produced a decrease in the hardness of the waste leaving the clarifier. An inadvertent ...

1962-12-19

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Radioactive Waste Politics and Technology

A critical review of the literature revealed no experiments on uranyl ion transfer from an aqueous to a tributyl phosphate phase which positively measured the kinetics of the chemical reaction at the interphase. Drawing isorhythmic lines on a three component diagram gives a complex correlation for the compaction of three sizes of glass beads. Neither the use of thoria sols nor high feed solution concentrations of thorium nitrate gave any significant increase in mean particle diameters over those obtained from nitrate solutions of lower concentrations in flame denitration. A hydraulic film resistance has been detected in the anion exchange of uranyl sulfate into Dowex 2lK, and chloride elution was found to give a higher apparent uranium diffusion coefficient than nitrate elution. The rate of dissolution of mixed thorium-uranium oxides was determined as a function of the per cent of mixed oxides dissolved. Mixing in tanks packed with boron glass Raschig rings ...

1960-10-27

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Radioactive Waste

1991-01-01

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Religion and waste.

Heterogeneous coupling of phenylethyne over Cu-Mg-Al mixed oxides. Influence of catalyst composition and calcination temperature on structural and catalytic properties

PMID:21763121

2011-07-16

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Production of a potassium silicate fertilizer from fly ash and red mud

The catalytic effects of copper-aluminium-magnesium oxides in the oxidative coupling of phenylethyne is described. The importance of surface properties as a redox site are discussed.

1997-07-01

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Computer processing of Moessbauer spectrum data

A study is reported of the use of three types of fly ash as a raw material in the production of a potassium silicate fertilizer. The results of high-temperature X-ray diffraction, calcination tests and chemical analyses indicate that a potassium silicate fertilizer conforming with fertilizer specifications can be produced by appropriate regulation of calcining temperature and the amounts of Fe/sub 2/0/sub 3/, Al/sub 2/O/sub 3/, MgO and CaO added. The results of tests of fertilizers incorporating red mud are also reported.

1985-01-01

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The Principles of Radioactive Waste Management

Computer processing was adopted to pick up significant signals from the undefined Moessbauer spectra. A program, by which smoothing and curve fitting was made possible, was devised and applied to the analysis of the Moessbauer spectra of "5"7Fe enriched iron and other specimens. Although this processing sometimes distorted the absorption peaks, it was quite effective for elimination of noise and finding of exact positions of absorption peaks. Availability of the processing was demonstrated by several examples obtained for "5"7Fe enriched iron, natural iron, calcined ferric oxyhydroxides, red mud residue and its calcined product. (auth.).

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Establishing a nationalsystem for radioactive waste management

The Principles of Radioactive Waste Management

1995-01-01

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Waste to energy technologies.

Establishing a nationalsystem for radioactive waste management

1995-01-01

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Waste Food Storage at Fortress Rocks

No abstract prepared.

2010-04-01

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Transesterification of palm oil and esterification of palm fatty acid in near- and super-critical methanol with SO4-ZrO2 catalysts

... of waste food generated at McMurdo Station. Some of the difficulties of disposing of waste food ... change waste generation or management at the site? Yes. This will be a temporary waste management ...

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British Library Electronic Table of Contents (United Kingdom)

Sulfated zirconia (SO4-ZrO2) catalysts, prepared with three different sulfur loading contents (0.75%, 1.8% and 2.5%) at two calcination temperatures (500degreeC and 700degreeC), were tested for use in the transesterification of purified palm oil (PPO) and the esterification of palm fatty acid (PFA) in near-critical and super-critical methanol. Techniques including BET, XRD, NH3- and CO2-TPD revealed that the sulfur content and calcination temperature strongly affects the catalyst base-acid site, specific surface area, average pore size, phase structure, and thus the catalytic reactivity. The most suitable sulfur loading content was found to be 1.8% and the optimum calcination temperature 500degreeC. The results show that the use of SO4-ZrO2 reduces esterification reaction times, the amount...

2010-01-01

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Studies on the acidity of mordenite and ZSM-5. 2. Loss of Broensted acidity by dehydroxylation and dealumination

Particulate composites in the TiC-TiYTZP system

Quantitative determination of Broensted acid site concentrations in calcined H-mordenite and H-ZSM-5 by means of conductometric titration and infrared spectroscopy reveals that the concentration of Broensted acid sites present is lower than would be expected on the basis of the aluminum content. This discrepancy is attributed to dealumination and dehydroxylation processes occurring during calcination. A model is proposed according to which the degree of these processes strongly depends on the concentration of vicinal aluminum T sites in the zeolite: Broensted acid sites associated with these T sites are lost, and the remaining Broensted acidity is related to the concentration of the (remaining) isolated aluminum T sites. This model quantitatively correlates the experimentally determined concentration of Broensted acid sites with the concentration of isolated aluminum T sites. 33 refs., 4 figs., 2 tabs.

1993-01-14

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Moessbauer spectroscopic determination of chemical state of iron in bauxite

Twelve powders of TiO_2-Y_2O_3-ZrO_2 solid solution of the methodically changed composition were prepared by a coprecipitation-calcination technique. After mixing with phenol-formaldehyde resin, the powders were calcinated for 2 hours at 1200"oC in vacuum. The resultant composite powders contained TiC and non-reacted carbon. Green compacts were sintered in vacuum at 1500"oC for 2 hours. A temperature increase was stopped at 1200"oC to react remains of carbon. There were two carbides in the composites TiC and ZrC. TiC non-stoichiometry depended on carbon content in the system. Phase composition of the depended on of titania and yttria in zirconia solid solution. The majority of the samples showed two tetragonal zirconia phases differing in lattice parameter and tetragonality. (author)

2004-09-12

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Catalyst and method for reduction of nitrogen oxides

The chemical state of iron contained in several kinds of bauxite, which are utilized as a raw material in the aluminum industry in Japan, were investigated by Moessbauer spectroscopy. The main compounds of iron were identified from the results, which showed variations of the Moessbauer absorption spectra with calcination and measuring temperature. Although the absorption intensities of the spectra differed significantly, major species identified were paramagnetic or superparamagnetic #alpha#-Fe_2O_3 in all of these bauxite samples. The superparamagnetic #alpha#-Fe_2O_3 was found mainly in the gibbsite-type bauxite, but not in the boehmite/gibbsite-type or the boehmite-type bauxite. The Moessbauer absorption spectra of red mud and its calcined products were also given. (author).

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Catalyst and method for reduction of nitrogen oxides

A Selective Catalytic Reduction (SCR) catalyst was prepared by slurry coating ZSM-5 zeolite onto a cordierite monolith, then subliming an iron salt onto the zeolite, calcining the monolith, and then dipping the monolith either into an aqueous solution of manganese nitrate and cerium nitrate and then calcining, or by similar treatment with separate solutions of manganese nitrate and cerium nitrate. The supported catalyst containing iron, manganese, and cerium showed 80 percent conversion at 113 degrees Celsius of a feed gas containing nitrogen oxides having 4 parts NO to one part NO.sub.2, about one equivalent ammonia, and excess oxygen; conversion improved to 94 percent at 147 degrees Celsius. N.sub.2O was not detected (detection limit: 0.6 percent N.sub.2O).

2008-08-19

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Immobilization of waste material

A Selective Catalytic Reduction (SCR) catalyst was prepared by slurry coating ZSM-5 zeolite onto a cordierite monolith, then subliming an iron salt onto the zeolite, calcining the monolith, and then dipping the monolith either into an aqueous solution of manganese nitrate and cerium nitrate and then calcining, or by similar treatment with separate solutions of manganese nitrate and cerium nitrate. The supported catalyst containing iron, manganese, and cerium showed 80 percent conversion at 113 degrees Celsius of a feed gas containing nitrogen oxides having 4 parts NO to one part NO.sub.2, about one equivalent ammonia, and excess oxygen; conversion improved to 94 percent at 147 degrees Celsius. N.sub.2O was not detected (detection limit: 0.6 percent N.sub.2O).

2008-05-27

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DISPOSING DEVICE FOR WASTE

A method is described for immobilizing or solidifying waste material, which includes blending the waste material with powdered metal and subjecting the mixture of waste material and powdered metal to high pressure. (author).

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J-STORE (Japan)

Full Text Available

2005-12-19

36

The influence of compound admixtures on the properties of high-content slag cement

Phosphorus-containing catalyst and catalytic cracking process utilizing the same

Based on the activation theory of alkali and sulfate, the influence of compound admixtures on the properties of high-content slag cement was studied by testing the strength, pore structure, hydrates, and microstructure, Test results show that compound admixtures can obviously improve the properties of high-content slag cement. The emphasis of the present research is two-fold: substituting gypsum with anhydrite and calcining gypsum. These both can improve early and later performance.

2000-01-01

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Phosphorus-containing catalyst and catalytic cracking process utilizing the same

A phosphorus-containing low alkali metal content zeolitic catalyst made from a clay starting material is provided. The catalyst is obtained by contacting a partially cation exchanged calcined zeolite-containing catalyst with a dihydrogen phosphate anion or a dihydrogen phosphite anion. A hydrocarbon catalytic cracking process utilizing the phosphorus-containing catalyst is also provided.

1985-02-12

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Ni/CeO{sub 2}/ZSM-5 catalysts for the production of hydrogen from the pyrolysis-gasification of polypropylene

A phosphorus-containing low alkali metal content zeolitic catalyst made from a clay starting material is provided. The catalyst is obtained by contacting a partially cation exchanged calcined zeolite-containing catalyst with an anion such as a dihydrogen phosphate anion or a dihydrogen phosphite anion and additionally with an ammonium salt other than a salt of an inorganic acid of phosphorus. A hydrocarbon catalytic cracking process utilizing the phosphorus-containing catalyst is also provided.

1985-03-12

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Desulphurization of hot reducing gases in the entrained bed reactor

The production of hydrogen from the two-stage pyrolysis-gasification of polypropylene using a Ni/CeO{sub 2}/ZSM-5 catalyst has been investigated. Experiments were conducted on CeO{sub 2} loading, calcination temperature and Ni loading of the Ni/CeO{sub 2}/ZSM-5 catalyst in relation to hydrogen production. The results indicated that with increasing CeO{sub 2} loading from 5 to 30 wt.% for the 10 wt.% Ni/CeO{sub 2}/ZSM-5 catalyst calcined at 750 C, hydrogen concentration in the gas product and the theoretical potential hydrogen production were decreased from 63.0 to 49.8 vol.% and 50.4 to 21.6 wt.%, respectively. In addition, the amount of coke deposited on the catalyst was reduced from 9.5 to 6.2 wt.%. The calcination temperature had little influence on hydrogen production for the catalyst containing 5 wt.% of CeO{sub 2}. However, for the 10 wt.% Ni/CeO{sub 2}/ZSM-5 catalyst with a CeO{sub 2} content of 10 or 30 wt.%, the ...

2009-08-15

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Catalysis over activated zeolites

Using an experimental pilot plant, designed and built for the tests, the influence of the following parameters was determined: desulphurization of the test gas, temperature, residence time in the reactor tube, concentration of the hydrogen sulphide and desulphurization agent, size of the particles which comprise the agent and composition of the gas. Allowance was made for the effect of calcination and carbonisation. Desulphurization was carried out with limestone on a gaseous mixture of CO and H/sub 2/. A mathematical description of the test findings and yield is presented. 8 refs.

1986-08-01

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41

European Commission - Environment

A process is provided for conducting organic compound conversion over a catalyst composition comprising a supported crystalline zeolite having a high initial silica-to-alumina mole ratio, said supported zeolite being prepared by compositing said crystalline zeolite with alumina, reacting the composite with a particular hydrogen fluoride solution in a specified way, drying the hydrogen fluoride reacted composite, treating the dried composite by hydrolysis, ammonolysis and/or by contact with an ammonium salt solution, and calcining the resulting material.

1985-02-19

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Subsurface Injection of Liquid Waste

...Species - see CITES Trade of Dangerous Chemicals Transport and Environment U Urban Environment Use of natural resources V Volatile Organic Compounds W Waste Landfills Waste electrical and electronic equipment - see WEEE Waste incineration Waste legislation - reporting Waste management planning Waste oils Waste shipments Waste water - see Urban waste water Water Bathing Water Drinking water Floods Marine environment Urban waste water Water Framework Directive WEEE - Waste Electric and Electronic Equipment Wildlife ...

43

Regulatory Control of Radioactive Waste Management Overview of 15 NEA Member Countries

... Other Sources Toxics Intranet Subsurface Injection of Liquid Waste -- Florida Surface features of a typical...

44

Radiation protection and the management of radioactive waste in the oil and gas industry

Regulatory Control of Radioactive Waste Management

2004-01-01

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Property Analysis of Municipal Solid Waste and Estimation of CO2 Emissions from Waste Incinerators

Radiation protection and the management of radioactive waste in the oil and gas industry

2003-01-01

46

On-site burning, remote camp

Full Text Available

2010-12-01

47

Liquid Radioactive Wastes Processing

... wood, kitchen wastes, and human faeces. The ash from such waste burning shall be deposited and ...

48

International Science & Technology Center (ISTC)

Methods of Decontamination, Utilization, and Deactivation of Liquid Radioactive Wastes

49

IEE, accelerated waste mgt, McM

Human Waste Handling-Kooyman

... in ATCM Recommendation XIV-2. The USAP's materials and waste management efforts are consistent with ...

50

Dioxins in the Baltic sea

... wood, kitchen wastes, and human faeces with the ash from such burning deposited and retained in an ...

51

Combustion of Crop Production Wastes

for municipal waste iron ore sinter plants incinerators for clinical waste facilities of the non-ferrous metal

52

International Science & Technology Center (ISTC)

Development, Investigation and Improvement of a System of Incinerating Crop Production Wastes in Small Capacity Boilers

53

Characteristics of the Food Waste and Wastewater Discharged from Food Waste Treatment Process

Transuranic contaminated waste form characterization and data base

Full Text Available

2009-12-01

54

Process Waste Assessment for inorganic solid waste and empty containers <30 gallons

This volume contains 5 appendices. Title listing are: technologies for recovery of transuranics; nondestructive assay of TRU contaminated wastes; miscellaneous waste characteristics; acceptance criteria for TRU waste; and TRU waste treatment technologies.

1980-07-01

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This Process Waste Assessment was conducted to evaluate the two largest hazardous waste streams generated on-site at Sandia National Laboratory (SNL)/California -- ``Other Inorganic Solid Waste`` and ``Empty Containers <30 Gallons.``

1993-12-01

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LAW ON WASTE MANAGEMENT

Waste management units - Savannah River Site. Volume 1, Waste management unit worksheets

1 to the operator of a waste collective system by an agreement or contract. The conditions for the ...Fees of the waste collective system are subject to the supervision of the authority responsible for market surveillance. ...The operator of waste collection system collects wastes from producers and holder and transports these to a collection

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Waste management at Los Alamos: Protecting our environment

This report is a compilation of worksheets from the waste management units of Savannah River Plant. Information is presented on the following: Solid Waste Management Units having received hazardous waste or hazardous constituents with a known release to the environment; Solid Waste Management Units having received hazardous waste or hazardous constituents with no known release to the environment; Solid Waste Management Units having received no hazardous waste or hazardous constituents; Waste Management Units having received source; and special nuclear, or byproduct material only.

1989-10-01

58

This report consists of a broad overview of activities at Los Alamos National Laboratory (LANL). The following topics are discussed: The growth of the waste management group; what we do today; the mission of the waste management group; the liquid waste treatment section; the radioactive liquid waste project office; the chemical waste section; the radioactive waste section; and the technical support section.

1993-11-01

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Radioactive waste

Thermogravimetric and specific heat determinations of a commercial reconcentrated sample of ulexite, between room temperature and 1,000 degree centigree; Determinaciones termogravimetricas y de calor especifico de un concentrado comercial de ulexita, entre temperature ambiente y 1.000 grados centigrados

The paper deals with the disposal of radioactive waste and the plans for dealing with solid wastes of intermediate and low levels of activity, which are the responsibility of NIREX. NIREX is an executive body which co-ordinates the waste-disposal plans of the main radioactive waste producers. The disposal routes for the active wastes are described including the deep disposal of wastes containing material that will remain active for thousands of years. Requirements for deep burial are outlined with reference to the geology and hydrogeology of the site. Monitoring, maintenance and surveillance are mentioned for the protection of the public.

1984-02-01

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Synthesis of yttrium iron garnet powder by homogeneous precipitation and its crystallization

The important amount of hydration water in the ulexite (NaCaN{sub 5}O{sub 9}.8H{sub 2}O), allows using calcination methods to increase its B{sub 2}O{sub 3} content. This paper analyses the thermal decomposition reaction of a preconcentrated ulexite through weight loss measurements, which occur during the heating of samples until 1000 degree centigree, Determinations of heat content at each temperature were made using an isoperibol calorimeter. The mean specific heat was calculated from these values, and its dependence on temperature was determined. The maximum weight loss was about 32.5% and the specific heat obtained was 1,13 kJ/kg 0 C for solid samples and 1,38 kJ/kg''0 C for fluid samples. The results are useful for the design of the industrial process, in order to determine the thermal requirements for heating calcined ulexite, and to obtain smelted ulexite. (Author) 19 refs.

2006-07-01

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61

Synthesis of (Bi0.5Na0.5)TiO3 (BNT) and Pr doped BNT using the soft combustion technique and its properties

YIG precursor powder was obtained by homogeneous precipitation in chloride salt solution by thermal decomposition of urea. It was found that ferric ions precipitated prior to yttrium ions. The precipitate was minute and spherical in shape. The precipitate formed consisted of the mixture of amorphous and ferric oxyhydroxide. Crystallization of YIG was proceeded by solid state reaction of intermediate YFeO{sub 3} and Fe{sub 2}O{sub 3} in the temperature range of 850 deg. C to 1400 deg. C. Single phase of YIG was obtained by heat-treatment of the powder at 1400 deg. C for 6 hrs in air. The powder calcined was molded into pellets and sintered in air. The maximum density of 4.92 g/cm{sup 3} (95.1% of theoretical density) was obtainable for the pellet sintered at 1450 deg. C using the powder calcined at 900 deg. C. (author) 20 refs., 8 figs., 1 tab.

1996-06-01

62

British Library Electronic Table of Contents (United Kingdom)

In this work, bismuth sodium titanate (Bi0.5Na0.5)TiO3 (BNT) and praseodymium (Pr)-doped BNT were successfully produced using the soft combustion technique. The effects of Pr doping on stoichiometry, microstructure, density and dielectric properties were studied. Pure Pr-doped BNT was obtained in all samples containing 5, 10 and 20mol% Pr after calcination at 800^oC for 3h. The produced powders were then pressed into pellets and sintered at 1100^oC for 3h. The very similar ionic radii of Pr^3^+ with Bi^3^+ and Na^+ made it possible to substitute both Bi and Na. The crystallite size and grain size decreased with increasing Pr amount because Pr acted as grain growth inhibitor, both for calcined powders and for sintered pellets. Maximum density was obtained in 5mol% Pr-doped BNT, beyond which...

2011-01-01

63

Regional assessment of nonforestry related biomass resources: Virginia

Regional assessment of nonforestry related biomass resources: Florida

This document is a collection of spreadsheets detailing on a county by county basis the agricultural crop, agricultural wastes, municipal wastes, and industrial wastes of Virginia that are potential biomass energy sources.

1988-11-01

64

Regional assessment of nonforestry related biomass resources: Alabama

This document is a collection of spreadsheets detailing in a county by county manner the agricultural crop, agricultural wastes, municipal wastes and industrial wastes in Florida that are potential biomass energy sources.

1988-11-01

65

This document is a collection of spreadsheets detailing on a county by county basis the agricultural crop, agricultural wastes, municipal wastes and industrial wastes of Alabama that are potential biomass energy sources.

1988-11-01

66

Department of the

Volume reduction: a short-term answer to the mounting radwaste problem

Waste Technology and Innovation Study Final Report ...Waste Technology and Innovation Study Final Report 21/18569/150554 ...Survey of waste and resource recovery related technology and innovation, including products and product uses

67

Synthesis of polyacrylonitrile (PAN) with different stereoregularity by urea radiation inclusion polymerization and its application to carbon fiber

Various volume-reduction methods are discussed and their capabilities evaluated. The following volume-reduction methods have the greatest potential at this time: forced-circulation evaporator/crystallizer; incinerator (conventional type); compactor; fluidized-bed calciner/incinerator; fluidized-bed dryer/incinerator; thin-film evaporator; extruder/evaporator; drum mixer; ribbon blender; inert-carrier evaporative process; molten-glass incinerator. The first eight system types listed above have been improved to the point of commercial viability.

1980-01-01

68

Relationship between fabrication parameters and structural characteristics of sintered lithium orthosilicate

Application to carbon fiber started in this Year. In this paper, a spinning and calcination process are explained. Fiber was obtained by wet spinning of the PAN solution. Ten solvents were tested and the results proved that dimethyl sulfoxide (DMSO) was the best solvent. Glycerine was used as a coagulating bath. The thin fiber (10 to 50 denier) was produced under the conditions of about 20wt% concentration at about 110degC. Heat-treat temperature was about 270 to 275degC. The viscosity-tacticity relationship and T{sub sol} vs. inverse tacticity were shown in the paper. (S.Y.)

1998-01-01

69

Production of blast furnace coke via novel briquetting system

Lithium orthosilicate (Li_4SiO_4) powder was synthesized by the solid-state reaction of lithium oxide with amorphous silica, and the effects of fabrication parameters on the structural characteristics of the product were investigated. Processing considerations such as milling media, drying technique, calcination time and temperature, pressing behavior, sintering time and temperatures, and impurity concentration were addressed. The initial powder particle size was observed to be important in achieving high sintered density, with densities as high as 98% TD achieved with a particle size of approximately 1 #mu#m. 9 refs., 6 figs.

1988-04-10

70

Simulation of uranium oxides reduction kinetics by hydrogen. Reactivities of germination and growth; Modelisation de la cinetique de reduction d`oxydes d`uranium par l`hydrogene. Reactivites de germination et de croissance

A method of making high strength coke briquettes suitable for use as blast furnace coke comprising, (A) providing coal, (B) heating the coal at a temperature at or above the softening point of the coal to form partially carbonized char, (C) cooling the partially carbonized char below the softening point of the coal, (D) mixing the cooled partially carbonized char and tar to form a mixture of tar and partially carbonized char, (E) briquetting the mixture of tar and partially carbonized char to form briquettes of tar and partially carbonized char, (F) calcinating the briquettes to form high strength briquettes.

1982-12-07

71

Removal of H2S and SO2 by CaCO3-Based Sorbents at High Pressure

The aim of this work is to simulate the reduction by hydrogen of the tri-uranium octo-oxide U{sub 3}O{sub 8} (obtained by uranium trioxide calcination) into uranium dioxide. The kinetics curves have been obtained by thermal gravimetric analysis, the hydrogen and steam pressures being defined. The geometrical modeling which has allowed to explain the trend of the kinetics curves and of the velocity curves is an anisotropic germination-growth modeling. The powder is supposed to be formed of spherical grains with the same radius. The germs of the new UO{sub 2} phase appear at the surface of the U{sub 3}O{sub 8} grains with a specific germination frequency. The growth reactivity is anisotropic and is very large in the tangential direction to the grains surface. Then, the uranium dioxide growths inside the grain and the limiting step is the grain surface. The variations of the growth reactivity and of the germination specific frequency in terms of the gases partial ...

1997-12-04

72

Formation and reaction activity of CeO{sub 2} nanoparticles of cubic structure and various shaped CeO{sub 2}-TiO{sub 2} composite nanostructures

The theoretical and experimental investigation of the mechanism of SO2 and H2S removal by CaCO3 -based sorbents (limestones and dolomites) in pressurized uidized-bed coal combustors (PFBC) and high pressure gasiers, respectively, is the main objective of this study. It is planned to carry out reactivity evolution experiments under simulated high pressure conditions or in high pressure thermogravimetric and, if needed, uidized- bed reactor (high pressure) arrangements. The pore structure of fresh, heat-treated, and half-calcined solids (dolomites) will be analyzed using a variety of methods. Our work will focus on limestones and dolomites whose reaction with SO2 or H2S under atmospheric conditions has been studied by us or other research groups in past studies. Several theoret- ical tools will be employed to analyze the obtained experimental data including a variable diusivity shrinking-core model and models for diusion, reaction, and structure evolution in ...

1998-02-01

73

Development of a stable cobalt-ruthenium Fischer-Tropsch catalyst. Technical progress report No. 12, July 1, 1992--September 30, 1992

Mono-dispersed cubic CeO{sub 2} nanoparticles have been synthesized using a surfactant-assisted method with laurylamine hydrochloride and cerium alkoxide modified with acetylacetone in an aqueous solution system. The prepared cubic CeO{sub 2} nanoparticles had a highly crystallized structure at 353 K and formed rod-like structures by calcination at 673 K after freeze-drying the CeO{sub 2} gel. We discovered a clear potential to make 1D, 2D or 3D CeO{sub 2}-materials with a well-controlled characteristic length and shape by assembling cubic-shaped CeO{sub 2} nanoparticle building blocks. CeO{sub 2}-TiO{sub 2} composite nanostructures have also been synthesized by changing the mole ratio of cerium alkoxide/titanium alkoxides. By utilizing the redox characteristic of CeO{sub 2}, CeO{sub 2} nanoparticles and CeO{sub 2}-TiO{sub 2} composite nanostructures after calcination, showed reaction activity toward the oxidization of I{sup -} to I{sub 2}, due ...

2007-07-15

74

Waste management plan for the APT

The fixed bed pilot plant, the catalyst testing procedure, and the calculations for conversion and selectivities were previously described in the technical progress report covering the period of 3/16/88 to 6/16/88 for Contract DE-AC22-87PC79812. Conversions and hydrocarbon selectivities were calculated using data from an on-line gas chromatography (GC) analyzer. Alcohol selectivities were calculated using data from an on-line boiling point GC analyzer which analyzed the liquid product. The catalysts were prepared via the steps of impregnation, calcination, and reduction on a special Y-zeolite-derived support. The impregnation step consisted of evaporation of metal salts on to the support from an aqueous solution. For one catalyst (No. 6531-188) the metal salts were evaporated on to the support from a reverse micelle solution containing the metal salts. All the catalysts were calcined for four hours at 450{degree}C. The ...

1992-12-31

75

Waste management and producer responsibility: a score behind - a new ahead.

This revision of the APT Waste Management Plan details the waste management requirements and issues specific to the APT plant for design considerations, construction, and operation. The APT Waste Management Plan is by its nature a living document and will be reviewed at least annually and revised as required.

1997-08-22

76

Strategies for Protecting Waste Collectors' Health and Safety

PMID:21900358

2011-09-01

77

Nuclear waste management: a perspective

Full Text Available

2010-06-01

78

New technologies for managing oil field wastes.

The scope of our problems with nuclear waste management is outlined. Present and future inventories of nuclear wastes are assessed for risk. A discussion of what is presently being done to solve waste management problems and what might be done in the future are presented. (DC)

1980-01-01

79

LOS ALAMOS PLUTONIUM FACILITY WASTE MANAGEMENT SYSTEM

No abstract prepared.

2000-10-25

80

E-waste hazard: The impending challenge

No abstract prepared.

2000-01-01

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81

Development of Ceramic Body using Waste Celadon

Electronic waste or e-waste is one of the rapidly growing problems of the world. E-waste comprises of a multitude of components, some containing toxic substances that can have an adverse impact on human...Full Text Available

2008-08-01

82

Bioplastic production from agro-industrial waste.

Full Text Available

2009-11-01

83

A Study on the Model of Sulfidation Kinetics Using Seashell Wastes

PMID:21769853

2011-09-01

84

40 CFR 261.2 - Definition of solid waste.

Full Text Available

2004-12-01

85

Hanford Waste Management Plan, 1987

...2009-07-01 false Definition of solid waste. 261.2 Section 261.2 Protection...PROTECTION AGENCY (CONTINUED) SOLID WASTES (CONTINUED) IDENTIFICATION AND LISTING OF HAZARDOUS WASTE General § 261.2 Definition...

2009-07-01

86

Ecological utilization of wastes. A manual for optimum waste management concepts. 3. rev. ed. Oekologische Muellverwertung. Handbuch fuer optimale Abfall-Konzepte

The purpose of the Hanford Waste Management Plan (HWMP) is to provide an integrated plan for the safe storage, interim management, and disposal of existing waste sites and current and future waste streams at the Hanford Site. The emphasis of this plan is, however, on the disposal of Hanford Site waste. The plans presented in the HWMP are consistent with the preferred alternative which is based on consideration of comments received from the public and agencies on the draft Hanford Defense Waste Environmental Impact Statement (HDW-EIS). Low-level waste was not included in the draft HDW-EIS whereas it is included in this plan. The preferred alternative includes disposal of double-shell tank waste, retrievably stored and newly generated TRU waste, one pre-1970 TRU solid waste site near the Columbia River ...

1987-01-01

87

Waste Management Project fiscal year 1998 multi-year work plan, WBS 1.2

From out of the numerous technical alternatives the manual develops a waste management concept with emphasis on methods which can be coordinated for maximum ecological use and minimum economic costs. A clear-cut analysis of the present state of waste utilization and waste disposal in the Federal Republic of Germany (chapter 1) is followed by a detailed description of conventional and modern state-of-the-art waste utilization methods based on ecological evaluation criteria (chapter 3). An optimum waste utilization concept for defined quantities of wastes is derived from the ecological and economic comparison of waste utilization techniques given in chapter 3. Chapter 4 points out different variants of waste utilization and waste disposal methods and shows how to determine the optimum variant of the ...

1991-01-01

88

Thermal waste disposal and utilization; Waste management in accordance with the German Municipal Waste Disposal Regulations. Abfaelle thermisch entsorgen und verwerten; Die Verwaltungsvorschrift TA Siedlungsabfall praegt gesamte Abfallbehandlung

The Waste Management Project manages and integrates (non-TWRS) waste management activities at the site. Activities include management of Hanford wastes as well as waste transferred to Hanford from other DOE, Department of Defense, or other facilities. This work includes handling, treatment, storage, and disposal of radioactive, nonradioactive, hazardous, and mixed solid and liquid wastes. Major Waste Management Projects are the Solid Waste Project, Liquid Effluents Project, and Analytical Services. Existing facilities (e.g., grout vaults and canyons) shall be evaluated for reuse for these purposes to the maximum extent possible.

1997-09-23

89

Surface Crystallization and Composition of Spinel and Acmite in High-Level Waste Glass

Drastic changes in waste management procedures are expected from the German Municipal Waste Disposal Regulations which became effective on June 1, 1993. Waste disposal will be subject to certain restrictions which, e.g. demand that wastes must be pretreated and inerted before they are stored. These regulations favor thermal waste disposal methods such as the carbonization/combustion method which is planned for a commercial-scale plant in the city of Fuerth. (orig./BBR)

1993-09-01

90

Safe management of wastes from the mining and milling of Uranium and Thorium ores

Surface crystallization and surface-to-bulk ratio in high-level waste glasses.

2000-07-10

91

Hazardous Waste Management on the Farm

Safe management of wastes from the mining and milling of Uranium and Thorium ores

1987-01-01

92

Control of Effluent Gases from Solid Waste Processing Using Carbon Nanotubes

Sep 2, 2008 ... Abstract: This tutorial is intended to serve as a guide towards proper hazardous waste management. Knowing the regulations, different ...

93

1998 Annual report on waste generation and waste minimization progress as required by DOE order 5400.1 Hanford Site

One of the major problems associated with solid waste processing technologies is the release of

2005-01-01

94

Paul Scherrer Institut Scientific Report 2001. Volume V: General Energy

No abstract prepared.

1999-02-25

95

Request for interim approval to operate Trench 94 of the 218-E-12B Burial Ground as a chemical waste landfill for disposal of polychlorinated biphenyl waste in submarine reactor compartments. Revision 2.

Major advances in 'Energy and Materials Cycles' have been achieved in the removal of heavy metals from the solid residues of municipal waste incineration. It has been conclusively shown that the oxidation/reduction conditions established during the thermal treatment of filter ash have a decisive influence on the evaporation of groups of heavy metals. With respect to biomass gasification, studies have been carried out with respect to the best way of extracting pure hydrogen from the low calorific value gas that is typically obtained from a biomass gasifier. The overarching goal of the laboratory 'High Temperature Solar Technology' is the use of solar energy for the production of solar fuels, or for the reduction of CO{sub 2} emissions in large scale industrial processes that are conventionally carried out with the use of fossil fuels. In a short-term project targeted at the solar production of lime, highly encouraging results (98% ...

2002-03-01

96

Radioactive and mixed waste management plan for the Lawrence Berkeley Laboratory Hazardous Waste Handling Facility

This request is submitted to seek interim approval to operate a Toxic Substances Control Act (TSCA) of 1976 chemical waste landfill for the disposal of polychlorinated biphenyl (PCB) waste. Operation of a chemical waste landfill for disposal of PCB waste ...

1994-01-01

97

Composting - environmentally compatible waste disposal - one of the incredients of waste management

This Radioactive and Mixed Waste Management Plan for the Hazardous Waste Handling Facility at Lawrence Berkeley Laboratory is written to meet the requirements for an annual report of radioactive and mixed waste management activities outlined in DOE Order 5820.2A. Radioactive and mixed waste management activities during FY 1994 listed here include principal regulatory and environmental issues and the degree to which planned activities were accomplished.

1995-01-01

98

Charging generators for waste management costs

Considering the fact that more than 40% of all household wastes are organic wastes composting could be an excellent relief and complement to other waste disposal methods (e.g. combustion or direct landfills). Provided the right conditions household wastes could be composted together with sewage sludges and manures. The paper discusses the legal aspects, quantitative evaluations, conveying systems, as well as the compost utilization and marketing aspects valid for the Federal Republic of Germany.

1988-09-20

99

AVLIS production plant waste management plan

Implementation of a plan to charge waste management costs to the facility that generates such waste requires a long-term commitment and consistent administration. The benefit is that generators are provided the incentive to optimize waste management practices if the charges are appropriately applied. This paper summarizes (1) a plan to charge waste generators, (2) the administrative structure of the plan, (3) a comparison between the rate structure and changes in waste disposal operations, and (4) issues that have surfaced as the plan is implemented. 2 refs., 1 fig., 1 tab.

1988-01-01

100

Hospital waste management in Lebanon

Following the executive summary, this document contains the following: (1) waste management facilities design objectives; (2) AVLIS production plant wastes; (3) waste management design criteria; (4) waste management plan description; and (5) waste management plan implementation. 17 figures, 18 tables.

1984-11-15

1 2 3 4 5 6 7 8 9 10 11 12 13 14 15 16 17 18 19 20 21 22 23 24 25

101

Waste recycling as evaluated from the viewpoint of energy environment, mainly about plastics; Haikibutsu recycle no energy kankyomen kara no hyoka. Plastic wo chushin to shite

Hospital wastes comprises approximately 80% domestic waste components, also known as non-risk waste and 20% hazardous or risk waste. The 20% of the hospital waste stream or the risk waste (also known as infectious, medical, clinical wastes) comprises components which could be potentially contaminated with infections, chemical or radioactive agents. Therefore, it should be handled and disposed of in such a manner as to minimize potential human exposure and cross-contamination. Hospital risk waste and be subdivided into seven general categories as follows: infections, anatomical/pathological, chemical, pharmaceutical, radioactive waste, sharps and pressurised containers. These waste categories are generated by many types of health care establishments, including hospitals, clinics, ...

1999-06-02

102

Hanford Waste Vitrification Plant Quality Assurance Program description for high-level waste form development and qualification

Some comments are given on the recycling of waste, mainly plastics, as evaluated from the viewpoint of energy environment. Discussed about the waste in general are the definition and classification, generation and resource recovery rates, current state of recycling, problems about recycling, related legislation, and current conditions overseas. Discussed about the treatment and recycling of plastics waste are the characters and use of plastic product, current state of waste plastics treatment, current state of waste plastics recycling (material recycling, thermal recycling), energy recovery by thermal recycling, quantity recyclable from waste plastics, energy consumption and cost for waste plastics recycling, effect and impact of increase in waste plastics in case material recycling is forwarded, and prospect of ...

1996-05-01

103

Waste laws. Waste Classification Ordinance. Residual Material Classification Ordinance. The Waste Technical Code. Ordinance on the Monitoring of Wastes and Residual Material. Ordinance on the Ban on CFCs and Halogenated Hydrocarbons. Packaging Ordinance. Sewage Ordinance. Text edition with index and an introduction by Dr. Clemens Weidemann. As of May 15, 1992. Abfallgesetz. AbfallbestimmungsV. ReststoffbestimmungsV. TA Abfall. Abfall- und ReststoffueberwachungsV. FCKW-Halon-VerbotsV. VerpackungsV. KlaerschlammV. Textausgabe mit Sachverzeichnis und einer Einfuehrung von Rechtsanwalt Dr. Clemens Weidemann. Stand: 15. Mai 1992

The Hanford Waste Vitrification Plant Project has been established to convert the high-level radioactive waste associated with nuclear defense production at the Hanford Site into a waste form suitable for disposal in a deep geologic repository. The Hanford Waste Vitrification Plant will mix processed radioactive waste with borosilicate material, then heat the mixture to its melting point (vitrification) to forin a glass-like substance that traps the radionuclides in the glass matrix upon cooling. The Hanford Waste Vitrification Plant Quality Assurance Program has been established to support the mission of the Hanford Waste Vitrification Plant. This Quality Assurance Program Description has been written to document the Hanford Waste Vitrification Plant Quality Assurance Program.

1993-05-06

104

Framework for managing wastes from oil and gas exploration and production (E&P) sites.

The turbulent history of legislature concerned with the waste-management industry and the amount of material on this subject as well as the significance of the material in its own right led to the decision to publish all legal regulations on waste in one volume. It includes above all the Waste Law, Regulations on Determination of Waste, Regulations on Determination of Residual Products, Technical Instructions for Waste, Regulations for Monitoring Waste and Residual Products, Regulations on Probition from the Use of Chlorofluorohydrocarbons and Halon, Regulations on Packaging and Regulations on Sewage Sludge. The introduction explains the development and the role of the Waste Law and its applicability, goals and principles: The concept of waste, avoidance of waste, avoidance of ...

1992-01-01

105

Development and pilot demonstration program of a waste minimization plan at Argonne National Laboratory

Oil and gas companies operate in many countries around the world. Their exploration and production (E&P) operations generate many kinds of waste that must be carefully and appropriately managed. Some of these wastes are inherently part of the E&P process; examples are drilling wastes and produced water. Other wastes are generic industrial wastes that are not unique to E&P activities, such as painting wastes and scrap metal. Still other wastes are associated with the presence of workers at the site; these include trash, food waste, and laundry wash water. In some host countries, mature environmental regulatory programs are in place that provide for various waste management options on the basis of the characteristics of the wastes and the environmental ...

2007-09-15

106

Attenuation of heavy metal leaching from hazardous wastes by co-disposal of wastes

In response to US Department of Energy directives, Argonne National Laboratory (ANL) has developed a waste minimization plan aimed at reducing the amount of wastes at this national research and development laboratory. Activities at ANL are primarily research- oriented and as such affect the amount and type of source reduction that can be achieved at this facility. The objective of ANL's waste minimization program is to cost-effectively reduce all types of wastes, including hazardous, mixed, radioactive, and nonhazardous wastes. The ANL Waste Minimization Plan uses a waste minimization audit as a systematic procedure to determine opportunities to reduce or eliminate waste. To facilitate these audits, a computerized bar-coding procedure is being implemented at ANL to track hazardous wastes ...

1991-01-01

107

Survey reveals Europe's refinery-waste disposal methods, amounts, and costs

The potential hazard of landfill wastes was previously evaluated by examining the extraction procedures for individual waste, although various wastes were co-disposed of in actual landfills. This paper investigates the reduction of extraction-procedure toxicity by co-disposing various combinations of two wastes. When two wastes are mixed homogeneously, the extraction of heavy metals from the waste mixture is critically affected by the extract pH. Thus, co-disposal wastes will have a resultant pH between the pH values of its constituent. The lower the resultant pH, the lower the concentrations of heavy metals in the extract. When these wastes are extracted sequentially, the latter extracted waste has a stronger influence on the final concentration of heavy metals in the extract. Small-scale lysimeter ...

1996-12-31

108

Savannah River Site Interim Waste Management Program Plan FY 1991--1992

Results of a survey conducted by Concawe on 75 oil refineries in Europe show that the total quantity of waste requiring disposal in 1986 was 0.5 million metric tons. This quantity of waste is but 0.13% of the total refinery throughput of 387 million metric tons during 1986. The survey revealed a wide range of disposal costs, depending on the particular properties of the waste and local conditions. A summary of total waste generation and how the waste is disposed of is shown. Details on the types of waste disposed, the disposal methods used, and the costs of disposal are detailed in this excerpt from the Concawe survey.

1989-08-28

109

ICDF Complex Operations Waste Management Plan

The primary purpose of the Waste Management Program Plan is to provide an annual report of how Waste Management's operations are conducted, what facilities are being used to manage wastes, what forces are acting to change current waste management systems, and what plans are in store for the coming fiscal year. In addition, this document projects activities for several years beyond the coming fiscal year in order to adequately plan for safe handling, storage, and disposal of radioactive wastes generated at the Savannah River Site and for developing technology for improved management of wastes. In this document, work descriptions and milestone schedules are current as of December 1991.

1992-05-01

110

Defense remote-handled transuranic waste implementation plan: Transuranic Waste Program System Integration Office

This Waste Management Plan functions as a management and planning tool for managing waste streams generated as a result of operations at the Idaho CERCLA Disposal Facility (ICDF) Complex. The waste management activities described in this plan support the selected remedy presented in the Waste Area Group 3, Operable Unit 3-13 Final Record of Decision for the operation of the Idaho CERCLA Disposal Facility Complex. This plan identifies the types of waste that are anticipated during operations at the Idaho CERCLA Disposal Facility Complex. In addition, this plan presents management strategies and disposition for these anticipated waste streams.

2006-12-01

111

Streams of solid municipal wastes. Evaluation of data on the basis of waste follow-up system; Kiinteaen yhdyskuntajaetteen virrat: aineistotarkastelua jaetealan seurantajaerjestelmaen avulla

This document presents a detailed schedule for the implementation of the strategy for managing defense remote-handled (RH) transuranic (TRU) waste. The baseline management strategy was defined in the Defense Remote-Handled Transuranic Waste Cost/Schedule Optimization Study and is summarized in this document. Also included are revised RH TRU waste inventory projections, current site management plans, a list of key decision points and milestones, and a discussion of uncertainties associated with management of RH TRU waste. The plans are summarized in a detailed schedule diagram and in an RH TRU waste work off diagram. 9 refs., 5 figs., 4 tabs.

1988-01-01

112

Environmental Research Database

The follow-up system for wastes (JAeSTI), developed at the end of the 1990s, forms a basis for today's followup activities in Finland. JAeSTI relies on an environmental protection database, the compliance monitoring system VAHTI operated by the environmental authorities. Waste followup and waste statistics depend very much on the annual waste quantities recorded in the VAHTI system. In the KYJ-project the coverage and reliability of the data in the VAHTI system was evaluated as for the streams of solid municipal waste. The project also included the compiling of national statistics on municipal waste for the year 2000. The project used other information sources, too, such as statistics compiled when the National Waste Plan and regional waste plans were revised in 2002. In addition, the extent and quantity of ...

2004-07-01

113

The Waste of the World

ObjectivesThis programme aims; To rethink how waste is thought about in social science; To provide a global analysis of waste; To examine how rethinking waste impinges on core social science concerns, notably: economies, researching globalisation, hazards and risk, and materiality. Social science understandings of waste position waste as the end-point of production and consumption, and see waste as a question of disposal.DescriptionThe Waste of the World is a five year research programme funded under ESRC's Large Grant Scheme. It brings together researchers in geography, anthropology and materials science from the University of Sheffield, Durham University, University College London and Goldsmiths College London, and connects the UK with South Asia (particularly India and Bangladesh), as well as the US, Europe and Kazakhstan. The ...

2011-01-30

114

Operable Unit 3-13, Group 3, Other Surface Soils Remediation Sets 4-6 (Phase II) Waste Management Plan

Treatment of radioactive metallic waste by the electro-slag melting method

This Waste Management Plan describes waste management and waste minimization activities for Group 3, Other Surface Soils Remediation Sets 4-6 (Phase II) at the Idaho Nuclear Technology and Engineering Center located within the Idaho National Laboratory. The waste management activities described in this plan support the selected response action presented in the Final Record of Decision for Idaho Nuclear Technology and Engineering Center, Operable Unit 3-13. This plan identifies the waste streams that will be generated during implementation of the remedial action and presents plans for waste minimization, waste management strategies, and waste disposition.

2006-07-01

115

Request for interim approval to operate 218-E-12B Trench 94 as a chemical waste landfill for disposal of polychlorinated biphenyl wastes in submarine reactor compartments.

The applicability of the electro-slag melting method for treating plutonium contaminated metallic waste was studied. A 100kg test furnace was built and simulated metallic waste was melted and solidified in this furnace. Waste volume was reduced to 1/25 with a decontamination factor of 25 and the slag and the copper mold are repeatedly usable. The process is expected to be employed in the project of PWTF (Plutonium contaminated Waste Treatment Facilities).

1983-01-01

116

Projected radionuclide inventories of DWPF glass from current waste at time of production

This request is submitted to seek interim approval to operate a chemical waste landfill for the disposal of polychlorinated biphenyl (PCB) wastes. This request covers only the disposal of small quantities of solid PCB wastes contained in decommissioned su...

1990-01-01

117

Industrial waste and pollution in Mongolia

The Waste Acceptance Preliminary Specifications (WAPS) require that the DWPF estimate the inventory of long-lived radionuclides present in the waste glass, and report the values in the Waste Form Qualification Report. In this report, conservative (biased high) estimates of the radionuclide inventory of glass produced from waste currently in the Tank Farm are provided. In most cases, these calculated values compare favorably with actual data. In those cases where the agreement is not good, the values reported here are conservative.

1993-02-04

118

Finally authorized supplementary report to the review on waste disposal in the Copenhagen area 1988. [Denmark]. Endelig godkendt bilagsrapport til affaldsredegoerelse for hovedstadsregionen 1988; Bilagsrapport nr. 1

This paper very briefly outlines hazardous waste management issues, including regulations, in Mongolia. Air, water, and soil pollutants are identified and placed in context with climatic, social, and economic circumstances. The primary need identified is technology for the collection and disposal of solid wastes. Municipal waste problems include rapid urbanization and lack of sanitary landfills. Industrial wastes of concern are identified from the mining and leather industries. 4 refs., 2 tabs.

1996-12-31

119

Thermal- and radiation-induced interactions of water on U02 surfaces.

A supplementary report to the plan for waste disposal in the Copenhagen area, Denmark. It presents a mapping of wastes and waste flow in invidual areas, a description of recycling methods and waste collection systems. In addition legislative demands and potentials are dealth with. (CLS).

1988-07-01

120

The role of surfactant in synthesis of magnetic nanocrystalline powder of NiFe2O4 by sol-gel auto-combustion method

Most plans for the disposition of surplus nuclear materials involve storage in sealed containers where the evolution of gases from reactions of adsorbed water could present both pressure and flammability hazards[l] . Despite efforts such as calcining the material to minimize the water content prior to packaging, both residual moisture and readsorbed water may be present in the final containers . Given the anticipated temperature excursions during transportation and storage, this water may thermally desorb, increasing the pressure, and/or thermally dissociate to produce H2 gas, increasing flammability hazards . In addition, the radiation from the nuclear material may induce radiolysis of the water with the likely products being water vapor, H2, 02 and H2O2. In order to better understand the relative importance of the thermal- and radiationinduced chemistry, we have studied the interactions of water on single crystals of uranium dioxide .

2003-01-01

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121

British Library Electronic Table of Contents (United Kingdom)

In this work, a new sol-gel auto-combustion method has been performed to synthesize single phase nickel ferrite nanocrystalline powders by using n-cetyltrimethylammonium bromide, as a cationic surfactant. The gels were prepared from ferric and nickel nitrates and citric acid. Ammonia was used as pH adjusting agent as well. The effects of the surfactant on the after combustion calcination process and the reduction of the resulting powder crystallite size which affects the magnetic properties of the material were investigated by XRD and DTA/TGA techniques. The results showed that the ignition of the gels in air have a self-propagating behavior. Addition of surfactant to the starting solution affected the crystallite size of the synthesized powders and their phase constitution. The crystallit...

2008-01-01

122

Process for preparing inorganic particulate adsorbent and process for treating nuclear reactor core-circulating water

Electrospun porous SnO2 nanotubes as high capacity anode materials for lithium ion batteries

An inorganic particulate adsorbent of a titania-alumina is described for treating a superheated water containing radioactive materials such as cobalt ions, which is free from release of corrosive impruities, and which has a high adsorption capacity of radioactive materials and a high mechanical strength is prepared by hydrolyzing a titanium alkoxide and an aluminum alkoxide, thereby forming a hydrous titanium oxide and a hydrous aluminum oxide, respectively; precalcining the hydrous titanium oxide and aluminum oxide, mixing and molding the resulting titania and alumina into a particulate mixture thereof having a titania mole fraction of 0.2 to 0.9, and calcining the particulate mixture at 500/sup 0/-700/sup 0/C. This absorbent is effectively used in treat boiling water-type nuclear reactor core-circulating water to remove radioactive substances therefrom.

1981-08-04

123

British Library Electronic Table of Contents (United Kingdom)

Porous SnO2 nanotubes were prepared via electrospinning followed by calcination in air. As anode materials for lithium ion batteries, the porous nanotubes delivered a high discharge capacity of 807mAhg^-^1 after 50cycles. Even after cycled at high rates, the electrode still retained a high fraction of its theoretical capacity. Such excellent performances of porous SnO2 nanotubes could be attributed to the porous and hollow structure which facilitated liquid electrolyte diffusion into the bulk materials and buffered large volume changes during lithium ions insertion/extraction. Furthermore, the nanoparticles of nanotubes provided the shorter diffusion length for lithium ions insertion which benefited in retaining the structural stability and good rate performance. Our results demonstrated t...

2010-01-01

124

Electrical properties of antimony doped PLZT ceramics prepared by mixed-oxide route

Effects of manganese doping on properties of sol-gel derived biphasic calcium phosphate ceramics

Ferroelectric [Pb_0_._9_2(La_1_-_zSb _z)_0_._0_8][Zr_0_._6_0Ti_0_._4_0]O_3 for z = 0.0, 0.3, 0.6, 0.9 and 1 were prepared from their constituent oxides by a solid state reaction technique. The powders were calcined in the temperature range of 1000 deg. C for 6 h. Phase formation, crystal structure and lattice parameter were investigated by X-ray diffraction (XRD) technique. The compacts were sintered at 1250 deg. C for 2 h and their dielectric, ferroelectric and conductive properties were measured. The ferroelectric behavior of the doped samples was studied from their hysteresis loop.

2006-12-21

125

British Library Electronic Table of Contents (United Kingdom)

We have investigated the effect of manganese (Mn) doping on properties of nanosized biphasic calcium phosphate powders and their dense bodies. Manganese levels of 0.6, 1.3, 1.9, 4.3, 7.0 and 11.9at.% were successfully incorporated into biphasic calcium phosphate via a sol-gel route. The prepared powders were calcined at temperatures of 500-1200^oC. The X-ray diffraction analysis revealed that a mix phase comprising of hydroxyapatite and @b-tricalcium phosphate were present, however the content of each phases in the structure was affected by the Mn content. The studies found that the largest portion of @b-tricalcium phosphate was detected at 4.3at.% Mn doping. The incorporation of Mn has also greatly increased the crystallinity of the biphasic calcium phosphate powder due to progressive den...

2011-01-01

126

Desulphurisation of fumes as a potential source of prime materials

Catalytic tar removal from biomass producer gas with secondary air

A survey is given by the authors of methods of removing the sulphur dioxide content of fumes which can be linked together with producing useful final products. From these technologies those suppling well utilizable gypsum, the Walther process, producing ammonium sulphate, the Wellman-Lord and Bergbau-Forschung processes, respectively adapted to produce sulphuric acid or sulphur, may be of interest. Also in the method of fumes desulphurisation by catalysis by manganese, developed in KBFI, utilizable final products are given. Background of the work of developing this method. Detailed description of the manganese catalytic method based on the use of a red mud desulphurizing agent. By this process, in addition to desulphurizing fumes, enriched red mud with reduced Na/sub 2/O content is produced, which as an iron carrier, is to be reckoned with, or to be used in the cement industry for replacing imported calcined pyrites.

1986-01-01

127

Catalytic desulfurization of organic sulfur compounds over zeolite catalysts

The effect of air addition on biomass tar conversion in catalytic packed bed crackers was studied using both an isothermal micro reactor and a fluidised bed bench scale biomass gasification set up with down stream tar crackers. The micro reactor was applied for experiments with artificial biomass producer gas containing naphthalene as a model tar compound. Experiments were carried out with inert silica and catalytically active calcined dolomite bed material both with and without air addition. Experimental results with real tar from the fluidised bed bench scale gasification set up were in qualitative agreement with results from the micro reactor experiments. (author)

1997-12-31

128

Anion capture with calcium, aluminium and iron containing layered double hydroxides

In the dehydrodesulfurization of ethanethiol at 400/sup 0/C, the activities of sodium X, Y, and A zeolites decreased in the order given as did the activities of nickel, cobalt, zinc, cadmium, copper, silver, lead, manganese, barium, calcium, sodium, and iron Y zeolite catalysts. A volcano-shape order was observed between the catalytic activity and the electronegativity of the metal ions. The changes in the activity of hydrogen Y zeolite catalyst in ethanethiol dehydrodesulfurization and cumene dealkylation by calcination agreed with the decrease in the Broensted acidity but were independent of Lewis acidity. For hydrodesulfurization of thiophene, the activities of nickel, cobalt, copper, and silver Y zeolite catalysts decreased in the order given and were greater than for a commercial hydrodesulfurization catalyst; reduced and presulfided catalysts showed selective hydrodesulfurization activity. Addition of 5% of nickel or molybdenum oxides to cobalt or nickel Y ...

1980-01-01

129

British Library Electronic Table of Contents (United Kingdom)

The competitive adsorption of nitrate, chloride and carbonate in layered double hydroxides (LHD) with the general formula Formula Not Shown was investigated. Both normal ion exchange by exposure to a solution containing different anions, as well as addition of calcined material to solution thereby exploiting the memory effect of LDHs was studied. Changes in the interlayer anion changed the interlayer spacing of the LDH. The order of preference of intercalation was Formula Not Shown . When multiple anions were present in the exchange solution, LDHs with several distinct interlayer spacing were produced indicating that LDHs with different anions in the interlayer existed at the same time. However for extended exchange times (14days) where high concentrations of carbonate anion were present, ...

2011-01-01

130

Acid-site distribution on Faujasite-type zeolites determined by n-butylamine titration--1. Comparison of the use of hammett and arylmethanol indicators on zeolites X

Waste Generation and Pollution Prevention Progress Fact Sheet: Oak Ridge National Laboratory

The combined Lewis and Broensted acidities were measured of 13X (sodium) zeolite and of its 84.2% calcium-exchanged, 86.0% lanthanum-exchanged, and 69.2% protonated forms, calcined at 400/sup 0/C. The butylamine titrations were performed to visible color changes of Hammett indicators. The H/sub 0/ acidities were 0 for the sodium X zeolite, and 0.2, 0.98, and 0.75 for the calcium, lanthanum, and hydrogen zeolites, respectively. These acidities compared well with trends reported in literature for zeolites pretreated under different conditions. Titration of Broensted sites with arylmethanol indicators did not give satisfactory visible endpoints.

1980-05-29

131

Regional assessment of nonforestry related biomass resources: South Carolina

This 2-page fact sheet gives statistics on routine waste generation and projected reduction by waste type, and 1994 pollution prevention and recycling accomplishments at ORNL.

1996-09-01

132

Regional assessment of nonforestry related biomass resources: North Carolina

This document is a collection of spreadsheets detailing in a county by county manner the agricultural crop, agricultural wastes, municipal wastes, and industrial wastes of South Carolina that are potential biomass energy sources.

1988-11-01

133

Probabilities of a catastrophic waste hoist accident at the Waste Isolation Pilot Plant

This document is a collection of spreadsheets detailing in a county by county manner the agricultural crop, agricultural wastes, municipal wastes and industrial wastes of North Carolina that are potential biomass energy sources.

1988-11-01

134

Oak Ridge National Laboratory Technology Logic Diagram. Volume 2, Technology Logic Diagram: Part C, Waste Management

This report shows the probability of a catastrophic accident involving the WIPP waste hoist system. Calculations and mitigation to reduce the probability of an accident and to minimize the impact of such an accident should be included. 10 refs., 8 figs., 4 tabs.

1990-01-01

135

ORNL nuclear waste programs annual progress report for period ending September 30, 1982

This report documents site remediation at ORNL, including ORNL site characterization technologies, waste management and robotics and automation of the laboratory for waste processing and analysis.

1993-09-01

136

Integrated Models for Solid Waste Management in Tourism Regions: Langkawi Island, Malaysia

Research progress is reported in 20 activities under the headings: spent fuels, defense waste management, commercial waste management, remedial action, and conventional reactors. Separate entries were prepared for each activity.

1983-05-01

137

Fusion Reactor Radioactive Waste Management.

The population growth, changing consumption patterns, and rapid urbanization contribute significantly to the growing volumes of solid waste that are generated in urban settings. As the rate of urbanization increases, demand on the services of solid waste management increases. The rapid urban growth in Langkawi Island, Malaysia, combined with the increasing rates of solid waste production has provided evidence that the traditional solid waste management practices, particularly the methods of waste collection and disposal, are inefficient and quite nonsustainable. Accordingly, municipal managers and planners in Langkawi ...

2011-09-04

138

Department of Energy low-level waste management strategy

Quantities and compositions of non-tritium radioactive waste are estimated for some current conceptual fusion reactor designs, and disposal of large amounts of radioactive waste appears necessary. Although the initial radioactivity of fusion reactor and f...

1976-01-01

139

Cumulative releases of radionuclides from uncontained waste packages

The DOE strategy recognizes that public perception of low-level waste management practices is not positive. Actions are included that are aimed at opening the system to the public. A better informed public will be able to better assess the performance of the low-level waste management system.

1980-01-01

140

Conditioning of plastic wastes for thermal utilization; Aufbereitung von Kunststoffabfaellen zur thermischen Verwertung

This report describes mathematical predictions for the migration of radionuclides from an emplaced radioactive waste container. The model assumes a spherical-equivalent waste solid surrounded by backfill but neglects the effect of decay heat. 7 refs., 2 tabs. (TEM)

1986-07-01

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141

Waste management considerations for fusion power reactors

This article describes the processes for the treatment of plastic waste: sampling, sorting, comminution. The requirements for the different processes for waste treatment (as recycling, utilization as raw material, energy recovery, combustion) are listed. (SR)

1996-12-31

142

Waste management considerations for fusion power reactors

To estimate the waste management needs of a fusion power reactor, a scheme for handling radioactive waste from a fusion plant has been devised. The handling scheme proceeds with radioactive waste, primarily from blanket replacement, being stored on-site; waste in cooled and shielded casks is then isolated off-site; finally, the materials are recycled. Using activities and component lifetimes supplied by designers, several conceptual fusion power reactors have been analyzed and their waste streams compared to fission reactors with regard to total activity, specific activity, and lifetimes of activity.

143

Solidification of problem wastes: Annual progress report, October 1985-September 1986

To estimate the waste management needs of a fusion power reactor, a scheme for handling radioactive waste from a fusion plant has been devised. The handling scheme proceeds with radioactive waste, primarily from blanket replacement, being stored on-site; waste in cooled and shielded casks is then isolated off-site; finally, the materials are recycled. Using activities and component lifetimes supplied by designers, several conceptual fusion power reactors have been analyzed and their waste streams compared to fission reactors with regard to total activity, specific activity, and lifetimes of activity.

1978-02-01

144

Present State of Radioactive Waste Management and Treatment Technology at the Research Centre Seibersdorf

This report describes initial work on the development of solidification systems for sodium nitrate waste and compacted waste. Sodium nitrate waste has been solidified in three types of materials: polyethylene, polyester-styrene (PES), and latex cement. Evaluations of the properties of the waste form, such as the ANS 16.1 leaching test, water immersion test and compressive strength measurements were performed on the waste forms containing various amounts of sodium nitrate. 9 refs., 9 figs., 7 tabs.

1987-02-01

145

Hazardous waste operational plan for site 300

Since 1976 the Austrian Research Centre Seibersdorf has the task to collect, treat and store radioactive waste (Radwaste) arising in Austria. Within the Department of Waste Management a variety of appropriate treatment systems are installed. For storing unconditioned and conditioned waste proper storage-halls are available. The collection of Radwaste is carried out using 100 l drums, for the conditioned waste the 200 l drum concept is used. The interim storage of conditioned waste is done at Seibersdorf until a final repository is built. The present plan foresees one to be in operation at the year 2012. (author).

1996-10-07

146

Hazardous waste and environmental trade: China`s issues

This plan outlines the procedures and operations used at LLNL's Site 300 for the management of the hazardous waste generated. This waste consists primarily of depleted uranium (a by-product of U-235 enrichment), beryllium, small quantities of analytical chemicals, industrial type waste such as solvents, cleaning acids, photographic chemicals, etc., and explosives. This plan details the operations generating this waste, the proper handling of this material and the procedures used to treat or dispose of the hazardous waste. A considerable amount of information found in this plan was extracted from the Site 300 Safety and Operational Manual written by Site 300 Facility personnel and the Hazards Control Department.

1982-02-12

147

Development of the alcohol waste processing equipment

By presenting some case studies, this paper analyzes China`s situation with regard to hazardous waste: its environmental trade, treatment, and management. The paper describes China`s experiences with the environmental trade of hazardous waste in both the internal and international market. Regulations for managing the import of waste are discussed, as are China`s major approaches to the trading of hazardous waste both at home and overseas. The major reasons for setting up the Asian-Pacific Regional Training Center for Technology Transfer and Environmental Sound Management of Wastes in China and the activities involved in this effort are also described. 1 tab.

1996-12-31

148

Waste reduction at the Savannah River Site

In the experimental fast Reactor JOYO, gripper of Fuel Handling Machine and Ex-Vessel Transfer Machine that the sodium adhered is being washed with alcohol. This radioactive alcohol waste that was used to the washing is stored to the tank. If it is able to separate the alcohol and sodium in the alcohol waste it becomes possible to dispose of the alcohol waste. Japan Nuclear Institute and Fuji Electric Systems CO., LTD. Developed the device that adds carbonic acid gas to the alcohol waste and cause the sodium in the alcohol waste separated as carbonate and remove this carbonate by using the thin film evaporator. (author)

2004-11-01

149

Waste reduction at the Savannah River Site

The Savannah River Site (SRS) is a key installation for the production and research of nuclear materials for national defense and peace time applications and has been operating a full nuclear fuel cycle since the early 1950s. Wastes generated include high level radioactive, transuranic, low level radioactive, hazardous, mixed, sanitary, and aqueous wastes. Much progress has been made during the last several years to reduce these wastes including management systems, characterization, and technology programs. The reduction of wastes generated and the proper handling of the wastes have always been a part of the Site's operation. This paper summarizes the current status and future plans with respect to waste reduction to waste reduction and reviews some specific examples of successful activities.

1990-01-01

150

Solid Waste & Financial Assistance Program

The Savannah River Site (SRS) is a key installation for the production and research of nuclear materials for national defense and peace time applications and has been operating a full nuclear fuel cycle since the early 1950s. Wastes generated include high level radioactive, transuranic, low level radioactive, hazardous, mixed, sanitary, and aqueous wastes. Much progress has been made during the last several years to reduce these wastes including management systems, characterization, and technology programs. The reduction of wastes generated and the proper handling of the wastes have always been a part of the Site`s operation. This paper summarizes the current status and future plans with respect to waste reduction to waste reduction and reviews some specific examples of successful activities.

1990-12-31

151

SUCCESSES AND EMERGING ISSUES IN SIMULATING THE MIXING BEHAVIOR OF LIQUID-PARTICLE NUCLEAR WASTE SLURRIES AT THE SAVANNAH RIVER SITE - 211B

This program deals with solid waste disposal with topics/services covering: Reusable Building Materials and Large Household Items Exchange, Beneficial Use Determination, Biosolids, Certification, Compost Facil...

152

Proceedings of the eighth annual DOE low-level waste management forum: Technical Session 6, Waste treatment

Aqueous radioactive high-level waste slurries are combined during processing steps that ultimately produce a stable borosilicate glass waste form. Chemically treated waste slurries are combined with each other and with glass frit-water slurries to produce the melter feed. Understanding the evolution of the rheological properties of the slurries is an important aspect of removing and treating the stored waste. To a first approximation, combinations of colloidal waste slurry with {approx}0.1-mm mean diameter glass frit or glass beads act in an analogous matter to slurries of spherical beads in Newtonian liquids. The non-Newtonian rheological properties of the waste slurries without frit, however, add complexity to the hydrodynamic analysis. The use of shear rate dependent apparent viscosities with the modified Einstein equation was used to model the rheological ...

2009-09-02

153

Nuclear waste plans enter critical phase

Nine papers in this proceedings have been processed for inclusion in the Energy Data Base. (AT)

1987-02-01

154

Nuclear power plant liquid waste solidification system. [Japan

A brief article considers the possible result of the enquiry into Nirex`s plan to build an underground rock laboratory at Sellafield in relation to radioactive waste disposal in the UK. (UK).

1996-10-31

155

Nuclear power plant liquid waste solidification system

The fundamental points to be considered in a waste treatment system for a country like Japan, where the final disposal method has not been decided and the wastes have to be stored in the power plants, are volume reduction of the wastes, safe storage of the wastes in the plant, and flexibility regarding the final disposal. A system has been developed that consists of a thin film evaporator for the direct solidification of the liquid waste, a pelletizer for producing hard pellets from the powdered wastes, a pellet storage unit, and a solidification unit for the final disposal. A pilot plant with waste treatment capacity of 200 kg/h was built in 1976 and has proved the system feasibility. This paper reports on pilot plant tests of the thin film evaporator and other components, tests on pellet deterioration during long term storage, and ...

1981-01-01

156

Nondestructive characterization of low-level transuranic waste

The fundamental points to be considered in a waste treatment system for a country like Japan, where the final disposal method has not been decided and the wastes have to be stored in the power plants, are volume reduction of the wastes, safe storage of the wastes in the plant, and flexibility regarding the final disposal. A system has been developed that consists of a thin film evaporator for the direct solidification of the liquid waste, a pelletizer for producing hard pellets from the powdered wastes, a pellet storage unit, and a solidification unit for the final disposal. A pilot plant with waste treatment capacity of 200 kg/h was built in 1976 and has proved the system feasibility. This paper reports on pilot plant tests of the thin film evaporator and other components, tests on pellet deterioration during long term storage, and ...

1981-02-26

157

The use of nondestructive evaluation (NDE) methods is proposed for characterization of transuranic (TRU) waste stored at the Radioactive Waste Management Complex. These NDE methods include real-time x-ray radiography, real-time neutron radiography, x-ray and neutron computed tomography, thermal imaging, container weighing, visual examination, and acoustic measurements. An integrated NDE system is proposed for characterization and certification of TRU waste destined for eventual shipment to the Waste Isolation Pilot Plant in New Mexico. Methods for automating both the classification waste and control of a complete nondestructive evaluation/nondestructive assay system are presented. Feasibility testing of the different NDE methods, including real-time x-ray radiography, and development of automated waste classification techniques are covered as part of a five year ...

1981-10-01

158

NASA - Waste Not

Jun 4, 2004 ... On a two-year trip to Mars, according to one estimate, a crew of six humans will generate more than six tons of solid organic waste--much of ...

159

NAME=\\

Mixed waste disposal facility at the Nevada Test Site

... Waste Collection Systems Products and Equipment Find and compare a variety of waste collection systems products and equipment on the world's largest environmental industry portal. View product ...

160

Kraft pulping of industrial wood waste

This report provides a brief overview of the history and planning for a proposed mixed waste disposal site on the Nevada Test Site. 8 figs.

1987-01-01

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161

Jun 16, 2011 ... Description: Most of the approximately 25 to 30 million tons of industrial wood waste generated in the United States per year is burned for ...

162

Fish waste - NASA Quest

Factoring Potential Accelerator Transmutation of Waste Demonstrations into Accelerator Production of Tritium Design Planning

Seriously, generally fish waste does drop, but quite slowly. But a good group of snails should still do a fine job of cleaning the tank. ...

163

Current waste-management practices and operations at Oak Ridge National Laboratory, 1982

Factoring Potential Accelerator Transmutation of Waste Demonstrations into Accelerator Production of Tritium Design Planning

1998-01-01

164

Converting Simulated Sodium-bearing Waste into a Single Solid Waste Form by Evaporation: Laboratory- and Pilot-Scale Test Results on Recycling Evaporator Overheads

The need for efficient management of industrial chemical wastes, especially those considered hazardous or radioactive, is receiving increased attention in the United States. During the past five years, several federal laws have addressed the establishment of stronger programs for the control of hazardous and residual wastes. At a facility such as Oak Ridge National Laboratory (ORNL), an efficient waste management program is an absolute necessity to ensure protection of human health and compliance with regulatory requirements addressing the treatment and disposal of hazardous, nonhazardous, and radioactive wastes. This report highlights the major regulatory requirements under which the Laboratory must operate and their impact on ORNL facilities. Individual waste streams, estimates of quantities of waste, and current waste management ...

1982-09-01

165

Acid Waste Equipment on Environmental Expert

Conversion of Idaho National Engineering and Environmental Laboratory radioactive sodium-bearing waste into a single solid waste form by evaporation was demonstrated in both flask-scale and pilot-scale agitated thin film evaporator tests. A sodium-bearing waste simulant was adjusted to represent an evaporator feed in which the acid from the distillate is concentrated, neutralized, and recycled back through the evaporator. The advantage to this flowsheet is that a single remote-handled transuranic waste form is produced in the evaporator bottoms without the generation of any low-level mixed secondary waste. However, use of a recycle flowsheet in sodium-bearing waste evaporation results in a 50% increase in remote-handled transuranic volume in comparison to a non-recycle flowsheet.

2004-01-01

166

Lubricating composition for processing of flushing fluids

...Systems by IPEX Enfield electrofusion acid waste systems give you the proven corrosion resistance of polypropylene, along with our patented, state-of-the-art electrofusion system....

167

Oak Ridge National Laboratory Waste Management Plan, fiscal year 1994. Revision 3

Proposed is a lubricating composition for processing flushing fluids, which contains synthetic fatty acids of the fraction carbon 11-20, oxidized petrolatum, mineral oil, and additives. In order to increase the antiwear, anticorrosion, and antiscratching properties of the composition under conditions of polymineral corrosion with simultaneous decrease in the water loss of the flushing fluids as additives the composition contains stearic acid, polyoxyethylated methyl phenol, naptha soap, 1,5-dibenzoylnapthaline-4', 4''-dicarboxylic acid, calcined soda, secondary nonsaponifiables, obtained in the production of synthetic fatty acids by oxidation of paraffin, and polyfunctional oxygen-bearing compounds, obtained by oxidation of secondary nonsaponifiables by atmospheric oxygen, with the following ratio of components, wt%: 17.2-19.2% synthetic fatty acids of the carbon 17-20 fraction, 5.2-5.8% oxidized petrolatum, 3.5-3.7% polyoxyethylated ...

1981-03-15

168

Wasted breath: Dispatcher-assisted CPR in out-of-hospital cardiac arrest meets cardio-cerebral resuscitation.

US Department of Energy (DOE) Order 5820.2A was promulgated in final form on September 26, 1988. The order requires heads of field organizations to prepare and to submit updates on the waste management plans for all operations under their purview according to the format in Chap. 6, {open_quotes}Waste Management Plan Outline.{close_quotes} These plans are to be submitted by the DOE Oak Ridge Operations Office (DOE-ORO) in December of each year and distributed to the DP-12, ES&H-1, and other appropriate DOE Headquarters (DOE-HQ) organizations for review and comment. This document was prepared in response to this requirement for fiscal year (FY) 1994. The Oak Ridge National Laboratory (ORNL) waste management mission is reduction, collection, storage, treatment, and disposal of DOE wastes, generated primarily in pursuit of ORNL missions, in order to protect human health and safety and the environment. ...

1993-12-01

169

Waste management facilities cost information for hazardous waste. Revision 1

PMID:21864481

2011-08-22

170

Waste Diversion | Greening EPA | US EPA

This report contains preconceptual designs and planning level life-cycle cost estimates for managing hazardous waste. The report`s information on treatment, storage, and disposal modules can be integrated to develop total life-cycle costs for various waste management options. A procedure to guide the US Department of Energy and its contractor personnel in the use of cost estimation data is also summarized in this report.

1995-06-01

171

Utilization of plastic wastes in a blast furnace - a contribution to ecological and economical recycling of plastic wastes; Kunststoffverwertung im Hochofen - ein Beitrag zum oekologischen und oekonomischen Recycling von Altkunststoffen

...diversion generates a host of environmental, financial, and social benefits, including conserving energy, reducing disposal costs, and reducing the burden on landfills and other waste disposal methods . Waste Diversion at EPA For many years, EPA has established waste diversion goals that exceed current federal requirements. EPA ...

172

The Characteristics of P.H.C Pile using Admixture by Waste TFT-LCD Glass Powder

This article describes the utilization of plastic wastes in a blast furnace. The plastic waste is a substitution for petroleum and coal as a raw material for synthesis gas production. The synthesis gas is the reducing agent in the blast furnace for the reduction of iron ores. You can find here an ecological and economical analysis of this process in comparison to the utilization of petroleum and coal. (SR)

1996-12-31

173

Study on the Development of Solid Fuel of Animal Wastes for Heating of Agricultural Facilities

Full Text Available

2010-09-01

174

Simulation of the flue gas treatment processes of an industrial-waste incinerator using Aspen plus

Full Text Available

2007-10-01

175

Resources | Environment Knowledge Hub

Full Text Available

2009-11-01

176

Request for interim approval to operate 218-E-12B Trench 94 as a chemical waste landfill for disposal of polychlorinated biphenyl wastes in submarine reactor compartments. Revision 1.

... MUNICIPAL SOLID WASTES (MANAGEMENT AND HANDLING) RULES, 2000 Plastic Bag ban in Dhaka City, Bangladesh Private Sector Participation in Municipal Solid Waste Management SKAT 2000 TECHNICAL GUIDELINES ON MUNICIPAL SOLID WASTE MANAGEMENT Hazardous Waste Management Unit, Environmental Pollution Control Division, Central Environmental Authority, Sri Lanka 2004 Subregional ...

177

Recycle of the chemicals from waste generated during fabrication of ceramic nuclear fuel material

This request is submitted to seek interim approval to operate a chemical waste landfill for the disposal of polychlorinated biphenyl (PCB) waste. Interim approval is requested for a period not to exceed 5 years. This request covers only the disposal of sm...

1992-01-01

178

Pretreatment of Waste Newspaper Using Ethylene Glycol for Bioethanol Production

Short communication.

179

Preparation and Physicochemical Properties of Chitosan from Red Crab Waste-Shell

Full Text Available

2010-12-01

180

Physicochemical Characteristics of Waste Catalyst and Their In-Process Products from Recycling

Full Text Available

2001-03-01

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181

Oil refinery waste disposal methods, quantities and costs, 1993 survey

Full Text Available

2011-04-01

182

Nanotechnology risk assessment from a waste management perspective: Are the current tools adequate?

This report summarizes the information gathered by CONCAVE in a 1993 survey of waste generation and disposal by the oil refineries in Western Europe. The survey covered the types of waste produced, their quantities, disposal routes and costs of disposal. The results are compared with those from a 1986 survey, but because of the increased numbers of refineries reporting, comparison is difficult. The survey revealed wide variations in disposal costs depending on waste type and local circumstances.

1995-06-01

183

CSIR Research Space (South Africa)

Full Text Available

184

Model analysis of an inter-industrial and inter-regional waste recycling system in Japan

Methane fermentation of agricultural wastes and domestic animal's wastes

In this study, we investigate an inter-industrial and inter-regional recycling system for industrial waste by the cement industry in Japan. We develop a linear programming model that represents cement production processes and waste transportation of all cement factories in Japan. We simulate cost and CO{sub 2}-minimizing systems. The result implies that making waste transportation more efficient in cost is an effective means for CO{sub 2} reduction. (author)

2007-04-15

185

Mechanical-biological waste treatment as an alternative to thermal processes; MBA-Konzepte als Alternative zur thermischen Abfallbehandlung

Cattle and pig wastes, orange peels, compost, and grain husks were hydrolyzed in an alkaline medium to investigate the CH4 generation capacity. The respective CH4 production capacities from pig wastes and rice hulls were approximately 1 and approximately 0.1 L/g. The CH4 produced can be used to supplement energy requirements of farms.

1981-01-01

186

Manufacturing Characteristics of Environmental-friendly Waste Ash Brick with Industrial By-Products

No abstract prepared.

2001-09-01

187

MANAGING WASTE AT LOS ALAMOS NATIONAL LABORATORY'S PLUTONIUM FACILITIES

Full Text Available

2009-06-01

188

Investigation into matrix materials for immobilization of plutonium electrochemical reprocessing radioactive wastes

No abstract prepared.

2000-01-01

189

Improvement of Kimchi Juice Fermentation by Combined method for Chinese Cabbage Waste Utilization

... NUCLEAR FUEL CYCLE AND FUEL MATERIALS borophosphate glass

2002-04-17

190

Idaho National Engineering Laboratory Nonradiological Waste Management Information for 1992 and record to date

Full Text Available

1997-10-01

191

GS1 - radiological protection objectives for the disposal of solid radioactive wastes

This document provides detailed data and graphics on airborne and liquid effluent releases, fuel oil and coal consumption, water usage, and hazardous and mixed waste generated for calendar year 1992. This report summarizes industrial waste data records compiled since 1971 for the Idaho National Engineering Laboratory (INEL). The data presented are from the INEL Nonradiological Waste Management Information System.

1993-08-01

192

Estimation of animal and olive solid wastes in Jordan and their potential as a supplementary energy source: An overview

A summary is given of the 1983 NRPB-GS1 Report on the 'Radiological protection objectives for the disposal of solid radioactive wastes'. The two principal difficulties in applying the ICRP system of dose limitation to some solid waste disposal methods are outlined. Despite these difficulties three radiological protection objectives for waste disposal were recommended based on the same fundamental principle as ICRP recommendations.

1984-01-01

193

Environmental assessment of coal waste mounds in Japan using remote sensing techniques

Biomass is a potential source of energy that can reduce our dependency on oil as the main source of energy. In addition to municipal solid waste, animal and olive wastes are the main sources of organic waste in Jordan. In 2005, there were more than 2.4 million heads of sheep, about 72 thousand cows, and 40 million hens being raised in farms distributed in all governorates of Jordan. These animals produce 5.3 million tons (as exerted) of solid waste per year. If these quantities can be effectively collected they may constitute a valuable source of energy. This paper is aiming to estimate the amounts of animal and solid wastes generated in Jordan and their energy potential. The total amount of BOD from animal waste is estimated at 200,000 tons per year. Significant quantities of organic waste can also be collected from olive mills distributed ...

2010-10-15

194

Energy recovery from waste by use of fluidized-bed technology

Focuses on the application of remote sensing techniques to the study of coal waste mounds. The situation at the coal waste mounds in Fukuoka, Japan is cited. Guidelines on film parameters, photographic keys and tasks required to inventory, monitor and manage coal waste mounds in Japan are addressed. Application of photogrammetry, remote sensing, aerial photography and satellite imagery techniques in monitoring spoil banks is reviewed. Applicability of the techniques is discussed. 24 refs.

1993-01-01

195

EVALUATION OF RISKS AND WASTE CHARACTERIZATION REQUIREMENTS FOR THE TRANSURANIC WASTE EMPLACED IN WIPP DURING 1999

Revolving type fluidized-bed technology, developed by Ebara Corp., is installed in more than 100 facilities worldwide. The technology is applied for waste, coal and in situations where a conventional fluidized bed is difficult to use. Waste and/or coal can be treated and valuable energy can be recovered from a non-renewable source. This paper describes the application of the revolving fluidized bed for waste, coal and tyres.

1999-07-01

196

Decomposition Mechanism of Waste Hard Metals using by ZDP (Zinc Decomposition Process)

Specifically this report: 1. Compares requirements of the WAP that are pertinent from a technical viewpoint with the WIPP pre-Permit waste characterization program, 2. Presents the results of a risk analysis of the currently emplaced wastes. Expected and bounding risks from routine operations and possible accidents are evaluated; and 3. Provides conclusions and recommendations.

2000-05-01

197

Decommissioning of facility for use of radioisotopes on waste management and disposal facility

Full Text Available

2011-03-01

198

Chracteristics of Cement Mortar Mixed with Incinerated Urban Solid Waste

All the tests have been finished up in the Waste Management and Disposal Facility which has been used for the safety tests of solidified radioactive waste on sea dumping disposal. The decommissioning of this facility was performed for use of radioisotopes. This report describes the plan on decommissioning of facility for use of radioisotopes, the contamination checking methods and measurement of radioactivity, the fore case and practice for amount of generated radioactive wastes, the operation procedures for dismantlement, the safety measures, the expenses for decommissioning and so on. (author)

1999-09-01

199

Characterisation of long-lived low and intermediate-level radioactive wastes in the Nordic Countries

Full Text Available

2010-05-01

200

The present report is final report from a study on characterisation of radioactive waters in the Nordic countries. The study has mainly been focused on long-lived low and intermediate level radioactive waste. Methods to measure or estimate the activity content and the general composition are discussed. Recommendations are given regarding characterisation of waste under treatment and characterisation of already produced waste packages. (au).

2005-01-01

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201

CONVERTING WASTE

condenser, gas refiner, oil (gas) storage tank and dual fuel engine

202

BC

criteria which would constitute environmentally sound management of mobile phone waste in accordance with the Basel Convention;

203

BC

Achievements and Perspectives of the Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management

all Certified ESM facilities capable of receiving used mobile phone waste from non-Annex VII countries.

204

A study on determinants having influence on heating value of waste-derived solid fuels

The Joint Convention on the Safety of Spent Fuel management and on the Safety of Radioactive Waste Management is the first legal instrument to directly address the safety of spent fuel and radioactive waste management on a global scale. The Joint Convention entered into force in 2001. This paper describes its process and its main achievements to date. The perspectives to establish of a Global Waste Safety Regime based on the Joint Convention are also discussed. (authors)

205

1993 Annual report on waste generation and waste minimization progress as required by DOE Order 5400.1, Hanford Site

Full Text Available

2010-01-01

206

Negotiating equity for management of DOE wastes

More important than waste generation numbers, the pollution prevention and waste minimization successes achieved at Hanford in 1993 have reduced waste and improved operations at the Site. Just a few of these projects are: A small research nuclear reactor, unused and destined for disposal as low level radioactive waste, was provided to a Texas University for their nuclear research program, avoiding 25 cubic meters of waste and saving $116,000. By changing the slope on a asphalt lot in front of a waste storage pad, run-off rainwater was prevented from becoming mixed low level waste water, preventing 40 cubic meters of waste and saving $750,000. Through more efficient electrostatic paint spraying equipment and a solvent recovery system, a paint shop reduced hazardous waste by 3,500 kilograms, saving ...

207

Low-level Waste Forum meeting report. Winter meeting, January 26--28, 1994

One important factor frustrating optimal management of Department of Energy (DOE)-complex wastes is the inability to use licensed and permitted facilities systematically. Achieving the goal of optimal use of DOE`s waste management facilities is politically problematic for two reasons. First, no locale wants to bear a disproportionate burden from DOE wastes. Second, the burden imposed by additional wastes transported from one site to another is difficult to characterize. To develop a viable framework for equitably distributing these burdens while achieving efficient use of all DOE waste management facilities, several implementation and equity issues must be addressed and resolved. This paper discusses stakeholder and equity issues and proposes a framework for joint research and action that could facilitate equity negotiations among stakeholder and move toward a more optimal use of ...

1994-09-01

208

Liquid radioactive waste discharges from B plant to cribs

The Low-Level Radioactive Waste Forum is an association of representatives of states and compacts established to facilitate state and compact commission implementation of the Low-Level Radioactive Waste Policy Act of 1980 and the Low-Level Radioactive Waste Policy Amendments Act of 1985 and to promote the objectives of low-level radioactive waste regional compacts. The Forum provides an opportunity for states and compacts to share information with one another and to exchange views with officials of federal agencies. The Forum participants include representatives from regional compacts, designated host states, unaffiliated states, and states with currently-operating low-level radioactive waste facilities. This report contains information synthesizing the accomplishments of the Forum, as well as any new advances that have been made in the management of low-level radioactive ...

1994-12-31

209

Theory and evidence of economies of scale in the development of waste management systems

This engineering report compiles information on types and quantities of liquid waste discharged from B-Plant directly to cribs, ditches, reverse wells, etc., that are associated with B-Plant. Waste discharges to these cribs via overflow form 241-B, 241-BX, and 241-BY tank farms, and waste discharged to these cribs from sources other than B-Plant are discussed.Discharges from B-Plant to other cribs, unplanned releases, or waste remaining in tanks are not included in the report. Waste stream composition information is used to predict quantities of individual chemicals sent to cribs. This provides an accurate mass balance of waste streams from B-Plant to these cribs. These predictions are compared with known crib inventories as a verification of the process.

1996-05-29

210

The control of radioactive wastes and the quality assurance requirements

Waste is a cost of doing business. This cost can be considered in terms of the potential adverse health and environmental impacts, or the waste management costs associated with avoiding, minimizing, and controlling those impacts. There is an anticipated increase in the cost of waste management as a result of the increasing requirements for regulatory compliance. To meet the total waste management capacity needs of the organization and the compliance requirements, low-level radioactive, hazardous, and mixed waste management will need demonstrated technologies strategically managed as a technology portfolio. The role of the decision maker is to select the optimum mix of technologies and facilities to provide the waste management capacity needed for the next twenty years. The waste management system resulting from this mix includes multiple ...

1989-01-01

211

The Los Alamos National Laboratory Transuranic Waste Retireval Project

For prolonged storage and eventual disposal radioactive wastes will be solidified to reduce the problems which accompany liquid waste whilst solid wastes will be encapsulated in an immobilising matrix. In the solidification and encapsulation process it will be important to produce a material in a form which is chemically stable, mechanically strong and which will not react with or allow free passage of groundwater. To this end a continuous check will be required to ensure that the various wastes are chemically compatible with the solidifying and binding matrices and that the associated processes are performed against a strict Quality Programme. The Quality Programme will be extensive requiring the specification of procedures for assessing the quality and nature of the wastes, the detailed operation of the solidification and/or encapsulation, the overpack requirements for ...

212

Nuclear waste treatment program: Annual report for FY 1987

This paper presents the status of the Los Alamos National Laboratory (LANL) project for remediation of transuranic (TRU) and TRU mixed waste from Pads 1, 2, and 4. Some of the TRU waste packages retrieved from Pad I are anticipated to be part of LANL`s initial inventory to be shipped to the Waste Isolation Pilot Plant (WIPP) in April 1998. The TRU Waste Inspectable Storage Project (TWISP) was initiated in February 1993 in response to the New Mexico Environment Department`s (NMED`s) Consent Agreement for Compliance Order, ``New Mexico Hazardous Waste Agreement (NMHWA) 93-03.`` The TWISP involves the recovery of approximately 16,865 TRU and TRU-mixed waste containers currently under earthen cover on Pads 1, 2, and 4 at Technical Area 54, Area G, and placement of that waste into inspectable storage. All waste will be moved ...

1997-02-01

213

Influence of temperature on strength of cemented surrogate nitrate salt waste

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 ...

1988-09-01

214

Influence of temperature on strength of cemented surrogate nitrate salt waste

The Rocky Flats Plant (RFP) generates large volumes of a low level aqueous waste stream high in nitrate salts. The aqueous waste is concentrated by evaporation and then mixed with Portland cement prior to transport and disposal. Planned process upgrades include a new horizontal thin film evaporator. Temperature of brine at discharge end of the new evaporator will be near boiling point. Introduction of hot water to cement can degrade the monolithic waste form. However, the RFP salt waste contains high concentrations of compounds known to retard hydration. This paper discusses impact of introducing high temperature waste to cement. The study evaluated three waste compositions: (1) highest probable nitrate composition, (2) highest probable chloride composition, and (3) current composition. Results showed that compressive strength of final waste ...

1993-01-01

215

DWPF waste form compliance plan (Draft Revision)

The Rocky Flats Plant (RFP) generates large volumes of a low level aqueous waste stream high in nitrate salts. The aqueous waste is concentrated by evaporation and then mixed with Portland cement prior to transport and disposal. Planned process upgrades include a new horizontal thin film evaporator. Temperature of brine at discharge end of the new evaporator will be near boiling point. Introduction of hot water to cement can degrade the monolithic waste form. However, the RFP salt waste contains high concentrations of compounds known to retard hydration. This paper discusses impact of introducing high temperature waste to cement. The study evaluated three waste compositions: (1) highest probable nitrate composition, (2) highest probable chloride composition, and (3) current composition. Results showed that compressive strength of final waste ...

1993-03-01

216

DWPF waste form compliance plan (Draft Revision)

The Department of Energy currently has over 100 million liters of high-level radioactive waste in storage at the Savannah River Site (SRS). In the late 1970's, the Department of Energy recognized that there were significant safety and cost advantages associated with immobilizing the high-level waste in a stable solid form. Several alternative waste forms were evaluated in terms of product quality and reliability of fabrication. This evaluation led to a decision to build the Defense Waste Processing Facility (DWPF) at SRS to convert the easily dispersed liquid waste to borosilicate glass. In accordance with the NEPA (National Environmental Policy Act) process, an Environmental Impact Statement was prepared for the facility, as well as an Environmental Assessment of the alternative waste forms, and issuance of a Record of Decision (in December, 1982) on ...

1991-01-01

217

Analysis of options for coal combustion waste management in the Pacific Basin

The Department of Energy currently has over 100 million liters of high-level radioactive waste in storage at the Savannah River Site (SRS). In the late 1970`s, the Department of Energy recognized that there were significant safety and cost advantages associated with immobilizing the high-level waste in a stable solid form. Several alternative waste forms were evaluated in terms of product quality and reliability of fabrication. This evaluation led to a decision to build the Defense Waste Processing Facility (DWPF) at SRS to convert the easily dispersed liquid waste to borosilicate glass. In accordance with the NEPA (National Environmental Policy Act) process, an Environmental Impact Statement was prepared for the facility, as well as an Environmental Assessment of the alternative waste forms, and issuance of a Record of Decision (in December, 1982) on the ...

1991-12-31

218

Yucca Mountain, Nevada - A Proposed Geologic Repository for High-Level Radioactive Waste (Volume 1) Introduction

Many Pacific Basin countries rely on oil for electricity production. Alternative fuel sources such as coal, which is available in the Pacific Basin, can help mitigate adverse impacts of sudden price increases or supply disruptions. Coal combustion produces solid and potentially hazardous wastes of concern to environmental regulators and utility managers. This paper identifies issues associated with managing coal combustion wastes in the Pacific Basin, using the state of Hawaii as a case study. Hawaii is typical of many Pacific Basin locations in that it depends on oil, has limited sites, for waste management operations, and is subject to domestic and international waste management regulations. The paper discusses coal-fired utility wastes, environmental impacts of coal combustion waste disposal, and regulatory requirements that impact coal ...

1993-10-01

219

Waste plastic treatment equipment; Hai plastic shori sochi

Yucca Mountain in Nevada represents the proposed solution to what has been a lengthy national effort to dispose of high-level radioactive waste, waste which must be isolated from the biosphere for tens of thousands of years. This chapter reviews the background of that national effort and includes some discussion of international work in order to provide a more complete framework for the problem of waste disposal. Other chapters provide the regional geologic setting, the geology of the Yucca Mountain site, the tectonics, and climate (past, present, and future). These last two chapters are integral to prediction of long-term waste isolation.

2006-09-25

220

Waste management systems model for energy systems sites on the Oak Ridge Reservation

In recent years, there has been increasing demand for resource-recycling of waste plastic, especially due to the introduction of legislation on recycling of materials used for packages of household goods. Methods of recycling waste plastic from household goods are currently still under development, and appropriate techniques to deal with such waste are required. Toshiba has developed a technique to dehydrochlorinate plastic containing polyvinyl chloride (PVC). This paper introduces our petrolization and dehydrochlorination system for waste plastic containing PVC. (author)

1999-04-01

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221

There is a model on the Oak Ridge Reservation which provides requirements for determining capacities and capabilities related to low-level, hazardous, and mixed wastes. In FY 1987, the model will be sufficiently advanced to provide various waste management scenarios. These scenarios will be compared technically, operationally, and financially by use of waste characterization data and process simulators that are currently under development. The results of the process simulations will be used to help identify waste treatment, storage, and disposal technologies that need to be demonstrated prior to full-scale development for DOE use. The information derived from this effort will be made available to all DOE facilities.

1986-01-01

222

Vitrification of waste

Quality assurance requirements for certification of TRU waste for shipment to the WIPP

A method for encapsulating and immobilizing waste for disposal. Waste, preferably, biologically, chemically and radioactively hazardous, and especially electronic wastes, such as circuit boards, are placed in a crucible and heated by microwaves to a temperature in the range of approximately 300{degrees}C to 800{degrees}C to incinerate organic materials, then heated further to a temperature in the range of approximately 1100{degrees}C to 1400{degrees}C at which temperature glass formers present in the waste will cause it to vitrify. Glass formers, such as borosilicate glass, quartz or fiberglass can be added at the start of the process to increase the silicate concentration sufficiently for vitrification.

1992-12-31

223

Projected radionuclide inventories of DWPF glass from current waste at time of production. Revision 1

This document presents the basic Quality Assurance (QA) requirements which shall be included in the Quality Assurance Program established by sites planning to certify Transuranic (TRU) Waste to Waste Isolation Pilot Plant (WIPP) Waste Acceptance Criteria. These QA requirements were modeled after ANSI/ASME NQA-1-1979. The application of quality assurance to Waste Certification Programs is required by WIPP-DOE-069 and DOE Order 5700.6A, as implemented by DOE Order AL 5700.6A.

224

Process and system for treatment of radioactive waste

The Waste Acceptance Preliminary Specifications (WAPS) require that the DWPF estimate the inventory of long-lived radionuclides present in the waste glass, and report the values in the Waste Form Qualification Report. In this report, conservative (biased high) estimates of the radionuclide inventory of glass produced from waste currently in the Tank Farm are provided. In most cases, these calculated values compare favorably with actual data. In those cases where the agreement is not good, the values reported here are conservative.

1993-02-04

225

PFP dangerous waste training plan

In a treatment system of radioactive waste solution including sodium sulfate generated from a boiling water type nuclear reactor, waste solution is fed into a thin film evaporator where the waste solution is evaporated and made into powder while precipitating in a peripheral surface of the evaporator vessel. The surface of the precipitated solid is wiped by rotating wiper blades and removed off as radioactive solid powder. The rotational speed of a rotor to which the wiper blades are secured is controlled at a minimum and necessary rotational speed which contributes to make the waste solution into the powder so that the rate of worn out of the wiper blade is decreased.

1985-07-02

226

Material-not-categorized-as-waste survey for 1992

This document establishes the minimum training requirements for the Plutonium Finishing Plant (PFP) personnel who are responsible for management of dangerous waste. The training plan outlines training requirements for handling of solid dangerous waste during generator accumulation and liquid dangerous waste during treatment and storage operations. The implementation of this training plan will ensure the PFP facility compliance with the training plan requirements of Dangerous Waste Regulation. Chapter 173-303-330. Washington Administrative Code (WAC). The requirements for such compliance is described in Section 11.0 of WHC-CM-7-5 Environmental Compliance Manual.

1996-01-01

227

Mastery of risks: we build the memory of radioactive waste disposal facilities

In October 1992, the US Department of Energy, Richland Field Office (RL) requested that Westinghouse Hanford Company (WHC) respond to a letter from EM-331 asking for completion of a survey of items in storage but not categorized as waste (Roberts 1992). The letter contained an attachment with instructions on how to fill out the attached form and what to exclude from the survey (Appendix A). This report is a summary of the information from the response issued to RL. This report primarily is for use in estimating future waste volumes that may have been overlooked because of the nature of their classification as material not categorized as waste (MNCAW) (i.e., not yet declared Waste).

1993-07-01

228

Feasibility study on the management of the disposal of Bangkok municipal waste. Final report

The ANDRA, the French national agency of radioactive wastes, is organizing today the information needs of tomorrow. The aim is to allow the future generations to have access to the knowledge of the existence of subsurface radioactive waste facilities and to understand the context and technologies of such facilities. The storage of this information is made on 'permanent paper', a high resistant paper with a lifetime of 600 to 1000 years. An updating of these data is made every 5 years for each waste disposal center. Another project, still in progress, concerns the memory management of deep geologic waste disposal facilities for which the time scale to be considered is of the order of millennia. (J.S.)

229

Co-processing; Waste-derived fuels help solve compliance problems and produce usable materials

In January, 1985, the Government of Thailand sought assistance from the United States Trade and Development Program (USTDP) to undertake a feasibility study to review and update the solid waste management master plan, with particular emphasis to be placed on waste disposal methods. In April, 1985, the USTDP engaged the firm of Engineering and Economic Research, Inc. to carry out a definitional/prefeasibility study to assess the potential of a project for solid waste management and energy production using municipal solid waste as fuel.

1989-09-01

230

Aqueous radioactive waste bituminization

An estimated 265 million tons of hazardous waste are generated annually in the United States. Traditional waste disposal methods are inadequate, and many are no longer environmentally acceptable. Still, the waste increases along with demands for clean, environmentally safe methods for dealing with it. Faced with these demands, many hazardous waste generators are turning for help to co-processing,'' technology that goes beyond a no-impact solution to one of net positive impact, both environmentally and economically. This paper describes co-processing.

1990-01-01

231

Anaerobic digestion of municipal solid waste: Technical developments

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

5049-01-01

232

The Waste Management Plan integration into Decommissioning Plan of the WWR-S research reactor from Romania

The anaerobic biogasification of organic wastes generates two useful products: a medium-Btu fuel gas and a compost-quality organic residue. Although commercial-scale digestion systems are used to treat municipal sewage wastes, the disposal of solid organic wastes, including municipal solid wastes (MSW), requires a more cost-efficient process. Modern biogasification systems employ high-rate, high-solids fermentation methods to improve process efficiency and reduce capital costs. The design criteria and development stages are discussed. These systems are also compared with conventional low-solids fermentation technology.

1996-01-01

233

Survey of agents and techniques applicable to the solidification of low-level radioactive wastes

The paper presents the progress of the Radioactive Waste Management Plan which accompanies the Decommissioning Plan for research reactor WWR-S located in Magurele, Ilfov, near Bucharest, Romania. The new variant of the Decommissioning Plan was elaborated taking into account the IAEA recommendation concerning radioactive waste management. A new feasibility study for WWR-S decommissioning was also developed. The preferred safe management strategy for radioactive wastes produced by reactor decommissioning is outlined. The strategy must account for reactor decommissioning, as well as rehabilitation of the existing Radioactive Waste Treatment Plant and the upgrade of the Radioactive Waste Disposal Facility at Baita-Bihor. Furthermore, the final rehabilitation of the laboratories and reusing of cleaned reactor building is envisaged. An inventory of each type of radioactive ...

2008-05-28

234

Solidification of DOE problem wastes

A review of the various solidification agents and techniques that are currently available or potentially applicable for the solidification of low-level radioactive wastes is presented. An overview of the types and quantities of low-level wastes produced is presented. Descriptions of waste form matrix materials, the wastes types for which they have been or may be applied and available information concerning relevant waste form properties and characteristics follow. Also included are descriptions of the processing techniques themselves with an emphasis on those operating parameters which impact upon waste form properties. The solidification agents considered in this survey include: hydraulic cements, thermoplastic materials, thermosetting polymers, glasses, synthetic minerals and composite materials. This survey is part of a program supported by the United States ...

1981-12-01

235

Recycling of waste polymeric materials using ionizing radiation techniques for possible applications and practical uses

Sodium nitrate waste has been successfully solidified in two types of polymeric materials: polyethylene, a thermoplastic material, and polyester styrene (PES), a thermosetting material. Waste form property evaluation tests such as ANS 16.1 leaching test and compressive strength measurements were performed on the waste forms containing various amounts of sodium nitrate. A single-screw extruder was employed for incorporating dry waste into polyethylene at its melt temperature of 120/sup 0/C to produce a homogenous mixture. Results of the leaching test for polyethylene waste forms containing 30, 50, 60 and 70 wt% sodium nitrate are presented as cumulative fraction leached and leaching indices ranging from 11 to 7.8. Two PES systems are discussed. The first is for solidification of dry salt wastes and the second is a water extendible system that is compatible with ...

1986-01-01

236

Recycling of plastic waste in blast furnace; Koro ni okeru hai plastic riyo gijutsu

recycling of waste polypropylene (WPP) and waste rubber (WR) originated from rejected worn-out tires present very important problem due to their huge amount and their negative impact on environment. many communities in the world are struggling with this problem of how to manage waste disposal, in order to eliminate or reduce waste rubber from the environment and to reduce costs of some rubber and polypropylene articles. trials to reuse waste rubber and waste polypropylene, have encountered some difficulties.such two substrate polymers differ from each other in nature, since waste polypropylene is thermoplastic while waste rubber exists in thermosetting state. accordingly, the study and use of their mixtures should be very interesting.the aim of this work is to modify the physical and chemical properties of WR and WPP ...

2007-01-01

237

Process development for remote-handled mixed-waste treatment

Features particular to the technology of using a blast furnace for the recycling of plastic waste are reported, and the behavior of plastic waste injected into a blast furnace is described. The plastic waste is injected into the furnace borne on a 1200degC hot blast through the tuyere. The plastic is converted into a reducing gas in the furnace, and the gas on its way up in the furnace is utilized as a reducing agent in the iron ore reducing reaction. The process is described below. All kinds of plastic waste may be utilized in this fashion, with the exception of polyvinyl chloride. As for polyvinyl chloride, efforts are under way to develop a technology to recycle this plastic. The method using the blast furnace tolerates a wide range of impurities, and the plastic waste is only to be crushed and granulated before use in the furnace. Plastic waste coarsely ...

1998-05-20

238

Nuclear waste form risk assessment for US defense waste at Savannah River Plant. Annual report fiscal year 1980

The Oak Ridge National Laboratory (ORNL) is developing a treatment process for remote-handled (RH) liquid transuranic mixed waste governed by the concept of minimizing the volume of waste requiring disposal. This task is to be accomplished by decontaminating the bulk components so the process effluent can be disposed with less risk and expense. Practical processes have been demonstrated on the laboratory scale for removing cesium 137 and strontium 90 isotopes from the waste, generating a concentrated waste volume, and rendering the bulk of the waste nearly radiation free for downstream processing. The process is projected to give decontamination factors of 10{sup 4} for cesium and 10{sup 3} for strontium. Because of the extent of decontamination, downstream processing will be contact handled. The transuranic, radioactive fraction of the mixed waste stream will ...

1990-01-01

239

Liquid waste evaporator operating experience

Waste form dissolution studies and preliminary performance analyses were carried out to contribute a part of the data needed for the selection of a waste form for the disposal of Savannah River Plant defense waste in a deep geologic repository. The first portion of this work provides descriptions of the chemical interactions between the waste form and the geologic environment. We reviewed critically the dissolution/leaching data for borosilicate glass and SYNROC. Both chemical kinetic and thermodynamic models were developed to describe the dissolution process of these candidate waste forms so as to establish a fundamental basis for interpretation of experimental data and to provide directions for future experiments. The complementary second portion of this work is an assessment of the impacts of alternate waste forms upon the consequences of disposal in various ...

1981-07-01

240

Liquid waste evaporator operating experience

Atomic Energy of Canada Limited (AECL) operates the Waste Treatment Centre (WTC) to treat and immobilize some of the low- level radioactive waste (LLRW) streams at the Chalk River Laboratories (CRL). The WTC at treats low- level radioactive liquid waste by removing the contaminants from the wastewater, concentrating them, and immobilizing them. The fundamental design concept for the WTC is to process the waste streams using forced circulation type liquid waste evaporation (LWE), to solidify the concentrates using thin film evaporator and to discharge the purified effluent into the Ottawa River following verification monitoring. The solidified product drums are stored in existing storage facilities in the CRL. The LWE was installed in the WTC to treat the LLRW. After about four (4) years of design, construction and cold commissioning, the active commissioning of the evaporator ...

2006-07-01

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241

Costs for off-site disposal of nonhazardous oil field wastes: Salt caverns versus other disposal methods

Atomic Energy of Canada Limited (AECL) operates the Waste Treatment Centre (WTC) to treat and immobilize some of the low- level radioactive waste (LLRW) streams at the Chalk River Laboratories (CRL). The WTC at treats low- level radioactive liquid waste by removing the contaminants from the wastewater, concentrating them, and immobilizing them. The fundamental design concept for the WTC is to process the waste streams using forced circulation type liquid waste evaporation (LWE), to solidify the concentrates using thin film evaporator and to discharge the purified effluent into the Ottawa River following verification monitoring. The solidified product drums are stored in existing storage facilities in the CRL. The LWE was installed in the WTC to treat the LLRW. After about four (4) years of design, construction and cold commissioning, the active commissioning of the evaporator ...

2005-05-08

242

Basic design of alpha aqueous waste treatment process in NUCEF

According to an American Petroleum Institute production waste survey reported on by P.G. Wakim in 1987 and 1988, the exploration and production segment of the US oil and gas industry generated more than 360 million barrels (bbl) of drilling wastes, more than 20 billion bbl of produced water, and nearly 12 million bbl of associated wastes in 1985. Current exploration and production activities are believed to be generating comparable quantities of these oil field wastes. Wakim estimates that 28% of drilling wastes, less than 2% of produced water, and 52% of associated wastes are disposed of in off-site commercial facilities. In recent years, interest in disposing of oil field wastes in solution-mined salt caverns has been growing. This report provides information on the availability of commercial disposal companies in oil-and gas-producing ...

1997-09-01

243

RH-TRU Waste Inventory Characterization by AK and Proposed WIPP RH-TRU Waste Characterization Objectives

This paper described the basic design of Alpha Aqueous Waste Treatment Process in NUCEF. Since various experiments using the TRU (transuranium) elements are carried out in NUCEF, wastes containing TRU elements arise. The liquid wastes in NUCEF are categorized into three types. Decontamination and volume reduction of the liquid waste mainly of recovery water from acid recovery process which has lowest radioactive concentration is the most important task, because the arising rate of the waste is large. The major function of the Alpha Aqueous Waste Treatment Process is to decontaminate the radioactive concentration below the level which is allowed to discharge into sea. Prior the process design of this facility, the followings are evaluated:property and arising rate of the liquid waste, room space to install and licensing condition. Considering ...

1996-11-01

244

Synthesis of nanocrystalline YSZ (ZrO_2-8Y_2O_3) powder by polymerized complex method

The U.S. Department of Energy (DOE)-Carlsbad Field Office (CBFO) has developed draft documentation to present the proposed Waste Isolation Pilot Plant (WIPP) remote-handled (RH-) transuranic (TRU) waste characterization program to its regulators, the U.S. Environmental Protection Agency and the New Mexico Environment Department. Compliance with Title 40, Code of Federal Regulations, Parts 191 and 194; the WIPP Land Withdrawal Act (PL 102-579); and the WIPP Hazardous Waste Facility Permit, as well as the Certificates of Compliance for the 72-B and 10-160B Casks, requires that specific waste parameter limits be imposed on DOE sites disposing of TRU waste at WIPP. The DOE-CBFO must control the sites' compliance with the limits by specifying allowable characterization methods. As with the established WIPP contact handled TRU waste characterization program, ...

2002-02-26

245

Synthesis of ?-Al2O3 nanowires through a boehmite precursor route

In this study nanocrystalline powders of yttria-stabilized zirconia (ZrO_2-8Y_2O_3) have been synthesized through 'polymerized complex method'. Zirconium chloride, yttrium nitrate, citric acid and ethylene glycol were polymerized at 80 "oC to produce a gel-like mass in which metallic ions were uniformly distributed. During the thermal treatment of dried gel, nanocrystalline powder was formed at 450 "oC and 650 "oC for 2 h. Thermal reactions and crystalline phase formation of the dried gel were investigated through thermal analysis and X-ray diffraction analysis, respectively. The results of thermal analysis and XRD showed the formation of nanocrystalline powder at less than 600 "oC. Chemical bonding of the dried gel was investigated by Fourier transform infrared spectroscopy analysis. Morphology of powder calcined at 650 "oC was analyzed by scanning electron microscope. Yttria-stabilized zirconia powders with the mean crystallite size of 6 nm were prepared ...

2010-02-18

246

British Library Electronic Table of Contents (United Kingdom)

Crystalline ?-Al2O3 nanowires with diameter, 20?40?nm, length above 600?nm and aspect ratio above 30 have been successfully synthesized by thermal decomposition of boehmite (?-AlOOH) precursors obtained via hydrothermal route by using AlCl3, NaOH and NH3 as starting materials. Thermogravimetric analysis (TG), differential thermal analysis (DTA), X-ray diffraction (XRD), transmission electron microscope (TEM), selected area electron diffraction (SAED) and high resolution transmission electron microscope (HRTEM) were used to characterize the features of the as-made ?-Al2O3 nanowires and their ?-AlOOH precursors. The pH value of the solution and the mixed precipitant play important roles in the formation of ?-AlOOH nanowires. After calcination at 500?C for 2?h, the orthorhombic ?-AlOOH transf...

2011-01-01

247

Synthesis and electrochemical performance of carbon nanofiber-cobalt oxide composites

Synthesis and electrochemical performance of carbon nanofiber-cobalt oxide composites

Carbon nanofiber (CNF) supported cobalt oxide composites as high-capacity anode materials were prepared through a facile, effective method for potential use in rechargeable lithium-ion batteries. The effects of the calcining temperature on the crystallinity, grain size, specific surface area of Co{sub 3}O{sub 4} and phase transformation from Co{sub 3}O{sub 4} to CoO were studied in detail. Both the specific surface area and CNF content in CNF-cobalt oxide composites strongly affect the electrochemical performance of these series composites. The CNF-Co{sub 3}O{sub 4} composite with 24.3% CNF pyrolyzed at 500 deg. C in Ar shows an excellent cycling performance, retaining a specific capacity of 881 mAh g{sup -1} beyond 100 cycles. Homogeneous deposition and distribution of nanosized Co{sub 3}O{sub 4} particles on the surface of CNF can stabilize the electronic and ionic conductivity as well as the morphology of Co{sub 3}O{sub 4} phase, which may be the main reason for ...

2008-10-15

248

Structural and morphology studies of praseodymium-doped bismuth titanate prepared using a wet chemical route

Carbon nanofiber (CNF) supported cobalt oxide composites as high-capacity anode materials were prepared through a facile, effective method for potential use in rechargeable lithium-ion batteries. The effects of the calcining temperature on the crystallinity, grain size, specific surface area of Co{sub 3}O{sub 4} and phase transformation from Co{sub 3}O{sub 4} to CoO were studied in detail. Both the specific surface area and CNF content in CNF-cobalt oxide composites strongly affect the electrochemical performance of these series composites. The CNF-Co{sub 3}O{sub 4} composite with 24.3% CNF pyrolyzed at 500{sup o}C in Ar shows an excellent cycling performance, retaining a specific capacity of 881 mAh g{sup -1} beyond 100 cycles. Homogeneous deposition and distribution of nanosized Co{sub 3}O{sub 4} particles on the surface of CNF can stabilize the electronic and ionic conductivity as well as the morphology of Co{sub 3}O{sub 4} phase, which may be the main reason ...

2008-10-15

249

Structural and morphology studies of praseodymium-doped bismuth titanate prepared using a wet chemical route

Praseodymium-doped Bi{sub 4}Ti{sub 3}O{sub 12} (BIT) with various compositions of dopant, Pr (x = 0.5, 0.6, 0.7, 0.8) in Bi{sub 4-x}Pr{sub x}Ti{sub 3}O{sub 12} (BPT) were synthesized using a low temperature wet chemical technique. Powders calcined at 800 deg. C exhibit a single phase polycrystalline perovskite bismuth-layered structure. Randomly oriented plate-like structures were observed under Scanning Electron Microscope (SEM). A small amount of Pr doping (x = 0.5) resulted in dramatically reduced of grain size from 2 {mu}m to less than 50 nm in which Pr plays the role as a grain growth inhibitor. However, by increasing the composition of Pr, bigger grain size of up to 1 {mu}m was observed for x = 0.8 that was caused by diffusion of Pr in the perovskite structure. Dielectric properties showed that dielectric permittivity decreased with the addition of x = 0.50, and increasing with further addition of Pr. Dissipation factor (tan {delta}) followed the same trend ...

2009-05-05

250

Structural and morphology studies of praseodymium-doped bismuth titanate prepared using a wet chemical route

Praseodymium-doped Bi_4Ti_3O_1_2 (BIT) with various compositions of dopant, Pr (x = 0.5, 0.6, 0.7, 0.8) in Bi_4_-_xPr_xTi_3O_1_2 (BPT) were synthesized using a low temperature wet chemical technique. Powders calcined at 800 deg. C exhibit a single phase polycrystalline perovskite bismuth-layered structure. Randomly oriented plate-like structures were observed under Scanning Electron Microscope (SEM). A small amount of Pr doping (x = 0.5) resulted in dramatically reduced of grain size from 2 #mu#m to less than 50 nm in which Pr plays the role as a grain growth inhibitor. However, by increasing the composition of Pr, bigger grain size of up to 1 #mu#m was observed for x = 0.8 that was caused by diffusion of Pr in the perovskite structure. Dielectric properties showed that dielectric permittivity decreased with the addition of x = 0.50, and increasing with further addition of Pr. Dissipation factor (tan #delta#) followed the same trend as dielectric constant that was ...

2009-05-05

251

British Library Electronic Table of Contents (United Kingdom)

Praseodymium-doped Bi4Ti3O12 (BIT) with various compositions of dopant, Pr (x=0.5, 0.6, 0.7, 0.8) in Bi4-xPrxTi3O12 (BPT) were synthesized using a low temperature wet chemical technique. Powders calcined at 800degreeC exhibit a single phase polycrystalline perovskite bismuth-layered structure. Randomly oriented plate-like structures were observed under Scanning Electron Microscope (SEM). A small amount of Pr doping (x=0.5) resulted in dramatically reduced of grain size from 2mm to less than 50nm in which Pr plays the role as a grain growth inhibitor. However, by increasing the composition of Pr, bigger grain size of up to 1mm was observed for x=0.8 that was caused by diffusion of Pr in the perovskite structure. Dielectric properties showed that dielectric permittivity decreased with the ad...

2009-01-01

252

Stearic acid gel derived MgTiO{sub 3} nanoparticles: A low temperature intermediate phase of Mg{sub 2}TiO{sub 4}

Silylated Co/SBA-15 catalysts for Fischer-Tropsch synthesis

Stearic acid gel is employed to study the phase evolution of MgTiO{sub 3} nanoparticles by thermal gravimetric analysis, X-ray diffraction, and Fourier transform infrared. During the preparation of stearic acid gel, tetrabutyl titanate easily absorbed moisture to hydrolyze into Ti(OH){sub 4} firstly, and then reacts with stearic acid and magnesium stearate to form magnesium-titanium oxide network polymer gel, meanwhile n-butanol is generated. When stearic acid gel is calcined in air, a series of oxidation and combustion reactions occur, meanwhile apparent heat is given off. The results show that a metastable intermediate phase Mg{sub 2}TiO{sub 4} is generated at 450 {sup o}C and nearly disappeared at 550 {sup o}C. Simultaneously, a new solid phase of MgTiO{sub 3} appears. The metastable intermediate phase Mg{sub 2}TiO{sub 4} is successfully identified in the current work.

2010-03-04

253

Novel alloys to improve the electrochemical behavior of zinc anodes for zinc/air battery

A series of silylated Co/SBA-15 catalysts were prepared via the reaction of surface Si-OH of SBA-15 with hexamethyldisilazane (HMDS) under anhydrous, vapor-phase conditions, and then characterized by FT-IR, N2 physisorption, TG, XRD, and TPR-MS. The results showed that organic modification led to a silylated SBA-15 surface composed of stable hydrophobic Si-(CH3)3 species even after calcinations and H2 reduction at 673 K. Furthermore, the hydrophobic surface strongly influenced both metal dispersion and reducibility. Compared with non-silylated Co/SBA, Co/S-SBA (impregnation after silylation) showed a high activity, due to the better cobalt reducibility on the hydrophobic support. However, S-Co/SBA (silylation after impregnation) had the lowest FT activity among all the catalysts, due to the lower cobalt reducibility along with the steric hindrance of grafted -Si(CH3)3 for the re-adsorption of ?-olefins. -- Graphical abstract: The silylation of an SBA-15 before ...

2011-03-01

254

Neutron shielding and constructional characteristics of a new type concrete and from borated clinker

In our continued efforts for improving the performance of zinc anodes for a Zn/air battery, we now report the preparation of three alloys and improved performances of anodes made up with these alloys. The alloys contained zinc, nickel, and indium with different weight percentages and were calcined at two different temperatures. Out of the six alloys, the alloy which has a composition of zinc 90%, nickel 7.5% and Indium 2.5% and fired at 500{sup o}C is found to be the best. In the case of the hydrogen evolution reaction, this alloy had its potential shifted to a more negative potential. As far as the cyclic voltammograms were concerned, the difference between the anodic and cathodic part was minimal when compared with other alloys. Surprisingly, this alloy had reversibility even after 100 cycles of the cyclic voltammogram. This is a clear indication that dendrite formation was reduced to a considerable extent. Images taken with a scanning electron microscope also ...

2006-10-06

255

High pressure thermogravimetric analysis of the direct sulfation of Spanish calcium-based sorbents

A boron containing cement, which can be used as nuclear shielding material, is produced at pilot plant scale applying two different methods. In the first method, the raw mixture of a normal portland cement is mixed with pre-calcined colemanite, a calcium borate mineral, and clinkerized in a rotary kiln (borated-clinker). In the second method, the colemanite is mixed with an admixture, which contains mainly limestone and marl, and burnt in the rotary kiln to obtain a borated-lime composite. The borated-lime composite is then added to the normal portland cement clinker up to 2% B_2O_3 content for shielding purpose. The results have shown that the borated-clinker contained untolerable amount of free lime resulting in a decrease in compressive strength. The addition of the borated-lime composite to the normal portland cement clinker up to 1% B_2O_3 content did not alter the setting time and the volume expansion properties. The reduction in the compressive strength was ...

1994-11-07

256

Electrospun porous SnO{sub 2} nanotubes as high capacity anode materials for lithium ion batteries

Under typical conditions found in Pressurized Fluidized Bed Combustion (PFBC), the calcination reaction of limestones is thermodynamically inhibited, and the sorbent reacts with SO{sub 2} by a direct mechanism. Direct sulfation reactivity of different Spanish sorbents was studied by high-pressure thermogravimetric analysis. It was found that the physical structure of the surface of the particles influence the sulfation behaviour of the sorbents. Total pore volume and pore surface area correlated well with the reactivity of the sorbents. Temperatures between 800 and 925{degree}C, and pressure between 12 and 25 bar, promoted an increase in reactivity, while the gas composition had no effect when changed from 15% CO{sub 2}, 3% O{sub 2}, 0.5% SO{sub 2}, balance N{sub 2} to 12% CO{sub 2}, 7% O{sub 2}, 0.5% SO{sub 2}, balance N{sub 2}. It was found that the unreacted shrinking core model could not satisfactorily describe the sulfation reaction under the conditions ...

1999-02-01

257

Development of heavy oil hydrocracking catalysts using amorphous silica-alumina and zeolites as catalyst supports

Porous SnO{sub 2} nanotubes were prepared via electrospinning followed by calcination in air. As anode materials for lithium ion batteries, the porous nanotubes delivered a high discharge capacity of 807 mAh g{sup -1} after 50 cycles. Even after cycled at high rates, the electrode still retained a high fraction of its theoretical capacity. Such excellent performances of porous SnO{sub 2} nanotubes could be attributed to the porous and hollow structure which facilitated liquid electrolyte diffusion into the bulk materials and buffered large volume changes during lithium ions insertion/extraction. Furthermore, the nanoparticles of nanotubes provided the shorter diffusion length for lithium ions insertion which benefited in retaining the structural stability and good rate performance. Our results demonstrated that this simple method could be extended for the synthesis of porous metal oxide nanotubes with high performances in the applications of lithium ion batteries ...

2010-10-15

258

Composites in the TiC-TiYTZP system

The overall objective of this research work was to prepare hydrocracking catalysts using amorphous silica-alumina (ASA) supports in combination with USY and {beta}-zeolites. Three supports: namely silica-alumina, USY and {beta}-zeolites were selected to prepare the extrudates using AP-1 as a binder, while two metal pairs: namely Ni-W and Ni-Mo were loaded on the extrudates through co-impregnation using incipient wetness technique. The catalysts were then calcined at 550C for 2h. The catalysts were tested in a fixed-bed flow reaction system for their activity, using desulfurized vacuum gas oil (DS-VGO) as a feedstock. The catalytic evaluation results of the catalysts showed that {beta}-zeolite alone and in combination with the ASA used in this study, has a potential as a support for developing heavy oil hydrocracking catalysts. A balance of weak and strong acidities of {beta}-zeolite provides control cracking, while high surface area and bigger pores of ...

2002-07-10

259

Combustion for high temperature heating process

Ceramic matrix composites in the TiC-Ti, Y-TZP system can be synthesized by the reaction between carbon and the TiO_2-Y_2O_3-ZrO_2 solid solution nanopowder. This method results in the more homogeneous powders than those prepared by the physical mixing of TiC and zirconia s.s. powders. Twelve TiO_2-Y_2O_3-ZrO_2 solid solution nanopowders differing in the proportions of the constituent oxides were prepared by the coprecipitation- calcination route. They were reacted with the pyrolytic carbon evenly distributed within the system. Carbon was introduced by the thermal decomposition of the phenol-formaldehyde resin dissolved in ethyl alcohol and mixed with the zirconia s.s. nanopowder. Reaction was performed in vacuum. Compacts of the composite powders sintered in vacuum give dense materials of evenly distributed TiC inclusions of sizes not surpassing 400 nm. Hardness of such materials was dependent on their chemical and phase composition but was generally higher than ...

2003-09-25

260

Characterization of nanosized Tb-MCM-41 synthesized by the sol-gel-assisted self-assembly method

This paper describes the high-temperature (1500/sup 0/C or higher) heating technology by combusting natural gas. The theoretical adiabatic flame temperature is 1957/sup 0/C at the theoretical air ratio and 2801/sup 0/C at the theoretical oxygen ratio. The flame temperature is increased by 40/sup 0/C every 1%-increase of oxygen up to 25% of the concentration of oxygen and by 28/sup 0/C to 30% of it. The flame temperature is increased by 37 to 38/sup 0/C every 100/sup 0/C-increase of the temperature of preheated air. The practical temperatures are significantly lower than the theoretical ones. The ceramic calciner is provided with a two-stage burner for 1600 to 1800/sup 0/C which can use also the oxygen-riched air. The glass melting furnace is operated at 1500/sup 0/C and the flat flame burner is used for a single kiln. A stabilizing burner is used for reducing the multing time for the steel making electric arc furnace. A high-temperature (1700/sup 0/C) radiant ...

1987-12-05

1 2 3 4 5 6 7 8 9 10 11 12 13 14 15 16 17 18 19 20 21 22 23 24 25

261

A facile one-pot hydrothermal method to prepare europium-doped titania hollow phosphors and their sensitized luminescence properties

The nanosized luminescent Tb-MCM-41 (1:10) is synthesized by means of sol-gel-assisted self-assembly under basic conditions at room temperature. The results of "2"9Si-MAS NMR and XRD prove that Tb"3"+ doped Si-O framework. The HRTEM image shows that the regular uniform particles with a diameter of 10 nm possess ultralarge pore with diameter 2.0 nm, which is consistent with the result of N_2 adsorption. The BET surface area and porosity of Tb-MCM-41 (1:10) are 1127 m"2/g and 0.84 cm"3/g, respectively. The patterns of selected-area electron diffraction and XRD of Tb-MCM-41 (1:10) show an Fm3m space group in the cubic. FT-IR results show that the peaks near 970 cm"-"1 are assigned to the deformation vibration of silanol group. The as-products are calcined at 800 deg. C and the mesoporous materials possess enormous specific areas and large porosity, it shows that the mesoporous materials are ultrastable.

2003-10-06

262

British Library Electronic Table of Contents (United Kingdom)

Monodisperse europium-activated titania hollow phosphors had been synthesized by a facile one-pot hydrothermal method using carbon spheres as hard templates. Samples were characterized by X-ray powder diffraction, transmission electron microscopy, X-ray photoelectron spectroscopy, energy dispersive spectrometer and photoluminescence spectrum. The strongest emission intensity was observed with TiO2:Eu0.2 hollow spheres and TiO2:Eu0.2 hollow spheres calcining at 550^oC. Moreover, the strongest excitation of TiO2:Eu0.2 hollow spheres transferred from 400 to 500^oC and the effective nonradiative energy transfer from the TiO2 hollow spheres host matrix to Eu^3^+ ions crystal field states was realized due to changes of crystalline field in the environment around Eu^3^+ ions occupying Ti^4^+ site...

2010-01-01

263

Waste disposal and treatment in the food processing industry. (Latest citations from the Biobusiness database). Published Search

Summary of non-US national and international radioactive waste management programs 1981

The bibliography contains citations concerning waste treatment and disposal in the food processing industry. Methods, equipment, and technology are considered. References discuss waste heat recovery and examine treatment of wastes resulting from meat and seafood processing, dairy and beverage production, and fruit and vegetable processing. The citations explore conversion of the treated waste to fertilizer and for use in animal feeds, combustion for energy production, biogas production, and composting. The recovery and recycling of usable chemicals from the food waste are also covered. Food packaging recycling is considered in a related bibliography. (Contains 250 citations and includes a subject term index and title list.)

1995-01-01

264

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

Many nations and international agencies are working to develop improved technology and industrial capability for neuclear fuel cycle and waste management operations. The effort in some countries is limited to research in university laboratories on treating low-level waste from reactor plant operations. In other countries, national nuclear research institutes are engaged in major programs in all phases of the fuel cycle and waste management, and there is a national effort to commercialize fuel cycle operations. Since late 1976, staff members of Pacific Northwest Laboratory have been working under US Department of Energy sponsorship to assemble and consolidate openly available information on foreign and international nuclear waste management programs and technology. This report summarizes the information collected on the status of fuel cycle and waste management programs in selected ...

1981-06-01

265

Status and progress in sludge washing: A pivotal pretreatment method

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.

1988-01-01

266

State of the art report on bituminized waste forms of radioactive wastes

Separation of the bulk soluble chemical salts from the insoluble metal hydroxides and radionuclides is central to the strategy of disposing Hanford tank waste. Sludge washing and caustic leaching have been selected as the primary methods for processing the 230 million L (61,000,000 gal) of Hanford tank waste. These processes are very similar to those selected for processing waste at the West Valley Site in New York and the Savannah River Site in South Carolina. The purpose of sludge washing is to dissolve and remove the soluble salts in the waste. Leaching of the insoluble solids with caustic will be used to dissolve aluminum hydroxide and chromium hydroxide, and convert insoluble bismuth phosphate to soluble phosphate. The waste will be separated into a high-level solids fraction and a liquid fraction that can be disposed of as low-level waste after cesium ...

1995-01-01

267

Research and development for treatment and disposal technologies of TRU waste

In this report, research and development results on the bituminization of radioactive wastes are closely reviewed, especially those regarding waste treatment technologies, waste solidifying procedures and the characteristics of asphalt and solidified forms. A new concept of the bituminization method is suggested in this report which can improve the characteristics of solidified forms. Stable solid forms with high leach resistance, high thermal resistance and good compression strength were produced by the suggested bituminization method, in which spent polyethylene from agricultural farms was added. This report can help further research and development of improved bituminized forms of radioactive wastes that will maintain long term stabilities in disposal sites. (author). 59 refs., 19 tabs., 18 figs

1997-06-08

268

Radioactive waste management in the USSR: A review of unclassified sources. Volume 2

After the publication of the 2nd progress report of geological disposal of TRU waste in Japan, policy and general scheme of future study for the waste disposal in Japan was published by ANRE and JAEA. This annual report summarized aim and progress of individual problem, which was assigned into JAEA in the published policy and general scheme. The problems are as follows; characteristics of TRU waste and its geologic disposal, treatment and waste production, quality control and inspection methodology for waste, mechanical analysis of near-field, data acquisition and preparation on radionuclides migration, cementitious material transition, bentonite and rock alteration in alkaline solution, nitrate effect, performance assessment of the disposal system and decomposition of nitrate as an alternative technology. (author)

2007-04-22

269

Radioactive waste management in the USSR: A review of unclassified sources

The Soviet Union does not currently have an overall radioactive waste management program or national laws that define objectives, procedures, and standards, although such a law is being developed, according to the Soviets. Occupational health and safety does not appear to receive major attention as it does in Western nations. In addition, construction practices that would be considered marginal in Western facilities show up in Soviet nuclear power and waste management operations. The issues involved with radioactive waste management and environmental restoration are being investigated at several large Soviet institutes; however, there is little apparent interdisciplinary integration between them, or interaction with the USSR Academy of Sciences. It is expected that a consensus on technical solutions will be achieved, but it may be slow in coming, especially for final disposal of high-level radioactive ...

1991-03-01

270

Quality assurance requirements for high-level waste form production

The Soviet Union does not currently have an overall radioactive waste management program or national laws that define objectives, procedures, and standards, although such a law is being developed, according to the Soviets. Occupational health and safety does not appear to receive major attention as it does in Western nations. In addition, construction practices that would be considered marginal in Western facilities show up in Soviet nuclear power and waste management operations. The issues involved with radioactive waste management and environmental restoration are being investigated at several large Soviet institutes; however, there is little apparent interdisciplinary integration between them, or interaction with the USSR Academy of Sciences. It is expected that a consensus on technical solutions will be achieved, but it may be slow in coming, especially for final disposal of high-level radioactive ...

1991-03-01

271

Process for treatment of detergent-containing radioactive liquid wastes

The Department of Energy has issued a Quality Assurance (QA) specification for organizations involved in making a canistered high-level waste form product that is acceptable for storage in a deep geologic federal repository. The logic for the waste form acceptance process is described. In addition to NQA-1 requirements, fourteen supplemental QA requirements have been drafted to fit the waste form production process. A review plan for assuring complicance with the QA specification is provided. Guidelines for preparation of a waste form producer QA program are also presented. It is expected that the QA program description that result will be influential in supporting the acceptybility of the product to OCRWM and for ultimate disposal of the high-level waste in a deep geologic repository. (author) 3 figs., 4 refs.

272

Process for treatment of detergent-containing radioactive liquid wastes

A detergent-containing radioactive liquid waste originating from atomic power plants is concentrated to have about 10 wt. % detergent concentration, then dried in a thin film evaporator, and converted into powder. Powdered activated carbon is added to the radioactive waste in advance to prevent the liquid waste from foaming in the evaporator by the action of surface active agents contained in the detergent. The activated carbon is added in accordance with the COD concentration of the radioactive liquid waste to be treated, and usually at a concentration 2-4 times as large as the COD concentration of the liquid waste to be treated. A powdery product having a moisture content of not more than 15 wt. % is obtained from the evaporator, and pelletized and then packed into drums to be stored for a predetermined period.

1984-02-21

273

Oil-tanker waste-disposal practices: A review

A detergent-containing radioactive liquid waste originating from atomic power plants is concentrated to have about 10 wt. % detergent concentration, then dried in a thin film evaporator, and converted into powder. Powdered activated carbon is added to the radioactive waste in advance to prevent the liquid waste from foaming in the evaporator by the action of surface active agents contained in the detergent. The activated carbon is added in accordance with the COD concentration of the radioactive liquid waste to be treated, and usually at a concentration 2-4 times as large as the COD concentration of the liquid waste to be treated. A powdery product having a moisture content of not more than 15 wt. % is obtained from the evaporator, and pelletized and then packed into drums to be stored for a predetermined period.

1984-02-01

274

Method of reducing volume of radioactive liquid waste

In the spring of 1991, the Environmental Protection Agency, Region 10 (EPA), launched an investigation into tanker waste disposal practices for vessels discharging ballast water at the Alyeska Pipeline Services Company's Ballast Water Treatment (BWT) facility and marine terminal in Valdez, Alaska. It had been alleged that the Exxon Shipping Company was transferring 'toxic wastes originating in California' to Valdez. In response, EPA decided to examine all waste streams generated on board and determine what the fate of these wastes were in addition to investigating the Exxon specific charges. An extensive Information Request was generated and sent to the shipping companies that operate vessels transporting Alaska North Slope Crude. Findings included information on cargo and fuel tank washings, cleaning agents, and engine room waste.

1992-01-01

275

Improvement on Liquid Radioactive Waste Treatment System of Nuclear Power Plant By Applying Ion Exchange Method

Purpose: To enable the solidification of liquid waste containing radioactive substance in a free shape with large volume reduction ratio without a pulverizing step by producing solute in the liquid waste as a slurry in a predetermined organic solvent and forming it into a cake by mechanical exfoliation. Method: Liquid waste containing suitably concentrated radioactive substances is supplied to a centrifugal thin film evaporator together with an organic agent having a higher boiling point than water and a non aqueous solution to evaporate the water content, the solute in the waste is produced as a slurry in the organic solvent, and removed as cake-state solute slightly residued with the organic solvent by the mechanical exfoliation such as centrifugal exfoliation or settling exfoliation from the slurry-state liquid. Accordingly, it can be increased in size as compared with the powder reduced in volume of ...

1981-08-01

276

Hazardous-waste disposal and the clinical laboratory. Final report, May-December 1989

Liquid radioactive waste treatment method of using evaporator was widely used from Kori 1 to Uljin 3 and 4, but a liquid radioactive waste treatment equipment that uses an ion exchange method instead of an evaporator was adopted aiming to minimize amount of radioactive waste and radiation exposure. However, the same equipment was introduced and applied for the first time in Korea and had experienced difficulties in securing credibility for the equipment and handling of liquid radioactive waste with inadequate data about performance and experience in operation and maintenance. In this study, examination, application and effect analysis was performed on the optimization measure for handling liquid radioactive waste of Yonggwang Nuclear Power Unit 5 and 6(YGN 5 and 6) that applies an ion exchange method

2010-10-01

277

Environmental assessment of alternative municipal solid waste management strategies. A Spanish case study

Negligent hazardous waste management has resulted in real threats to public health. The Federal Government has responded to the situation with laws and regulations aimed at the producers of hazardous waste, including clinical laboratories. The Resources Conservation and Recovery Act (RCRA) imposes controls on hazardous waste management through the Code of Federal Regulations (CFR). The Environmental Protection Agency (EPA) and the Department of Transportation (DOT) regulate these activities through 40 CFR and 49 CFR. Most clinical laboratories can operate satellite accumulation points and accumulate, store, transport, and dispose of waste in accordance with EPA and DOT regulations. Regulations pertaining to infectious waste, sure to affect many clinical laboratories, are being developed now by he EPA. The cradle to grave tracking system mandated by the Federal Government can be ...

1990-01-01

278

British Library Electronic Table of Contents (United Kingdom)

The aim of this study is to compare, from an environmental point of view, different alternatives for the management of municipal solid waste generated in the town of Castellon de la Plana (Spain). This town currently produces 207ton of waste per day and the waste management system employed today involves the collection of paper/cardboard, glass and light packaging from materials banks and of rest waste at street-side containers. The proposed alternative scenarios were based on a combination of the following elements: selective collection targets to be accomplished by the year 2015 as specified in the Spanish National Waste Plan (assuming they are reached to an extent of 50% and 100%), different collection models implemented nationally, and diverse treatments of both the separated biodegrad...

2010-01-01

279

E-Waste recycling: new algorithm for hyper spectral identification

Comparative Assessment of long-term waste management options for high-level and/or long-lived radioactive waste in Belgium

Waste electrical and Electronic Equipment (WEEE) constitutes 4% of the municipal waste in Europe, being increased by 16-28% every five years. Nowadays, Europe produces 6,5 million tonnes of WEEE per year and currently 90% goes to landfill. WEEE waste is growing 3 times faster than municipal waste and this figure is expected to be increased up to 12 million tones by 2015. Applying a new technology to separate non-ferrous metal Waste from WEEE is the aim of this paper, by identifying multi-and hyper-spectral materials and inserting them in a recycling plant. This technology will overcome the shortcomings passed by current methods, which are unable to separate valuable materials very similar in colour, size or shape. For this reason, it is necessary to develop new algorithms able to distinguish among these materials and to face the timing requirements. (Author). 22 refs.

2010-01-01

280

''Experiences of waste reduction, planning of the integrated waste management system experimental of ''pay as you throw'' in Veneto/Italy''

The Belgian radioactive waste management agency NIRAS/ONDRAF has undertaken a comparative assessment study on long-term waste management options for the high-level and/or long-lived radioactive waste that should be managed as a result of the use of nuclear energy in Belgium. This study is one of the supportive documents to a Strategic Environmental Assessment (SEA) process initiated end of 2008 and geared towards a decision in principle by the Belgian Government in 2010 on the long-term management of such radioactive waste. NIRAS/ONDRAF, together with Belgian and international research organisations, has developed a reference option for such high-level and long-lived radioactive waste, called Category B and C Waste, consisting of the disposal of such waste in a clay formation [SAFIR-2]. More than 30 years of R and D have been undertaken ...

2009-06-01

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281

Zeolite-supported Ni and Mo catalysts for hydrotreatments. 2. HRTEM observations

In the past years I have been dealing with the following aspects of waste planning: a) waste reduction (regarding particularly home composting); b) transformation and reorganisation of waste collection systems; c) experimental introduction of a new way to pay for waste collection and treatment services, from ''tax'' to ''tariff''. In these years, I have been a consultant for municipalities in the planning of these three points. In the city (Venice) and in the Region I come from (''Veneto'') there are some of the most important Italian experiences about them. (orig).

2000-07-01

282

Review of potential processing techniques for the encapsulation of wastes in thermoplastic polymers

Calcined and sulfided Ni-Mo catalysts supported on ultrastable Y zeolite (USY), NaY zeolite, mordenite, and ZSM-5 were studied by high-resolution electron transmission microscopy (HRTEM) with selected-area electron diffraction (SAED) and energy-dispersive spectroscopy (EDS). Ni and Mo oxide aggregates were rarely observed in the USY-supported Ni-Mo catalyst, indicating that most of Ni and Mo may be incorporated into USY, e.g., supercavities and possibly sodalite cages. However, there were a large number of {alpha}-NiMoO{sub 4} aggregates of different particle sizes in NaY-, mordenite-, and ZSM-5-supported catalysts, and the mordenite-supported catalyst also contained MoO{sub 3} crystals. The {alpha}-NiMoO{sub 4} may be attached to the surface of substrates as individual particles or needle aggregates, it may be disseminated into mordenite particles, or it may even form an isolated sphere (in Ni-Mo/NaY) or a needle (in Ni-Mo/ZSM-5) aggregates. Thus, most of Ni and ...

2000-01-25

283

A survey of monitoring and assay systems for release of metals from radiation controlled areas at LANL.

Thermoplastic encapsulation has been extensively studied at Brookhaven National Laboratory`s (BNL) Environmental and Waste Technology Center (EWTC) as a waste encapsulation technology applicable to a wide range of waste types including radioactive, hazardous and mixed wastes. Encapsulation involves processing thermoplastic and waste materials into a waste form product by heating and mixing both materials into a homogeneous molten mixture. Cooling of the melt results in a solid monolithic waste form in which contaminants have been completely surrounded by a polymer matrix. Heating and mixing requirements for successful waste encapsulation can be met using proven technologies available in various types of commercial equipment. Processing techniques for thermoplastic materials, such as low density polyethylene (LDPE), are ...

1995-08-01

284

Technology for safe treatment of radioisotope organic wastes

At Los Alamos National Laboratory (LANL), a recent effort in waste minimization has focused on scrap metal from radiological controlled areas (RCAs). In particular, scrap metal from RCAs needs to be dispositioned in a reasonable and cost effective manner. Recycling of DOE scrap metals from RCAs is currently under a self-imposed moratorium. Since recycling is not available and reuse is difficult, often metal waste from RCAs, which could otherwise be recycled, is disposed of as low-level waste. Estimates at LANL put the cost of low-level waste disposal at $550 to $4000 per cubic meter, depending on the type of waste and the disposal site. If the waste is mixed, the cost for treatment and disposal can be as high as $50,000 per cubic meter. Disposal of scrap metal as low-level waste uses up valuable space in the low-level ...

2002-01-01

285

THE ANAEROBIC TREATMENT OF WASTES CONTAINING RECALCITRANT AND INHIBITORY COMPOUNDS

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 ...

1999-12-01

286

Environmental Research Database

ObjectivesObjectives Not AvailableDescriptionA collaborative study of the anaerobic treatment of wastes containing recalcitrant and inhibitory compounds using the SERC Anaerobic facility, in particular biomass structure, monitoring and control, catabolism and toxicity, pre-acidification and microbial growth and mesophilic and thermophilic lignocellulose degradation.~%~

1995-01-20

287

Strategic principles workshops: Discussion drafts and workshop notes

Recycling of postconsumer plastic waste via new solid-state shear extrusion pulverization process

The Office of Civilian Radioactive Waste-Management in the Department of Energy (DOE) is responsible for disposing of this nation`s spent fuel and high-level radioactive waste in a manner that protects the health and safety of the public and the quality of the environment. Although embodied in the Federal repository program that began with studies in the late 1950s, this mission was explicitly established by the Nuclear Waste Policy Act of 1982 and reaffirmed by the Nuclear Waste Policy Amendments Act of 1987. To fulfill our mission, we are developing a waste management system consisting of a geologic repository for permanent disposal deep beneath the surface of the earth, a facility for monitored retrievable storage, and a system for transporting the waste. This discussion draft was developed to help involve parties affected by or interested in the ...

1991-09-01

288

Radionuclide X-ray fluorescence analysis of waste water from the production of citric acid

We have demonstrated that the SSSE pulverization process can convert multicomponent plastic waste into a powder with very promising properties. A variety of mixed color plastic chips have been pulverized.

1996-12-31

289

Radionuclide X-ray fluorescence analysis of waste water from the production of citric acid

Radionuclide X-ray fluorescence analysis was used for the determination of iron, calcium, potassium, copper, manganese and zinc in waste water from the production process of citric acid.

1982-02-18

290

Radioactive Waste Disposal for Fission and Fusion Reactors.

Radionuclide X-ray fluorescence analysis was used for the determination of iron, calcium, potassium, copper, manganese and zinc in waste water from the production process of citric acid. (author).

1982-02-01

291

Quality assurance requirements for high-level waste form production

The calculated radioactive waste inventories of the Turkey Point pressurized water fission reactor (PWR) and the Starfire conceptual fusion tokamak are compared as a function of time from initial start-up to 10,000 years after decommissioning. Only materi...

1989-01-01

292

Proceedings of waste stream minimization and utilization innovative concepts: An experimental technology exchange. Volume 2, Industrial liquid waste processing, industrial gaseous waste processing

This paper discusses the quality assurance requirements for high-level canistered waste form products which would be acceptable for disposal in a deep geologic repository. A review plan and guidelines are provided.

1989-04-02

293

Pollution prevention: Avoiding the need to manage wastes

This two-volume proceedings summarize the results of fifteen innovations that were funded through the US Department of Energy`s Innovative Concept Program. The fifteen innovations were presented at the sixth Innovative Concepts Fair, held in Austin, Texas, on April 22--23, 1993. The concepts in this year`s fair address innovations that can substantially reduce or use waste streams. Each paper describes the need for the proposed concept, the concept being proposed, and the concept`s economics and market potential, key experimental results, and future development needs. The papers are divided into two volumes: Volume 1 addresses innovations for industrial solid waste processing and municipal waste reduction/recycling, and Volume 2 addresses industrial liquid waste processing and industrial gaseous waste processing. Individual reports are indexed separately.

1993-04-01

294

Plastic wastes as support fuel. Jaetemuovin kaeyttoe tukipolttoaineena

Today`s industrial processes generate many types of waste products that constitute risks to human health and the surrounding environment. While proper waste management procedures can lower this risk, prevention of the waste`s generation will eliminate the risk. For this reason, the United States has established pollution prevention as a national objective, through the passage of its Pollution Prevention Act of 1990. Pollution prevention involves a wide range of approaches, all with the same objective: to reduce or eliminate the creation of waste at its source in other words, within the process that generates it. This objective, so beneficial to the environment, also coincides with industrial economic interests. Pollution prevention measures and greater process efficiency go hand in hand, and typically result in lower operating costs as well as greatly reduced waste management ...

1993-12-01

295

Overview of hazardous-waste regulation at federal facilities

The association of Finnish Plastics Industry examined the possibilities to utilize energy content of plastic wastes in spring 1990. A bark fuelled boiler plant of forest industry was used as test power plant. The power of the plant was 60 Mw. This report discusses shortly the theory of combustion of plastics. About 130 000-15 000 tons of plastic waste, corresponding to 7 % of the solid municipal waste, is dumped annually in Finland. Utilization of the plastic waste recovered from municipal wastes for energy production is technically viable in present power plants among present energy production. The chipping and mixing of the plastic in the other fuel are the only pretreatment required for the plastic waste. In Finland there are several power plants using suitable fuels for plastic mixture combustion. The portion of the plastic of the total fuel power was 10 %. ...

1991-01-01

296

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

This report is organized in a fashion that is intended to explain the legal duties imposed on officials responsible for hazardous waste at each stage of its existence. Section 2 describes federal hazardous waste laws, explaining the legal meaning of hazardous waste and the protective measures that are required to be taken by its generators, transporters, and storers. In addition, penalties for violation of the standards are summarized, and a special discussion is presented of so-called imminent hazard provisions for handling hazardous waste that immediately threatens public health and safety. Although the focus of Sec. 2 is on RCRA, which is the principal federal law regulating hazardous waste, other federal statutes are discussed as appropriate. Section 3 covers state regulation of hazardous waste. First, Sec. 3 explains the system of state enforcement of the ...

1982-05-01

297

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

The experiments at the incinerator for low-level wastes processing, (containing transuranium radionuclides) are described. Air decontamination factors and detector readings correction factors for efficiency and absorption are indicated.

1983-01-01

298

Monitoring potential neurotoxic effects of hazardous waste disposal

The experiments at the incinerator for low-level wastes processing, (containing transuranium radionuclides) are described. Air decontamination factors and detector readings correction factors for efficiency and absorption are indicated.

299

Mixed waste solidification testing on polymer and cement-based waste forms in support of Hanford`s WRAP 2A facility

This report reviews neurotoxicological principles relevant to situations of hazardous waste disposal. Some of the diagnostic techniques currently used for field assessment of nervous system dysfunction...Full Text Available

1983-02-01

300

Methodology to evaluate the energy associated to the industrial solid wastes: application in a metropolitan region of Campinas, Sao Paulo state, Brazil; Metodologia para avaliacao da energia associada ao residuo solido industrial: aplicacao a regiao metropolitada de Campinas

A testing program has been conducted by the Westinghouse Hanford Company to confirm the baseline waste form selection for use in Waste Receiving and Processing (WRAP) Module 2A. WRAP Module 2A will provide treatment required to properly dispose of containerized contact-handled, mixed low-level waste at the US Department of Energy Hanford Site in south-central Washington State. Solidification/stabilization has been chosen as the appropriate treatment for this waste. This work is intended to test cement-based, thermosetting polymer, and thermoplastic polymer solidification media to substantiate the technology approach for WRAP Module 2A. Screening tests were performed using the major chemical constituent of each waste type to measure the gross compatibility with the immobilization media and to determine formulations for more detailed testing. Surrogate materials representing each of ...

1993-10-01

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301

Methodology for assessing performance of waste management systems

The aim of this work is to the application of a methodology to evaluate the energy associated to the industrial solid wastes in the metropolitan region of Campinas. The methodological route proposed is: the characterization of the research area and the production/management of the industrial solid wastes; the energetic classification and the qualitative/quantitative research of the energy associated to the industrial solid wastes; and, the valuation of the applicability of the energetic utilization mechanisms proposed to the region. This methodology when applied at the Campinas metropolitan region proved to be valid and it resulted in a synthetically presentation of the social and environmental reality of the industrial sector and the destination of the wastes, as well as it indicated the potentialities related to the energetic utilization of the industrial solid waste in the ...

2004-07-01

302

Logistics modeling of future solid waste storage, treatment, and disposal

The purpose of the methodology provided in this report is to select the optimal way to manage particular sets of waste streams from generation to disposal in a safe and cost-effective manner. The methodology described is designed to review the entire waste management system, assess its performance, ensure that the performance objectives are met, compare different LLW management alternatives, and select the optimal alternative. The methodology is based on decision analysis approach, in which costs and risk are considered for various LLW management alternatives, a comparison of costs, risks, and benefits is made, and an optimal system is selected which minimizes costs and risks and maximizes benefits. A ''zoom-lens'' approach is suggested, i.e., one begins by looking at gross features and gradually proceeds to more and more detail. Performance assessment requires certain information about the characteristics of ...

1988-01-01

303

Logistics modeling is a powerful analytical technique for effective planning of waste storage, treatment, and disposal activities. Logistics modeling facilitates analyses of alternate scenarios for future waste flows, facility schedules, and processing or handling capacities. These analyses provide an increased understanding of the specific needs for waste storage, treatment, and disposal while adequate time remains to plan accordingly. They also help to determine the sensitivity of these needs to various system parameters. This paper discusses a logistics modeling system developed by the Pacific Northwest Laboratory (PNL) to aid in solid waste planning for a large industrial complex managing many different types and classifications of waste. The basic needs for such a system are outlined, and the approach adopted in developing the system is described. A key component of this ...

1993-11-01

304

Jane Powell

Installation Restoration Program. Stage 3. McClellan Air Force ...

...The Political Evolution of the Landfill Tax in the UK wm-1996-03 Green Taxes, Waste Management and Political Economy 1995 ^ Top ...on civil engineering Lifecycle assessment - an overlooked opportunity Refereed Journal Articles: Green taxes, waste management and political economy Reports: Environmental cost benefit ...

305

Fiscal year 1987 program plan

... pits, waste oil and solvent storage ponds (used from the 1940s to 1971), surface storage areas, settling ponds, waste water ponds, and unlined ...

1990-03-01

306

FIELD CORROSION TESTS IN REDOX AND PUREX UNDERGROUND WASTE STORAGE TANKS

The Defense TRU Waste Program (DTWP) is the focal point for the Department of Energy in national planning, integration, operation, and technical development for TRU waste management. The scope of this program extends from the point of TRU waste generation through delivery to a permanent repository. The TRU program maintains a close interface with repository development to ensure program compatibility and coordination. The defense TRU program does not directly address commercial activities that generate TRU waste. Instead, it is concerned with providing alternatives to manage existing and future defense TRU wastes. The FY 87 Program Plan is consistent with the Defense TRU Waste Program goals and objectives stated in the Defense Transuranic Waste Program Strategy Document, January 1984. The roles of participants, the responsibilities and ...

1986-12-01

307

Exposure to nitroaromatic explosives and health effects during disposal of military waste

A corrosion-testing program has been initiated in Purex and Redox storage tnnks to obtain corrosion data on carbon steel and three associated materials in neutralized process wastes. (C.W.H.)

1955-06-28

308

Economic Impact Analysis of Proposed Effluent Limitations Guidelines and Standards for the Centralized Waste Treatment Industry.

Aims: To investigate the exposure to dinitrotoluene (DNT) and trinitrotoluene (TNT) and the resulting effects in workers which occur during the disposal of military waste. Methods:...Full Text Available

2003-07-01

309

This report estimates the economic and financial effects of compliance with the proposed effluent limitations guidelines and standards for the Centralized Waste Treatment (CWT) industry. The Environmental Protection Agency (EPA) has measured these impacts...

1995-01-01

310

EXECUTIVE SUMMARY

Development of value-added products from alumina industry mineral wastes using low-temperature-setting phosphate ceramics

disposal through HC, and the effects of kerbside collection (KC) of recyclable materials, by measuring ...waste equivalent to 12 % could be attributed to HC and KC.Comparisons between the residual weight data for ...Control showed that the contributions of HC and KC to the overall reduction in residual waste were

311

Development of engineered structural barriers for nuclear-waste packages

A room-temperature process for stabilizing mineral waste streams has been developed, based on acid-base reaction between MgO and H3PO4 or acid phosphate solution. The resulting waste form sets into a hard ceramic in a few hours. In this way, various alumina industry wastes, such as red mud and treated potliner waste, can be solidified into ceramics which can be used as structural materials in waste management and construction industry. Red mud ceramics made by this process were low-porosity materials ({approx}2 vol%) with a compression strength equal to portland cement concrete (4944 psi). Bonding mechanism appears to be result of reactions of boehmite, goethite, and bayerite with the acid solution, and also encapsulation of red mud particles in Mg phosphate matrix. Possible applications include liners for ponds and thickned tailings disposal, dikes for waste ...

1996-01-01

312

Decontamination factors of ceramic filter in radioactive waste incineration system

The development of structural barriers for nuclear waste packages involves selection of candidate materials, their screening by mechanical and corrosion testing, rigorous accelerated testing, and evaluation and comparison with other package elements. This document presents results from work conducted on titanium and ferrous alloys.

1981-09-01

313

Cost-Effectiveness Analysis of Proposed Effluent Limitations Guidelines and Standards for the Centralized Waste Treatment Industry.

A suspension-firing type radioactive waste incineration system is developed and cold demonstration testing of ceramic filters for the system are carried out. The incineration system, which is useful for a wide variety of waste materials, can serve to simplify the facilities and to reduce the costs for waste disposal. The incineration system can be used for drying-processing of concentrated waste liquids and disposal of flame resistant materials including ion exchange resins and rubber, as well as for ordinary combustible solid materials. An on-line backwash system is adopted to allow the ceramic filters to operate stably for a long period of time. For one-step filtering using the ceramic filter, the decontamination factor is greater than 10"5 for the processing of various wastes. In a practical situation, there exist vapor produced by the spray drier and the cladding in used ion ...

314

Chronic Wasting Disease Prions in Elk Antler Velvet

This analysis, submitted in support of proposed effluent limitations guidelines and standards for the centralized waste treatment (CWT) industry, investigates the cost-effectiveness of 24 regulatory options, representing all possible combinations of nine ...

1995-01-01

315

Chromium stabilization chemistry of paint removal wastes in Portland cement and blast furnace slag

Chronic wasting disease (CWD) is a contagious, fatal prion disease of deer and elk that continues to emerge in new locations. To explore the means by which prions are transmitted with high efficiency...Full Text Available

2009-05-01

316

British waste plans face fierce local opposition

The use of cement based systems for solidification and stabilization of hazardous wastes has been proposed. The stabilization of Cr contaminated paint removal wastes in ordinary Portland cement and in a Portland cement and blast furnace slag matrix was investigated. A loading by volume of 75% waste and 25% cement (or cement + slag) was used. The expression of pore solution was utilized to determine the chemical environment encountered by the waste species in the cement matrix. The highly alkaline conditions of ordinary Portland cement determined the stability of the metal species, with Cr being highly soluble. The replacement of 25% of the Portland cement by blast furnace slag was found to decrease the [OH-] of the pore solution resulting in a decrease of the Cr concentration. For cement wastes forms hydrated for 28 days, the Cr concentration decreased in the expressed pore ...

1995-12-31

317

Benzene Enabling Document for Standards on Benzene Transfer and Waste Operations.

UK Nirex has announced four sites which it wishes to assess for the disposal of low-level and short-lived intermediate-level radioactive wastes. There is local opposition at all four of the potential sites. (U.K.).

1986-05-01

318

Base program on energy-related research. Quarterly report, February 1995--April 1995

On February 27, 1990, standards for Benzene were promulgated for benzene transfer and benzene waste operations. The benzene enabling document summarizes these standards. The basic purpose of the document is to assist the EPA regional enforcement personnel...

1990-01-01

319

This report describes research performed by the Morgantown Energy Technology Center in the following areas: oil and gas; advanced systems describing a coal solid fuel and an eastern shale oil residue waste program; environmental remediation; and waste management technologies.

1995-06-01

320

BOOKMARKS:

AN EVALUATION OF THE DISPOSAL OF FLUE GAS DESULFURIZATION WASTES IN MINES AND THE OCEAN: INITIAL ASSESSMENT

Secretariat of the Basel Convention United Nations Office at Geneva ...such as public utilities, waste disposal sites, large energy dependent facilities including factories, institutions (hospitals, ...it provides immediate identification of PCB wastes, informs company officials of any special handling or disposal techniques

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321

Thermal Conductivity and Pore Characteristics of Low-Temperature Sintered Lightweight Aggregates Mode from Waste Glass and Bottom Ash

The report gives an initial assessment of the feasibility of disposing of flue gas desulfurization wastes in mines and in the ocean. The purpose of the assessment was to evaluate environmental, technical, regulatory, and economic aspects of the use of such disposal sites. Availab...

322

THE POSITIVE IMPACTS OF ARRA (AMERICAN REINVESTMENT AND RECOVERY ACT) FUNDING TO THE WASTE MANAGEMENT PROGRAM ON HANFORD'S PLATEAU REMEDIATION PROJECT

Full Text Available

2010-12-01

323

Standardisation of techniques for evaluation of solidified high level waste product: A status report

No abstract prepared.

2010-02-17

324

Seismic evaluation of underground facilities for a nuclear waste repository

The results of studies on: (1) development of suitable glass compositions for solidification and vitrification of high level radioactive wastes, and (2) the characteristics of these compositions, namely, leaching, mechanical properties, thermal conductivity, viscosity and homogeneity evaluation are reported. Inactive simulated purex waste was used for compositions reported herein. The data generated on leaching and other product characteristics of the selected vitrified waste products was used to evaluate the performance of corresponding experimental units and techniques with respect to their reproducibility and reliability.

1981-01-01

325

Radionuclide Concentrations in Soils and Vegetation at Low-Level Radioactive Waste Disposal Area G During the 1999 Growing Season

(1981). United States Chen, SW Wise, RD Wu, CL Bechtel, Downey, CA 90241

326

No abstract prepared.

2000-11-01

327

PowerPoint Presentation

Optimum Configuration, Filter Media Depth and Wastewater Load of Small-scale Constructed Wetlands for Treating the Hydroponic Waste Solution in Greenhouses

facilities, building hygienic latrines and introducing regular solid waste collection systems . These methods are constantly being developed and

328

MASER"'\\ - NASA Technical Report Server (NTRS)

Full Text Available

2008-09-01

329

Media Training

ScienceCinema

...global warming issues ...people stopping we put a big issue with global warming copenhagen going on at the moment it's a waste of money ...

330

Low-level and transuranic waste transportation, disposal, and facility decommissioning cost sensitivity analysis

cooling system designed to reject waste heat producedwithin the alternatorand. To other equipment operatingat much lower tempera- ...

331

Low-level and transuranic waste transportation, disposal, and facility decommissioning cost sensitivity analysis

The Systems Design Study (SDS) identified technologies available for the remediation of low-level and transuranic waste stored at the Radioactive Waste Management Complex's Subsurface Disposal Area at the Idaho National Engineering Laboratory. The SDS study intentionally omitted the costs of transportation and disposal of the processed waste and the cost of decommissioning the processing facility. This report provides a follow-on analysis of the SDS to explore the basis for life-cycle cost segments of transportation, disposal, and facility decommissioning; to determine the sensitivity of the cost segments; and to quantify the life-cycle costs of the 10 ex situ concepts of the Systems Design Study.

1992-05-01

332

Legal Analysis of the Korea Radioactive Waste Management Act in the aspect of IAEA Principles

The Systems Design Study (SDS) identified technologies available for the remediation of low-level and transuranic waste stored at the Radioactive Waste Management Complex`s Subsurface Disposal Area at the Idaho National Engineering Laboratory. The SDS study intentionally omitted the costs of transportation and disposal of the processed waste and the cost of decommissioning the processing facility. This report provides a follow-on analysis of the SDS to explore the basis for life-cycle cost segments of transportation, disposal, and facility decommissioning; to determine the sensitivity of the cost segments; and to quantify the life-cycle costs of the 10 ex situ concepts of the Systems Design Study.

1992-05-01

333

Iodine decontamination factor for liquid radioactive waste volume reduction system

According to the Principles of Radioactive Waste Management, the IAEA SAFETY SERIES NO-111-F, IAEA declared 9 doctrines. The IAEA advised a country that operates nuclear power plant to adopt the principles. As a member of the IAEA, Korea has also discussed about a unified policy and enacting law for radioactive waste management to follow the doctrines. This study analyzed the recently enacted Korea Radioactive Waste Management Act and verified whether the Act successfully follows the doctrine or not

2009-05-01

334

Industrial hazardous waste in the framework of EU and international legislation

(Jun 1976). United States Tokerud, LD Garcia, R. Aerojet Energy Conversion

1976-06-13

335

British Library Electronic Table of Contents (United Kingdom)

Purpose - The aim of the present study is to present in a systematic way the subject of industrial hazardous waste from the point-of-view of definitions in engineering, science and legislation. This analysis is necessary, as many different approaches and overlapping definitions are used for the classification of waste, leading to different results, a situation that often complicates the collection and interpretation of data on waste. Design/methodology/approach - The study is conducted by bringing together the extended experience of the authors and other experts in the field of environmental legislation and a wide variety of scientific and legislative sources as well as articles and research reports. The focus is the European Union, while several approaches from the international area are ...

2011-01-01

336

Hanford tanks initiative plan

Dynamic stability and vibration monitoring for No. 9 mine, M-1 dump

Abstract: The Hanford Tanks Initiative (HTI) is a five-year project resulting from the technical and financial partnership of the U.S. Department of Energy`s Office of Waste Management (EM-30) and Office of Science and Technology Development (EM-50). The HTI project accelerates activities to gain key technical, cost performance, and regulatory information on two high-level waste tanks. The HTI will provide a basis for design and regulatory decisions affecting the remainder of the Tank Waste Remediation System`s tank waste retrieval Program.

1997-07-01

337

Development of waste plastics utilization system in rotary lime-kiln; Sekkaishoseiro ni okeru purasuchikku nenryoka gijutsu

This study examines the effects of blasting on waste dumps at open pit mining operations. Of specific concern were mining operations at the base of a five hundred foot high waste dump such as the operation at the South Pit of the Smoky-River Coal Ltd. property near Grande Cache, Alberta. An assessment of waste dump stability including factors such as quasi-static deformation behaviour, historical dump deformation behaviours and potential blasting effects was undertaken. It is concluded that safe blasting may be carried out in proximity to waste dumps, but monitoring of dump behaviour is recommended to ensure operational safety. 22 refs., 4 apps.

1988-11-01

338

Deployment Scenarios for Nuclear Waste Management

We developed the technology of using a waste plastic as fuel in the rotary kiln from reducing the fuel cost and recycling resource point of view. It has established based upon the research of a primary combustion characteristics on waste plastics, the research of the combustion mode of the fuel in the rotary kiln by simulation and the actual examination of kiln. The first rotary kiln equipped with the waste plastic injection system has been operating since 1994, and has achieved a good operating result. (author)

1999-03-01

339

Corrosion and failure processes in high-level waste tanks

A major objective of the DOE Advanced Fuel Cycle Initiative, AFCI, is to explore technologies that may reduce the long-term environmental burden of nuclear energy through more efficient disposal of waste materials. In this work, the potential impact of the AFCI technology and its beneficial effects on waste management and its ability to meet waste management objectives are demonstrated. In addition, practical scenarios to improve permanent disposal utilization and/or reduce the temporary spent nuclear fuel (SNF) storage inventory by closing the fuel cycle through transition to fast reactor (FR) converters are also discussed. (authors)

340

Analysis of salt creep for a nuclear waste repository

A large amount of radioactive waste has been stored safely at the Savannah River and Hanford sites over the past 46 years. The aim of this report is to review the experimental corrosion studies at Savannah River and Hanford with the intention of identifying the types and rates of corrosion encountered and indicate how these data contribute to tank failure predictions. The compositions of the High-Level Wastes, mild steels used in the construction of the waste tanks and degradation-modes particularly stress corrosion cracking and pitting are discussed. Current concerns at the Hanford Site are highlighted.

1992-11-01

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341

A Study on the H??S Removal with Utilization of Seashell Waste(II) - The Characteristics of Sulfided Reaction Using Fixed Bed Reactor-

(1981). United States Kadar, I. Li, WT Todeschini, R. Wu, CL Bechtel, Downey,

342

Waste treatment by dialysis. (Latest citations from Pollution abstracts). Published Search

Full Text Available

2003-09-01

343

Waste monitoring system for effluents

The bibliography contains citations concerning the use of dialysis in the treatment of wastewaters. Techniques for the removal of metals, ammonia, waste acids, nitrates, and phosphates are described. Special attention is given to the desalination of liquid wastes. Applications of this technology to the treatment of effluent from the agrochemical, petrochemical, tanning, and electroplating industries are discussed. (Contains 50-250 citations and includes a subject term index and title list.) (Copyright NERAC, Inc. 1995)

1996-02-01

344

Treatment for dismantled radioactive solid waste from the TRIGA Mark-2 and 3

The waste monitoring system in use at Los Alamos National Laboratory`s Plutonium Facility, TA-55, is a computer-based system that proves real-time information on industrial effluents. Remote computers monitor discharge events and data moves from one system to another via a local area network. This report describes the history, system design, summary, instrumentation list, displays, trending screens, and layout of the waste monitoring system.

1995-07-01

345

The feasibility of closing the loop

Radioactive wastes are generally classified into 3 type depending on their physical property: liquid, solid and gaseous type. State-of -the art concerning liquid waste treatment has already been published; KAERI/TR-1315/99. Solid wastes classification package and treatment method will be studied to effectively manage them during the practical decommissioning work. All of the spent fuel produced during the operation of the TRIGA Mark-2 and 3 have been transported to the US last year, 1998, according to the spent fuel management strategy set-up by the US government for the non-proliferation of nuclear energy. Solid wastes are mainly all equipment existing inside of the reactors, activated concrete among the bio-shielded concrete, pipes, pimps, resin filter and it's housings, heat-exchangers, liquid waste storage tanks, to radioactive waste storage ...

1999-06-01

346

Summary of Initial Testing of SuperLig 644 at the TFL Ion Exchange Facility

Current European and the US experiences in waste management are reviewed in the perspective of sustainable development. This publication questions the validity of the current approach taken by the Germany at ``closing the loop`` based on the example of packaging and packaging waste. The product item focus of current German legislation is compared with Danish and US approaches that are based on an integrated policy which covers the whole of waste generation and handling and is not product/item oriented. 1 fig., 2 tabs.

1998-12-01

347

Research at the Savannah River Technology Center aided development of a technical design basis for a Waste Treatment Plant (WTP) to pre-treat and vitrify Hanford tank waste as part of the River Protection Project (RPP). The research addresses safety concerns, process optimization, and waste form compliance. This program will provide technical data to ensure that the process functions as it was designed and minimizes costs.

2001-04-17

348

Rev. 3 (15.01.2003)

Rational energy generation with residual materials from the paper industry. Rationelle Energieerzeugung mit Reststoffen aus der Papierindustrie

such as public utilities, waste disposal sites, large energy dependent facilities including factories, institutions ( ...provides immediate identification of PCB wastes, informs company officials of any special handling or disposal techniques ...provides immediate identification of PCB wastes, informs company officials of any special handling or disposal techniques

349

Proceedings of the tenth annual DOE low-level waste management conference: Session 1: Institutional and regulatory issues

The paper industry needs alternative waste disposal methods rather than dumping sites. The combustion properties of these waste materials make them suitable for thermal disposal. A process has been developed in which the waste materials are burnt on an oscillating bar grate without supplying external energy. Electrical energy and process steam are generated while small amounts of a sintered slag remain behind. (orig.).

1991-05-01

350

Possible global environmental impacts of solid waste practices

This document contains eleven papers on various aspects of low-level radioactive waste regulation. Topics include: EPA environmental standards; international exemption principles; the concept of below regulatory concern; envirocare activities in Utah; mixed waste; FUSRAP and the Superfund; and a review of various incentive programs. Individual papers are processed separately for the data base. (TEM)

1988-12-01

351

Paris 2000 researches and men; Paris 2000 des recherches et des hommes

Pollutants resulting from the management of solid waste have been shown to affect the air, land, oceans, and waterways. In addition, solid wastes have other, more indirect impacts such as reduction in feedstocks of natural resources, because useful materials are disposed of rather than recycled. The objective of this study is to evaluate solid waste management practices that have negative implications on the global environment and develop recommendations for reducing such impacts. Recommendations identifying needed changes are identified that will reduce global impacts of solid waste practices in the future. The scope of this study includes the range of non-hazardous solid wastes produced within our society, including municipal solid waste (MSW) and industrial solid waste (ISW), as well as industry-specific wastes from ...

1994-09-01

352

Municipal solid waste management in Lebanon: the need for an integrated approach

The IWA and ISWA congresses organized in Paris in july showed the latest research developments in the field of water and wastes management. The water sector is more mature than the waste sector but for both a closer association of the public and private is increasing. A summary of the presentations in successively the water and the wastes management is proposed bringing an analysis of the international situation and regulations. (A.L.B.)

2000-07-01

353

Moving Forward with Lessons Learned About Long-term Radioactive Waste Management

Full text.This study focuses on the management of municipal solid waste (MSW) in Lebanon. It addresses the current status of MSW management in Lebanon in terms of collection, transport and disposal, infers the associated impacts of such practices and discusses mitigation measures and finally proposes basic guidelines for a national strategy for solid waste management in the country. The study is based on available previous investigations and on a field survey of 113 villages in four different countries. The study revealed the absence of an effective environmental policy and poor collection and disposal methods throughout the country, except for the Greater Beirut Area (G A), where better solid waste management practices are employed. Although collection of MSW outside GBA was found to be acceptable by local authorities, resources (labor and equipment) were not used efficiently. Furthermore, treatment of collected ...

2000-11-23

354

Infrastructure support for the Waste Management Institute at North Carolina A ampersand T State University. Progress report, September 1994--January 1995

A range of lessons have been identified from previous attempts to implement long term radioactive waste management policy in the UK and internationally. Many of these relate to the way the decision-making process is undertaken and the fact that there needs to be an open, transparent process that enables continuous stakeholder involvement. Nirex believes that using the SEA and EIA frameworks will help to incorporate the lessons learned into the future decision-making process relating to long-term radioactive waste management.

2006-09-15

355

Industrial waste management information for 1990 and record-to-date

The mission of the Waste Management Institute is two-fold: (1) to enhance awareness and understanding of waste problems and their management in our society and, (2) to provide leadership in research, instruction and outreach to improve the quality of life on a global scale and protect the environment.

1993-10-11

356

Federal Facilities Compliance Act, Draft Site Treatment Plan: Compliance Plan Volume. Part 2, Volume 2

This product provides detailed data and graphics on airborne and liquid effluent releases, fuel oil consumption, and water usage for the calendar year 1990. It summarizes industrial waste data records compiled since 1971 for the Idaho National Engineering Laboratory (INEL). The data presented are from the INEL Industrial Waste Management Information System (IWMIS).

1991-08-01

357

Environmental Sciences Division annual progress report for period ending September 30, 1981

This document presents the details of the implementation of the Site Treatment Plan developed by Ames Laboratory in compliance with the Federal Facilities Compliance Act. Topics discussed in this document include: implementation of the plan; milestones; annual updates to the plan; inclusion of new waste streams; modifications of the plan; funding considerations; low-level mixed waste treatment plan and schedules; and TRU mixed waste streams.

1994-08-31

358

EUROPA-Site on LCA Tools, Services and Data -

Research programs from the following sections and programs are summarized: aquatic ecology, environmental resources, earth sciences, terrestrial ecology, advanced fossil energy program, toxic substances program, environmental impacts program, biomass, low-level waste research and development program, US DOE low-level waste management program, and waste isolation program.

1982-04-01

359

An online monitoring system for nuclear waste storage

...htm Waste Framework Directive 75/442/EEC (amended by Directive 91/156/EEC) and Waste Management Planning http://ec.europa.eu/environment/waste/plans/index.htm Selected EC commissioned/supported projects including LCA IPP Pilot Product exercise on mobile phones and on tropical garden furniture http://ec.europa.eu/environment/ipp/pilot.htm \\

360

A comparison and study for the processing ability of liquid radioactive waste using ion-exchange demineralizer and evaporator

We propose a system for the on-line monitoring of short and medium term radioactive waste repositories. Such a system is distributed, fine-grained, robust, reliable, and must be based on low-cost components. It could, in principle, open new perspectives on the modality of waste packaging and storage. In particular we propose to employ a new family of cheap and powerful micro sensors to be placed in shape of a fine grid around each single drum. (authors)

2009-06-07

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361

2007 SB14 Source Reduction Plan/Report

Most of the low-level liquid radioactive wastes generated from PWR plants are classified into high or low total suspended solid(HTDS or LTDS), radio-chemical waste and radioactive laundry waste. Although the evaporation process has a high decontamination ability, it has several problems such as corrosion, foaming, and congestion. A new liquid waste disposal process using the ion-exchange demineralizer(IED) has been introduced into the Yonggwang NPP 5 and 6 to complement the current evaporation process. To determine the differences, these two methods have been compared in this study. Those aspects compared here were the released radioactivity volume of the liquid radioactive wastes, The dose of off-site residents, the decontamination factor, and the amount of the solid radioactive wastes. While it was expected that the liquid radioactive ...

2003-11-05

362

Waste form development. [Hydraulic cements, hydraulic cements with additives, polymer modified gypsum cement, thermosetting polymers

Aqueous solutions (mixed waste) generated from various LLNL operations, such as debris washing, sample preparation and analysis, and equipment maintenance and cleanout, were combined for storage in the B695 tank farm. Prior to combination the individual waste streams had different codes depending on the particular generating process and waste characteristics. The largest streams were CWC 132, 791, 134, 792. Several smaller waste streams were also included. This combined waste stream was treated at LLNL's waste treatment facility using a vacuum filtration and cool vapor evaporation process in preparation for discharge to sanitary sewer. Prior to discharge, the treated waste stream was sampled and the results were reviewed by LLNL's water monitoring specialists. The treated solution was discharged following confirmation that ...

2007-07-24

363

In this program, contemporary solidification agents are being investigated relative to their applications to major fuel cycle and non-fuel cycle low-level waste (LLW) streams. Work is being conducted to determine the range of conditions under which these solidification agents can be applied to specific LLW streams. These studies are directed primarily towards defining operating parameters for both improved solidification of problem wastes and solidification of new LLW streams generated from advanced volume reduction technologies. Work is being conducted to measure relevant waste form properties. These data will be compiled and evaluated to demonstrate compliance with waste form performance and shallow land burial acceptance criteria and transportation requirements (both as they exist and as they are modified with time). 6 tables.

1982-01-01

364

Waste form development

Use plan for demonstration radioactive-waste incinerator

In this program, contemporary solidification agents are being investigated relative to their applications to major fuel cycle and non-fuel cycle low-level waste (LLW) streams. Work is being conducted to determine the range of conditions under which these solidification agents can be applied to specific LLW streams. These studies are directed primarily towards defining operating parameters for both improved solidification of problem wastes and solidification of new LLW streams generated from advanced volume reduction technologies. Work is being conducted to measure relevant waste form properties. These data will be compiled and evaluated to demonstrate compliance with waste form performance and shallow land burial acceptance criteria and transportation requirements (both as they exist and as they are modified with time). 6 tables.

1986-09-22

365

Treatment feasibility of the radioactive liquid waste originated from MOX fuel characterization

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

1982-04-01

366

Transuranic waste form characterization and data base. Executive summary

Different types of radioactive liquid waste are being generated at Advanced Fuel Fabrication Facility (AFFF), Tarapur during the quality control analysis of the mixed oxide (MOX) fuel pellets. A laboratory scale study was performed for treatment of such waste. Some of the waste streams originating from U and Pu analysis contain components like sulphate and phosphate which interfere during chemical precipitation of alpha activity from the waste. Various chemical co-precipitation experiments were conducted based on alkaline precipitation. Reductive precipitation using sodium sulphite and Fe(II) was found to be promising and the same was suggested for plant scale treatment. (author)

2011-02-22

367

Toward integrated design of waste management technologies

The Transuranic Waste Form Characterization and Data Base (Volume 1) provides a wide range of information from which a comprehensive data base can be established and from which standards and criteria can be developed for the present NRC waste management program. Supplementary information on each of the areas discussed in Volume 1 is presented in Appendices A through K (Volumes 2 and 3). The structure of the study (Volume 1) is outlined and appendices of Volumes 2 and 3 correlate with each main section of the report. The Executive Summary reviews the sources, quantities, characteristics and treatment of transuranic wastes in the United States. Due to the variety of potential treatment processes for transuranic wastes, the end products for long-term storage may have corresponding variations in quantities and characteristics.

1980-09-30

368

Three-dimensional assessment of the propagation and concentration distribution of waste gas from waste incinerators and sanitary landfills in built-up areas by means of specific examples. Dreidimensionale Erfassung der Ausbreitung und Konzentrationsverteilung von Abgaben aus Muellverbrennungsanlagen und Deponien in bebauten Gebieten an konkreten Beispielen

What technical, economic and institutional factors make radioactive and/or hazardous waste management technologies publicly acceptable? The goal of this paper is to initiate an identification of factors likely to render radioactive and hazardous waste management technologies publicly acceptable and to provide guidance on how technological R&D might be revised to enhance the acceptability of alternative waste management technologies. Technology development must attend to the full range of technology characteristics (technical, engineering, physical, economic, health, environmental, and socio-institutional) relevant to diverse stakeholders. ORNL`s efforts in recent years illustrate some attempts to accomplish these objectives or, at least, to build bridges toward the integrated design of waste management technologies.

1993-11-01

369

Thermal denitration and mineralization of waste constituents

Within the framework of efforts to optimize state-of-the-art waste disposal methods, this research project makes a theoretical analysis of the propagation behaviour of pollutants from landfills and waste incineration plants into the immediate vicinity of such plants. In order to judge the propagation of pollutants near the above-mentioned waste disposal facilities, a calculation program was developed within the framework of this research project which permits simulation of the propagation of such emissions in a three-dimensional space by application of an Eulerian grid model. It is capable of realistically representing fluid flow conditions and pollutant concentrations for certain points of times within the complex building patterns of such plants, for randomly chosen atmospheric conditions. (orig.)

1992-01-01

370

The Work and Lives of Street Waste Pickers in Pretoria?A Case Study of Recycling in South Africa?s Urban Informal Economy

In order to produce a quality grout from LLW using hydraulic cements, proper conditioning of the waste is essential for complete cement curing. Several technologies were investigated as options for conditions. Since the LLW is dilute, removal of all, or most, of the water will significantly reduce the final waste volume. Neutralization of the LLW is also desirable since acidic liquids to not allow cement to cure properly. The nitrate compounds are very soluble and easily leached from solid waste forms; therefore, denitration is desirable. Thermal and chemical denitration technologies have the advantages of water removal, neutralization, and denitration. The inclusion of additives during thermal treatment were investigated as a method of forming insoluable waste conditions.

1997-08-01

371

British Library Electronic Table of Contents (United Kingdom)

High levels of unemployment are a permanent feature in the urban areas of many developing countries. South Africa is no exception in this regard. Poverty and hardship caused by unemployment force many participants in the labour market to venture into the urban informal economy in order to survive. The activities of the waste pickers fall within the urban informal economy. In spite of the fact that waste pickers are a common sight in the urban areas of Pretoria and other South African cities, remarkably little is known about them and scant attention is paid to them. The aim of the study was to establish a socio-economic profile of the street waste pickers in Pretoria and to describe the social interaction and relationship dynamics between the waste pickers and their families, each other, th...

2011-01-01

372

Survey of systems safety analysis methods and their application to nuclear waste management systems

Scenario development for the optimization of energy production from waste materials in the Netherlands; Scenario-ontwikkeling voor de optimalisatie van energieproductie in Nederland

This report reviews system safety analysis methods and examines their application to nuclear waste management systems. The safety analysis methods examined include expert opinion, maximum credible accident approach, design basis accidents approach, hazard indices, preliminary hazards analysis, failure modes and effects analysis, fault trees, event trees, cause-consequence diagrams, G0 methodology, Markov modeling, and a general category of consequence analysis models. Previous and ongoing studies on the safety of waste management systems are discussed along with their limitations and potential improvements. The major safety methods and waste management safety related studies are surveyed. This survey provides information on what safety methods are available, what waste management safety areas have been analyzed, and what are potential areas for future study.

1981-11-01

373

Nigeria's radioactive waste management policy and strategy document

The main purpose of the study on the title subject is to gain insight into the strategic options to optimize energy production from waste processing in the Netherlands in the long term. The developed optimization model will be used by the Dutch Ministry of Public Health, Spatial Planning en Environment (VROM) for scenarios to calculate and determine expectations and uncertainties in the development of waste processing in the Netherlands. Attention is paid to (1) the impact of present and future technology on the costs and energetic efficiency of waste processing, (2) several techniques for the generation of electricity and heat, the production of fuels, and recycling, (3) the impact of scale (capacity) on costs and energetic efficiency of waste processing installations, and (4) the impact of transport and heat distribution. The time frame is the year 2020. 66 refs.

2001-01-01

374

Linking emerging hazardous waste technologies with the electronic information era

Radioactive waste for legal and regulatory purposes may be defined as material that contains or is contaminated with radio-nuclides at concentrations or activities greater than clearance levels as established by the regulatory body, and for which no use is foreseen. Safe management of radioactive waste is essential to ensure protection of humans and environment. Radioactive waste management policy is a guideline for the safe management of radioactive waste. It expresses the commitment of the country towards the goal. Government should initiate investigation into best long-term option for management of spent nuclear fuels. Process of selecting option and eventual site should involve comprehensive public participation within set time frames (with deep geological disposal as preferred management option).

2009-07-14

375

Infrastructure support for a waste management institute. Final project report, September 12, 1994--September 11, 1997

In looking to the future and the development of new approaches or strategies for managing hazardous waste, it is important to understand and appreciate the factors that have contributed to current successful approaches. In the United States, several events in the last two decades have had a significant impact in advancing remediation of hazardous waste, including environmental legislation, legislative reforms on licensing federally funded research, and electronic transfer of information. Similar activities also have occurred on a global level. While each of these areas is significant, the electronic exchange of information has no national boundaries and has become an active part of major hazardous waste research and management programs. It is important to realize that any group or society that is developing a comprehensive program in hazardous waste management should be able to take advantage of this ...

1996-12-31

376

From waste prevention to promotion of material efficiency: change of discourse in the waste policy of Finland

North Carolina A and T State University has completed the development of an infrastructure for the interdisciplinary Waste Management Institute (WMI). The Interdisciplinary Waste Management Institute (WMI) was approved in June, 1994 by the General Administration of the University of North Carolina as an academic support unit with research and public service functions. The mission of the WMI is to enhance awareness and understanding of waste management issues and to provide instructional support including research and outreach. The goals of WMI are as follows: increase the number of minority professionals who will work in waste management fields; develop cooperative and exchange programs involving faculty, students, government, and industry; serve as institutional sponsor of public awareness workshops and lecture series; and support interdisciplinary research programs. The vision of the WMI is to provide ...

1997-11-01

377

British Library Electronic Table of Contents (United Kingdom)

This article analyses the process of preparing the proposal for a new Finnish National Waste Plan (NWP 2007-2016). The focus of this study is on the use of the alternative concepts of waste prevention or material efficiency and on the shift in discourse from the former to the latter concept. The strengths and weaknesses of these competing concepts were analysed using criteria such as synergy, semantic aspects, legal context and applicability to monitoring. The discourse presented by different stakeholder groups was analysed. The implications of choosing either of the concepts were illustrated. The author concludes that waste prevention can be promoted just as well, or even better from the perspective of improving material efficiency. The concept must be complemented by policy instruments w...

2009-01-01

378

Fixation of high-level wastes in glasses

Determination and removal of malondialdehyde and other 2-thiobarbituric acid reactive substances in waste cooking oil

A plant for the fixation of high-level wastes in borosilicate glass has been operating in France since 1978. A large plant is under construction in the U.S. for the fixation of defence high-level waste and plans for other glass fixation plants are well advanced at several sites around the world. Among the reasons for the selection of borosilicate glass as a fixation medium are the relative ease of processing wastes of variable composition by means of well established technology, and the long-term radiation and thermal stability of the glass. Well formulated glass also has sufficient resistance to the action of groundwater so that it can serve as an important barrier against the spread of radionuclides via groundwater in any forseeable situation. Research is continuing to quantify the reactions of waste glass in site-specific geological repository environments.

1986-07-30

379

British Library Electronic Table of Contents (United Kingdom)

Waste cooking oil can be recovered and processed into animal feed additives after purification. Unfortunately, the traditional purification processes are insufficient for the removal of the harmful compounds formed during frying, mainly about malondialdehyde and other 2-thiobarbituric acid reactive substances. In the present paper, firstly, a simple and reliable HPLC method was developed to measure the content of malondialdehyde in purified waste cooking oil. The detection limit and the standard recovery of the analysis method are 1.20x10-5gl-1 and 96.5-99.2%, respectively, which is accurate and valid enough for the detection of malondialdehyde in waste cooking oil. Furthermore, the removal of malondialdehyde and other 2-thiobarbituric acid reactive substances from waste cooking oil was in...

2011-01-01

380

Contingency plan for the Lawrence Livermore National Laboratory's hazardous-waste operations

Bioconversion of chicken wastes to value-added products

The Lawrence Livermore National Laboratory (LLNL) has the necessary equipment and trained personnel to respond to a large number of hazardous material spills and fires or other emergencies resulting from these spills including injured personnel. This response capability is further expanded by the agreements that LLNL has with a number of outside response agencies. The Hazards Control Department at LLNL functions as the central point for coordinating the response of the equipment and personnel. Emergencies involving hazardous waste are also coordinated through the Hazards Control Department, but the equipment and personnel in the Toxic Waste Control Group would be activated for large volume waste pumpouts. Descriptions of response equipment, hazardous waste locations communication systems, and procedures for personnel involved in the emergency are provided.

1981-03-20

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381

Application of probabilistic methods to accident analysis at waste management facilities

Increasing quantities of chicken waste concerns the poultry industry because of escalating disposal costs and the potential for environmental pollution. Biological conversion of these wastes to valuable products such as methane and/or chemical feed-stocks appears to be feasible. Biomethanation of chicken waste by a sewage sludge microbial consortium produced as much as 69 mol% methane in the gas phase. Acetic and propionic acids were the major acids produced during the bioconversion. Addition of chelating agents and other micro-nutrients enhanced methane production and shifted the ratios of intermediates accumulated. Preliminary data indicate that more than 60% of the chicken waste carbon was converted and that the nitrogen-rich residue may have potential as a soil additive. (author).

1991-01-01

382

Waste Minimization/Pollution Prevention Crosscut Plan, 1994

Probabilistic risk assessment is a technique used to systematically analyze complex technical systems, such as nuclear waste management facilities, in order to identify and measure their public health, environmental, and economic risks. Probabilistic techniques have been utilized at the Waste Isolation Pilot Plant (WIPP) near Carlsbad, New Mexico, to evaluate the probability of a catastrophic waste hoist accident. A probability model was developed to represent the hoisting system, and fault trees were constructed to identify potential sequences of events that could result in a hoist accident. Quantification of the fault trees using statistics compiled by the Mine Safety and Health Administration (MSHA) indicated that the annual probability of a catastrophic hoist accident at WIPP is less than one in 60 million. This result allowed classification of a catastrophic hoist accident as ''not credible'' at WIPP per DOE ...

383

The Waste Isolation Pilot Plant: A Success Story with International Cooperation

This plan establishes a Department-wide goal to reduce total releases of toxic chemicals to the environment and off-site transfers of such toxic chemicals by 50 percent by December 31, 1999, in compliance with Executive Order 12856. Each site that meets the threshold quantities of toxic chemicals established in the Emergency Planning and Community Right-to-Know Act (EPCRA) will participate in this goal. In addition, each DOE site will establish site-specific goals to reduce generation of hazardous, radioactive, radioactive mixed, and sanitary wastes and pollutants, as applicable. Implementation of this plan will represent a major step toward the environmental risks and costs associated with DOE operations and increasing the Department's use of preventive environmental management practices. Investing in Waste Minimization Pollution Prevention (WMin/PP) steadily reduce hazardous and radioactive waste generation and will ...

384

Corrosion studies of carbon steel under impinging jets of simulated slurries of neutralized current acid waste (NCAW) and neutralized cladding removal waste (NCRW)

The U.S. Department of Energy (DOE) Carlsbad Field Office (CBFO) administers and operates the Waste Isolation Pilot Plant (WIPP) site, which hosts a deep geologic repository for safe disposal of U.S. defense-related TRU waste and is located 42 kilometers (km) east of Carlsbad, New Mexico. CBFO also manages the National Transuranic Waste Program (NTP), which oversees TRU waste management from generation to disposal. The WIPP began receiving waste in March 1999. In some areas of broad international interest, the CBFO has developed a leading expertise through its 25-year WIPP repository and TRU waste characterization activities. In addition to participating in relevant and beneficial experiments, the CBFO will provide the international community convenient access to this information by sponsoring and hosting symposia and workshops on relevant topics and by ...

2002-02-26

385

Corrosion studies of carbon steel under impinging jets of simulated slurries of neutralized current acid waste (NCAW) and neutralized cladding removal waste (NCRW)

Plans for the disposal of radioactive liquid and solid wastes presently stored in double-shell tanks at the Hanford Site call for retrieval and processing of the waste to create forms suitable for permanent disposal. Waste will be retrieved from a tank using a submerged slurry pump in conjunction with one or more rotating slurry jet mixer pumps. Pacific Northwest Laboratory (PNL) has conducted tests using simulated waste slurries to assess the effects of a impinging slurry jet on the corrosion rate of the tank wall and floor, an action that could potentially compromise the tank's structural integrity. Corrosion processes were investigated on a laboratory scale with a simulated neutralized cladding removal waste (NCRW) slurry and in a subsequent test with simulated neutralized current acid waste (NCAW) slurry. The test slurries simulated the actual NCRW ...

1992-01-01

386

Combustion of refuse-derived fuels in grate and fluidised bed furnaces; Ersatzbrennstoffverbrennung in Rost- und Wirbelschichtoefen

Plans for the disposal of radioactive liquid and solid wastes presently stored in double-shell tanks at the Hanford Site call for retrieval and processing of the waste to create forms suitable for permanent disposal. Waste will be retrieved from a tank using a submerged slurry pump in conjunction with one or more rotating slurry jet mixer pumps. Pacific Northwest Laboratory (PNL) has conducted tests using simulated waste slurries to assess the effects of a impinging slurry jet on the corrosion rate of the tank wall and floor, an action that could potentially compromise the tank`s structural integrity. Corrosion processes were investigated on a laboratory scale with a simulated neutralized cladding removal waste (NCRW) slurry and in a subsequent test with simulated neutralized current acid waste (NCAW) slurry. The test slurries simulated the actual NCRW and NCAW ...

1992-01-01

387

Upward migration of underground injected wastes through hydrologic conduits around the wellbore

In addition to the goal of ensuring waste disposal, thermal waste treatment has always been aimed at the energy-efficient utilisation of wastes. Developments in waste management have led to an increase in high-calorific waste arisings. This is attributable to the use of mechanical-biological waste treatment as well as to segregated waste collection systems. High-calorific wastes are equivalent to fossil fuels in terms of their calorific content. Furthermore, they fulfil the legal requirements for conversion to energy. Another source of high-calorific wastes suitable for conversion to energy can be made available through the segregated disposal of industrial wastes, in many cases at low cost. These high-calorific fractions of varying origin and composition are referred to ...

2005-07-01

388

The review of radioactive waste management in the world

Underground injection, compared to other waste disposal methods, is considered to have the advantages of isolating wastes in a confined brine aquifer well below the horizon of human activity and underground sources of drinking water (USDWs). While most of injected wastes move laterally in the injection zone, posing a long-term concern to the human health and environment, a small amount can migrate upward to the upper aquifers, causing a greater threat to the quality of USDWs. Both the dual porosity and the single porosity models were used to investigate the migration of injected wastes through these hydrologic conduits. The results indicate that regional upward migration through an extensive confining formation is a slow process. Nevertheless, injected wastes can move upward rapidly through microannuli and channels in the cement sheath and spread over a distance in the upper ...

1988-01-01

389

The mixed waste management facility: Cost-benefit for the Mixed Waste Management Facility at Lawrence Livermore National Laboratory

Radioactive waste is generally classified on the basis of how much radiation and the type of radiation it emits as well as the length of time over which it will continue to emit radiation. Many activities dealing with radioactive materials produce nuclear wastes, including civilian nuclear power programs (nuclear Power plant operations and nuclear fuel-cycle activities), defense nuclear programs (nuclear weapons production, naval nuclear reactor programs, and related R and D), and industrial and institutional activities (scientific research, medical operations, and other industrial uses of Radioisotopic sources or Radio chemicals). To minimize the potential adverse health and environment impacts to people and other systems including of animals, plant and etc, during the entire lifetime of the radionuclides involved, nuclear waste must be carefully and properly managed. The scope of nuclear - waste ...

390

The Proposed Yucca Mountain Repository From A Corrosion Perspective

The Mixed Waste Management Facility, or MWMF, has been proposed as a national testbed facility for the demonstration and evaluation of technologies that are alternatives to incineration for the treatment of mixed low-level waste. The facility design will enable evaluation of technologies at pilot scale, including all aspects of the processes, from receiving and feed preparation to the preparation of final forms for disposal. The MWMF will reduce the risk of deploying such technologies by addressing the following: (1) Engineering development and scale-up. (2) Process integration and activation of the treatment systems. (3) Permitting and stakeholder issues. In light of the severe financial constraints imposed on the DOE and federal programs, DOE/HQ requested a study to assess the cost benefit for the MWMF given other potential alternatives to meet waste treatment needs. The MVVMF Project was asked to consider alternatives ...

2005-10-01

391

Technical considerations associated with waste-to-energy systems

Corrosion is a primary determinant of waste package performance at the proposed Yucca Mountain Repository and will control the delay time for radionuclide transport from the waste package. Corrosion is the most probable and most likely degradation process that will determine when packages will be penetrated and the shape, size, and distribution of those penetrations. The general issues in corrosion science, materials science and electrochemistry are well defined, and the knowledge base is substantial for understanding corrosion processes. In this paper, the Yucca Mountain Repository is viewed from a corrosion perspective. A major component of the long-term strategy for safe disposal of nuclear waste at the Yucca Mountain Repository is first to completely isolate the radionuclides in the waste packages for long times and to greatly retard the egress and transport of radionuclides from penetrated ...

2005-04-12

392

TWR Bench-Scale Steam Reforming Demonstration

The average American generates four pounds of solid waste per day, yet increasing constraints are being placed on the ability of municipalities to handle waste disposal. Most cities face a scarcity of acceptable landfill sites and conventional incineration and landfill methods have come under strict air, water and soil pollution standards. City administrators are being encouraged to select from a variety of proposed technologies that supplant traditional waste disposal methods, some of which offer the promise of revenues from energy and resource recovery. The problem is to select from available near-term technologies those systems that will fit into a city's long-term solid-waste management program. Broadly, waste-to-energy recovery systems now available to cities may be classified as combustion, pyrolysis, biodegradation, and mechanical front-end systems. It is important ...

1981-01-01

393

TWR Bench-Scale Steam Reforming Demonstration

The Idaho Nuclear Technology and Engineering Center (INTEC) was home to nuclear fuel reprocessing activities for decades at the Idaho National Engineering and Environmental Laboratory. As a result of the reprocessing activities, INTEC has accumulated approximately one million gallons of acidic, radioactive, sodium-bearing waste (SBW). The purpose of this demonstration was to investigate a reforming technology, offered by ThermoChem Waste Remediation, LLC, (TWR) for treatment of SBW into a "road ready" waste form that would meet the waste acceptance criteria for the Waste Isolation Pilot Plant (WIPP). TWR is the licensee of Manufacturing Technology Conservation International (MTCI) steam-reforming technology in the field of radioactive waste treatment. A non-radioactive simulated SBW was used based on the known composition of ...

2003-05-01

394

Resource Conservation and Recovery Act, Part B permit application [for the Waste Isolation Pilot Plant (WIPP)]. Volume 4, Revision 1.0

The Idaho Nuclear Technology and Engineering Center (INTEC) was home to nuclear fuel reprocessing activities for decades at the Idaho National Engineering and Environmental Laboratory. As a result of the reprocessing activities, INTEC has accumulated approximately one million gallons of acidic, radioactive, sodium-bearing waste (SBW). The purpose of this demonstration was to investigate a reforming technology, offered by ThermoChem Waste Remediation, LLC, (TWR) for treatment of SBW into a ''road ready'' waste form that would meet the waste acceptance criteria for the Waste Isolation Pilot Plant (WIPP). TWR is the licensee of Manufacturing Technology Conservation International (MTCI) steam-reforming technology in the field of radioactive waste treatment. A non-radioactive simulated SBW was used based on the known composition of ...

2003-05-21

395

Pyrochemical Processing for Low-Level Waste Production in PEACER

The US Department of Energy is currently constructing the Waste Isolation Pilot near Carlsbad, New Mexico. The full-scale pilot plant will demonstrate the feasibility of the safe disposal of defense-related nuclear waste in a bedded salt formation at a depth of 2160 feet below the surface. WIPP will provide for the permanent storage of 25,000 cu ft of remote-handled (RH) transuranic waste and 6,000,000 cu ft of contact-handled (CH) transuranic waste. This paper covers the major mechanical/structural design considerations for the waste hoist and its hoist tower structure. The design of the hoist system and safety features incorporates state-of-the-art technology developed in the hoist and mining industry to ensure safe operation for transporting nuclear waste underground. Also included are design specifications for VOC-10 monitoring system.

1991-12-31

396

Pyrochemical Processing for Low-Level Waste Production in PEACER

A pyrochemical partitioning process has been conceptually designed so that the transmutation of spent LWR fuels in PEACER can produce mainly low-level waste (Class C waste) for near-surface burial. Chloride salt technology developed for IFR has been employed as the baseline. Electrorefining, reductive extraction and salt recycling steps are used to construct overall flowsheet in order to support PEACER operation. The decontamination factor for transuranic elements was estimated based on both thermodynamic models and reported experimental data. It is expected that overall decontamination factor can be as high as 10{sup 5} for transuranic elements. Final wastes from pyrochemical processing for PEACER are noble metals, alkaline earth metal, and lanthanides. The final wastes are stabilized by mixing with zeolite and glass-frits such that concentration limit for class C waste can be met. ...

2002-07-01

397

Proceedings of the 2. international conference on accelerator-driven transmutation technologies and applications

A pyrochemical partitioning process has been conceptually designed so that the transmutation of spent LWR fuels in PEACER can produce mainly low-level waste (Class C waste) for near-surface burial. Chloride salt technology developed for IFR has been employed as the baseline. Electrorefining, reductive extraction and salt recycling steps are used to construct overall flowsheet in order to support PEACER operation. The decontamination factor for transuranic elements was estimated based on both thermodynamic models and reported experimental data. It is expected that overall decontamination factor can be as high as 10"5 for transuranic elements. Final wastes from pyrochemical processing for PEACER are noble metals, alkaline earth metal, and lanthanides. The final wastes are stabilized by mixing with zeolite and glass-frits such that concentration limit for class C waste can be met. The ...

2002-06-09

398

Pollution prevention opportunity assessment for Building 922 solid office waste

Technical developments in the construction of high power accelerators have created new research activities on accelerator-driven transmutation technologies (ADTT) with main applications for energy production and nuclear waste transmutation. The on-going research was reported and discussed at the conference. The studies of energy production based on ADTT indicate possible important advantages compared to the present nuclear power reactors. Natural Uranium or Thorium is burned in a subcritical reactor with or without simultaneous incineration and transmutation of nuclear waste. High level radioactive wastes and weapons Plutonium constitute an environmental and proliferation problem. Studies were reported on the possibilities to use ADTT to considerably shorten the life-time and reduce the amount of long-lived radioactive waste in order to decrease the volumes needed for long-term geologic deposition. A ...

1996-06-03

399

Modification of SGS system for application to various sized drums

Building 922 houses all of SNL/California`s ES and H Departments: Health Protection, Environmental Protection, Safety, and Environmental Operations. It covers approximately 10,000 square feet and houses about 80 people. The office personnel generate nonhazardous solid office wastes in their daily activities. To determine the types and amounts of waste generated, a special PPOA sorting team sorted all of the trash collected from the building for a period of one-week (including paper and aluminum cans in the recycling bins). The team sorted the trash into major categories: paper, plastic, metals, glass, wet garbage, rest room waste, and miscellaneous materials. They then sorted it into subcategories within each major category. Rest room waste was collected but not sorted. The waste in each category was weighed separately. The total amount of trash collected during the week was ...

1995-01-01

400

Modification of SGS system for application to various sized drums

To dispose the radioactive waste drums, the waste form's integrity and the nuclides inventories must be assured according to the national and site waste acceptance criteria. Because they might be would gravely affected the performance objectives of disposal site. Our national regulation for the waste inventory related to 'Radioactive Waste Acceptance Criteria' requires that the activities of 13 nuclides and gross {alpha} must be measured and the 95 % of nuclides incorporated in the drum must be identified. It is very difficult to measure the radioactivity with accuracy from the regulated waste drum(200L), and have a large error in the analysis results. In present, there are two system, SGS (Segmented Gamma Scanning System) and TGS (Tomographic Gamma Scanning System) for the analysis of radionuclides from the waste ...

2005-11-15

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401

Mine waste disposal and managements

To dispose the radioactive waste drums, the waste form's integrity and the nuclides inventories must be assured according to the national and site waste acceptance criteria. Because they might be would gravely affected the performance objectives of disposal site. Our national regulation for the waste inventory related to 'Radioactive Waste Acceptance Criteria' requires that the activities of 13 nuclides and gross #alpha# must be measured and the 95 % of nuclides incorporated in the drum must be identified. It is very difficult to measure the radioactivity with accuracy from the regulated waste drum(200L), and have a large error in the analysis results. In present, there are two system, SGS (Segmented Gamma Scanning System) and TGS (Tomographic Gamma Scanning System) for the analysis of radionuclides from the waste drums. In general, it is ...

2005-11-01

402

How does one develop the right quality assurance program for waste management projects?

Acid Rock Drainage (ARD) is the product formed by the atmospheric oxidation of the relatively common pyrite and pyrrhotite. Waste rock dumps and tailings containing sulfide mineral have been reported at toxic materials producing ARD. Mining in sulphide bearing rock is one of activity which may lead to generation and release of ARD. ARD has had some major detrimental affects on mining areas. The purpose of this study was carried out to develop disposal method for preventing contamination of water and soil environment by waste rocks dump and tailings, which could discharge the acid drainage with high level of metals. Scope of this study was as following: environmental impacts by mine wastes, geochemical characteristics such as metal speciation, acid potential and paste pH of mine wastes, interpretation of occurrence of ARD underneath tailings impoundment, analysis of slope stability of tailings dam etc. ...

1998-12-01

403

Hospital waste management status in Lebanon

The quality assurance requirements in use today for radioactive waste facilities, geologic repositories and hazardous waste projects were developed initially for the nuclear power plant industry, and their intent is being applied by regulations and guidance documents to radioactive and hazardous waste programs. The wording of the NRC quality assurance requirements in Appendix B of 10CFR50, the related guidance documents and the industry's ANSI/ASME NQA-1 were developed over a period of several years to address quality assurance for the design and construction of the complex and interactive systems to produce electrical power using nuclear fuel. Now, those same documents are the basis for the quality assurance requirements and guidance for waste management facilities and repositories. The intent of Appendix B of 10CFR50 and NQA-1 can easily be applied to waste projects, providing one ...

1988-10-03

404

Enhanced sludge washing evaluation plan

author.The existing management of hospital waste in Lebanon currently poses both an environmental hazard as well as a public health risk. This is due mainly to lack of legislation, information and modern treatment and disposal facilities designed for this purpose. A nation-wide questionnaire survey was conducted to asses the status of hospital waste management. The study started from October 1997 till August 1998. We found that 75% of the surveyed hospitals completely ignore their total waste quantity: 73% of hospitals surveyed practice segregation at source of infectious, pathological, sharps and pharmaceuticals; more than 40% dispose of their hospital risk wastes through the municipality waste disposal, 24% by burning in open fires, 14% by on-site hospital incinerators, 11% in on-site dumping, 8% handled by a private contractor and 1% in uncontrolled landfill. We conclude that ...

405

Air pollutants emissions from waste treatment and disposal facilities.

The Tank Waste Remediation System (TWRS) Program mission is to store, treat, and immobilize highly radioactive Hanford Site waste (current and future tank waste and the strontium/cesium capsules) in an environmentally sound, safe, and cost-effective manner. The scope of the TWRS Waste Pretreatment Program is to treat tank waste and separate that waste into HLW and LLW fractions and provide additional treatment as required to feed LLW and HLW immobilization facilities. Enhanced sludge washing was chosen as the baseline process for separating Hanford tank waste sludge. Section 1.0 briefly discusses the purpose of the evaluation plan and provides the background that led to the choice of enhanced sludge washing as the baseline process. Section 2.0 provides a brief summary of the evaluation plan details. Section 3.0 discusses, in some detail, the ...

1994-09-01

406

Actinides in liquid waste formed in the regeneration of nuclear fuel from a VVER-1000 reactor

This study examined the atmospheric pollution created by some waste treatment and disposal facilities in the State of Kuwait. Air monitoring was conducted in a municipal wastewater treatment plant, an industrial wastewater treatment plant established in a petroleum refinery, and at a landfill site used for disposal of solid wastes. Such plants were selected as models for waste treatment and disposal facilities in the Arabian Gulf region and elsewhere. Air measurements were made over a period of 6 months and included levels of gaseous emissions as well as concentrations of volatile organic compounds (VOCs). Samples of gas and bioaerosols were collected from ambient air surrounding the treatment facilities. The results obtained from this study have indicated the presence of VOCs and other gaseous pollutants such as methane, ammonia, and hydrogen sulphide in air surrounding the waste treatment and disposal ...

2006-01-01

407

Fate of Mercury in Synthetic Gypsum Used for Wallboard Production

In the radiochemical reprocessing of spent fuel from nuclear reactors, a considerable amount of liquid, solid, and gaseous waste is formed; this waste is potentially dangerous to humans and requires the development of special and complex technological techniques for its localization and reliable long-term storage. The most hazardous are liquid wastes of high specific activity - water-tailings solutions obtained in the first cycle of extraction after the removal of uranium and plutonium. These solutions contain more than 99.9% of all the other transuranic elements - isotopes of neptunium, americium, and curium. Where necessary, some fission products and actinides may be removed from wastes of high specific activity for subsequent use. The quantity, composition, and activity of these wastes varies within broad limits, depending on the type and power of the reactor, the initial nuclide ...

408

The newest achievements of studies on the reutilization, treatment, and disposal technology of hazardous wastes

This report presents and discusses results from Task 5 of the study ''Fate of Mercury in Synthetic Gypsum Used for Wallboard Production,'' performed at a full-scale commercial wallboard plant. Synthetic gypsum produced by wet flue gas desulfurization (FGD) systems on coal-fired power plants is commonly used in the manufacture of wallboard. The FGD process is used to control the sulfur dioxide emissions which would result in acid rain if not controlled. This practice has long benefited the environment by recycling the FGD gypsum byproduct, which is becoming available in increasing quantities, decreasing the need to landfill this material, and increasing the sustainable design of the wallboard product. However, new concerns have arisen as recent mercury control strategies developed for power plants involve the capture of mercury in FGD systems. The objective of this study is to determine whether any mercury is released into the atmosphere when the ...

2006-06-01

409

The Comparison on Treatment Method of Liquid Radioactive Waste in Yonggwang No 3 and 4 and No 5 and 6

From 1991 to 1996, key studies on the reutilization, treatment, and disposal technology of hazardous wastes have been incorporated into the national plan for environmental protection science and technology. At present, the research achievements have been accomplished, have passed national approval, and have been accepted. The author of this paper, as leader of the national group for this research work, expounds the newest achievements of the studies involving four parts: (1) the reutilization technology of electroplating sludge, including the ion-exchange process for recovering the sludge and waste liquor for producing chromium tanning agent and extracting chromium and colloidal protein from tanning waste residue; on the recovery of heavy metals from the electroplating waste liquor with microbic purification; on the demonstration project of producing modified plastics from the sludge and the ...

1996-12-31

410

Low-activity waste envelope definitions for the TWRS Privatization Phase I Request For Proposal

Most of the low-level liquid radioactive wastes generated from PWR plants are classified into high or low total suspended solid(HTDS or LTDS), and into radiochemical and radioactive laundry waste. Although the evaporation process has a high decontamination ability, it has several problems such as corrosion, foam, and congestion. A new liquid waste disposal process using the ion-exchange demineralizer(IED), instead of the current evaporation process, has been introduced into the Yonggwang NPP No 5 and 6. These two methods have been compared to understand the differences in this study. Aspects compared here were the released radioactivity amount of the liquid radioactive wastes, the dose of off-site residents, the decontamination factor, and the amount of the solid radioactive wastes. The IED system is designed to discharge higher radioactivity about 20% than the evaporating system, ...

2004-09-01

411

Final environmental impact statement. Waste Isolation Pilot Plant

Radioactive waste has been stored in large underground storage tanks at the Hanford Site since 1944. Approximately 212 million liters of waste containing approximately 240,000 metric tons of processed chemicals and 177 mega-curies of radionuclides are now stored in 177 tanks. These caustic wastes are in the form of liquids, slurries, saltcakes, and sludge. In 1991, the Tank Waste Remediation System (TWRS) Program was established to manage, retrieve, treat, immobilize, and dispose of these wastes in a safe, environmentally sound, and cost-effective manner. The Department of Energy (DOE) has believes that it is feasible to privatize portions of the TWRS Program. Under the privatization strategy embodied in the Request for Proposal (RFP), DOE will purchase services from a contractor-owned, contractor-operated facility under a fixed-price contract. Phase I of the TWRS privatization ...

1996-11-01

412

Defense Waste and Environmental Restoration Program Plan: Defense Waste Management Division

In accordance with the National Environmental Policy Act (NEPA) of 1969, the US Department of Energy (DOE) has prepared this document as environmental input to future decisions regarding the Waste Isolation Pilot Plant (WIPP), which would include the disposal of transuranic waste, as currently authorized. The alternatives covered in this document are the following: (1) Continue storing transuranic (TRU) waste at the Idaho National Engineering Laboratory (INEL) as it is now or with improved confinement. (2) Proceed with WIPP at the Los Medanos site in southeastern New Mexico, as currently authorized. (3) Dispose of TRU waste in the first available repository for high-level waste. The Los Medanos site would be investigated for its potential suitability as a candidate site. This is administration policy and is the alternative preferred by the DOE. (4) Delay the WIPP to allow other ...

1980-10-01

413

Bitumen immobilization of aqueous radwaste by thin-film evaporation

The DEFENSE WASTE MANAGEMENT PROGRAM has been chartered by the Department of Energy (DOE) to receive, reduce, store, and maintain all radioactive defense waste generated by Hanford and received from offsite DOE contractors in a safe condition and in accordance with DOE and Westinghouse Hanford Company (WHC) standards. These activities are accomplished through the use of TRU retrievable storage sites, solid waste burial grounds, liquid waste storage tanks, capsule storage pools, and other low-level waste disposal methods. Continuous and/or periodic surveillance is maintained. Through the use of improved packaging methods, evaporator-crystallization and capsule production waste has been and continues to be put in a safe and economic storage condition pending future reprocessing or final disposition. For this Program Plan, the scope of Defense ...

1988-09-01

414

Assessing waste management systems using reginalt software

In the early 1980s, AECL built a Waste Treatment Centre (WTC) for managing low-level solid and aqueous liquid wastes for converting CANDU wastes. At present, two liquid waste streams are being treated at the WTC. The liquid waste streams are volume-reduced by a combination of continuous crossflow microfiltration (MF), spiral wound reverse osmosis (SWRO) and tubular reverse osmosis (TRO) membrane technologies. The concentrate produced from the TRO system and the volume-reduced MF backwash solutions are evaporated while simultaneously adding bitumen in a thin-film evaporator. A water-free product of chemical and radiochemical salts and bitumen is removed in 200-L galvanized steel drums for storage. The radiation field of product drums on contact typically has a value of 0.5 to 3 R/h depending upon the feed concentration of radioactivity to the evaporator. The total solids content in ...

1996-02-25

415

Application of molten salt oxidation for the minimization and recovery of plutonium-238 contaminated wastes

A method for assessing management systems for low-level radioactive waste is being developed for US Department of Energy. The method is based on benefit-cost-risk analysis. Waste management is broken down into its component steps, which are generation, treatment, packaging, storage, transportation, and disposal. Several different alternatives available for each waste management step are described. A particular waste management system consists of a feasible combination of alternatives for each step. Selecting an optimal waste management system would generally proceed as follows: (1) qualitative considerations are used to narrow down the choice of waste management system alternatives to a manageable number; (2) the costs and risks for each of these system alternatives are evaluated; (3) the number of alternatives is further reduced by eliminating alternatives with ...

1988-03-01

416

All the Spent Nuclear Wastes to Low and Intermediate Level Wastes: PyroGreen

Molten salt oxidation (MSO) is proposed as a {sup 238}Pu waste treatment technology that should be developed for volume reduction and recovery of {sup 238}Pu and as an alternative to the transport and permanent disposal of {sup 238}Pu waste to the WIPP repository. In MSO technology, molten sodium carbonate salt at 800--900 C in a reaction vessel acts as a reaction media for wastes. The waste material is destroyed when injected into the molten salt, creating harmless carbon dioxide and steam and a small amount of ash in the spent salt. The spent salt can be treated using aqueous separation methods to reuse the salt and to recover 99.9% of the precious {sup 238}Pu that was in the waste. Tests of MSO technology have shown that the volume of combustible TRU waste can be reduced by a factor of at least twenty. Using this factor the present inventory of 574 TRU drums ...

1998-05-01

417

Recovery of uranium from aqueous solutions using calcined powders of CaO-Al/sub 2/O/sub 3/-SO/sub 3/ system

Spent nuclear wastes are inevitable issues to use nuclear power as a sustainable energy. Therefore, every country has their fuel cycles which are best for their environmental and/or political circumstances for the use of nuclear energy. These days agreements are made that spent nuclear fuels should be recycled to minimize waste volume and its toxicity all around the world. Republic of Korea also has a plan to recycle the spent nuclear fuels by using Gen-IV concept burner reactors and pyro-process plants. Not many options of national nuclear strategies are exist because Korea has too many people for its limited land space. KAERI already has been proposing a national fuel cycle concept called 'KIEP-21' that encompasses all the requirements of the advanced nuclear fuel cycle such as reduction of volume, toxicity, HLW heat load and so on. Authors suggest non-national fuel cycle concept called 'PyroGreen' for the sustainable nuclear energy system. ...

2009-06-01

418

Waste treatment process for removal of contaminants from aqueous, mixed-waste solutions using sequential chemical treatment and crossflow microfiltration, followed by dewatering

Aqueous solutions of Al/sub 2/(SO/sub 4/)/sub 3/ (1.05 g/100 ml), AlCl/sub 3/ (0.82 g/100 ml) and Ca(OH)/sub 2/ slurry (0.94 g/50 ml) were mixed in various volume ratios and passed through a filter. White cakes left on the filter consisted mainly of ettringite (6CaO.Al/sub 2/O/sub 3/.3SO/sub 3/.32H/sub 2/O). The cakes were then calcined at various temperatures of 300/sup 0/ -- 1000/sup 0/C for 30 and 60 min and pulverized to 80 -- 200 mesh powders. The adsorption capacity of the powders for U(VI) ions dissolved in aqueous solutions was determined by immersing 0.100 g of their powders in 50 ml of the aqueous solution containing 100 ppm of U(VI) ions mainly in the form of (UO/sub 2/(CO/sub 3/)/sub 3/)/sup 4 -/ for 2 hours. The results obtained were summarized as follows. 1) Among the powders prepared, those of the oxide compositions, 2.9CaO.Al/sub 2/O/sub 3/.1.4SO/sub 3/ and 2.5CaO.Al/sub 2/O/sub 3/.1.2SO/sub 3/, all fired at 500/sup 0/C or 600/sup 0/C showed high ...

1981-11-01

419

Waste treatment process for removal of contaminants from aqueous, mixed-waste solutions using sequential chemical treatment and crossflow microfiltration, followed by dewatering

In processes of this invention aqueous waste solutions containing a variety of mixed waste contaminants are treated to remove the contaminants by a sequential addition of chemicals and adsorption/ion exchange powdered materials to remove the contaminants including lead, cadmium, uranium, cesium-137, strontium-85/90, trichloroethylene and benzene, and impurities including iron and calcium. Staged conditioning of the waste solution produces a polydisperse system of size enlarged complexes of the contaminants in three distinct configurations: water-soluble metal complexes, insoluble metal precipitation complexes, and contaminant-bearing particles of ion exchange and adsorbent materials. The volume of the waste is reduced by separation of the polydisperse system by cross-flow microfiltration, followed by low-temperature evaporation and/or filter pressing. The water produced as filtrate is discharged if it ...

1994-01-01

420

Unrestricted disposal of minimal activity levels of radioactive wastes: exposure and risk calculations

In processes of this invention aqueous waste solutions containing a variety of mixed waste contaminants are treated to remove the contaminants by a sequential addition of chemicals and adsorption/ion exchange powdered materials to remove the contaminants including lead, cadmium, uranium, cesium-137, strontium-85/90, trichloroethylene and benzene, and impurities including iron and calcium. Staged conditioning of the waste solution produces a polydisperse system of size enlarged complexes of the contaminants in three distinct configurations: water-soluble metal complexes, insoluble metal precipitation complexes, and contaminant-bearing particles of ion exchange and adsorbent materials. The volume of the waste is reduced by separation of the polydisperse system by cross-flow microfiltration, followed by low-temperature evaporation and/or filter pressing. The water produced as filtrate is discharged if it ...

1994-11-22

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421

Status of the WIPP Project

The US Nuclear Regulatory Commission is currently considering revision of rule 10 CFR Part 20, which covers disposal of solid wastes containing minimal radioactivity. In support of these revised rules, we have evaluated the consequences of disposing of four waste streams at four types of disposal areas located in three different geographic regions. Consequences are expressed in terms of human exposures and associated health effects. Each geographic region has its own climate and geology. Example waste streams, waste disposal methods, and geographic regions chosen for this study are clearly specified. Monetary consequences of minimal activity waste disposal are briefly discussed. The PRESTO methodology was used to evaluate radionuclide transport and health effects. This methodology was developed to assess radiological impacts to a static local population for a 1000-year period ...

1984-08-01

422

Risk perception on management of nuclear high-level and transuranic waste storage

The Waste Isolation Pilot Plant (WIPP), located in southeastern New Mexico, has been constructed to be a repository for transuranic (TRU) radioactive wastes generated from the US defense activities. In order to use WIPP as a repository for permanent disposal of TRU waste, the US Department of Energy (DOE) has to demonstrate compliance with the Standards for the Management and Disposal of Spent Nuclear Fuel, High Level and Transuranic Radioactive Wastes'' promulgated by the US Environmental Protection Agency (EPA) in the US Code of Federal Regulations 40 CFR Part 191. The DOE initially plans to perform experiments with a small quantity of waste at WIPP and would like to bring additional quantities for operational demonstration'', before determining whether WIPP is to be a repository for permanent disposal. There are serious problems in pursuing ...

1991-01-01

423

Potential for erosion corrosion of SRS high level waste tanks

The Department of Energy`s program for disposing of nuclear High-Level Waste (HLW) and transuranic (TRU) waste has been impeded by overwhelming political opposition fueled by public perceptions of actual risk. Analysis of these perceptions shows them to be deeply rooted in images of fear and dread that have been present since the discovery of radioactivity. The development and use of nuclear weapons linked these images to reality and the mishandling of radioactive waste from the nations military weapons facilities has contributed toward creating a state of distrust that cannot be erased quickly or easily. In addition, the analysis indicates that even the highly educated technical community is not well informed on the latest technology involved with nuclear HLW and TRU waste disposal. It is not surprising then, that the general public feels uncomfortable with DOE`s management plans for with nuclear HLW ...

1994-08-15

424

Pilot-scale testing of pyrolysis for the volume reduction of organic waste

SRS high-level radioactive waste tanks will not experience erosion corrosion to any significant degree during slurry pump operations. Erosion corrosion in carbon steel structures at reported pump discharge velocities is dominated by electrochemical (corrosion) processes. Interruption of those processes, as by the addition of corrosion inhibitors, sharply reduces the rate of metal loss from erosion corrosion. The well-inhibited SRS waste tanks have a near-zero general corrosion rate, and therefore will be essentially immune to erosion corrosion. The experimental data on carbon steel erosion corrosion most relevant to SRS operations was obtained at the Hanford Site on simulated Purex waste. A metal loss rate of 2.4 mils per year was measured at a temperature of 102 C and a slurry velocity comparable to calculated SRS slurry velocities on ground specimens of the same carbon steel used in SRS waste tanks. ...

1994-01-01

425

Pilot-scale testing of pyrolysis for the volume reduction of organic waste

Pilot-scale pyrolysis units have been in operation since 1980 to test the efficiency of thermal treatment of transuranic (TRU) solid waste to retrieve the TRUs and to reduce the volume of wastes such as spent solvent, spent resin, and others. These wastes are generated by reprocessing, fuel production, and utilities. NUKEM has developed a criticality-safe, ring-slab reactor to decompose solid TRU waste. The plant processes 25 kg/h with a polyvinyl chloride content up to 70%. The overall throughput (inactive) up to the spring of 1982 was 2000 kg. The decontamination factor for the reactor itself is 1000. The liquid wastes, mainly spent solvent, are cracked under nitrogen at 400 to 700/sup 0/C in a reactor that is filled by a packed bed kept in motion by a specially designed agitator. This unit was built for 15 kg/h water equivalent evaporation. Up to 1982 the unit processed 2000 kg ...

1982-11-01

426

Operating experience with solidification of radioactive waste by a thin-film evaporator

Pilot-scale pyrolysis units have been in operation since 1980 to test the efficiency of thermal treatment of transuranic (TRU) solid waste to retrieve the TRUs and to reduce the volume of wastes such as spent solvent, spent resin, and others. These wastes are generated by reprocessing, fuel production, and utilities. NUKEM has developed a criticality-safe, ring-slab reactor to decompose solid TRU waste. The plant processes 25 kg/h with a polyvinyl chloride content up to 70%. The overall throughput (inactive) up to the spring of 1982 was 2000 kg. The decontamination factor for the reactor itself is 1000. The liquid wastes, mainly spent solvent, are cracked under nitrogen at 400 to 700"0C in a reactor that is filled by a packed bed kept in motion by a specially designed agitator. This unit was built for 15 kg/h water equivalent evaporation. Up to 1982 the unit processed 2000 kg of ...

427

Operating experience with solidification of radioactive waste by a thin-film evaporator

In the nuclear power stations of GDR the rough radioactive waste includes borat-containing evaporator bottoms and spent ion exchanger resins. For its final disposal in deep geological formations (rock salt mines) this waste has to be solidified. The experience of one year lasting operation of a steam heated thin-film evaporator (heating surface 2 m{sup 3}) for evaporator bottoms to be solidified with a solid content of 200-250 g/l are reported on. In short time such amount of water is abstracted from the rough waste that due to the borate content a hot high-viscous product passes from evaporator to waste drum and there solidifies like glass to monolith. The product quality depends on the adjustment of the flow-equilibrium in the evaporator. Boric acid is used as matrix for the radioactive residues. The residual water content of the solidified waste product was about 15-20%, the ...

1990-01-01

428

Mixed waste landfill corrective measures study final report Sandia National Laboratories, Albuquerque, New Mexico.

In the nuclear power stations of GDR the rough radioactive waste includes borat-containing evaporator bottoms and spent ion exchanger resins. For its final disposal in deep geological formations (rock salt mines) this waste has to be solidified. The experience of one year lasting operation of a steam heated thin-film evaporator (heating surface 2 m"3) for evaporator bottoms to be solidified with a solid content of 200-250 g/l are reported on. In short time such amount of water is abstracted from the rough waste that due to the borate content a hot high-viscous product passes from evaporator to waste drum and there solidifies like glass to monolith. The product quality depends on the adjustment of the flow-equilibrium in the evaporator. Boric acid is used as matrix for the radioactive residues. The residual water content of the solidified waste product was about 15-20%, the volume ...

1990-06-01

429

Maintenance Implementation Plan for solid waste

The Mixed Waste Landfill occupies 2.6 acres in the north-central portion of Technical Area 3 at Sandia National Laboratories, Albuquerque, New Mexico. The landfill accepted low-level radioactive and mixed waste from March 1959 to December 1988. This report represents the Corrective Measures Study that has been conducted for the Mixed Waste Landfill. The purpose of the study was to identify, develop, and evaluate corrective measures alternatives and recommend the corrective measure(s) to be taken at the site. Based upon detailed evaluation and risk assessment using guidance provided by the U.S. Environmental Protection Agency and the New Mexico Environment Department, the U.S. Department of Energy and Sandia National Laboratories recommend that a vegetative soil cover be deployed as the preferred corrective measure for the Mixed Waste Landfill. The cover would be of sufficient thickness to store ...

2004-03-01

430

Laboratory for characterization of spent nuclear fuel and high/medium level radioactive waste. Experimental results and performances

This Maintenance Implementation Plan (MIP) has been developed for. implementation of the US Department of Energy (DOE) Order 4330.4A. Maintenance Implementation Program (DOE 1990) at the Hanford Site Solid Waste complex. It addresses maintenance functions associated with Solid Waste Management, which includes the field operational group and the facilities operational group. An assessment of the existing maintenance programs for Solid Waste was performed, and the results of this assessment were evaluated to determine corrective actions required to bring Solid Waste Maintenance into compliance with the order. The MIP assessment disclosed that most elements defined in the order are currently implemented for Solid Waste. It also identified issues which must be addressed to bring the maintenance function into full compliance with DOE Order 4330.4A. These include documentation of the ...

1992-06-01

431

Inventory determination of low and intermediate level radioactive waste of Paks Nuclear Power Plant origin

During the phases of separation, treatment, conditioning and storage of radioactive waste, destructive and nondestructive methods for their characterization are needed. In order to satisfy this necessity, in the frame of the National Program of Research and Development, the 'Laboratory for characterization of spent nuclear fuel and high/medium level radioactive waste- LABORAD' was created. The purpose of the project was to accredit the analysis methods available in the laboratory, and also to develop new methods for the characterization of the radioactive waste. A special attention was paid to the high-level radioactive waste and spent nuclear fuel characterization that require special facilities for handling. These facilities (e.g. hot cells, remote handlers, transport container) are already available in our institute. Experimental results and performances obtained during validation of the methods are ...

2009-05-27

432

Graphite electrode arc melter demonstration Phase 2 test results

In the execution of disposal of low and intermediate level radioactive wastes, it is important to evaluate accurately the kind and quantity of each radionuclide in the wastes. For such an evaluation, correlation of non-gamma-emitting nuclides based on gamma-emitting nuclides is recommended and regarded as a partial method. This method necessitates a completion of a highly accurate and reliable nondestructive assay system of gamma-emitting nuclides for partical use. In 1992, in support of the new waste disposal program in Hungary, Paks NPP initiated a waste characterization program to determine the radiological properties of its rad wastes. A segmented gamma scanning system has been set up to measure the gamma-emitting nuclides in 2000 litre low level drums following in-drum compaction. In the framework of the program a radiochemical analysis sub-program was stated to determine the ...

433

Control of the reduction/oxidation potential of Hanford Waste Vitrification Plant feeds

Several U.S. Department of Energy organizations and the U.S. Bureau of Mines have been collaboratively conducting mixed waste treatment process demonstration testing on the near full-scale graphite electrode submerged arc melter system at the Bureau`s Albany (Oregon) Research Center. An initial test series successfully demonstrated arc melter capability for treating surrogate incinerator ash of buried mixed wastes with soil. The conceptual treatment process for that test series assumed that buried waste would be retrieved and incinerated, and that the incinerator ash would be vitrified in an arc melter. This report presents results from a recently completed second series of tests, undertaken to determine the ability of the arc melter system to stably process a wide range of {open_quotes}as-received{close_quotes} heterogeneous solid mixed wastes containing high levels of organics, representative of the ...

1996-06-01

434

Characterization system for Germanium detectors dedicated to gamma spectroscopy applied to nuclear waste

A schematic diagram shows the various processing steps to be performed during feed preparation in the Hanford Waste Vitrification Plant (HWVP). The pretreated NCAW is transferred to the slurry receipt adjustment tank (SRAT) in the HWVP for concentration. Water removed during boildown is collected in the slurry mix evaporator condensate tank (SMECT). After waste treatment the water is returned to the storage tanks for eventual disposal. The pretreated Neutralized Current Acid Waste (NCAW) is concentrated in the SRAT to approximately 125 g waste oxides/ liter. Formic acid is then added at a controlled rate to improve rheological properties and achieve a required reduction/oxidation state. Reflux boiling is initiated and continued for several hours. The concentrated slurry is cooled and pumped to the slurry mix evaporator (SME). In the SME, glass frit is added, and the slurry is further concentrated to ...

1988-09-11

435

Bioenergy systems report: prospects in developing countries for energy from urban solid wastes

CEA-Valduc produces some radioactive waste (mainly alpha emitters). Legislation requires producers to sort their waste by activity and type of isotopes, and to package them in order to forward them to the appropriate reprocessing or storage facility. Our lab LMDE (laboratory for measurements on nuclear wastes and valuation) is in charge of the characterization of the majority of waste produced by CEA-Valduc. Among non-destructive methods to characterize a radioactive object, gamma-spectroscopy is one of the most efficient. We present to this conference the method we use to characterize nuclear waste and the system we developed to characterize our germanium detectors. The goal of this system is to obtain reliable numerical models of our detectors and calculate their efficiency curves. Measurements are necessary to checks models and improve them. These measurements are made on a bench ...

2009-06-07

436

Annual report on monitoring of the unsaturated zone and recharge areas at INEL to the state of Idaho INEL Oversight Committee

The severe health and environmental hazards posed by inadequate waste-collection systems in the rapidly growing cities of the Third World have stimulated interest in the waste-to-energy options developed in industrialized countries over the past 20 years. This economic study, the first of its kind, provides: (1) a comparative analysis of the characteristics of urban solid wastes in the United States, Europe, and developing countries; (2) basic information on the characteristics and operation of the two main types of waste-to-energy systems used in the developed world - landfill gas (LFG) systems and waste combustion systems; and (3) a preliminary assessment of the feasibility of using these systems in developing countries. The main conclusion is that present technology for the recovery and utilization of LFG appears to be suitable for developing country use, although the design of ...

1988-09-01

437

Annual report on monitoring of the unsaturated zone and recharge areas at INEL to the state of Idaho INEL Oversight Committee

During the early years of the INEL, the USGS conducted extensive studies (sitewide drilling program) of the geology and hydrology of the area collecting varied data over the years. The unsaturated zone has not received much attention until recently. The studies that have been done are a result of problems or concerns arising from liquid radioactive waste disposal. The TRA facility has the most information published about its waste disposal activities. The ICPP has less data about the unsaturated zone due to the fact that most waste water disposal has been to a well. Little is known about the effect of waste water disposal at the NRF on the unsaturated zone. Essentially no information was found about waste disposal activities at other facilities, primarily because there does not appear to be any reported problems associated with waste water disposal at these ...

1992-01-01

438

Advanced organic analysis and analytical methods development: FY 1995 progress report. Waste Tank Organic Safety Program

During the early years of the INEL, the USGS conducted extensive studies (sitewide drilling program) of the geology and hydrology of the area collecting varied data over the years. The unsaturated zone has not received much attention until recently. The studies that have been done are a result of problems or concerns arising from liquid radioactive waste disposal. The TRA facility has the most information published about its waste disposal activities. The ICPP has less data about the unsaturated zone due to the fact that most waste water disposal has been to a well. Little is known about the effect of waste water disposal at the NRF on the unsaturated zone. Essentially no information was found about waste disposal activities at other facilities, primarily because there does not appear to be any reported problems associated with waste water disposal at these ...

1992-12-31

439

Absorption of CO{sub 2}, H{sub 2}, S, and NO using dry FGD wastes

This report describes the work performed during FY 1995 by Pacific Northwest Laboratory in developing and optimizing analysis techniques for identifying organics present in Hanford waste tanks. The main focus was to provide a means for rapidly obtaining the most useful information concerning the organics present in tank waste, with minimal sample handling and with minimal waste generation. One major focus has been to optimize analytical methods for organic speciation. Select methods, such as atmospheric pressure chemical ionization mass spectrometry and matrix-assisted laser desorption/ionization mass spectrometry, were developed to increase the speciation capabilities, while minimizing sample handling. A capillary electrophoresis method was developed to improve separation capabilities while minimizing additional waste generation. In addition, considerable emphasis has been placed on developing a rapid ...

1995-09-01

440

A PC-based software package for modeling DOE mixed-waste management options

Limestone-based sorbents are used extensively in utility boilers and tail-gas desulfurization units to remove sulfur oxides formed during the combustion of fossil fuels. Such units generate {approximately}20 million tons of flue-gas desulfurization (FGD) wastes in the U.S. annually, the bulk of which ({approximately}95%) are discarded in landfills or holding ponds. However, a significant portion of the Ca in these materials is not sulfated (remains as CaO or Ca(OH){sub 2}), particularly in units that generate dry wastes. When hydrated, such wastes exhibit a strong affinity to absorb acid gases at ambient temperature. This study represents a continuation of previously reported CO{sub 2}-absorption studies and includes more recent work on the absorption of H{sub 2}S and NO. Ten FGD-waste samples along with a control fly ash were examined. Absorption capacities, the role of available calcium and particle ...

1996-10-01

1 2 3 4 5 6 7 8 9 10 11 12 13 14 15 16 17 18 19 20 21 22 23 24 25

441

Wastes behavior and environmental impacts, researches and methods; Comportement des dechets et impacts environnementaux, recherches et methodes

The U.S. Department of Energy (DOE) Headquarters and associated contractors have developed an IBM PC-based software package that estimates costs, schedules, and public and occupational health risks for a range of mixed-waste management options. A key application of the software package is the comparison of various waste-treatment options documented in the draft Site Treatment Plans prepared in accordance with the requirements of the Federal Facility Compliance Act of 1992. This automated Systems Analysis Methodology consists of a user interface for configuring complexwide or site-specific waste-management options; calculational algorithms for cost, schedule and risk; and user-selected graphical or tabular output of results. The mixed-waste management activities modeled in the automated Systems Analysis Methodology include waste storage, characterization, handling, transportation, ...

1995-02-01

442

Wastage of stump wood in terms of energy in spruce (Picea smithiana) and silver fir (Abies pindrow) forests

The wastes management policy takes into account more and more often the environmental impacts mastership. This evolution is particularly appreciable when the wastes directly interact with the environment: storage, utilization for roads construction and so on. In this context the ADEME organized the 8 june 2000 a colloquium to present the new evaluation methods and tools, to describe the regulations and to identify the research programs needed for this environmental policy. Eleven papers are presented. (A.L.B.)

2001-07-01

443

Utilisation and disposal of residues (ash, gypsum and granulate) from BEWAG pulverised coal and fluidised bed fired power stations

A study of two forest areas in India investigated how much energy is wasted when high stumps are left after trees are cut to produce wooden boxes for packing the apple harvest. Measurements of the stumps determined the total wood pulp wasted, which was 1191 tons during 1981. The calorific value of the stumps would supply a year's cooking and heating fuels for 747 families of five. Additional fuel is wasted by abandoning the branches and tree tops which are unsuitable for box construction. 5 references, 4 tables.

1984-11-01

444

Use and disposal of large home electronic appliances in Vietnam

Describes the wastes produced and the waste disposal methods used at BEWAG power plants. Wastes covered include fly ash, fluidized bed ash, gypsum from flue gas desulfurization and evaporation residues. Disposal methods include using ashes and gypsum to make building materials. Despite many years of experience in the utilization and disposal of residues from coal-fired power stations BEWAG have not encountered any disposal problems. 5 tabs.

1993-01-01

445

British Library Electronic Table of Contents (United Kingdom)

In this study, e-waste flows of five large home appliances (color televisions, refrigerators, washing machines, personal computers, and air conditioners) in Vietnam are investigated. A social survey was performed to investigate the situation on using appliances in households as well as on the disposal of appliances by the first users. Future quantities of e-waste were estimated using a model that combines use of the Weibull distribution, the logistic function, and the population balance model. It was forecast that about 3.86 million appliances, or 114 000 tons, will be discarded in 2010, and about 17.2 million appliances, or 567 000 tons, in 2025, showing a rapid increase of e-waste in the near future.

2009-01-01

446

Transmission electron microscopy of simulated DWPF high level nuclear waste glasses following gamma irradiation

The influence of plastic materials on the formation of tars in the gasification of urban waste wood

Thermal analysis testing revealed slight weight changes, which were a function of gamma irradiation, in a highly reduced Defense Waste Processing Facility (DWPF) simulated waste glass. Transmission electron microscopy (TEM) was performed on this glass to determine if the weight change corresponded to microstructural variations. TEM analyses showed that no microstructural changes were attributable to gamma irradiation. Exposure of the samples to the electron beam in the TEM did cause changes in the glass microstructures in some cases. These changes were likely due to localized heating of the glass due to interactions with the transmitted electrons.

1994-04-25

447

The development of automatic surface dose-rate measuring and recording system for radioactive waste drum

Gasification experiments were performed using urban waste wood (Altholz) with additions of polymers typical for separately collected waste plastics. The resulting tar product distributions are discussed in this paper. The amount of tars is shown to be a function of operation parameters of the gasifier as well as the fuel. Plastics admixture yields higher concentrations of aromatic tar compounds in the gases, even if the plastic used is not aromatic in its structure. Such mixtures can be gasified for the production of synthesis gas, but clearly a larger effort will be required in cleaning the gases. (author)

2001-03-01

448

Study on the use of zirconium phosphate for radioactive waste treatment

The system which is performed the transportation and measurement of drum automatically to measure the surface dose-rate of radioactive waste drum and can inspect place of contaminated sources and precise dose-rate within a drum according to measuring many places equally at the same time has been developed. It is expected that the system be used to minimized radiation exposure of workers and manage the drum effectively according to established at the production facilities as well as the radioactive waste treatment facilities. (author). 7 refs., 9 tabs., 16 figs.

449

Studies on radioactive liquid waste treatment by reverse osmosis

Zirconium phosphate was one of the earliest inorganic ion-exchange suggested for removing strontium and cesium from aqueous nuclear waste. This paper studied ionic exchange to remove Cs-137 and Sr-90 by using different cationic of zirconium phosphate. In this case the parameters studied were the effect of temperature and ion concentration to percent up take and distribution coefficients. It is also conducted the study on column experiments to determine the breakthrough curves for Cs-137 and Sr-90. The result showed the potential of use of zirconium phosphate in radioactive waste treatment. (author)

1998-12-01

450

Studies on radioactive liquid waste treatment by reverse osmosis

Reverse osmosis is a simple process and has relatively high decontamination factor compared to other processes used for the treatment of radioactive liquid waste. Furthermore the quantity of secondary waste of this process is small. In this study, test solution containing nine elements such as cesium, strontium, cobalt etc. in chloride forms are treated by reverse osmosis. Permeate rate decreases as the increase of osmotic pressure of feed solution and is expressed by linear equation. Decontamination factor of cations of univalency is more than ten, and about one tenth of that of bivalency. Decontamination factors of all the elements used in this experiment are approximately estimated using the solution-diffusion model.

1982-06-01

451

Role of the transport in management of MSW. Part 1.: global balance

Reverse osmosis is a simple process and has relatively high decontamination factor comparing to other processes used for the treatment of radioactive liquid waste. Furthermore the quantity of secondary waste of this process is small. In this study, test solution containing nine elements such as cesium, strontium, cobalt etc. in chloride forms are treated by reverse osmosis. Permeate rate decreases as the increase of osmotic pressure of feed solution and is expressed by linear equation. Decontamination factor of cations of univalency is more than ten, and about one tenth of that of bivalency. Decontamination factors of all the elements used in this experiment are approximately estimated using the solution-diffusion model. (author).

452

Reflections on a future international convention on safety in radioactive waste management - September 1994

An important aspect, which has to be considered in terms of municipal solid waste (MSW) management, is the stage of collection. The emissions generated from these systems can arrive to values that are of the same order of magnitude of emissions from combustion of waste in waste-to-energy plants. The present work faces the problem of transport, from intermediate station to the center of final combustion, placing attention to the emissions from scenarios that has been selected between real systems of management. This analysis can lead to highlight some important elements that can be useful to minimize the impacts.

453

Protocol for the E-Area Low Level Waste Facility Disposal Limits Database

This probably is a suitable moment for work to begin on an international Convention in this area, although it is a difficult task. Generally speaking, the RADWASS (Radioactive Waste Safety Standards) Programme has achieved sufficient consensus, and might serve as an important basis for work in relation to the Convention. The Convention should not go into highly technical details since consensus at this level is more difficult at the present moment, although this will undoubtedly be achieved in the medium term. An important element of the Convention should be the regulation of movements of radioactive wastes at international level. (orig./HP)

1995-12-31

454

Program functionality and information analysis

A database has been developed to contain the disposal limits for the E-Area Low Level Waste Facility (ELLWF). This database originates in the form of an EXCEL{copyright} workbook. The pertinent sheets are translated to PDF format using Adobe ACROBAT{copyright}. The PDF version of the database is accessible from the Solid Waste Division web page on SHRINE. In addition to containing the various disposal unit limits, the database also contains hyperlinks to the original references for all limits. It is anticipated that database will be revised each time there is an addition, deletion or revision of any of the ELLWF radionuclide disposal limits.

2006-01-31

455

Pre-waste-emplacement ground-water travel time sensitivity and uncertainty analyses for Yucca Mountain, Nevada; Yucca Mountain Site Characterization Project

The Office of Civilian Radioactive Waste Management (OCRWM) is executing a plan for improvement of the United States Nuclear Waste Management Program. As part of the plan, OCRWM is performing a systems engineering analysis of both the physical system, i.e., the Nuclear Waste Management System (NWMS), and the programmatic functions that must be accomplished to bring the physical system into being. The functional analysis effort is being performed by two separate teams working in parallel, one of which addresses the physical system functions and the other the programmatic functions. This paper presents information on the analysis of the programmatic functions.

1992-04-01

456

Physical aspects of FGD by-products

Yucca Mountain, Nevada is a potential site for a high-level radioactive-waste repository. Uncertainty and sensitivity analyses were performed to estimate critical factors in the performance of the site with respect to a criterion in terms of pre-waste-emplacement ground-water travel time. The degree of failure in the analytical model to meet the criterion is sensitive to the estimate of fracture porosity in the upper welded unit of the problem domain. Fracture porosity is derived from a number of more fundamental measurements including fracture frequency, fracture orientation, and the moisture-retention characteristic inferred for the fracture domain.

1993-01-01

457

Partitioning and transmutation of nuclear waste: the Dutch RAS programme and its relation to international studies

Air pollution constraints continue to intensify, resulting in solid waste volume increases. An example of this is coal burning power plant flue gas desulfurization by scrubbing. The aqueous suspensions of calcium sulfate hemihydrate or calcium sulfate dihydrate will exceed 200 million tons annually by the year 2000. Disposal of these wastes can have massive environmental effects, due to physical instability and leaching to groundwater. One alternate disposal technique is sulfopozzolanic fixation, converting the FGD waste by addition of fine coal ash and an alkaline earth additive, into a monolithic mass. 6 refs., 17 figs., 3 tabs.

1992-01-01

458

National Low-Level Waste Management Program final summary report of key activities and accomplishments for fiscal year 1996

In the present paper a review of the Dutch RAS programme is presented. The objectives and achievements of the programme are described. Special attention is given to a recent assessment of the international status of P and T that has been made for the Dutch authorities. The major conclusion of this assessment is that P and T is an important instrument in the management of nuclear waste to achieve the technical limits (ALARA) with respect to radiotoxicity of the waste inventory as well as radiological effects of the disposal. The technology for P and T is, however, only partially available at present and recommendations for the directions of the RAS programme are given. (orig.).

1996-08-01

459

How Waste Management Can Be Influenced By Transport Packagings

To assist the Department of Energy (DOE) in fulfilling its responsibilities under the Low-Level Radioactive Waste Policy Amendments Act of 1985, the National Low-Level Waste Management Program (NLLWMP) outlines the key activities tat the NLLWMP will accomplish in the following fiscal year. Additional activities are added during the fiscal year as necessary to accomplish programmatic goals. This report summarizes the activities and accomplishments of the NLLWMP during Fiscal Year 1996.

1996-12-01

460

Gamma Radiation Detectors of the TA-55 Waste Line Monitoring System

With major D&D projects ongoing or being planned, and also with the daily management of radwaste from nuclear facilities, the potential role of transport packagings has often been overlooked: here will one rely essentially on drums, there several local waste processing units are built, elsewhere decommissioned facilities are cut in small bits to fit into small containers by far less efficient. The present paper proposes to illustrate how integrating a transport system from the start may influence operational choices of waste management.

2002-02-28

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461

Fluidized-bed energy technology for biomass conversion

This report covers the gamma detectors, measurement instrumentation, and testing results of a system developed at Los Alamos National Laboratory. This system monitors the process liquid waste streams at the Plutonium Facility (TA-55) for the presence of radioactive contamination. The detectors are at various points on the acid, caustic, and industrial waste lines. Two of the detectors are on the sanitary sewer lines from the facility. A custom interface unit associated with these two detectors furnishes the facility operation center with a notification of the detection of material. All of the detectors furnish measurement information to a central computer system for storage and trending.

1999-06-01

462

Evaluation and compilation of DOE [Department of Energy] waste package test data; Biannual report, February 1988--July 1988

Fluidized bed technology was experimentally evaluated for the combustion and gasification of cotton gin waste. The isothermal bed temperatures in the reactors could be maintained below the ash fusion point of the waste. Raw stripper harvested cotton gin trash could be metered directly into the fluidized-bed reactors indicating that little feed preparation is required. H and CO were the primary products of gasification, and approximately 3200-400 Btu of gas were produced per lb of cotton gin waste. These techniques offer the potential of providing small-scale energy conversion systems for use on farms.

1980-01-01

463

Environmental system analysis of waste management. Experiences from applications of the ORWARE model

This report summarizes evaluations by the National Institute of Standards and Technology (NIST) of Department of Energy (DOE) activities on waste packages designed for containment of radioactive high-level nuclear waste (HLW) for the six month period February 1988 through July 1988. Activities for the DOE Materials Characterization Center are reviewed for the period January 1988 through June 1988. A summary is given of the Yucca Mountain, Nevada disposal site activities. Short discussions relating to the reviewed publications are given and complete reviews and evaluations are included. 20 refs., 1 fig., 1 tab.

1989-10-01

464

Electronic waste management cost: a scenario-based analysis for Greece.

Waste management has gone through a history of shifting problems, demands, and strategies over the years. In contrast to the long prevailing view that the problem could be solved by hiding or moving it, waste is now viewed as a problem ranging from local to global concern, and as being an integral part of several sectors in society. Decisive for this view has been society's increasing complexity and thus the increasing complexity of waste, together with a general development of environmental consciousness, moving from local focus on point emission sources, to regional and global issues of more complex nature. This thesis is about the development and application ORWARE; a model for computer aided environmental systems analysis of municipal waste management. Its origin is the hypothesis that widened perspectives are needed in waste management decision-making to avoid severe ...

2000-11-01

465

Effect of chloride concentration and pH on pitting corrosion of waste package container materials

Waste electrical and electronic equipment (WEEE) is recognized as a priority waste stream internationally, mostly due to their volume and hazardousness. This paper presents an analysis for the quantification of WEEE management cost for Greece, taking into consideration scenarios for reverse logistics network's development and WEEE volume scenarios. Transportation cost, which represents a major cost element for any reverse logistics network, is modelled with the use of mathematical programming, targeting towards the optimization of locations for the development of required intermediate storage infrastructures. Additionally, overall operational cost and recycling fees are estimated. PMID:21242175

2011-01-17

466

Development of a solvent extraction process for cesium removal from SRS tank waste

Electrochemical cyclic potentiodynamic polarization experiments were performed on several candidate waste package container materials to evaluate their susceptibility to pitting corrosion at 90 degrees C in aqueous environments relevant to the potential underground high-level nuclear waste repository. Results indicate that of all the materials tested, Alloy C-22 and Ti Grade-12 exhibited the maximum corrosion resistance, showing no pitting or observable corrosion in any environment tested. Efforts were also made to study the effect of chloride ion concentration and pH on the measured corrosion potential (Ecorr), critical pitting and protection potential values.

1996-12-01

467

Deploying anaerobic digesters: Current status and future possibilities

An alkaline-side solvent extraction process was developed for cesium removal from Savannah River Site (SRS) tank waste. The process was invented at Oak Ridge National Laboratory and developed and tested at Argonne National Laboratory using singlestage and multistage tests in a laboratory-scale centrifugal contactor. The dispersion number, hydraulic performance, stage efficiency, and general operability of the process flowsheet were determined. Based on these tests, further solvent development work was done. The final solvent formulation appears to be an excellent candidate for removing cesium from SRS tank waste.

2001-06-30

468

DECOVALEX - Mathematical models of coupled T-H-M processes for nuclear waste repositories. Executive summary for Phases I,II and III

Unmanaged pollutants from putrescible farm, industrial, and municipal wastes degrade in the environment, and methane emitted from their decomposition may contribute to global climate change. Under modern environmental regulations, these wastes are becoming difficult to dispose of using traditional means. One waste management system, anaerobic digestion or AD, not only provides pollution prevention but can also convert a disposal problem into a new profit center. This report is drawn from a special session of the Second Biomass Conference of the Americas. Selected papers are indexed separately for inclusion in the Energy Science and Technology Database.

1996-01-01

469

Wasting Time: Black Participation in the Combat Arms ...

This executive summary presents the motivation, structure, objectives, methodologies and results of the first stage of the international DECOVALEX project - DECOVALEX I (1992-1995). The acronym stands for Development of Coupled Models and their Validation against Experiment in Nuclear Waste Isolation, and the project is an international effort to develop mathematical models, numerical methods and computer codes for coupled thermo-hydro-mechanical processes in fractured rocks and buffer materials for geological isolation of spent nuclear fuel and other radioactive wastes, and validate them against laboratory and field experiments. 24 refs.

1996-06-01

470

Waste minimization in a non-production oriented metal finishing operation

... after Roscoe Robinson relinquished command of the 82nd Airborne Division in 1978, it would be 25 ... taking command of the 10th Mountain Division. ...

2009-04-15

471

Waste and dust utilisation in shaft furnaces

This paper provides information on activities undertaken in a non- production oriented metal finishing operation to minimize waste and conserve resources. The facility is a 6000 sq foot shop that typically only deals with prototype parts. Utilizing a plan that includes employee awareness, common sense and existing technology, a noticeable reduction in waste volume has been obtained. Initiatives that are covered include: segregation of cyanide plating solutions, elimination of copper cyanide plating, elimination of hexavalent chromium plating, elimination of vapor degreasing, changing of rinsing practices, and changing a process for cleaning of aluminum parts. Some discussion is also presented on the effectiveness of combining the technologies of physical vapor deposition and electrodeposition to help minimize waste. Plans for additional initiatives including water recycling, elimination of cyanide plating and substitution ...

1991-11-01

472

The EPA (Environmental Protection Agency) low-level waste standard-a status report

Wastes and dusts from steel industry, non-ferrous metallurgy and other branches can be utilised e.g. in agglomeration processes (sintering, pelletising or briquetting) and by injection into shaft furnaces. This paper deals with the second way. Combustion and reduction behaviour of iron- and carbon-rich metallurgical dusts and sludges containing lead, zinc and alkali as well as other wastes with and without pulverised coal (PC) has been studied when injecting into shaft furnaces. Following shaft furnaces have been examined: blast furnace, cupola furnace, OxiCup furnace and imperial-smelting furnace. Investigations have been done at laboratory and industrial scale. Some dusts and wastes under certain conditions can be not only reused but can also improve combustion efficiency at the tuyeres as well as furnace performance and productivity.

2005-07-01

473

Terbuthylazine: Reregistration Eligibility Decision (RED)

The Environmental Protection Agency (EPA) is developing generally applicable environmental standards for land disposal of Atomic Energy Act (AEA) low-level radioactive wastes (LLW) and certain naturally occurring and accelerator-produced radioactive material (NARM) wastes. It is EPA's intention that the LLW standards will protect public health and the environment. The LLW standards would cover disposal of all AEA materials not controlled by other EPA standards and some natural radioactive materials. Coverage of federal waste is significant, because the federal government generates and disposes of >40% of all LLW nationwide, and a uniform standard for all LLW disposal is both a desirable and an achievable goal. Publication of a proposed LLW standard is planned in 1988, and a final standard a year later. This standard will have several important and closely related areas of focus which are discussed in the paper.

1988-01-01

474

Selection of melter systems for the DOE/Industrial Center for Waste Vitrification Research

... practically non-toxic to birds. Exposure to birds can occur at ponds, aquaria, and waste water ponds. The typical exposure case ...

1999-03-18

475

Savannah River Technology Center monthly report, January 1994

The EPA has designated vitrification as the best developed available technology for immobilization of High-Level Nuclear Waste. In a recent federal facilities compliance agreement between the EPA, the State of Washington, and the DOE, the DOE agreed to vitrify all of the Low Level Radioactive Waste resulting from processing of High Level Radioactive Waste stored at the Hanford Site. This is expected to result in the requirement of 100 ton per day Low Level Radioactive Waste melters. Thus, there is increased need for the rapid adaptation of commercial melter equipment to DOE`s needs. DOE has needed a facility where commercial pilot scale equipment could be operated on surrogate (non-radioactive) simulations of typical DOE waste streams. The DOE/Industry Center for Vitrification Research (Center) was established in 1992 at the Clemson University Department of Environmental Systems ...

1993-12-31

476

Robotic complex control system with copying manipulator for radioactive waste storage facility

This is the monthly progress report for the Savannah River Technology Center, which covers the following areas of interest, Tritium, Separation processes, Environmental Issues, and Waste Management.

1994-01-01

477

Preliminary performance assessment for the Waste Isolation Pilot Plant, December 1992. Volume 1, Third comparison with 40 CFR 191, Subpart B

... Russian Federation) 978-5-85855-125-6 246 p. ENGINEERING adaptive

478

Permissibility under international law of the disposal of radioactive waste into the sub-seabed. Die voelkerrechtliche Zulaessigkeit des Verbringens radioaktiver Stoffe in den Meeresuntergrund

Before disposing of transuranic radioactive wastes in the Waste Isolation Pilot Plant (WIPP), the United States Department of Energy (DOE) must evaluate compliance with applicable long-term regulations of the United States Environmental Protection Agency (EPA). Sandia National Laboratories is conducting iterative performance assessments of the WIPP for the DOE to provide interim guidance while preparing for final compliance evaluations. This volume contains an overview of WIPP performance assessment and a preliminary comparison with the long-term requirements of the Environmental Radiation Protection Standards for Management and Disposal of Spent Nuclear Fuel, High-Level and Transuranic Radioactive Wastes (40 CFR 191, Subpart B).

1992-12-01

479

Patients receiving maintenance dialysis have more severe functionally significant skeletal muscle wasting than patients with dialysis-independent chronic kidney disease.

The author investigates whether the international law regime so far has developed any legal principles dealing with the problem of the dumping of radioactive waste in the sub-seabed, and whether any of such provisions available adequately tackle the problem in the light of the gravity of danger emanating from radioactive waste. The study covers over 30 different texts of international treaties and protocols. Points of main interest are the London Dumping Convention and the Montego Bay Convention on the Law of the Sea. The author concludes that the disposal of radioactive waste into the seabed belongs to the permissible, although not specially allowed activities within the framework of the freedom of the high seas, and therefore urgently calls for establishing an international regulatory system pertaining to the planning and accomplishment of such activities. An outline legal concept of a regulatory system is explained. ...

1986-01-01

480

PMID:16504974

2006-02-27

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481

Paratuberculosis.

N. Mariana Islands Wildlife Action Plan

Paratuberculosis (Johne's disease) is a chronic, wasting, widespread mycobacteriosis of ruminants. It involves extensive mycobacterial shedding, which accounts for the high contagiousness, and ends...Full Text Available

1994-07-01

482

Modelling the work flow of a nuclear waste management program

... will utilize man-made habitats, including artificial wetlands, waste water ponds, water hazards on golf courses, and an abandoned ... ...

483

Inhibiting pitting corrosion in carbon steel exposed to dilute radioactive waste slurries

In this paper we describe a modelling project to improve a nuclear waste management program in charge of the creation of a new system for the permanent disposal of nuclear waste. SADT (Structural Analysis and Design Technique) is used in order to provide a work-flow description of the functions to be performed by the waste management program. This description is then translated into a number of Coloured Petri Nets (CPN or CP-nets) corresponding to different program functions where additional behavioural inscriptions provide basis for simulation. Each of these CP-nets is simulated to produce timed event charts that are useful for understanding the behaviour of the program functions under different scenarios. Then all the CPN models are linked together to form a single stand-alone application that is useful for validating the interaction and cooperation between the different program functions. A technique for linking ...

1997-03-01

484

Industrial hazardous wastes in Finland - trends related to the waste prevention goal

Dilute caustic high-level radioactive waste slurries can induce pitting corrosion in carbon steel. Cyclic potentiodynamic polarization tests were conducted in simulated and actual waste solutions to determine minimum concentrations of sodium nitrate which inhibit pitting in ASTM A537 class 1 steel exposed to these solutions. Susceptibility to pitting was assessed through microscopic inspection of specimens and inspection of polarization scans. Long-term coupon immersion tests were conducted to verify the nitrite concentrations established by the cyclic potentiodynamic polarization tests. The minimum effective nitrite concentration is expressed as a function of the waste nitrate concentration and temperature.

1991-01-01

485

British Library Electronic Table of Contents (United Kingdom)

The objective of this study was to analyse one of the goals of the latest National Waste Plan of Finland: the relative reduction of hazardous waste (HW) generation by 15% over the period 1992 to 2005.Official statistics and a national database of the annual reports of HW generators were used as one basis for this study. A case study was focused on a selection of HW classes that were considered to be typical to the metal workshop industry. These HW classes were combined to form functional HW groups for the purpose of forming time series. Trends at the company level were studied by performing interviews and by studying the environmental permit documents of about 50 companies.The total amount of HW reported in Finland increased by 133% over the studied period. Meanwhile the GDP of Finland gre...

2008-01-01

486

Independent power plant using wood waste

Immobilization of sodium nitrate waste with polymers: Topical report

A 1 MWe power plant using waste wood fuel is to be installed at a US Marine Corps base, which will supply all wood from a landfill site. The core energy conversion technology is a down-draft gasifier supplying approximately 150 Btu/scf gas to both spark ignition and diesel dual-fuel engine-generator sets. Features of the plant design include: (1) grinding wood fuel from a wide range of waste resources, (2) specialized screening for fines removal, (3) complete tar and other waste product control without landfill disposal, and (4) use of process heat for bulk fuel drying, gasifier air pre-heating, and wastewater evaporation.

1995-08-01

487

Immobilization of sodium nitrate waste with polymers: Topical report

This report describes the development of solidification systems for sodium nitrate waste. Sodium nitrate waste was solidified in the polymers polyethylene, polyester-styrene (PES), and water-extendible polyester-styrene (WEP). Evaluations were made of the properties of waste forms containing various amounts of sodium nitrate by leaching immersion in water, measuring compressive strengths and by the EPA Extraction Procedure. Results of the leaching test are presented as cumulative fraction leached (CFL), incremental leaching rate, and average leaching indices (LI). For waste forms containing 30 to 70 wt% sodium nitrate, the CFL ranged from 9.0 x 10"-"3 to 7.3 x 10"-"1 and the LI from 11 to 7.8. After ninety days immersion in water, the compressive strengths ranged from 720 psi to 2550 psi. The nitrate releases from these samples using the EPA Extraction Procedure were below 500 ppM. The nitrate releases ...

2005-06-01

488

Health and environmental chemistry: Analytical techniques, data management, and quality assurance. Volume 1, Manual

This report describes the development of solidification systems for sodium nitrate waste. Sodium nitrate waste was solidified in the polymers polyethylene, polyester-styrene (PES), and water-extendible polyester-styrene (WEP). Evaluations were made of the properties of waste forms containing various amounts of sodium nitrate by leaching immersion in water, measuring compressive strengths and by the EPA Extraction Procedure. Results of the leaching test are presented as cumulative fraction leached (CFL), incremental leaching rate, and average leaching indices (LI). For waste forms containing 30 to 70 wt% sodium nitrate, the CFL ranged from 9.0 x 10/sup -3/ to 7.3 x 10/sup -1/ and the LI from 11 to 7.8. After ninety days immersion in water, the compressive strengths ranged from 720 psi to 2550 psi. The nitrate releases from these samples using the EPA Extraction Procedure were below 500 ppM. The nitrate ...

1987-04-01

489

Gasification of waste from furniture industries for generation of sustainable energy

Analytical procedures are described for the determination of organic compounds, metals and radioisotopes in environmental materials, human tissues, urine, feces, and waste water.

1993-11-01

490

Functional Consequences of Sarcopenia and Dynapenia in the Elderly

The global interest in renewable energy is attributed to the decline in fossil fuel sources and the need for technical, economic, social and environmental sustainability. This study focused on the new techniques that have been developed for the use of biomass for energy from wood wastes from the forest-based industry. As an energy source, wood waste contributes positively to the environment by reducing environmental problems related to contamination of soil, air and water through improper disposal of waste. Biomass gasification has the advantage of converting biomass into a combustible gas that can be used for heat generation, electricity and synthesis of chemicals. Syngas produced from gasification of eucalyptus residues has significant potential, with an average High Heating Value of 6.60 MJ/m{sup 3}, and regular composition during the process, with predominance of carbon monoxide, followed by hydrogen, carbon dioxide and ...

2010-07-01

491

Detecting hot spots at hazardous-waste sites

Purpose of reviewThe economic burden due to the sequela of sarcopenia (muscle wasting in the elderly) are staggering and rank similarly to the costs...Full Text Available

2010-05-01

492

Evaluating the need for remedial cleanup at a waste site involves both finding the average contaminant concentration and identifying highly contaminated areas, or hot spots. A nomographic procedure to determine the sample configuration needed to locate a hot spot is presented. The technique can be used to develop a waste-site sampling plant - to determine either the grid spacing required to detect a hot spot at a given level of confidence, or the probability of finding a hot spot of a certain size, given a particular grid spacing. The method and computer program (ELIPGRID) were developed for locating geologic deposits, but the basic procedure can also be used to detect hot spots at chemical- or nuclear-waste disposal sites. Nomographs based on the original program are presented for three sampling-grid configurations - square, rectangular and triangular.

1984-07-09

493

Cutting Waste

Comparison of sodium zirconium phosphate-structured HLW forms and synroc for high-level nuclear waste immobilization

market is addressed through a move to a recycling-led area-based franchise model. ...market is addressed through a move to a recycling-led area-based franchise model.

494

Charging systems and PAYT experiences for waste management in Spain

The incorporation of (a) Cs/Sr as simulated heat-generating isotopes contained in Purex reprocessing waste, (b) simulated actinides, and (c) simulated Purex waste in sodium zirconium phosphate (NZP) has been studied. The samples were prepared by sintering, by hot pressing and by hot isostatic pressing in metal bellows containers. The short-term chemical durability of the phosphate-based material containing Purex waste was within an order of magnitude of that for Synroc-C, as measured by 7-day MCC-1 tests at 90{degrees}C. The dissolution behavior showed evidence of re-precipitation phenomena, even after times as short as 28 days. Potential for improvement of NZP-based ceramics for HLW management is discussed. 19 refs., 4 figs., 3 tabs.

1996-12-31

495

British Library Electronic Table of Contents (United Kingdom)

Municipal waste charges in Spain are very widespread, although their application varies significantly among different municipalities. Most commonly, waste charges are implemented as a flat rate, but some of them depend on indicators such as household water consumption, the land area of the property or the value of the real estate. Only one residential pay-as-you-throw scheme has been applied so far. It was a pay-per-bag scheme implemented in Torrelles de Llobregat, Barcelona. A number of other systems focussing only on commercial waste have been implemented in Spain. Several factors suggest that new pay-as-you-throw schemes will be adopted in the near future. In 2000 no municipalities had door-to-door collection schemes; since then over 70 municipalities have implemented them. In addition ...

2008-01-01

496

A Research Needs Assessment for waste plastics recycling: Volume 2, Project report. Final report