Energetic materials standards – Chemical compatibility

NARCIS (Netherlands)

Tuukkanen, I.M.; Bouma, R.H.B.

2014-01-01

Subgroup A Energetic Materials Team, SG/A (EMT), develops and maintains standards that are relevant to all life-cycle phases of ammunition/weapon systems. STANAG 4147 is the standard regarding chemical compatibility of explosives with munition components, and is a document of prime importance.

Reuse of materials from recyclable-waste collection for road building

International Nuclear Information System (INIS)

Messineo, A.; Panno, D.; Ticali, D.

2006-01-01

A right policy of waste management should look to nature: in fact in nature nothing of produced is lost; everything could be considered food to energy resource for another subject. A diffusion of right policy of waste reuse is the leit motive of this study. Heavy problem of pollution and the protection of the natural environment, is the one of the most important problem of this society, and so to think waste to reuse for civil engineering research has a double aim: a) to reduce quantity to send to dump; b) to reuse good materials for civil engineering building, as substitute of natural aggregate. It look very innovative and actual to think to possibility of reuse glass from recyclable-waste collection for road building, and so we could consider road as a valid substitute to dump. The aim is to consider waste as an element with high energetic power and value added [it

Ultrafast Vibrational Spectrometer for Engineered Nanometric Energetic Materials

National Research Council Canada - National Science Library

Dlott, Dana

2002-01-01

The proposer requested funding for laser equipment that would be used to study engineered nanometric energetic materials consisting of nanometer metal particles, passivation layers and oxidizing binders...

Chemical rocket propulsion a comprehensive survey of energetic materials

CERN Document Server

Shimada, Toru; Sinditskii, Valery; Calabro, Max

2017-01-01

Developed and expanded from the work presented at the New Energetic Materials and Propulsion Techniques for Space Exploration workshop in June 2014, this book contains new scientific results, up-to-date reviews, and inspiring perspectives in a number of areas related to the energetic aspects of chemical rocket propulsion. This collection covers the entire life of energetic materials from their conceptual formulation to practical manufacturing; it includes coverage of theoretical and experimental ballistics, performance properties, as well as laboratory-scale and full system-scale, handling, hazards, environment, ageing, and disposal. Chemical Rocket Propulsion is a unique work, where a selection of accomplished experts from the pioneering era of space propulsion and current technologists from the most advanced international laboratories discuss the future of chemical rocket propulsion for access to, and exploration of, space. It will be of interest to both postgraduate and final-year undergraduate students in...

Co-combustion of waste materials using fluidized bed technology

Energy Technology Data Exchange (ETDEWEB)

M. Lopes; I. Gulyurtlu; P. Abelha; T. Crujeira; D. Boavida; I. Cabrita [INETI-DEECA, Lisbon (Portugal)

2004-07-01

There is growing interest in using renewable fuels in order to sustain the CO{sub 2} accumulation. Several waste materials can be used as coal substitutes as long as they contain significant combustible matter, as for example MSW and sewage sludge. Besides the outcome of the energetic valorization of such materials, combustion must be regarded as a pre-treatment process, contributing to the safe management of wastes. Landfilling is an expensive management option and requires a previous destruction of the organic matter present in residues, since its degradation generates greenhouse gases and produces acidic organic leachates. Fluidized bed combustion is a promising technology for the use of mixtures of coal and combustible wastes. This paper presents INETI's experience in the co-combustion of coal with this kind of residues performed in a pilot fluidized bed. Both the RDF (from MSW and sewage sludge) and sewage sludge combustion problems were addressed, relating the gaseous emissions, the behaviour of metals and the leachability of ashes and a comparison was made between co-combustion and mono-combustion in order to verify the influence of the utilization of coal. 9 refs., 1 fig., 3 tabs.

Stabilized super-thermite colloids: A new generation of advanced highly energetic materials

Science.gov (United States)

Elbasuney, Sherif; Gaber Zaky, M.; Radwan, Mostafa; Mostafa, Sherif F.

2017-10-01

One of the great impetus of nanotechnology on energetic materials is the achievement of nanothermites (metal-oxide/metal) which are characterized by massive heat output. Yet, full exploitation of super-thermites in highly energetic systems has not been achieved. This manuscript reports on the sustainable fabrication of colloidal Fe2O3 and CuO nanoparticles for thermite applications. TEM micrographs demonstrated mono-dispersed Fe2O3 and CuO with an average particle size of 3 and 15 nm respectively. XRD diffractograms demonstrated highly crystalline materials. SEM micrographs demonstrated a great tendency of the developed oxides to aggregate over drying process. The effective integration and dispersion of mono-dispersed colloidal thermite particles into energetic systems are vital for enhanced performance. Aluminum is of interest as highly energetic metal fuel. In this paper, synthesized Fe2O3 and CuO nanoparticles were re-dispersed in isopropyl alcohol (IPA) with aluminum nanoparticles using ultrasonic prope homogenizer. The colloidal thermite peraticles can be intgegrated into highly energetic system for subsequent nanocomposite development. Thanks to stabilization of colloidal CuO nanoparticles in IPA which could offer intimate mixing between oxidizer and metal fuel. The stabilization mechanism of CuO in IPA was correlated to steric stabilization with solvent molecules. This approach eliminated nanoparticle drying and the re-dispersion of dry aggregates into energetic materials. This manuscript shaded the light on the real development of colloidal thermite mixtures and their integration into highly energetic systems.

Report for MaRIE Drivers Workshop on needs for energetic material's studies.

Energy Technology Data Exchange (ETDEWEB)

Specht, Paul Elliott [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States)

2018-01-01

Energetic materials (i.e. explosives, propellants, and pyrotechnics) have complex mesoscale features that influence their dynamic response. Direct measurement of the complex mechanical, thermal, and chemical response of energetic materials is critical for improving computational models and enabling predictive capabilities. Many of the physical phenomena of interest in energetic materials cover time and length scales spanning several orders of magnitude. Examples include chemical interactions in the reaction zone, the distribution and evolution of temperature fields, mesoscale deformation in heterogeneous systems, and phase transitions. This is particularly true for spontaneous phenomena, like thermal cook-off. The ability for MaRIE to capture multiple length scales and stochastic phenomena can significantly advance our understanding of energetic materials and yield more realistic, predictive models.

Climate protection, natural resources management and soil improvement by combined Energetic and Material Utilization of lignocellulosic agricultural WAstes and residues (CEMUWA); Klimaschutz, Naturressourcenschutz und Bodenverbesserung durch kombinierte energetische und stoffliche Verwertung lignozelluloser landwirtschaftlicher Abfaelle und Reststoffe

Energy Technology Data Exchange (ETDEWEB)

Schuech, Andrea; Nelles, Michael; Tscherpel, Burckhard; El Behery, Ahmed; Menanz, Rania; Bahl, Hubert; Scheel, Michael; Nipkow, Mareen

2015-07-01

The project Climate protection, natural resources management and soil improvement by combined Energetic and Material Utilization of lignocellulosic agricultural WAstes and residues (CEMUWA) was implemented with long-term partners from Egypt and Germany leaded by the Department Waste Management and Material Flow from September 2011 until October 2013. Aim of the project was the development of technologies for the utilization of agricultural wastes and residues at the example of rice straw, with the focus on the energetic and material use. In the long term a contribution to climate protection and natural resource management could be reached. The focus was on investigations in the field of biogas, ethanol and butanol production including pretreatment as well as the material use in horticulture. The results show that the biogas and ethanol production with adapted pretreatments of rice straws is possible. The technical adaptation of a biogas plant (eo-digestion) would be associated with about 20% higher investment costs and higher operating costs with an approximately 15% higher energy demand. In Germany, however, this may still economically by the substitution of expensive or difficult available energy crops (reduction of substrate costs by 30 to 35% for a 600 kWel-BGP using maize silage). The investigated solutions for material use in Egypt showed good results, which in some cases exceeded the expectations. By the use of rice straw imported peat substrates could be substitute or irrigation water saved, what is ecologically and economically useful. The production of ethanol from rice straw was implemented on laboratory scale and preconditions for investigations in semi-industrial and partly pilot scale were created. The bilateral project'' was funded in the framework of the German-Egypt-Research-Fond (GERF) by the German Federal Ministry of Education and Research (BMBF) and the Egyptian Science and Technology Development Fund in Egypt (STDF). The total budget

Flexible energetic materials and related methods

Energy Technology Data Exchange (ETDEWEB)

Heaps, Ronald J.

2018-03-06

Energetic compositions and methods of forming components from the compositions are provided. In one embodiment, a composition includes aluminum, molybdenum trioxide, potassium perchlorate, and a binder. In one embodiment, the binder may include a silicone material. The materials may be mixed with a solvent, such as xylene, de-aired, shaped and cured to provide a self-supporting structure. In one embodiment, one or more reinforcement members may be added to provide additional strength to the structure. For example, a weave or mat of carbon fiber material may be added to the mixture prior to curing. In one embodiment, blade casting techniques may be used to form a structure. In another embodiment, a structure may be formed using 3-dimensional printing techniques.

Material stream management of biomass wastes for the optimization of organic wastes utilization; Stoffstrommanagement von Biomasseabfaellen mit dem Ziel der Optimierung der Verwertung organischer Abfaelle

Energy Technology Data Exchange (ETDEWEB)

Knappe, Florian; Boess, Andreas; Fehrenbach, Horst; Giegrich, Juergen; Vogt, Regine [ifeu-Institut fuer Energie- und Umweltforschung GmbH, Heidelberg (Germany); Dehoust, Guenter; Schueler, Doris; Wiegmann, Kirsten; Fritsche, Uwe [Oeko-Institut, Inst. fuer Angewandte Oekologie, Darmstadt (Germany)

2007-02-15

The effective use of the valuable substances found in waste materials can make an important contribution to climate protection and the conservation of fossil and mineral resources. In order to harness the potential contribution of biomass waste streams, it is necessary to consider the potential of the waste in connection with that of the total biomass. In this project, relevant biogenous material streams in the forestry, the agriculture as well as in several industries are studied, and their optimization potentials are illustrated. Scenarios are then developed, while taking various other environmental impacts into considerations, to explore possible optimized utilization of biomass streams and biomass waste substances for the future. Straw that is not needed for humus production and currently left on the field can be used for its energy content. The realisation of this potential would be significant contribution towards climate protection. The energetic use of liquid manure without negatively influencing its application as commercial fertilizer can also be similarly successful because of its large volume. The results of our study also support an increased energetic use of saw residues as fuel (in form of pellets) in small furnaces. For household organic wastes, the report suggests the fermentation with optimized energy use and intensified marketing of the aerobically treated compost as peat substitution. While for waste cooking fat that is currently disposed in the residual waste, a separate collection and direct use in motors that are used as combined heat and power generation are recommended. For meat and bone meal and communal sludge that are not being used substantial currently or in the future, phosphorus can be recovered with promising success from the ash produced when the waste is burnt in mono incinerators. These technical options should however be tested against disposal standard. (orig.)

Exergo-economic analysis of biogas production from residual and waste materials for use in energy conversion plants; Exergooekonomische Analyse der Biogaserzeugung aus Rest- und Abfallstoffen fuer den Einsatz in Energieumwandlungsanlagen

Energy Technology Data Exchange (ETDEWEB)

Nagel, Janet [Beuth Hochschule fuer Technik Berlin (Germany)

2015-07-01

Biogenic residual and waste materials are subject to fundamentally different conditions than other renewable resources. Also the purposes for their use in conversion plants are different. Whereas the use of renewable energies in energy conversions plants serves to produce power and heat, biogenic residual and waste materials are primarily focused to be disposed. Considering the sustainable philosophy ''cradle to cradle'' an additional use for these input materials is gaining interest. Energy and exergy balances show that plant and process concepts have a great influence on the energetic conversion. Especially by looking at an exergy-analysis an overall assessment is made based on the working part of the product like power or heat. If economic factors are added, local, regional, and supra-regional influences can be observed and a comprehensive overview of the optimal energetic and economic use of the input materials can be given. A decision which concept of converting biogenic residual and waste materials is to be preferred cannot be made yet. Furthermore, additional ecologic/energetic, economic, and social factors should be taken into account. These factors could be included into the exergoeconomic analysis using a scoring system with economic values.

Waste Material Management: Energy and materials for industry

Energy Technology Data Exchange (ETDEWEB)

1993-05-01

This booklet describes DOE`s Waste Material Management (WMM) programs, which are designed to help tap the potential of waste materials. Four programs are described in general terms: Industrial Waste Reduction, Waste Utilization and Conversion, Energy from Municipal Waste, and Solar Industrial Applications.

Energetic use of the urban solid wastes (waste-to-energy); Aproveitamento energetico de residuos solidos urbanos (waste-to-energy)

Energy Technology Data Exchange (ETDEWEB)

Dodde, Paula Arrais Moreira; Fonseca, Zilton Jose Sa da [Universidade Federal do Rio de Janeiro (PPE/COPPE/UFRJ), RJ (Brazil). Coordenacao dos Programas de Pos-Graduacao de Engenharia. Programa de Planejamento Energetico], Emails: pauladodde@yahoo.com.br, ziltonfonseca@ig.com.br

2010-07-01

This paper approaches the advantages and disadvantages of energetic using of biomass present in the garbage (the urban solid residue is composed by average 65% of organic material)This paper effluents technologically.

Energetic and exergetic analysis of waste heat recovery systems in the cement industry

International Nuclear Information System (INIS)

Karellas, S.; Leontaritis, A.-D.; Panousis, G.; Bellos, E.; Kakaras, E.

2013-01-01

In a typical cement producing procedure, 25% of the total energy used is electricity and 75% is thermal energy. However, the process is characterized by significant heat losses mainly by the flue gases and the ambient air stream used for cooling down the clinker (about 35%–40% of the process heat loss). Approximately 26% of the heat input to the system is lost due to dust, clinker discharge, radiation and convection losses from the kiln and the preheaters. A heat recovery system could be used to increase the efficiency of the cement plant and thus contribute to emissions decrease. The aim of this paper is to examine and compare energetically and exergetically, two different WHR (waste heat recovery) methods: a water-steam Rankine cycle, and an Organic Rankine Cycle (ORC). A parametric study proved that the water steam technology is more efficient than ORC in exhaust gases temperature higher than 310 °C. Finally a brief economic assessment of the most efficient solution was implemented. WHR installations in cement industry can contribute significantly in the reduction of the electrical consumptions operating cost thus being a very attractive investment with a payback period up to 5 years. - Highlights: • This paper presents waste heat recovery as a way to gain energy from the exhaust gases in a cement plant. • Water steam cycle and ORC has been analyzed for waste heat recovery. • The energetic and exergetic evaluation of the two waste heat recovery processes is presented and compared

Computational Chemistry Toolkit for Energetic Materials Design

Science.gov (United States)

2006-11-01

industry are aggressively engaged in efforts to develop multiscale modeling and simulation methodologies to model and analyze complex phenomena across...energetic materials design. It is hoped that this toolkit will evolve into a collection of well-integrated multiscale modeling methodologies...Experimenta Theoreticala This Work 1-5-Diamino-4- methyl- tetrazolium nitrate 8.4 41.7 47.5 1-5-Diamino-4- methyl- tetrazolium azide 138.1 161.6

Probing the Dynamics of Ultra-Fast Condensed State Reactions in Energetic Materials

Science.gov (United States)

Piekiel, Nicholas William

2012-01-01

Energetic materials (EMs) are substances with a high amount of stored energy and the ability to release that energy at a rapid rate. Nanothermites and green organic energetics are two classes of EMs which have gained significant interest as they each have desirable properties over traditional explosives. These systems also possess downfalls, which…

Synthesis and evaluation of energetic materials

Science.gov (United States)

Santhosh, G.

Over the years new generations of propellants and explosives are being developed. High performance and pollution prevention issues have become the subject of interest in recent years. Desired properties of these materials are a halogen-free, nitrogen and oxygen rich molecular composition with high density and a positive heat of formation. The dinitramide anion is a new oxy anion of nitrogen and forms salts with variety of metal, organic and inorganic cations. Particular interest is in ammonium dinitramide (ADN, NH4N(NO 2)2) which is a potentially useful energetic oxidizer. ADN is considered as one of the most promising substitutes for ammonium perchlorate (AP, NH4ClO4) in currently used composite propellants. It is unique among energetic materials in that it has no carbon or chlorine; its combustion products are not detrimental to the atmosphere. Unquestionable advantage of ADN over AP is the significant improvement in the performance of solid rocket motors by 5-15%. The present thesis is centered on the experimental results along with discussion of some of the most pertinent aspects related to the synthesis and characterization of few dinitramide salts. The chemistry, mechanism and kinetics of the formation of dinitramide salts by nitration of deactivated amines are investigated. The evaluation of the thermal and spectral properties along with the adsorption and thermal decomposition characteristics of the dinitramide salts are also explored in this thesis.

Ultrafast Vibrational Spectrometer for Engineered Nanometric Energetic Materials

National Research Council Canada - National Science Library

Dlott, Dana

2002-01-01

.... The needed equipment was ordered and installed, and assembled into a working SFG set up that has been tested on a model system consisting of a self assembled monolayer of alkane on gold. The next step will be to finish integrating the carbon dioxide laser system and to begin looking at aluminum based energetic materials.

New fluidized bed reactor for coating of energetic materials

NARCIS (Netherlands)

Abadjieva, E.; Huijser, T.; Creyghton, Y.L.M.; Heijden, A.E.D.M. van der

2009-01-01

The process of altering and changing the properties of the energetic materials by coating has been studied extensively by several scientific groups. According to the desired application different coating techniques have been developed and applied to achieve satisfactory results. Among the already

Organic tank safety project: Preliminary results of energetics and thermal behavior studies of model organic nitrate and/or nitrite mixtures and a simulated organic waste

International Nuclear Information System (INIS)

Scheele, R.D.; Sell, R.L.; Sobolik, J.L.; Burger, L.L.

1995-08-01

As a result of years of production and recovery of nuclear defense materials and subsequent waste management at the Hanford Site, organic-bearing radioactive high-level wastes (HLW) are currently stored in large (up to 3. ML) single-shell storage tanks (SSTs). Because these wastes contain both fuels (organics) and the oxidants nitrate and nitrite, rapid energetic reactions at certain conditions could occur. In support of Westinghouse Hanford Company's (WHC) efforts to ensure continued safe storage of these organic- and oxidant-bearing wastes and to define the conditions necessary for reactions to occur, we measured the thermal sensitivities and thermochemical and thermokinetic properties of mixtures of selected organics and sodium nitrate and/or nitrite and a simulated Hanford organic-bearing waste using thermoanalytical technologies. These thermoanalytical technologies are used by chemical reactivity hazards evaluation organizations within the chemical industry to assess chemical reaction hazards

Organic tank safety project: Preliminary results of energetics and thermal behavior studies of model organic nitrate and/or nitrite mixtures and a simulated organic waste

Energy Technology Data Exchange (ETDEWEB)

Scheele, R.D.; Sell, R.L.; Sobolik, J.L.; Burger, L.L.

1995-08-01

As a result of years of production and recovery of nuclear defense materials and subsequent waste management at the Hanford Site, organic-bearing radioactive high-level wastes (HLW) are currently stored in large (up to 3. ML) single-shell storage tanks (SSTs). Because these wastes contain both fuels (organics) and the oxidants nitrate and nitrite, rapid energetic reactions at certain conditions could occur. In support of Westinghouse Hanford Company`s (WHC) efforts to ensure continued safe storage of these organic- and oxidant-bearing wastes and to define the conditions necessary for reactions to occur, we measured the thermal sensitivities and thermochemical and thermokinetic properties of mixtures of selected organics and sodium nitrate and/or nitrite and a simulated Hanford organic-bearing waste using thermoanalytical technologies. These thermoanalytical technologies are used by chemical reactivity hazards evaluation organizations within the chemical industry to assess chemical reaction hazards.

Study of thermal sensitivity and thermal explosion violence of energetic materials in the LLNL ODTX system

International Nuclear Information System (INIS)

Hsu, P C; Hust, G; Zhang, M X; Lorenz, T K; Reynolds, J G; Fried, L; Springer, H K; Maienschein, J L

2014-01-01

Incidents caused by fire and combat operations can heat energetic materials that may lead to thermal explosion and result in structural damage and casualty. Some explosives may thermally explode at fairly low temperatures (< 100 °C) and the violence from thermal explosion may cause significant damage. Thus it is important to understand the response of energetic materials to thermal insults. The One Dimensional Time to Explosion (ODTX) system at the Lawrence Livermore National Laboratory has been used for decades to measure times to explosion, threshold thermal explosion temperature, and determine kinetic parameters of energetic materials. Samples of different configurations (pressed part, powder, paste, and liquid) can be tested in the system. The ODTX testing can also provide useful data for assessing the thermal explosion violence of energetic materials. Recent ODTX experimental data are reported in the paper.

Potential for the energetic use of waste gas in Flanders; Potentieel voor het energetisch gebruik van stortgassen in Vlaanderen

Energy Technology Data Exchange (ETDEWEB)

De Spiegeleer, E. [Vlaamse Instelling voor Technologisch Onderzoek, Mol (Belgium)

1999-03-01

The department of Natural Resources and Energy of the Ministry of the Flemish Community wanted to know the stand of affairs of the use of waste gas on the Flemish landfills in 1998. On the basis of a multi-phase model for waste gas production (according Dutch model) and data provided by the operators, the waste gas potential could be calculated for each landfill. The total waste gas production in Flanders is estimated at 75 million m3 in 1999. This brings the extracting amount of waste gas at 60 million m3 (in optimal circumstances, extracting efficiency 80%). Because the activities will continue for some years on categorie2 landfills, the waste gas production will increase. But the global waste gas potential will decrease as an effect of the evolution in the composition (less organic material) and the amount of waste that will be dumped, plus the landfills will be closed gradually. The possible savings of primary energy and the reduced CO2-emissions by the energetic apply of the global waste potential in Flanders is being estimated at about 695.000 GJ or 63.000 ton CO2. The generation of electricity with the help of a gas engine-generator unit is from technical and economical point of view the most achievable option for the operators. The price of the delivered energy is decisive for the cost-effectiveness of concrete investment projects. Only subsidies of the government makes the pay-back time for waste gas projects acceptable.

Energy from biogenic wastes and residual materials. Potentials, perspectives and examples; Energie aus biogenen Abfaellen und Reststoffen. Potenziale, Perspektiven und Beispiele

Energy Technology Data Exchange (ETDEWEB)

Nelles, Michael [Rostock Univ. (Germany). Lehrstuhl Abfall- und Stoffstromwirtschaft; Deutsches Biomasseforschungszentrum gemeinnuetzige GmbH (DBFZ) Leipzig (Germany); Morscheck, Gert; Schuech, Andrea; Scholwin, Frank [Rostock Univ. (Germany). Lehrstuhl Abfall- und Stoffstromwirtschaft

2013-10-01

One of the most important global tasks in the future is to secure a sustainable supply of raw material and energy, which must be economically, ecologically and socially acceptable. In both fields - energy and raw material - the waste management can contribute a substantial share. In particular, the positive environmental effects of waste recycling have been shown by numerous scientific studies. Waste management in Germany has achieved a high level of development and already makes significant contributions to sustainability. Here in Germany the waste management contributes significantly to climate protection, whereas in many developing and emerging countries about 10 to 15 percent of the greenhouse gas emissions results from waste handling processes. The previous success of the German waste management according to the climate protection goals primarily results from the recycling and energetic utilization of the biogenic waste and residues, whereby in this field still exists potential for further development and optimization, which must be used in the next years. (orig.)

Use of energetic ion beams in materials synthesis and processing

International Nuclear Information System (INIS)

Appleton, B.R.

1992-01-01

A brief review of the use energetic ion beams and related techniques for the synthesis, processing, and characterization of materials is presented. Selected opportunity areas are emphasized with examples, and references are provided for more extensive coverage. (author)

Enhancing Reactivity in Structural Energetic Materials

Science.gov (United States)

Glumac, Nick

2017-06-01

In many structural energetic materials, only a small fraction of the metal oxidizes, and yet this provides a significant boost in the overall energy release of the system. Different methodologies to enhance this reactivity include alloying and geometric modifications of microstructure of the reactive material (RM). In this presentation, we present the results of several years of systematic study of both chemical (alloy) and mechanical (geometry) effects on reactivity for systems with typical charge to case mass ratios. Alloys of aluminum with magnesium and lithium are considered, as these are common alloys in aerospace applications. In terms of geometric modifications, we consider surface texturing, inclusion of dense additives, and inclusion of voids. In all modifications, a measurable influence on output is observed, and this influence is related to the fragment size distribution measured from the observed residue. Support from DTRA is gratefully acknowledged.

Radioactive waste material melter apparatus

Science.gov (United States)

Newman, D.F.; Ross, W.A.

1990-04-24

An apparatus for preparing metallic radioactive waste material for storage is disclosed. The radioactive waste material is placed in a radiation shielded enclosure. The waste material is then melted with a plasma torch and cast into a plurality of successive horizontal layers in a mold to form a radioactive ingot in the shape of a spent nuclear fuel rod storage canister. The apparatus comprises a radiation shielded enclosure having an opening adapted for receiving a conventional transfer cask within which radioactive waste material is transferred to the apparatus. A plasma torch is mounted within the enclosure. A mold is also received within the enclosure for receiving the melted waste material and cooling it to form an ingot. The enclosure is preferably constructed in at least two parts to enable easy transport of the apparatus from one nuclear site to another. 8 figs.

Radioactive waste material melter apparatus

International Nuclear Information System (INIS)

Newman, D.F.; Ross, W.A.

1990-01-01

An apparatus for preparing metallic radioactive waste material for storage is disclosed. The radioactive waste material is placed in a radiation shielded enclosure. The waste material is then melted with a plasma torch and cast into a plurality of successive horizontal layers in a mold to form a radioactive ingot in the shape of a spent nuclear fuel rod storage canister. The apparatus comprises a radiation shielded enclosure having an opening adapted for receiving a conventional transfer cask within which radioactive waste material is transferred to the apparatus. A plasma torch is mounted within the enclosure. A mold is also received within the enclosure for receiving the melted waste material and cooling it to form an ingot. The enclosure is preferably constructed in at least two parts to enable easy transport of the apparatus from one nuclear site to another. 8 figs

Laser-shocked energetic materials with metal additives: evaluation of detonation performance

Science.gov (United States)

Gottfried, Jennifer; Bukowski, Eric

A focused, nanosecond-pulsed laser with sufficient energy to exceed the breakdown threshold of a material generates a laser-induced plasma with high peak temperatures, pressures, and shock velocities. Depending on the laser parameters and material properties, nanograms to micrograms of material is ablated, atomized, ionized and excited in the laser-induced plasma. The subsequent shock wave expansion into the air above the sample has been monitored using high-speed schlieren imaging in a recently developed technique, laser-induced air shock from energetic materials (LASEM). The estimated detonation velocities using LASEM agree well with published experimental values. A comparison of the measured shock velocities for various energetic materials including RDX, DNTF, and LLM-172 doped with Al or B to the detonation velocities predicted by CHEETAH for inert or active metal participation demonstrates that LASEM has potential for predicting the early time participation of metal additives in detonation events. The LASEM results show that reducing the amount of hydrogen present in B formulations increases the resulting detonation velocities

Synergistic and alkaline stability studies of mixtures of simulated high level waste sludge with selected energetic compounds

International Nuclear Information System (INIS)

Fondeur, F.F.

2000-01-01

This study examined the stability of mercury oxalate and mercury fulminate in alkaline sludge simulating Savannah River Site waste. These compounds represent two classes of energetic compounds previously speculated as potential components in sludge stored without a supernatant liquid

2007 Insensitive Munitions and Energetic Materials Technology Symposium

Science.gov (United States)

2007-10-18

Assessment – EIPT chair rotates each calendar year between NAVAIR and NAVSEA Page 9 Networks for collaboration Technology Oriented: Energetic Materials...Analysis IM Explosive Fill for 120mm and/or 155mm Arena Test & Qualificationr t lifi ti Must Show Improvement Review of Filter 1 Data for 3...Arena Test & Qualificationr t lifi ti Must Show Improvement PM-CAS Common Low-cost IM Explosives Program “Funnel” framework to progressively screen

Consideration of the energetic use of waste wood versus re-use of materials

International Nuclear Information System (INIS)

Bergsma, G.C.; Sas, H.

1997-01-01

Recycling of wood wastes to chipboard is compared with the combustion of waste wood in combination with high-efficient energy recovery. Both options show much better environmental effects than the disposal of wood wastes. The differences between the environmental effects of the first two options can be neglected. The reprocessing of wood wastes to chipboard results in a decrease of the production of gypsum board. That benefit is equal to the benefit of cocombustion of wood wastes in a coal-fired power plant, i.e. saving coal. 18 refs

Sensitivity Characterization of Pressed Energetic Materials using Flyer Plate Mesoscale Simulations

Science.gov (United States)

Rai, Nirmal; Udaykumar, H. S.

Heterogeneous energetic materials like pressed explosives have complicated microstructure and contain various forms of heterogeneities such as pores, micro-cracks, energetic crystals etc. It is widely accepted that the presence of these heterogeneities can affect the sensitivity of these materials under shock load. The interaction of shock load with the microstructural heterogeneities may leads to the formation of local heated regions known as ``hot spots''. Chemical reaction may trigger at the hot spot regions depending on the hot spot temperature and the duration over which the temperature can be maintained before phenomenon like heat conduction, rarefaction waves withdraws energy from it. There are different mechanisms which can lead to the formation of hot spots including void collapse. The current work is focused towards the sensitivity characterization of two HMX based pressed energetic materials using flyer plate mesoscale simulations. The aim of the current work is to develop mesoscale numerical framework which can perform simulations by replicating the laboratory based flyer plate experiments. The current numerical framework uses an image processing approach to represent the microstructural heterogeneities incorporated in a massively parallel Eulerian code SCIMITAR3D. The chemical decomposition of HMX is modeled using Henson-Smilowitz reaction mechanism. The sensitivity characterization is aimed towards obtaining James initiation threshold curve and comparing it with the experimental results.

Theoretical Studies of Small-System Thermodynamics in Energetic Materials

Science.gov (United States)

2016-01-06

SECURITY CLASSIFICATION OF: This is a comprehensive theoretical research program to investigate the fundamental principles of small-system thermodynamics ...a.k.a. nanothermodynamics). The proposed work is motivated by our desire to better understand the fundamental dynamics and thermodynamics of...for Public Release; Distribution Unlimited Final Report: Theoretical Studies of Small-System Thermodynamics in Energetic Materials The views, opinions

Effects of void anisotropy on the ignition and growth rates of energetic materials

Science.gov (United States)

Rai, Nirmal Kumar; Sen, Oishik; Udaykumar, H. S.

2017-06-01

Initiation of heterogeneous energetic materials is thought to occur at hot spots; reaction fronts propagate from sites of such hot spots into the surrounding material resulting in complete consumption of the material. Heterogeneous materials, such as plastic bonded explosives (PBXs) and pressed materials contain numerous voids, defects and interfaces at which hot spots can occur. Amongst the various mechanisms of hot spot formation, void collapse is considered to be the predominant one in the high strain rate loading conditions. It is established in the past the shape of the voids has a significant effect on the initiation behavior of energetic materials. In particular, void aspect ratio and orientations play an important role in this regard. This work aims to quantify the effects of void aspect ratio and orientation on the ignition and growth rates of chemical reaction from the hot spot. A wide range of aspect ratio and orientations is considered to establish a correlation between the ignition and growth rates and the void morphology. The ignition and growth rates are obtained from high fidelity reactive meso-scale simulations. The energetic material considered in this work is HMX and Tarver McGuire HMX decomposition model is considered to capture the reaction mechanism of HMX. The meso-scale simulations are performed using a Cartesian grid based Eulerian solver SCIMITAR3D. The void morphology is shown to have a significant effect on the ignition and growth rates of HMX.

Ecological, energetic and economical comparison of fermentation, composting and incineration of solid biogenic waste materials; Oekologischer, energetischer und oekonomischer Vergleich von Vergaerung, Kompostierung und Verbrennung fester biogener Abfallstoffe

Energy Technology Data Exchange (ETDEWEB)

Edelmann, W. [Arbeitsgemeinschaft Bioenergie GmbH, Arbi, Baar (Switzerland); Schleiss, K. [Umwelt- und Kompostberatung Schleiss, Baar (Switzerland)

2001-07-01

This study compares different technologies for the treatment of biogenic wastes, including open windrow and enclosed tunnel composting, anaerobic digestion, the combination of both these methods and burning in waste incineration plants. The methods are compared from the points of view of environmental impact, energy use and production, and economics. The environmental impact, calculated for normalised quantities of waste using the 'Ecoindicator 95+' tool, are discussed and the methane and carbon dioxide emissions of the different methods of treatment are compared. Also, the considerable differences to be found in the energy balances of the different systems are discussed in the light of efforts to substitute nuclear and fossil-fuel generated power. Cost and energetic comparisons are also made between compost and artificial fertilisers. The report is concluded with recommendations for adapting bio-technological methods for the treatment of wastes with an emphasis on anaerobic processes.

Sustainable Materials Management: Non-Hazardous Materials and Waste Management Hierarchy

Science.gov (United States)

EPA developed the non-hazardous materials and waste management hierarchy in recognition that no single waste management approach is suitable for managing all materials and waste streams in all circumstances.

The quest for greater chemical energy storage in energetic materials: Grounding expectations

Science.gov (United States)

Lindsay, C. Michael; Fajardo, Mario E.

2017-01-01

It is well known that the performance of modern energetic materials based on organic chemistry has plateaued, with only ˜ 40% improvements realized over the past half century. This fact has stimulated research on alternative chemical energy storage schemes in various U.S. government funded "High Energy Density Materials" (HEDM) programs since the 1950's. These efforts have examined a wide range of phenomena such as free radical stabilization, metallic hydrogen, metastable helium, polynitrogens, extended molecular solids, nanothermites, and others. In spite of the substantial research investments, significant improvements in energetic material performance have not been forthcoming. This paper discusses the lessons learned in the various HEDM programs, the different degrees of freedom in which to store energy in materials, and the fundamental limitations and orders of magnitude of the energies involved. The discussion focuses almost exclusively on the topic of energy density and only mentions in passing other equally important properties of explosives and propellants such as gas generation and reaction rate.

Shock interactions with heterogeneous energetic materials

Science.gov (United States)

Yarrington, Cole D.; Wixom, Ryan R.; Damm, David L.

2018-03-01

The complex physical phenomenon of shock wave interaction with material heterogeneities has significant importance and nevertheless remains little understood. In many materials, the observed macroscale response to shock loading is governed by characteristics of the microstructure. Yet, the majority of computational studies aimed at predicting phenomena affected by these processes, such as the initiation and propagation of detonation waves in explosives or shock propagation in geological materials, employ continuum material and reactive burn model treatment. In an effort to highlight the grain-scale processes that underlie the observable effects in an energetic system, a grain-scale model for hexanitrostilbene (HNS) has been developed. The measured microstructures were used to produce synthetic computational representations of the pore structure, and a density functional theory molecular dynamics derived equation of state (EOS) was used for the fully dense HNS matrix. The explicit inclusion of the microstructure along with a fully dense EOS resulted in close agreement with historical shock compression experiments. More recent experiments on the dynamic reaction threshold were also reproduced by inclusion of a global kinetics model. The complete model was shown to reproduce accurately the expected response of this heterogeneous material to shock loading. Mesoscale simulations were shown to provide a clear insight into the nature of threshold behavior and are a way to understand complex physical phenomena.

ZeroWaste BYG: Redesigning construction materials towards zero waste society

DEFF Research Database (Denmark)

Kirkelund, Gunvor Marie; Schmidt, Jacob Wittrup; Ottosen, Lisbeth M.

2014-01-01

material. The physical‐chemical characteristics of fly ash, such as large uniformity coefficient, clay‐sized particles and rich in some metal elements and salts, show the possibility ofbeing a raw material also for bricks and lightweight aggregates. In the future we expect increasing political pressure......The ZeroWaste research group (www.zerowaste.byg.dtu.dk) at the Department of Civil Engineering was established in 2012 and covers the broad range of expertise required for turning waste materials into attractive, new materials. Members of the group have developed methods for removal of heavy metals...... and phosphorous from waste incineration, sewage sludge and other bio ashes [1], providing the basis to make these ash types an attractive, new material for the building sector.The amount of waste increases and it is both difficult and expensive to handle many waste types as e.g.different ashes. At the same time...

Study on Energetic Ions Behavior in Plasma Facing Materials at Lower Temperature

International Nuclear Information System (INIS)

Morimoto, Y.; Sugiyama, T.; Akahori, S.; Kodama, H.; Tega, E.; Sasaki, M.; Oyaidu, M.; Kimura, H.; Okuno, K.

2003-01-01

An apparatus equipped with X-ray Photoelectron Spectroscopy (XPS) and Thermal Desorption Spectroscopy (TDS) was constructed to study interactions of energetic hydrogen isotopes with plasma facing materials. It is a remarkable feature of the apparatus that energetic ion implantation is carried out at around 150K to study reactions of energetic ions with matrix by suppressing the reactions of thermalized ions. Using this apparatus, TDS experiments for pyrolytic graphite implanted with energetic D 2 ions at 173 and 373K were carried out. The experimental results suggest that the deuterium implanted was released through a four-step release processes, involving three D 2 and one CD x (x = 2, 3 and 4) desorption processes. Two deuterium and CD x desorption processes were observed in the temperature range from 700 to 1200 K. In addition, a new deuterium desorption process was observed for the deuterium-implanted sample at 173 K. This has never been observed for deuterium-implanted graphite implanted at temperatures higher than room temperature

Experimental flame speed in multi-layered nano-energetic materials

Energy Technology Data Exchange (ETDEWEB)

Manesh, Navid Amini; Basu, Saptarshi; Kumar, Ranganathan [Department of Mechanical, Material and Aerospace Engineering, University of Central Florida, Orlando, FL (United States)

2010-03-15

This paper deals with the reaction of dense Metastable Intermolecular Composite (MIC) materials, which have a higher density than conventional energetic materials. The reaction of a multilayer thin film of aluminum and copper oxide has been studied by varying the substrate material and thicknesses. The in-plane speed of propagation of the reaction was experimentally determined using a time of- flight technique. The experiment shows that the reaction is completely quenched for a silicon substrate having an intervening silica layer of less than 200 nm. The speed of reaction seems to be constant at 40 m/s for silica layers with a thickness greater than 1 {mu}m. Different substrate materials such as glass and photoresist were also used. (author)

Recovery of fissile materials from nuclear wastes

Science.gov (United States)

Forsberg, Charles W.

1999-01-01

A process for recovering fissile materials such as uranium, and plutonium, and rare earth elements, from complex waste feed material, and converting the remaining wastes into a waste glass suitable for storage or disposal. The waste feed is mixed with a dissolution glass formed of lead oxide and boron oxide resulting in oxidation, dehalogenation, and dissolution of metal oxides. Carbon is added to remove lead oxide, and a boron oxide fusion melt is produced. The fusion melt is essentially devoid of organic materials and halogens, and is easily and rapidly dissolved in nitric acid. After dissolution, uranium, plutonium and rare earth elements are separated from the acid and recovered by processes such as PUREX or ion exchange. The remaining acid waste stream is vitrified to produce a waste glass suitable for storage or disposal. Potential waste feed materials include plutonium scrap and residue, miscellaneous spent nuclear fuel, and uranium fissile wastes. The initial feed materials may contain mixtures of metals, ceramics, amorphous solids, halides, organic material and other carbon-containing material.

Waste package materials selection process

International Nuclear Information System (INIS)

Roy, A.K.; Fish, R.L.; McCright, R.D.

1994-01-01

The office of Civilian Radioactive Waste Management (OCRWM) of the United States Department of Energy (USDOE) is evaluating a site at Yucca Mountain in Southern Nevada to determine its suitability as a mined geologic disposal system (MGDS) for the disposal of high-level nuclear waste (HLW). The B ampersand W Fuel Company (BWFC), as a part of the Management and Operating (M ampersand O) team in support of the Yucca Mountain Site Characterization Project (YMP), is responsible for designing and developing the waste package for this potential repository. As part of this effort, Lawrence Livermore National Laboratory (LLNL) is responsible for testing materials and developing models for the materials to be used in the waste package. This paper is aimed at presenting the selection process for materials needed in fabricating the different components of the waste package

Thermal-spectrum recriticality energetics

International Nuclear Information System (INIS)

Schwinkendorf, K.N.

1993-12-01

Large computer codes have been created in the past to predict the energy release in hypothetical core disruptive accidents (CDA), postulated to occur in liquid metal reactors (LMR). These codes, such as SIMMER, are highly specific to LMR designs. More recent attention has focused on thermal-spectrum criticality accidents, such as for fuel storage basins and waste tanks containing fissile material. This paper resents results from recent one-dimensional kinetics simulations, performed for a recriticality accident in a thermal spectrum. Reactivity insertion rates generally are smaller than in LMR CDAs, and the energetics generally are more benign. Parametric variation of input was performed, including reactivity insertion and initial temperature

The viability and performance characterization of nano scale energetic materials on a semiconductor bridge (SCB)

Science.gov (United States)

Strohm, Gianna Sophia

The move from conventional energetic composites to nano scale energetic mixtures (nano energetics) has shown dramatic improvement in energy release rate and sensitivity to ignition. A possible application of nano energetics is on a semiconductor bridge (SCB). An SCB typically requires a tenth of the energy input as compared to a bridge wire design with the same no-fire and is capable of igniting in tens of microseconds. For very low energy applications, SCBs can be manufactured to extremely small sizes and it is necessary to find materials with particle sizes that are even smaller to function. Reactive particles of comparable size to the bridge can lead to problems with ignition reliability for small bridges. Nano-energetic composites and the use of SCBs have been significantly studied individually, however, the process of combining nano energetics with an SCB has not been investigated extensively and is the focus of this work. Goals of this study are to determine if nano energetics can be used with SCBs to further reduce the minimum energy required and improve reliability. The performance of nano-scale aluminum (nAl) and bismuth oxide (Bi2O3) with nitrocellulose (NC), Fluorel(TM) FC 2175 (chemically equivalent to VitonRTM) and Glycidyl Azide Polymer (GAP) as binders where quantified initially using the SenTest(TM) algorithm at three weight fractions (5, 7, and 9%) of binder. The threshold energy was calculated and compared to previous data using conventional materials such as zirconium potassium chlorate (ZPC), mercuric 5-Nitrotetrazol (DXN-1) and titanium sub-hydride potassium per-chlorate (TSPP). It was found that even though there where only slight differences in performance between the binders with nAl/Bi2O 3 at any of the three binder weight fractions, the results show that these nano energetic materials require about half of the threshold energy compared to conventional materials using an SCB with an 84x42 mum bridge. Binder limit testing was conducted to

CONSTRUCTION MATERIALS FROM WASTE PRODUCTS

Directory of Open Access Journals (Sweden)

Тахира Далиевна Сидикова

2016-02-01

Full Text Available We have studied the physical and chemical processes occurring during the thermal treatment of ceramic masses on the basis of compositions of natural raw materials and waste processing facilities. The study of structures of ceramic samples species has shown different types of crystalline phases.The results have shown that the waste of Kaytashsky tungsten-molybdenum ores (KVMR may be used as the main raw material to develop new compositions for ceramic materials. The optimal compositions of ceramic tiles for the masses and technological parameters of obtaining sintered materials based on the compositions of kaolin fireclay KVMR have been developed.It has been found that the use of the waste of Kaytashskoy tungsten-molybdenum ore (KVMR in the composition of the ceramic material will expand the raw material base of ceramic production, reduce the roasting temperature and the cost of ceramic materials and products.

Experimental Study on Reaction Characteristics of PTFE/Ti/W Energetic Materials under Explosive Loading

Directory of Open Access Journals (Sweden)

Yan Li

2016-11-01

Full Text Available Metal/fluoropolymer composites represent a new category of energetic structural materials that release energy through exothermic chemical reactions initiated under shock loading conditions. This paper describes an experiment designed to study the reaction characteristics of energetic materials with low porosity under explosive loading. Three PTFE (polytetrafluoroethylene/Ti/W mixtures with different W contents are processed through pressing and sintering. An inert PTFE/W mixture without reactive Ti particles is also prepared to serve as a reference. Shock-induced chemical reactions are recorded by high-speed video through a narrow observation window. Related shock parameters are calculated based on experimental data, and differences in energy release are discussed. The results show that the reaction propagation of PTFE/Ti/W energetic materials with low porosity under explosive loading is not self-sustained. As propagation distance increases, the energy release gradually decreases. In addition, reaction failure distance in PTFE/Ti/W composites is inversely proportional to the W content. Porosity increased the failure distance due to higher shock temperature.

Sustainable Materials Management (SMM) WasteWise Data

Science.gov (United States)

EPA??s WasteWise encourages organizations and businesses to achieve sustainability in their practices and reduce select industrial wastes. WasteWise is part of EPA??s sustainable materials management efforts, which promote the use and reuse of materials more productively over their entire lifecycles. All U.S. businesses, governments and nonprofit organizations can join WasteWise as a partner, endorser or both. Current participants range from small local governments and nonprofit organizations to large multinational corporations. Partners demonstrate how they reduce waste, practice environmental stewardship and incorporate sustainable materials management into their waste-handling processes. Endorsers promote enrollment in WasteWise as part of a comprehensive approach to help their stakeholders realize the economic benefits to reducing waste. WasteWise helps organizations reduce their impact on global climate change through waste reduction. Every stage of a product's life cycle??extraction, manufacturing, distribution, use and disposal??indirectly or directly contributes to the concentration of greenhouse gases (GHGs) in the atmosphere and affects the global climate. WasteWise is part of EPA's larger SMM program (https://www.epa.gov/smm). Sustainable Materials Management (SMM) is a systemic approach to using and reusing materials more productively over their entire lifecycles. It represents a change in how our society thinks about the use of natural resources

Radiation Effects in Nuclear Waste Materials

International Nuclear Information System (INIS)

Weber, William J.; Wang, Lumin; Hess, Nancy J.; Icenhower, Jonathan P.; Thevuthasan, Suntharampillai

2003-01-01

The objective of this project is to develop a fundamental understanding of radiation effects in glasses and ceramics, as well as the influence of solid-state radiation effects on aqueous dissolution kinetics, which may impact the performance of nuclear waste forms and stabilized nuclear materials. This work provides the underpinning science to develop improved glass and ceramic waste forms for the immobilization and disposition of high-level tank waste, excess plutonium, plutonium residues and scrap, other actinides, and other nuclear waste streams. Furthermore, this work is developing develop predictive models for the performance of nuclear waste forms and stabilized nuclear materials. Thus, the research performed under this project has significant implications for the immobilization of High-Level Waste (HLW) and Nuclear Materials, two mission areas within the Office of Environmental Management (EM). With regard to the HLW mission, this research will lead to improved understanding of radiation-induced degradation mechanisms and their effects on dissolution kinetics, as well as development of predictive models for waste form performance. In the Nuclear Materials mission, this research will lead to improvements in the understanding of radiation effects on the chemical and structural properties of materials for the stabilization and long-term storage of plutonium, highly-enriched uranium, and other actinides. The research uses plutonium incorporation, ion-beam irradiation, and electron-beam irradiation to simulate the effects of alpha decay and beta decay on relevant glasses and ceramics. The research under this project has the potential to result in improved glass and ceramic materials for the stabilization and immobilization of high-level tank waste, plutonium residues and scraps, surplus weapons plutonium, highly-enriched uranium, other actinides, and other radioactive materials

Radiation Effects in Nuclear Waste Materials

International Nuclear Information System (INIS)

Weber, William J.

2005-01-01

The objective of this project is to develop a fundamental understanding of radiation effects in glasses and ceramics, as well as the influence of solid-state radiation effects on aqueous dissolution kinetics, which may impact the performance of nuclear waste forms and stabilized nuclear materials. This work provides the underpinning science to develop improved glass and ceramic waste forms for the immobilization and disposition of high-level tank waste, excess plutonium, plutonium residues and scrap, other actinides, and other nuclear waste streams. Furthermore, this work is developing develop predictive models for the performance of nuclear waste forms and stabilized nuclear materials. Thus, the research performed under this project has significant implications for the immobilization of High-Level Waste (HLW) and Nuclear Materials, two mission areas within the Office of Environmental Management (EM). With regard to the HLW mission, this research will lead to improved understanding of radiation-induced degradation mechanisms and their effects on dissolution kinetics, as well as development of predictive models for waste form performance. In the Nuclear Materials mission, this research will lead to improvements in the understanding of radiation effects on the chemical and structural properties of materials for the stabilization and long-term storage of plutonium, highly-enriched uranium, and other actinides. The research uses plutonium incorporation, ion-beam irradiation, and electron-beam irradiation to simulate the effects of alpha decay and beta decay on relevant glasses and ceramics. The research under this project has the potential to result in improved glass and ceramic materials for the stabilization and immobilization of high-level tank waste, plutonium residues and scraps, surplus weapons plutonium, highly-enriched uranium, other actinides, and other radioactive materials

Reactive thermal waves in energetic materials

Energy Technology Data Exchange (ETDEWEB)

Hill, Larry G [Los Alamos National Laboratory

2009-01-01

Reactive thermal waves (RTWs) arise in several energetic material applications, including self-propagating high-temperature synthesis (SHS), high explosive cookoff, and the detonation of heterogeneous explosives. In this paper I exmaine ideal RTWs, by which I mean that (1) material motion is neglected, (2) the state dependence of reaction is Arrhenius in the temperature, and (3) the reaction rate is modulated by an arbitrary mass-fraction-based reaction progress function. Numerical simulations demonstrate that one's natural intuition, which is based mainly upon experience with inert materials and which leads one to expect diffusion processes to become relatively slow after a short time period, is invalid for high energy, state-sensitive reactive systems. Instead, theory predicts that RTWs can propagate at very high speeds. This result agrees with estimates for detonating heterogeneous explosives, which indicate that RTWs must spread from hot-spot nucleation sites at rates comparable to the detonation speed in order to produce experimentally-observed reaction zone thicknesses. Using dimensionless scaling and further invoking the high activation energy approximation, I obtain an analytic formula for the steady plane RTW speed from numerical calculations. I then compute the RTW speed for real explosives, and discuss aspects of their behavior.

Absorption properties of waste matrix materials

Energy Technology Data Exchange (ETDEWEB)

Briggs, J.B. [Idaho National Engineering Lab., Idaho Falls, ID (United States)

1997-06-01

This paper very briefly discusses the need for studies of the limiting critical concentration of radioactive waste matrix materials. Calculated limiting critical concentration values for some common waste materials are listed. However, for systems containing large quantities of waste materials, differences up to 10% in calculated k{sub eff} values are obtained by changing cross section data sets. Therefore, experimental results are needed to compare with calculation results for resolving these differences and establishing realistic biases.

Biogas - energetical and environmental point of view

International Nuclear Information System (INIS)

Skele, A.; Upitis, A.; Kristapsons, M.; Goizevskis, O.; Ziemelis, I.

2003-01-01

Energy sector has been one of the most important priorities since reestablishment of independence of Latvia. The deficiency of energy resources in Latvia has created a need to assess all the possibilities to utilise all possibilities to utilise all the energy resources, including the biological ones, to motivate the trends in the development of energetic in Latvia. A huge non-utilised reserve in Latvia is methane fermentation of organic agricultural and municipal residue and sewage from food industry. The organic mass of solid and liquid waste of different origin and its energetic potential for rural region have been investigated. The work deals with an integrated system of the utilisation of agricultural waste with the anaerobic (biogas) and the thermal processes. Presently the anaerobic waste utilisation, in combination with the production of biogas and organic fertiliser, is considered as one of the energetically most efficient and environment-friendly ways of organic fertiliser utilisation (authors)

Chemical physics of decomposition of energetic materials. Problems and prospects

International Nuclear Information System (INIS)

Smirnov, Lev P

2004-01-01

The review is concerned with analysis of the results obtained in the kinetic and mechanistic studies on decomposition of energetic materials (explosives, powders and solid propellants). It is shown that the state-of-the art in this field is inadequate to the potential of modern chemical kinetics and chemical physics. Unsolved problems are outlined and ways of their solution are proposed.

DGMK conference 'Energetic utilisation and recycling of waste and biomass'. Authors' manuscripts; Beitraege zur DGMK-Fachbereichstagung 'Energetische und stoffliche Nutzung von Abfaellen und Biomassen'. Autorenmanuskripte

Energy Technology Data Exchange (ETDEWEB)

NONE

2000-07-01

This conference of Deutsche Wissenschaftliche Gesellschaft fuer Erdoel, Erdgas und Kohle focused on energetic utilisation and recycling of waste materials and biomass, i.e. combustion, gasification and pyrolysis. Aspects of process control were gone into as well. [German] Die Fachbereichstagung der Deutschen Wissenschaftlichen Gesellschaft fuer Erdoel, Erdgas und Kohle beschaeftigte sich mit der energetischen und stofflichen Nutzung von Abfall und Biomasse. Verbrennung, Vergasung und Pyrolyse verschiedener Abfallstoffe sowie die Prozesssteuerung wurden eroertert.

Energetics Conditioning Facility

Data.gov (United States)

Federal Laboratory Consortium — The Energetics Conditioning Facility is used for long term and short term aging studies of energetic materials. The facility has 10 conditioning chambers of which 2...

Theoretical study of energetic interactions between high temperature molten materials and a low temperature fluid

International Nuclear Information System (INIS)

Chen, S.H.H.

1984-01-01

Analytical models are developed to predict the hydrodynamical transients resulting from the energetic interactions between a high temperature molten material and a low temperature liquid coolant. Initially, the molten material at high temperature and pressure is separated from the low temperature fluid by a solid metal barrier. Upon contact between the molten material and solid barrier, thermal attack occurs eventually resulting in a loss of barrier integrity. Subsequently, the molten material is injected into the liquid pool resulting in energetic interactions. The analytical models integrate a wide variety of potentially mutually-interacting transport phenomena which dominate the transient process into a deterministic scheme to predict the hydrodynamic transient process into a deterministic scheme to predict the hydrodynamic transient process. The model calculations are compared with the existing experimental results to show its engineering accuracy and adequacy in predicting such energetic interactions. Two models are formulated to bracket the transport of molten material to the rupture site for the reactor system. The stratified model minimized the rate of transport of material to the break location while the dispersed model maximized such transport. These two models are applied to a reference pressure tube reactor to evaluate the pressure transients and the potential structural damages as a result of a postulated severe primary coolant blockage in a power channel

Surface Thermometry of Energetic Materials by Laser-Induced Fluorescence

Science.gov (United States)

1989-09-01

at 34 yttrium- aluminum -garnet (Dy:YAG). The simplified energy diagram of Dy:YAG is shown in Fig. 1. Absorbed laser light (at 355 nrm) can 5 excite the...the thermometric technique on a surface similar to that of an energetic material, a thermal-setting plastic supplied by Buehler, Ltd., was employed...temperature over the temperature range of interest. The rare-earth ion dysprosium (Dy) doped into a yttrium- aluminum -garnet (YAG) crystal was I determined

Electrostatic interactions for directed assembly of high performance nanostructured energetic materials of Al/Fe2O3/multi-walled carbon nanotube (MWCNT)

International Nuclear Information System (INIS)

Zhang, Tianfu; Ma, Zhuang; Li, Guoping; Wang, Zhen; Zhao, Benbo; Luo, Yunjun

2016-01-01

Electrostatic self-assembly in organic solvent without intensively oxidative or corrosive environments, was adopted to prepare Al/Fe 2 O 3 /MWCNT nanostructured energetic materials as an energy generating material. The negatively charged MWCNT was used as a glue-like agent to direct the self-assembly of the well dispersed positively charged Al (fuel) and Fe 2 O 3 (oxide) nanoparticles. This spontaneous assembly method without any surfactant chemistry or other chemical and biological moieties decreased the aggregation of the same nanoparticles largely, moreover, the poor interfacial contact between the Al (fuel) and Fe 2 O 3 (oxide) nanoparticles was improved significantly, which was the key characteristic of high performance nanostructured energetic materials. In addition, the assembly process was confirmed as Diffusion-Limited Aggregation. The assembled Al/Fe 2 O 3 /MWCNT nanostructured energetic materials showed excellent performance with heat release of 2400 J/g, peak pressure of 0.42 MPa and pressurization rate of 105.71 MPa/s, superior to that in the control group Al/Fe 2 O 3 nanostructured energetic materials prepared by sonication with heat release of 1326 J/g, peak pressure of 0.19 MPa and pressurization rate of 33.33 MPa/s. Therefore, the approach, which is facile, opens a promising route to the high performance nanostructured energetic materials. - Graphical abstract: The negatively charged MWCNT was used as a glue-like agent to direct the self-assembly of the well dispersed positively charged Al (fuel) and Fe 2 O 3 (oxide) nanoparticles. - Highlights: • A facile spontaneous electrostatic assembly strategy without surfactant was adopted. • The fuels and oxidizers assembled into densely packed nanostructured composites. • The assembled nanostructured energetic materials have excellent performance. • This high performance energetic material can be scaled up for practical application. • This strategy can be applied into other nanostructured

Unreacted equation of states of typical energetic materials under static compression: A review

International Nuclear Information System (INIS)

Zheng Zhaoyang; Zhao Jijun

2016-01-01

The unreacted equation of state (EOS) of energetic materials is an important thermodynamic relationship to characterize their high pressure behaviors and has practical importance. The previous experimental and theoretical works on the equation of state of several energetic materials including nitromethane, 1,3,5-trinitrohexahydro-1,3,5-triazine (RDX), 1,3,5,7-tetranitro-1,3,5,7-tetrazacyclooctane (HMX), hexanitrostilbene (HNS), hexanitrohexaazaisowurtzitane (HNIW or CL-20), pentaerythritol tetranitrate (PETN), 2,6-diamino-3,5-dinitropyrazine-1-oxide (LLM-105), triamino-trinitrobenzene (TATB), 1,1-diamino-2,2-dinitroethene (DADNE or FOX-7), and trinitrotoluene (TNT) are reviewed in this paper. The EOS determined from hydrostatic and non-hydrostatic compressions are discussed and compared. The theoretical results based on ab initio calculations are summarized and compared with the experimental data. (topical review)

Environmental restoration waste materials co-disposal

International Nuclear Information System (INIS)

Phillips, S.J.; Alexander, R.G.; England, J.L.; Kirdendall, J.R.; Raney, E.A.; Stewart, W.E.; Dagan, E.B.; Holt, R.G.

1993-09-01

Co-disposal of radioactive and hazardous waste is a highly efficient and cost-saving technology. The technology used for final treatment of soil-washing size fractionization operations is being demonstrated on simulated waste. Treated material (wasterock) is used to stabilize and isolate retired underground waste disposal structures or is used to construct landfills or equivalent surface or subsurface structures. Prototype equipment is under development as well as undergoing standardized testing protocols to prequalify treated waste materials. Polymer and hydraulic cement solidification agents are currently used for geotechnical demonstration activities

Concerning enactment of regulations on burying of waste of nuclear fuel material or waste contaminated with nuclear fuel material

International Nuclear Information System (INIS)

1988-01-01

The Atomic Safety Commission of Japan, after examining a report submitted by the Science and Technology Agency concerning the enactment of regulations on burying of waste of nuclear fuel material or waste contaminated with nuclear fuel material, has approved the plan given in the report. Thus, laws and regulations concerning procedures for application for waste burying business, technical standards for implementation of waste burying operation, and measures to be taken for security should be established to ensure the following. Matters to be described in the application for the approval of such business and materials to be attached to the application should be stipulated. Technical standards concerning inspection of waste burying operation should be stipulated. Measures to be taken for the security of waste burying facilities and security concerning the transportation and disposal of nuclear fuel material should be stipulated. Matters to be specified in the security rules should be stipulated. Matters to be recorded by waste burying business operators, measures to be taken to overcome dangers and matters to be reported to the Science and Technology Agency should be stipulated. (Nogami, K.)

Waste minimization for commercial radioactive materials users generating low-level radioactive waste

International Nuclear Information System (INIS)

Fischer, D.K.; Gitt, M.; Williams, G.A.; Branch, S.; Otis, M.D.; McKenzie-Carter, M.A.; Schurman, D.L.

1991-07-01

The objective of this document is to provide a resource for all states and compact regions interested in promoting the minimization of low-level radioactive waste (LLW). This project was initiated by the Commonwealth of Massachusetts, and Massachusetts waste streams have been used as examples; however, the methods of analysis presented here are applicable to similar waste streams generated elsewhere. This document is a guide for states/compact regions to use in developing a system to evaluate and prioritize various waste minimization techniques in order to encourage individual radioactive materials users (LLW generators) to consider these techniques in their own independent evaluations. This review discusses the application of specific waste minimization techniques to waste streams characteristic of three categories of radioactive materials users: (1) industrial operations using radioactive materials in the manufacture of commercial products, (2) health care institutions, including hospitals and clinics, and (3) educational and research institutions. Massachusetts waste stream characterization data from key radioactive materials users in each category are used to illustrate the applicability of various minimization techniques. The utility group is not included because extensive information specific to this category of LLW generators is available in the literature

Test plan for buried waste containment system materials

International Nuclear Information System (INIS)

Weidner, J.; Shaw, P.

1997-03-01

The objectives of the FY 1997 barrier material work at the Idaho National Engineering and Environmental Laboratory are to (1) select a waste barrier material and verify that it is compatible with the Buried Waste Containment System Process, and (2) determine if, and how, the Buried Waste Containment System emplacement process affects the material properties and performance (on proof of principle scale). This test plan describes a set of measurements and procedures used to validate a waste barrier material for the Buried Waste Containment System. A latex modified proprietary cement manufactured by CTS Cement Manufacturing Company will be tested. Emplacement properties required for the Buried Waste Containment System process are: slump between 8 and 10 in., set time between 15 and 30 minutes, compressive strength at set of 20 psi minimum, and set temperature less than 100 degrees C. Durability properties include resistance to degradation from carbonate, sulfate, and waste-site soil leachates. A set of baseline barrier material properties will be determined to provide a data base for comparison with the barrier materials when tested in the field. The measurements include permeability, petrographic analysis to determine separation and/or segregation of mix components, and a set of mechanical properties. The measurements will be repeated on specimens from the field test material. The data will be used to determine if the Buried Waste Containment System equipment changes the material. The emplacement properties will be determined using standard laboratory procedures and instruments. Durability of the barrier material will be evaluated by determining the effect of carbonate, sulfate, and waste-site soil leachates on the compressive strength of the barrier material. The baseline properties will be determined using standard ASTM procedures. 9 refs., 1 fig., 2 tabs

Cement-Based Materials for Nuclear Waste Storage

CERN Document Server

Cau-di-Coumes, Céline; Frizon, Fabien; Lorente, Sylvie

2013-01-01

As the re-emergence of nuclear power as an acceptable energy source on an international basis continues, the need for safe and reliable ways to dispose of radioactive waste becomes ever more critical. The ultimate goal for designing a predisposal waste-management system depends on producing waste containers suitable for storage, transportation and permanent disposal. Cement-Based Materials for Nuclear-Waste Storage provides a roadmap for the use of cementation as an applied technique for the treatment of low- and intermediate-level radioactive wastes.Coverage includes, but is not limited to, a comparison of cementation with other solidification techniques, advantages of calcium-silicate cements over other materials and a discussion of the long-term suitability and safety of waste packages as well as cement barriers. This book also: Discusses the formulation and production of cement waste forms for storing radioactive material Assesses the potential of emerging binders to improve the conditioning of problemati...

Aqueous Corrosion Rates for Waste Package Materials

Energy Technology Data Exchange (ETDEWEB)

S. Arthur

2004-10-08

The purpose of this analysis, as directed by ''Technical Work Plan for: Regulatory Integration Modeling and Analysis of the Waste Form and Waste Package'' (BSC 2004 [DIRS 171583]), is to compile applicable corrosion data from the literature (journal articles, engineering documents, materials handbooks, or standards, and national laboratory reports), evaluate the quality of these data, and use these to perform statistical analyses and distributions for aqueous corrosion rates of waste package materials. The purpose of this report is not to describe the performance of engineered barriers for the TSPA-LA. Instead, the analysis provides simple statistics on aqueous corrosion rates of steels and alloys. These rates are limited by various aqueous parameters such as temperature (up to 100 C), water type (i.e., fresh versus saline), and pH. Corrosion data of materials at pH extremes (below 4 and above 9) are not included in this analysis, as materials commonly display different corrosion behaviors under these conditions. The exception is highly corrosion-resistant materials (Inconel Alloys) for which rate data from corrosion tests at a pH of approximately 3 were included. The waste package materials investigated are those from the long and short 5-DHLW waste packages, 2-MCO/2-DHLW waste package, and the 21-PWR commercial waste package. This analysis also contains rate data for some of the materials present inside the fuel canisters for the following fuel types: U-Mo (Fermi U-10%Mo), MOX (FFTF), Thorium Carbide and Th/U Carbide (Fort Saint Vrain [FSVR]), Th/U Oxide (Shippingport LWBR), U-metal (N Reactor), Intact U-Oxide (Shippingport PWR, Commercial), aluminum-based, and U-Zr-H (TRIGA). Analysis of corrosion rates for Alloy 22, spent nuclear fuel, defense high level waste (DHLW) glass, and Titanium Grade 7 can be found in other analysis or model reports.

Aqueous Corrosion Rates for Waste Package Materials

International Nuclear Information System (INIS)

Arthur, S.

2004-01-01

The purpose of this analysis, as directed by ''Technical Work Plan for: Regulatory Integration Modeling and Analysis of the Waste Form and Waste Package'' (BSC 2004 [DIRS 171583]), is to compile applicable corrosion data from the literature (journal articles, engineering documents, materials handbooks, or standards, and national laboratory reports), evaluate the quality of these data, and use these to perform statistical analyses and distributions for aqueous corrosion rates of waste package materials. The purpose of this report is not to describe the performance of engineered barriers for the TSPA-LA. Instead, the analysis provides simple statistics on aqueous corrosion rates of steels and alloys. These rates are limited by various aqueous parameters such as temperature (up to 100 C), water type (i.e., fresh versus saline), and pH. Corrosion data of materials at pH extremes (below 4 and above 9) are not included in this analysis, as materials commonly display different corrosion behaviors under these conditions. The exception is highly corrosion-resistant materials (Inconel Alloys) for which rate data from corrosion tests at a pH of approximately 3 were included. The waste package materials investigated are those from the long and short 5-DHLW waste packages, 2-MCO/2-DHLW waste package, and the 21-PWR commercial waste package. This analysis also contains rate data for some of the materials present inside the fuel canisters for the following fuel types: U-Mo (Fermi U-10%Mo), MOX (FFTF), Thorium Carbide and Th/U Carbide (Fort Saint Vrain [FSVR]), Th/U Oxide (Shippingport LWBR), U-metal (N Reactor), Intact U-Oxide (Shippingport PWR, Commercial), aluminum-based, and U-Zr-H (TRIGA). Analysis of corrosion rates for Alloy 22, spent nuclear fuel, defense high level waste (DHLW) glass, and Titanium Grade 7 can be found in other analysis or model reports

RADIATION EFFECTS IN NUCLEAR WASTE MATERIALS

International Nuclear Information System (INIS)

Weber, William J.

2000-01-01

The objective of this research was to develop fundamental understanding and predictive models of radiation effects in glasses and ceramics at the atomic, microscopic, and macroscopic levels, as well as an understanding of the effects of these radiation-induced solid-state changes on dissolution kinetics (i.e., radionuclide release). The research performed during the duration of this project has addressed many of the scientific issues identified in the reports of two DOE panels [1,2], particularly those related to radiation effects on the structure of glasses and ceramics. The research approach taken by this project integrated experimental studies and computer simulations to develop comprehensive fundamental understanding and capabilities for predictive modeling of radiation effects and dissolution kinetics in both glasses and ceramics designed for the stabilization and immobilization of high-level tank waste (HLW), plutonium residues and scraps, surplus weapons plutonium, other actinides, and other highly radioactive waste streams. Such fundamental understanding is necessary in the development of predictive models because all experimental irradiation studies on nuclear waste materials are ''accelerated tests'' that add a great deal of uncertainty to predicted behavior because the damage rates are orders of magnitude higher than the actual damage rates expected in nuclear waste materials. Degradation and dissolution processes will change with damage rate and temperature. Only a fundamental understanding of the kinetics of all the physical and chemical processes induced or affected by radiation will lead to truly predictive models of long-term behavior and performance for nuclear waste materials. Predictive models of performance of nuclear waste materials must be scientifically based and address both radiation effects on structure (i.e., solid-state effects) and the effects of these solid-state structural changes on dissolution kinetics. The ultimate goal of this

Enzymes for Degradation of Energetic Materials and Demilitarization of Explosives Stockpiles - SERDP Annual (Interim) Report, 12/98

Energy Technology Data Exchange (ETDEWEB)

Shah, M.M.

1999-01-18

The current stockpile of energetic materials requiring disposal contains about half a million tons. Through 2001, over 2.1 million tons are expected to pass through the stockpile for disposal. Safe and environmentally acceptable methods for disposing of these materials are needed. This project is developing safe, economical, and environmentally sound processes using biocatalyst (enzymes) to degrade energetic materials and to convert them into economically valuable products. Alternative methods for destroying these materials are hazardous, environmentally unacceptable, and expensive. These methods include burning, detonation, land and sea burial, treatment at high temperature and pressure, and treatment with harsh chemicals. Enzyme treatment operates at room temperature and atmospheric pressure in a water solution.

Insensitive high-energy energetic structural material of tungsten-polytetrafluoroethylene-aluminum composites

Directory of Open Access Journals (Sweden)

Liu Wang

2015-11-01

Full Text Available Energetic structural material is a kind of materials that are inert under normal conditions but could produce exothermic chemical reaction when subjected to impact. This report shows a kind of energetic structural material of tungsten (W-polytetrafluoroethylene (PTFE-aluminum (Al with density of 4.12 g/cm3, excellent ductility and dynamic compressive strength of 96 MPa. Moreover, 50W-35PTFE-15Al (wt% can exhibit a high reaction energy value of more than 2 times of TNT per unit mass and 5 times of TNT per unit volume, respectively, but with excellent insensitivity compared with traditional explosives. Under thermal conditions, the W-PTFE-Al composite can keep stable at 773 K. Under impact loading, when the strain rate up to ∼4820 s−1 coupled with the absorbed energy per unit volume of 120 J/cm3, deflagration occurs and combustion lasts for 500 μs. During impact compressive deformation, the PTFE matrix is elongated into nano-fibers, thus significantly increases the reaction activity of W-PTFE-Al composites. The nano-fiber structure is necessary for the reaction of W-PTFE-Al composites. The formation of PTFE nano-fibers must undergo severe plastic deformation, and therefore the W-PTFE-Al composites exhibit excellent insensitivity and safety. Furthermore, the reaction mechanisms of W-PTFE-Al composites in argon and in air are revealed.

Papers of 5. Scientific-Technical Seminar: Material Study for Electric Power Stations and Energetics

International Nuclear Information System (INIS)

1998-01-01

The review of material research designed for energetic use has been done. The special emphasis have been put on the steels and alloys with desirable mechanical and corrosion properties in high temperature and pressure conditions. The methods for testing and non-destructive diagnostics of materials and welded joints have been also presented and discussed

Construct 3D porous hollow Co3O4 micro-sphere: A potential oxidizer of nano-energetic materials with superior reactivity

Science.gov (United States)

Wang, Jun; Zheng, Bo; Qiao, Zhiqiang; Chen, Jin; Zhang, Liyuan; Zhang, Long; Li, Zhaoqian; Zhang, Xingquan; Yang, Guangcheng

2018-06-01

High energy density and rapid reactivity are the future trend for nano-energetic materials. Energetic performance of nano-energetic materials depends on the interfacial diffusion and mass transfer during the reacted process. However, the development of desired structure to significantly enhance reactivity still remains challenging. Here we focused on the design and preparation of 3D porous hollow Co3O4 micro-spheres, in which gas-blowing agents (air) and maximize interfacial interactions were introduced to enhance mass transport and reduce the diffusion distance between the oxidizer and fuel (Aluminum). The 3D hierarchical Co3O4/Al based nano-energetic materials show a low-onset decomposition temperature (423 °C), and high heat output (3118 J g-1) resulting from porous and hollow nano-structure of Co3O4 micro-spheres. Furthermore, 3D hierarchical Co3O4/Al arrays were directly fabricated on the silicon substrate, which was fully compatible with silicon-based microelectromechanical systems to achieve functional nanoenergetics-on-a-chip. This approach provides a simple and efficient way to fabricate 3D ordered nano-energetic arrays with superior reactivity and the potential on the application in micro-energetic devices.

Materials aspects of nuclear waste isolation

International Nuclear Information System (INIS)

Bennett, J.W.

1984-01-01

This paper is intended to provide an overview of the nuclear waste repository performance requirements and the roles which we expect materials to play in meeting these requirements. The objective of the U.S. Dept. of Energy's (DOE) program is to provide for the safe, permanent isolation of high-level radioactive wastes from the public. The Nuclear Waste Policy Act of 1982 (the Act) provides the mandate to accomplish this objective by establishing a program timetable, a schedule of procedures to be followed, and program funding (1 mil/kwhr for all nuclear generated electricity). The centerpiece of this plan is the design and operation of a mined geologic repository system for the permanent isolation of radioactive wastes. A nuclear waste repository contains several thousand acres of tunnels and drifts into which the nuclear waste will be emplaced, and several hundred acres for the facilities on the surface in which the waste is received, handled, and prepared for movement underground. With the exception of the nuclear material-related facilities, a repository is similar to a standard mining operation. The difference comes in what a repository is supposed to do - to contain an isolate nuclear waste from man and the environment

Gas from waste materials

Energy Technology Data Exchange (ETDEWEB)

Leroux, H

1943-01-01

Various efforts to produce fuel gas from waste materials by fermentation are reviewed. Although the thermal yield appears to be attractive (60%) in the formation of CH/sub 4/ + CO/sub 2/ from cellulose the process requires very large equipment owing to the slowness of the reaction. From 1 ton of waste, a daily production of 1 m/sup 2/ of gas (7700 cal) is obtained for 50 days.

Nuclear-waste-package materials degradation modes and accelerated testing

International Nuclear Information System (INIS)

1981-09-01

This report reviews the materials degradation modes that may affect the long-term behavior of waste packages for the containment of nuclear waste. It recommends an approach to accelerated testing that can lead to the qualification of waste package materials in specific repository environments in times that are short relative to the time period over which the waste package is expected to provide containment. This report is not a testing plan but rather discusses the direction for research that might be considered in developing plans for accelerated testing of waste package materials and waste forms

Disposal of radioactive waste material to sea

International Nuclear Information System (INIS)

Burton, W.R.

1985-01-01

Radioactive waste liquid of a low or intermediate activity level is mixed with a suitable particulate material and discharged under the sea from a pipeline. The particulate material is chosen so that it sorbs radio-nuclides from this waste, has a good retention for these nuclides when immersed in sea water, and has a particle size or density such that transfer of the particles back to the shore by naturally occurring phenomena is reduced. Radio nuclide concentration in the sea water at the end of the pipeline may also be reduced. The particulate material used may be preformed or co-precipitated in the waste. Suitable materials are oxides or hydroxides of iron or manganese or material obtained from the sea-bed. (author)

Utilisation of biological and secondary raw materials VI. Recycling - conversion to energy; Bio- und Sekundaerrohstoffverwertung VI. Stofflich - energetisch

Energy Technology Data Exchange (ETDEWEB)

Wiemer, Klaus; Kern, Michael

2011-07-01

In a lot of contributions the Kasseler waste and bio-energy forum reports on a sustainable management of wastes. The organizers hope that this results in a lively dialogue on sustainable activities in waste management corresponding to the responsibility towards future generations. Within the 23rd Kasseler waste and bio-energy forum at 12th to 14th April, 2010 in Kassel (Federal Republic of Germany) lectures were held to the following themes: (1) Perspectives of the waste management; (2) Ressource conservation and securing of raw material; (3) Common capture of packages and high-grade materials; (4) Bin for reusable materials - system trusteeship, material flows, qualities, financing, practical examples; (5) Industrial waste flows, EBS quality assurance and increase of efficiency; (6) New technological developments in the area of fermentation of biological wastes; (7) Perspectives of material and energetical utilization of biological wastes; (8) Renewable Energy Law and direct marketing of 'green' electricity; (9) Technology and experiences with biogas processing; (10) Fermentation of biogenic residues and catering waste; (11) Increase of efficiency of mechanical-biological treatment plants; (12) Mechanical-biological treatment technology in an international environment; (13) Concepts of energetic utilization for landfill sites; (14) Landfill law and landfill after-care; (15) Renaturation of landfills.

Material selection for Multi-Function Waste Tank Facility tanks

International Nuclear Information System (INIS)

Carlos, W.C.

1994-01-01

This report briefly summarizes the history of the materials selection for the US Department of Energy's high-level waste carbon steel storage tanks. It also provide an evaluation of the materials for the construction of new tanks at the Multi-Function Waste Tank Facility. The evaluation included a materials matrix that summarized the critical design, fabrication, construction, and corrosion resistance requirements; assessed each requirement; and cataloged the advantages and disadvantages of each material. This evaluation is based on the mission of the Multi-Function Waste Tank Facility. On the basis of the compositions of the wastes stored in Hanford waste tanks, it is recommended that tanks for the Multi-Function Waste Tank Facility be constructed of normalized ASME SA 516, Grade 70, carbon steel

Disposal containers for radioactive waste materials and separation systems for radioactive waste materials

International Nuclear Information System (INIS)

Rubin, L.S.

1986-01-01

A separation system for dewatering radioactive waste materials includes a disposal container, drive structure for receiving the container, and means for releasably attaching the container to the drive structure. The separation structure disposed in the container adjacent the inner surface of the side wall structure retains solids while allowing passage of liquids. The inlet port structure in the container top wall is normally closed by first valve structure that is centrifugally actuated to open the inlet port and the discharge port structure at the container periphery receives liquid that passes through the separation structure and is normally closed by a second valve structure that is centrifugally actuated to open the discharge ports. The container also includes a coupling structure for releasable engagement with the centrifugal drive structure. The centrifugal force produced when the container is driven in rotation by the drive structure opens the valve structures, and radioactive waste material introduced into the container through the open inlet port is dewatered, and the waste is compacted. The ports are automatically closed by the valves when the container drum is not subjected to centrifugal force such that containment effectiveness is enhanced and exposure of personnel to radioactive materials is minimized. (author)

Electrostatic interactions for directed assembly of high performance nanostructured energetic materials of Al/Fe{sub 2}O{sub 3}/multi-walled carbon nanotube (MWCNT)

Energy Technology Data Exchange (ETDEWEB)

Zhang, Tianfu; Ma, Zhuang; Li, Guoping; Wang, Zhen; Zhao, Benbo; Luo, Yunjun, E-mail: yjluo@bit.edu.cn

2016-05-15

Electrostatic self-assembly in organic solvent without intensively oxidative or corrosive environments, was adopted to prepare Al/Fe{sub 2}O{sub 3}/MWCNT nanostructured energetic materials as an energy generating material. The negatively charged MWCNT was used as a glue-like agent to direct the self-assembly of the well dispersed positively charged Al (fuel) and Fe{sub 2}O{sub 3} (oxide) nanoparticles. This spontaneous assembly method without any surfactant chemistry or other chemical and biological moieties decreased the aggregation of the same nanoparticles largely, moreover, the poor interfacial contact between the Al (fuel) and Fe{sub 2}O{sub 3} (oxide) nanoparticles was improved significantly, which was the key characteristic of high performance nanostructured energetic materials. In addition, the assembly process was confirmed as Diffusion-Limited Aggregation. The assembled Al/Fe{sub 2}O{sub 3}/MWCNT nanostructured energetic materials showed excellent performance with heat release of 2400 J/g, peak pressure of 0.42 MPa and pressurization rate of 105.71 MPa/s, superior to that in the control group Al/Fe{sub 2}O{sub 3} nanostructured energetic materials prepared by sonication with heat release of 1326 J/g, peak pressure of 0.19 MPa and pressurization rate of 33.33 MPa/s. Therefore, the approach, which is facile, opens a promising route to the high performance nanostructured energetic materials. - Graphical abstract: The negatively charged MWCNT was used as a glue-like agent to direct the self-assembly of the well dispersed positively charged Al (fuel) and Fe{sub 2}O{sub 3} (oxide) nanoparticles. - Highlights: • A facile spontaneous electrostatic assembly strategy without surfactant was adopted. • The fuels and oxidizers assembled into densely packed nanostructured composites. • The assembled nanostructured energetic materials have excellent performance. • This high performance energetic material can be scaled up for practical application. • This

Plastic waste depolymerization as a source of energetic heating oils

Directory of Open Access Journals (Sweden)

Wołosiewicz-Głąb Marta

2017-01-01

Full Text Available In the past years there has been an increase in production and consumption of plastics, which are widely used in many areas of life. Waste generated from this material are a challenge for the whole of society, regardless of awareness of sustainable development and its technological progress. Still the method of disposal of plastic waste are focused mainly on their storage and incineration, not using energy contained there. In this paper technology for plastic waste depolymerization with characteristics of fuel oil resulting in the process, as an alternative to traditional energy carriers such as: coal, fine coal or coke used in households will be presented. Oil has a high calorific value and no doubt could replace traditional solutions which use conventional energy sources. Furthermore, the fuel resulting from this process is sulfur-free and chemically pure. The paper presents the installation for plastics waste depolymerization used in selected Polish Institute of Plastics Processing, along with the ability to use the main thermocatalytic transformation product.

EVALUATION OF CAUSES OF CONSTRUCTION MATERIAL WASTE

African Journals Online (AJOL)

Osondu

factors contributing to construction material waste generation on building sites in Rivers State, ... the studied factors at every level of the construction processes and in their waste management plan. ..... Evaluation of Solid Waste in Building.

Methods for the Evaluation of Waste Treatment Processes

Directory of Open Access Journals (Sweden)

Hans-Joachim Gehrmann

2017-01-01

Full Text Available Decision makers for waste management are confronted with the problem of selecting the most economic, environmental, and socially acceptable waste treatment process. This paper elucidates evaluation methods for waste treatment processes for the comparison of ecological and economic aspects such as material flow analysis, statistical entropy analysis, energetic and exergetic assessment, cumulative energy demand, and life cycle assessment. The work is based on the VDI guideline 3925. A comparison of two thermal waste treatment plants with different process designs and energy recovery systems was performed with the described evaluation methods. The results are mainly influenced by the type of energy recovery, where the waste-to-energy plant providing district heat and process steam emerged to be beneficial in most aspects. Material recovery options from waste incineration were evaluated according to sustainability targets, such as saving of resources and environmental protection.

Papers of 4. Scientific-Technical Seminar: Material Study for Electric Power Stations and Energetics

International Nuclear Information System (INIS)

1997-01-01

The research on the materials commonly used in electric power stations and energetics have been summarized in the course of the seminar. Especially a different kinds of steels have been investigated from the view point of their desirable mechanical and corrosion properties

A Coupled Damage and Reaction Model for Simulating Energetic Material Response to Impact Hazards

International Nuclear Information System (INIS)

BAER, MELVIN R.; DRUMHELLER, D.S.; MATHESON, E.R.

1999-01-01

The Baer-Nunziato multiphase reactive theory for a granulated bed of energetic material is extended to allow for dynamic damage processes, that generate new surfaces as well as porosity. The Second Law of Thermodynamics is employed to constrain the constitutive forms of the mass, momentum, and energy exchange functions as well as those for the mechanical damage model ensuring that the models will be dissipative. The focus here is on the constitutive forms of the exchange functions. The mechanical constitutive modeling is discussed in a companion paper. The mechanical damage model provides dynamic surface area and porosity information needed by the exchange functions to compute combustion rates and interphase momentum and energy exchange rates. The models are implemented in the CTH shock physics code and used to simulate delayed detonations due to impacts in a bed of granulated energetic material and an undamaged cylindrical sample

Glass-crystalline materials for active waste incorporation

International Nuclear Information System (INIS)

Kulichenko, V.V.; Krylova, N.V.; Vlasov, V.I.; Polyakov, A.S.

1979-01-01

This paper presents the results of investigations into the possibility and conditions for using glass-crystalline materials for the incorporation of radionuclides. Materials of a cast pyroxene type that are obtained by smelting calcined wastes with acid blast furnace slags are described. A study was also made of materials of a basalt type prepared from wastes with and without alkali metal salt. Changes in the structure and properties of materials in the process of storage at different temperatures have been studied

Radiation effects on materials in the near-field of nuclear waste repository. 1998 annual progress report

International Nuclear Information System (INIS)

Ewing, R.C.; Wang, L.M.

1998-01-01

'Site restoration activities at DOE facilities and the permanent disposal of nuclear waste generated at DOE facilities involve working with and within various types and levels of radiation fields. Once the nuclear waste is incorporated into a final form, radioactive decay will decrease the radiation field over geologic time scales, but the alpha-decay dose for these solids will still reach values as high as 10 18 alpha-decay events/gm in periods as short as 1,000 years. This dose is well within the range for which important chemical (e.g., increased leach rate) and physical (e.g., volume expansion) changes may occur in crystalline ceramics. Release and sorption of long-lived actinides (e.g., 237 Np) can provide a radiation exposure to backfill materials, and changes in important properties (e.g., cation exchange capacity) may occur. The objective of this research program is to evaluate the long term radiation effects in the materials in the near-field of a nuclear waste repository with accelerated experiments in the laboratory using energetic particles (electrons, ions and neutrons). Experiments on the microstructural evolution during irradiation of two important groups of materials, sheet silicates (e.g., clays) and zeolites (analcime), have been conducted; and studies of radiation-induced changes in chemical properties (e.g. cation exchange capacity) are underway. As of the mid-2nd year of the 3-year project, experiments on the microstructural evolution during irradiation of two important group of materials, sheet silicates (mica) and zeolites (analcime), have been conducted; and studies of radiation-induced changes in chemical properties (e.g., cation exchange capacity) are underway.'

Use of selected waste materials in concrete mixes

International Nuclear Information System (INIS)

Batayneh, Malek; Marie, Iqbal; Asi, Ibrahim

2007-01-01

A modern lifestyle, alongside the advancement of technology has led to an increase in the amount and type of waste being generated, leading to a waste disposal crisis. This study tackles the problem of the waste that is generated from construction fields, such as demolished concrete, glass, and plastic. In order to dispose of or at least reduce the accumulation of certain kinds of waste, it has been suggested to reuse some of these waste materials to substitute a percentage of the primary materials used in the ordinary portland cement concrete (OPC). The waste materials considered to be recycled in this study consist of glass, plastics, and demolished concrete. Such recycling not only helps conserve natural resources, but also helps solve a growing waste disposal crisis. Ground plastics and glass were used to replace up to 20% of fine aggregates in concrete mixes, while crushed concrete was used to replace up to 20% of coarse aggregates. To evaluate these replacements on the properties of the OPC mixes, a number of laboratory tests were carried out. These tests included workability, unit weight, compressive strength, flexural strength, and indirect tensile strength (splitting). The main findings of this investigation revealed that the three types of waste materials could be reused successfully as partial substitutes for sand or coarse aggregates in concrete mixtures

Use of selected waste materials in concrete mixes.

Science.gov (United States)

Batayneh, Malek; Marie, Iqbal; Asi, Ibrahim

2007-01-01

A modern lifestyle, alongside the advancement of technology has led to an increase in the amount and type of waste being generated, leading to a waste disposal crisis. This study tackles the problem of the waste that is generated from construction fields, such as demolished concrete, glass, and plastic. In order to dispose of or at least reduce the accumulation of certain kinds of waste, it has been suggested to reuse some of these waste materials to substitute a percentage of the primary materials used in the ordinary portland cement concrete (OPC). The waste materials considered to be recycled in this study consist of glass, plastics, and demolished concrete. Such recycling not only helps conserve natural resources, but also helps solve a growing waste disposal crisis. Ground plastics and glass were used to replace up to 20% of fine aggregates in concrete mixes, while crushed concrete was used to replace up to 20% of coarse aggregates. To evaluate these replacements on the properties of the OPC mixes, a number of laboratory tests were carried out. These tests included workability, unit weight, compressive strength, flexural strength, and indirect tensile strength (splitting). The main findings of this investigation revealed that the three types of waste materials could be reused successfully as partial substitutes for sand or coarse aggregates in concrete mixtures.

Nuclear energetics all over the world

International Nuclear Information System (INIS)

Wojcik, T.

2000-01-01

The actual state and tendencies of nuclear power further development for different world regions have been presented and discussed. The problem of safety of energetic nuclear reactors, radioactive waste management and related problems have been discussed in respect of regulations in different countries. The economical aspects of nuclear energetics in comparison with different fossil fuel power plants exploitation costs has been presented as well. The official state of international organizations (IAEA, WANO, HASA etc.) have been also shown in respect to subject presented

Bioenergy, material, and nutrients recovery from household waste: Advanced material, substance, energy, and cost flow analysis of a waste refinery process

International Nuclear Information System (INIS)

Tonini, Davide; Dorini, Gianluca; Astrup, Thomas Fruergaard

2014-01-01

Highlights: • We modeled material, substance, energy, and cost flows of a waste refinery process. • Ca. 56% of 1 Mg dry waste input can be recovered as bioliquid yielding 6.2 GJ biogas. • Nutrients and carbon recovery in the bioliquid was estimated to 81–89%. • The biogenic carbon in the input waste was 63% of total carbon based on 14 C analyses. • The quality of the digestate may be critical with respect to use on land. - Abstract: Energy, materials, and resource recovery from mixed household waste may contribute to reductions in fossil fuel and resource consumption. For this purpose, legislation has been enforced to promote energy recovery and recycling. Potential solutions for separating biogenic and recyclable materials are offered by waste refineries where a bioliquid is produced from enzymatic treatment of mixed waste. In this study, potential flows of materials, energy, and substances within a waste refinery were investigated by combining sampling, analyses, and modeling. Existing material, substance, and energy flow analysis was further advanced by development of a mathematical optimization model for determination of the theoretical recovery potential. The results highlighted that the waste refinery may recover ca. 56% of the dry matter input as bioliquid, yielding 6.2 GJ biogas-energy. The potential for nitrogen, phosphorous, potassium, and biogenic carbon recovery was estimated to be between 81% and 89% of the input. Biogenic and fossil carbon in the mixed household waste input was determined to 63% and 37% of total carbon based on 14 C analyses. Additional recovery of metals and plastic was possible based on further process optimization. A challenge for the process may be digestate quality, as digestate may represent an emission pathway when applied on land. Considering the potential variability of local revenues for energy outputs, the costs for the waste refinery solution appeared comparable with alternatives such as direct incineration

Pilot-Plant for Energy Recovery from Tropical Waste Food Materials ...

African Journals Online (AJOL)

An experimental unit for obtaining gaseous methane from waste food materials is discussed and results are presented for experimental tests with animal wastes and tropical waste food materials. The tropical waste food considered include garri, boiled beans and plantains. As expected, the animal wastes produced higher ...

Radiation damage in nuclear waste materials

International Nuclear Information System (INIS)

Jencic, I.

2000-01-01

Final disposal of high-level radioactive nuclear waste is usually envisioned in some sort of ceramic material. The physical and chemical properties of host materials for nuclear waste can be altered by internal radiation and consequently their structural integrity can be jeopardized. Assessment of long-term performance of these ceramic materials is therefore vital for a safe and successful disposal. This paper presents an overview of studies on several possible candidate materials for immobilization of fission products and actinides, such as spinel (MgAl 2 O 4 ), perovskite (CaTiO 3 ), zircon (ZrSiO 4 ), and pyrochlore (Gd 2 Ti 2 O 7 and Gd 2 Zr 2 O 7 ). The basic microscopic picture of radiation damage in ceramics consists of atomic displacements and ionization. In many cases these processes result in amorphization (metaminctization) of irradiated material. The evolution of microscopic structure during irradiation leads to various macroscopic radiation effects. The connection between microscopic and macroscopic picture is in most cases at least qualitatively known and studies of radiation induced microscopic changes are therefore an essential step in the design of a reliable nuclear waste host material. The relevance of these technologically important results on our general understanding of radiation damage processes and on current research efforts in Slovenia is also addressed. (author)

Nuclear Materials: Reconsidering Wastes and Assets - 13193

International Nuclear Information System (INIS)

Michalske, T.A.

2013-01-01

The nuclear industry, both in the commercial and the government sectors, has generated large quantities of material that span the spectrum of usefulness, from highly valuable ('assets') to worthless ('wastes'). In many cases, the decision parameters are clear. Transuranic waste and high level waste, for example, have no value, and is either in a final disposition path today, or - in the case of high level waste - awaiting a policy decision about final disposition. Other materials, though discardable, have intrinsic scientific or market value that may be hidden by the complexity, hazard, or cost of recovery. An informed decision process should acknowledge the asset value, or lack of value, of the complete inventory of materials, and the structure necessary to implement the range of possible options. It is important that informed decisions are made about the asset value for the variety of nuclear materials available. For example, there is a significant quantity of spent fuel available for recycle (an estimated $4 billion value in the Savannah River Site's (SRS) L area alone); in fact, SRS has already blended down more than 300 metric tons of uranium for commercial reactor use. Over 34 metric tons of surplus plutonium is also on a path to be used as commercial fuel. There are other radiological materials that are routinely handled at the site in large quantities that should be viewed as strategically important and / or commercially viable. In some cases, these materials are irreplaceable domestically, and failure to consider their recovery could jeopardize our technological leadership or national defense. The inventories of nuclear materials at SRS that have been characterized as 'waste' include isotopes of plutonium, uranium, americium, and helium. Although planning has been performed to establish the technical and regulatory bases for their discard and disposal, recovery of these materials is both economically attractive and in the national interest. (authors)

Bacterial leaching of waste uranium materials.

Science.gov (United States)

Barbic, F F; Bracilović, D M; Krajincanić, B V; Lucić, J L

1976-01-01

The effect of ferrobacteria and thiobacteria on the leaching of waste uranium materials from which 70-80% of uranium was previously leached by classical chemical hydrometallurgical procedure has been investigated. The bacteria used are found in the ore and the mine water of Zletovska River locality, Yugoslavia. Parameters of biological leaching were examined in the laboratory. Leaching conditions were changed with the aim of increasing the amount of uranium leached. The effect of pyrite added to the waste materials before the beginning of leaching has also been examined. Uranium leaching is directly proportional to the composition and number of ferrobacteria and thiobacteria, and increased by almost twice the value obtained from the same starting materials without using bacteria. Increased sulphuric acid concentrations stimulate considerably the rate of leaching. Uranium leaching is increased up to 20% while sulphuric acid consumption is simultaneously decreased by the addition of pyrite. Uranium concentrations in starting waste materials used for leaching were extremely low (0.0278 and 0.372% U) but about 60% recovery of uranium was obtained, with relatively low consumption of sulphuric acid.

Bacterial leaching of waste uranium materials

International Nuclear Information System (INIS)

Barbic, F.F.; Bracilovic, D.M.; Krajincanic, B.V.; Lucic, J.L.

1976-01-01

The effect of ferrobacteria and thiobacteria on the leaching of waste uranium materials from which 70-80% of uranium was previously leached by classical chemical hydrometallurgical procedure has been investigated. The bacteria used are found in the ore and the mine water of Zletovska River locality, Yugoslavia. Parameters of biological leaching were examined in the laboratory. Leaching conditions were changed with the aim of increasing the amount of uranium leached. The effect of pyrite added to the waste materials before the beginning of leaching has also been examined. Uranium leaching is directly proportional to the composition and number of ferrobacteria and thiobacteria, and increased by almost twice the value obtained from the same starting materials without using bacteria. Increased sulphuric acid concentrations stimulate considerably the rate of leaching. Uranium leaching is increased up to 20% while sulphuric acid consumption is simultaneously decreased by the addition of pyrite. Uranium concentrations in starting waste materials used for leaching were extremely low (0.0278 and 0.0372% U) but about 60% recovery of uranium was obtained, with relatively low consumption of sulphuric acid. (author)

Reaction path of energetic materials using THOR code

Science.gov (United States)

Durães, L.; Campos, J.; Portugal, A.

1998-07-01

The method of predicting reaction path, using THOR code, allows for isobar and isochor adiabatic combustion and CJ detonation regimes, the calculation of the composition and thermodynamic properties of reaction products of energetic materials. THOR code assumes the thermodynamic equilibria of all possible products, for the minimum Gibbs free energy, using HL EoS. The code allows the possibility of estimating various sets of reaction products, obtained successively by the decomposition of the original reacting compound, as a function of the released energy. Two case studies of thermal decomposition procedure were selected, calculated and discussed—pure Ammonium Nitrate and its based explosive ANFO, and Nitromethane—because their equivalence ratio is respectively lower, near and greater than the stoicheiometry. Predictions of reaction path are in good correlation with experimental values, proving the validity of proposed method.

Radioactive waste solidification material

International Nuclear Information System (INIS)

Nishihara, Yukio; Wakuta, Kuniharu; Ishizaki, Kanjiro; Koyanagi, Naoaki; Sakamoto, Hiroyuki; Uchida, Ikuo.

1992-01-01

The present invention concerns a radioactive waste solidification material containing vermiculite cement used for a vacuum packing type waste processing device, which contains no residue of calcium hydroxide in cement solidification products. No residue of calcium hydroxide means, for example, that peak of Ca(OH) 2 is not recognized in an X ray diffraction device. With such procedures, since calcium sulfoaluminate clinker and Portland cement themselves exhibit water hardening property, and slugs exhibit hydration activity from the early stage, the cement exhibits quick-hardening property, has great extension of long term strength, further, has no shrinking property, less dry- shrinkage, excellent durability, less causing damages such as cracks and peeling as processing products of radioactive wastes, enabling to attain highly safe solidification product. (T.M.)

Co-disposal of mixed waste materials

International Nuclear Information System (INIS)

Phillips, S.J.; Alexander, R.G.; Crane, P.J.; England, J.L.; Kemp, C.J.; Stewart, W.E.

1993-08-01

Co-disposal of process waste streams with hazardous and radioactive materials in landfills results in large, use-efficiencies waste minimization and considerable cost savings. Wasterock, produced from nuclear and chemical process waste streams, is segregated, treated, tested to ensure regulatory compliance, and then is placed in mixed waste landfills, burial trenches, or existing environmental restoration sites. Large geotechnical unit operations are used to pretreat, stabilize, transport, and emplace wasterock into landfill or equivalent subsurface structures. Prototype system components currently are being developed for demonstration of co-disposal

The waste of assistance material perceived by nursing students

Directory of Open Access Journals (Sweden)

Magaly Cecília Franchini Reichert

2017-11-01

Full Text Available The study aimed to identify the opinion of nursing students about the waste of assistance materials in practical learning activities. We conducted an exploratory, descriptive study with a quantitative approach. One hundred and eighty-six students composed the sample and they answered to an instrument with affirmatives measured by a Likert-type scale. More than half of students believed that institutions where they are interns waste materials; 76% of fourth grade students (p<0.001 acknowledged to waste materials during their internships and, 89% of the same year (p<0.001 attributed waste to conducting a procedure for the first time. The study allowed the discussion about waste materials during nursing training, alerting about the importance of adequate management of these resources besides the nursing responsibility with the environment and sustainable practices.

Method of treating radioactive waste material

International Nuclear Information System (INIS)

Allison, W.

1980-01-01

A method of treating radioactive waste material, particularly a radioactive sludge, is described comprising separating solid material from liquid material, compressing the solid material and encapsulating the solid material in a hardenable composition such as cement, bitumen or a synthetic resin. The separation and compaction stages are conveniently effected in a tube press. (author)

Study on penetration-induced initiation of energetic fragment

Science.gov (United States)

Qiao, Xiangxin; Xu, Heyang

2017-09-01

In order to investigate penetration-induced initiation of energetic fragment penetrating target, PTFE/Al (mass ratio 73.5/26.5) pressed and sintered into a Ф8mm × 8mm cylinder. To form energetic fragment, the cylinder was put into a closed container made by 35CrMnSiA. The container is 12mm long, 2mm thick. Energetic fragments were launched by a 14.5mm ballistic gun with a series of velocities and the penetrate process was simulated by AUTODYN-3D. The results show that the stress peak of energetic material exceed the initiation threshold, and energetic material will deflagrate, when energetic fragments impact velocity more than 800 m/s. The research results can provide reference for designs of energetic warhead.

Real time in-situ sensing of damage evolution in nanocomposite bonded surrogate energetic materials

Science.gov (United States)

Sengezer, Engin C.; Seidel, Gary D.

2016-04-01

The current work aims to explore the potential for in-situ structural health monitoring in polymer bonded energetic materials through the introduction of carbon nanotubes (CNTs) into the binder phase as a means to establish a significant piezoresistive response through the resulting nanocomposite binder. The experimental effort herein is focused towards electro-mechanical characterization of surrogate materials in place of actual energetic (explosive) materials in order to provide proof of concept for the strain and damage sensing. The electrical conductivity and the piezoresistive behavior of samples containing randomly oriented MWCNTs introduced into the epoxy (EPON 862) binder of 70 wt% ammonium perchlorate-epoxy hybrid composites are quantitatively and qualitatively evaluated. Brittle failure going through linear elastic behavior, formation of microcracks leading to reduction in composite load carrying capacity and finally macrocracks resulting in eventual failure are observed in the mechanical response of MWNT-ammonium perchlorateepoxy hybrid composites. Incorporating MWNTs into local polymer binder improves the effective stiffness about 40% compared to neat ammonium perchlorate-polymer samples. The real time in-situ relative change in resistance for MWNT hybrid composites was detected with the applied strains through piezoresistive response.

Solid waste and materials systems alternatives study summary

International Nuclear Information System (INIS)

Kasper, J.R.; Smith, S.T.

1996-01-01

The Hanford Site is a 560-sq.-mi. area in southeastern Washington State owned and operated by the U.S. Department of Energy (DOE). Previous weapons program activities and recent environmental cleanup activities at the Hanford Site have resulted in an accumulation of large quantities of solid wastes and materials. Future Decontamination and Decommissioning (D ampersand D) and Environmental Remediation activities will generate additional wastes. This paper provides a summary of a recently completed analysis of the Hanford Site Solid Wastes and Materials. The analysis involved development and compilation of waste stream and material information including type, classification. location current and project volumes, and curie content. Current program plans for treatment, storage, and disposal/disposition (TSD) have also been included in this analysis

Material control and accountability procedures for a waste isolation repository

International Nuclear Information System (INIS)

Jenkins, J.D.; Allen, E.J.; Blakeman, E.D.

1978-05-01

The material control and accountability needs of a waste isolation repository are examined. Three levels of control are discussed: (1) item identification and control, (2) tamper indication, and (3) quantitative material assay. A summary of waste characteristics is presented and, based on these, plus a consideration of the accessibility of the various types of waste, material control by item identification and accountability (where the individual waste container is the basic unit) is recommended. Tamper indicating procedures are also recommended for the intermediate and low level waste categories

Laboratory Testing of Waste Isolation Pilot Plant Surrogate Waste Materials

Science.gov (United States)

Broome, S.; Bronowski, D.; Pfeifle, T.; Herrick, C. G.

2011-12-01

The Waste Isolation Pilot Plant (WIPP) is a U.S. Department of Energy geological repository for the permanent disposal of defense-related transuranic (TRU) waste. The waste is emplaced in rooms excavated in the bedded Salado salt formation at a depth of 655 m below the ground surface. After emplacement of the waste, the repository will be sealed and decommissioned. WIPP Performance Assessment modeling of the underground material response requires a full and accurate understanding of coupled mechanical, hydrological, and geochemical processes and how they evolve with time. This study was part of a broader test program focused on room closure, specifically the compaction behavior of waste and the constitutive relations to model this behavior. The goal of this study was to develop an improved waste constitutive model. The model parameters are developed based on a well designed set of test data. The constitutive model will then be used to realistically model evolution of the underground and to better understand the impacts on repository performance. The present study results are focused on laboratory testing of surrogate waste materials. The surrogate wastes correspond to a conservative estimate of the degraded containers and TRU waste materials after the 10,000 year regulatory period. Testing consists of hydrostatic, uniaxial, and triaxial tests performed on surrogate waste recipes that were previously developed by Hansen et al. (1997). These recipes can be divided into materials that simulate 50% and 100% degraded waste by weight. The percent degradation indicates the anticipated amount of iron corrosion, as well as the decomposition of cellulosics, plastics, and rubbers. Axial, lateral, and volumetric strain and axial and lateral stress measurements were made. Two unique testing techniques were developed during the course of the experimental program. The first involves the use of dilatometry to measure sample volumetric strain under a hydrostatic condition. Bulk

Materials Science of High-Level Nuclear Waste Immobilization

International Nuclear Information System (INIS)

Weber, William J.; Navrotsky, Alexandra; Stefanovsky, S. V.; Vance, E. R.; Vernaz, Etienne Y.

2009-01-01

With the increasing demand for the development of more nuclear power comes the responsibility to address the technical challenges of immobilizing high-level nuclear wastes in stable solid forms for interim storage or disposition in geologic repositories. The immobilization of high-level nuclear wastes has been an active area of research and development for over 50 years. Borosilicate glasses and complex ceramic composites have been developed to meet many technical challenges and current needs, although regulatory issues, which vary widely from country to country, have yet to be resolved. Cooperative international programs to develop advanced proliferation-resistant nuclear technologies to close the nuclear fuel cycle and increase the efficiency of nuclear energy production might create new separation waste streams that could demand new concepts and materials for nuclear waste immobilization. This article reviews the current state-of-the-art understanding regarding the materials science of glasses and ceramics for the immobilization of high-level nuclear waste and excess nuclear materials and discusses approaches to address new waste streams

Buried waste containment system materials. Final Report

International Nuclear Information System (INIS)

Weidner, J.R.; Shaw, P.G.

1997-10-01

This report describes the results of a test program to validate the application of a latex-modified cement formulation for use with the Buried Waste Containment System (BWCS) process during a proof of principle (POP) demonstration. The test program included three objectives. One objective was to validate the barrier material mix formulation to be used with the BWCS equipment. A basic mix formula for initial trials was supplied by the cement and latex vendors. The suitability of the material for BWCS application was verified by laboratory testing at the Idaho National Engineering and Environmental Laboratory (INEEL). A second objective was to determine if the POP BWCS material emplacement process adversely affected the barrier material properties. This objective was met by measuring and comparing properties of material prepared in the INEEL Materials Testing Laboratory (MTL) with identical properties of material produced by the BWCS field tests. These measurements included hydraulic conductivity to determine if the material met the US Environmental Protection Agency (EPA) requirements for barriers used for hazardous waste sites, petrographic analysis to allow an assessment of barrier material separation and segregation during emplacement, and a set of mechanical property tests typical of concrete characterization. The third objective was to measure the hydraulic properties of barrier material containing a stop-start joint to determine if such a feature would meet the EPA requirements for hazardous waste site barriers

Nuclear Materials: Reconsidering Wastes and Assets - 13193

Energy Technology Data Exchange (ETDEWEB)

Michalske, T.A. [Savannah River National Laboratory (United States)

2013-07-01

The nuclear industry, both in the commercial and the government sectors, has generated large quantities of material that span the spectrum of usefulness, from highly valuable ('assets') to worthless ('wastes'). In many cases, the decision parameters are clear. Transuranic waste and high level waste, for example, have no value, and is either in a final disposition path today, or - in the case of high level waste - awaiting a policy decision about final disposition. Other materials, though discardable, have intrinsic scientific or market value that may be hidden by the complexity, hazard, or cost of recovery. An informed decision process should acknowledge the asset value, or lack of value, of the complete inventory of materials, and the structure necessary to implement the range of possible options. It is important that informed decisions are made about the asset value for the variety of nuclear materials available. For example, there is a significant quantity of spent fuel available for recycle (an estimated $4 billion value in the Savannah River Site's (SRS) L area alone); in fact, SRS has already blended down more than 300 metric tons of uranium for commercial reactor use. Over 34 metric tons of surplus plutonium is also on a path to be used as commercial fuel. There are other radiological materials that are routinely handled at the site in large quantities that should be viewed as strategically important and / or commercially viable. In some cases, these materials are irreplaceable domestically, and failure to consider their recovery could jeopardize our technological leadership or national defense. The inventories of nuclear materials at SRS that have been characterized as 'waste' include isotopes of plutonium, uranium, americium, and helium. Although planning has been performed to establish the technical and regulatory bases for their discard and disposal, recovery of these materials is both economically attractive and in the

Rock-welding materials for deep borehole nuclear waste disposal.

Energy Technology Data Exchange (ETDEWEB)

Yang, Pin [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Wang, Yifeng [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Rodriguez, Mark A. [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Brady, Patrick Vane [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Swift, Peter N. [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States)

2015-11-01

The concept of deep borehole nuclear waste disposal has recently been proposed. Effective sealing of a borehole after waste emplacement is generally required. In a high temperature disposal mode, the sealing function will be fulfilled by melting the ambient granitic rock with waste decay heat or an external heating source, creating a melt that will encapsulate waste containers or plug a portion of the borehole above a stack of the containers. However, there are certain drawbacks associated with natural materials, such as high melting temperatures, slow crystallization kinetics, the resulting sealing materials generally being porous with low mechanical strength, insufficient adhesion to waste container surface, and lack of flexibility for engineering controls. Here we show that natural granitic materials can be purposefully engineered through chemical modifications to enhance the sealing capability of the materials for deep borehole disposal. This work systematically explores the effect of chemical modification and crystallinity (amorphous vs. crystalline) on the melting and crystallization processes of a granitic rock system. A number of engineered granitic materials have been obtained that have decreased melting points, enhanced viscous densification, and accelerated recrystallization rates without compromising the mechanical integrity of the materials.

Coastal structures, waste materials and fishery enhancement

Energy Technology Data Exchange (ETDEWEB)

Collins, K.J.; Jensen, A.C.; Lockwood, A.P.M.; Lockwood, S.J. [University of Southampton, Southampton (United Kingdom). Dept. of Oceanography

1994-09-01

Current UK practice relating to the disposal of material at sea is reviewed. The use of stabilization technology relating to bulk waste materials, coal ash, oil ash and incinerator ash is discussed. The extension of this technology to inert minestone waste and tailings, contaminated dredged sediments and phosphogypsum is explored. Uses of stabilized wastes are considered in the areas of habitat restoration, coastal defense and fishery enhancement. It is suggested that rehabilitation of marine dump sites receiving loose waste such as pulverized fuel ash (PFA) could be enhanced by the continued dumping of the material but in a stabilized block form, so creating new habitat diversity. Global warming predictions include sea level rise and increased storm frequency. This is of particular concern along the southern and eastern coasts of the UK. The emphasis of coastal defense is changing from hard seawalls to soft options which include offshore barriers to reduce wave energy reaching the coast. Stabilized waste materials could be included in these and other marine constructions with possible economic benefit. Ministry of Agriculture, Fisheries and Food (MAFF), the regulatory authority in England and Wales for marine disposal/construction, policy regarding marine structures and fishery enhancement is outlined. A case is made for the inclusion of fishery enhancement features in future coastal structures. Examples of the productivity of man-made structures are given. Slight modification of planned structures and inclusion of suitable habitat niches could allow for the cultivation of kelp, molluscs, crustacea and fish.

Materials characterization center workshop on compositional and microstructural analysis of nuclear waste materials. Summary report

International Nuclear Information System (INIS)

Daniel, J.L.; Strachan, D.M.; Shade, J.W.; Thomas, M.T.

1981-06-01

The purpose of the Workshop on Compositional and Microstructural Analysis of Nuclear Waste Materials, conducted November 11 and 12, 1980, was to critically examine and evaluate the various methods currently used to study non-radioactive, simulated, nuclear waste-form performance. Workshop participants recognized that most of the Materials Characterization Center (MCC) test data for inclusion in the Nuclear Waste Materials Handbook will result from application of appropriate analytical procedures to waste-package materials or to the products of performance tests. Therefore, the analytical methods must be reliable and of known accuracy and precision, and results must be directly comparable with those from other laboratories and from other nuclear waste materials. The 41 participants representing 18 laboratories in the United States and Canada were organized into three working groups: Analysis of Liquids and Solutions, Quantitative Analysis of Solids, and Phase and Microstructure Analysis. Each group identified the analytical methods favored by their respective laboratories, discussed areas needing attention, listed standards and reference materials currently used, and recommended means of verifying interlaboratory comparability of data. The major conclusions from this workshop are presented

Youth Solid Waste Educational Materials List, November 1991.

Science.gov (United States)

Cornell Univ., Ithaca, NY. Cooperative Extension Service.

This guide provides a brief description and ordering information for approximately 300 educational materials for grades K-12 on the subject of solid waste. The materials cover a variety of environmental issues and actions related to solid waste management. Entries are divided into five sections including audiovisual programs, books, magazines,…

Incentivizing secondary raw material markets for sustainable waste management.

Science.gov (United States)

Schreck, Maximilian; Wagner, Jeffrey

2017-09-01

Notwithstanding several policy initiatives in many countries over a number of years, there remains a general sense that too much municipal solid waste is generated and that too much of the waste that is generated is landfilled. There is an emerging consensus that a sustainable approach to waste management requires further development of secondary raw material markets. The purpose of this paper is to propose a theoretical economic model that focuses upon this stage of a sustainable waste management program and explores policy options that could motivate efficiency in secondary raw material markets. In particular, we show how firm profit and social welfare optimizing objectives can be reconciled in a two-product market of waste management processes: landfilling and material reclamation. Our results provide theoretical support for building out recent Circular Economy initiatives as well as for the relatively recent emergence of landfill mining as a means for procuring secondary raw materials. Copyright © 2017 Elsevier Ltd. All rights reserved.

Characterization of materials for waste-canister compatibility studies

International Nuclear Information System (INIS)

McCoy, H.E.; Mack, J.E.

1981-10-01

Sample materials of 7 waste forms and 15 potential canister materials were procured for compatibility tests. These materials were characterized before being placed in test, and the results are the main topic of this report. A test capsule was designed for the tests in which disks of a single waste form were contacted with duplicate samples of canister materials. The capsules are undergoing short-term tests at 800 0 C and long-term tests at 100 and 300 0 C

Effect of Waste Materials on Performance of Self Compacting Concrete

OpenAIRE

DEMİREL, Sevgi; ÖZ, Hatice Öznur

2017-01-01

Asustainable waste management approach is increasingly important in order toconserve natural resources and reduce industrial waste. Creating new areas andmethods for evaluating waste materials has become one of the important researchareas of the scientific world. Due to the limited natural resources, recyclingapplications have emerged as a potential source of raw materials, especially inthe construction industry. For example, the use of industrial wastes (fly ash,marble dust, waste glass and ...

Material chemistry challenges in vitrification of high level radioactive waste

International Nuclear Information System (INIS)

Kaushik, C.P.

2008-01-01

Full text: Nuclear technology with an affective environmental management plan and focused attention on safety measures is a much cleaner source of electricity generation as compared to other sources. With this perspective, India has undertaken nuclear energy program to share substantial part of future need of power. Safe containment and isolation of nuclear waste from human environment is an indispensable part of this programme. Majority of radioactivity in the entire nuclear fuel cycle is high level radioactive liquid waste (HLW), which is getting generated during reprocessing of spent nuclear fuels. A three stage strategy for management of HLW has been adopted in India. This involves (i) immobilization of waste oxides in stable and inert solid matrices, (ii) interim retrievable storage of the conditioned waste product under continuous cooling and (iii) disposal in deep geological formation. Borosilicate glass matrix has been adopted in India for immobilization of HLW. Material issue are very important during the entire process of waste immobilization. Performance of the materials used in nuclear waste management determines its safety/hazards. Material chemistry therefore has a significant bearing on immobilization science and its technological development for management of HLW. The choice of suitable waste form to deploy for nuclear waste immobilization is difficult decision and the durability of the conditioned product is not the sole criterion. In any immobilization process, where radioactive materials are involved, the process and operational conditions play an important role in final selection of a suitable glass formulation. In remotely operated vitrification process, study of chemistry of materials like glass, melter, materials of construction of other equipment under high temperature and hostile corrosive condition assume significance for safe and un-interrupted vitrification of radioactive to ensure its isolation waste from human environment. The present

Molecular Modeling of Energetic Materials: The Parameterization and Validation of Nitrate Esters in the COMPASS Force Field

National Research Council Canada - National Science Library

Bunte, Steven

2000-01-01

To investigate the mechanical and other condensed phase properties of energetic materials using atomistic simulation techniques, the COMPASS force field has been expanded to include high-energy nitro functional groups...

An information system for sustainable materials management with material flow accounting and waste input–output analysis

Directory of Open Access Journals (Sweden)

Pi-Cheng Chen

2017-05-01

Full Text Available Sustainable materials management focuses on the dynamics of materials in economic and environmental activities to optimize material use efficiency and reduce environmental impact. A preliminary web-based information system is thus developed to analyze the issues of resource consumption and waste generation, enabling countries to manage resources and wastes from a life cycle perspective. This pioneering system features a four-layer framework that integrates information on physical flows and economic activities with material flow accounting and waste input–output table analysis. Within this framework, several applications were developed for different waste and resource management stakeholders. The hierarchical and interactive dashboards allow convenient overview of economy-wide material accounts, waste streams, and secondary resource circulation. Furthermore, the system can trace material flows through associated production supply chain and consumption activities. Integrated with economic models; this system can predict the possible overloading on the current waste management facility capacities and provide decision support for designing strategies to approach resource sustainability. The limitations of current system are specified for directing further enhancement of functionalities.

Physico-chemical characterisation of material fractions in household waste

DEFF Research Database (Denmark)

Götze, Ramona; Boldrin, Alessio; Scheutz, Charlotte

2016-01-01

State-of-the-art environmental assessment of waste management systems rely on data for the physico-chemical composition of individual material fractions comprising the waste in question. To derive the necessary inventory data for different scopes and systems, literature data from different sources...... and backgrounds are consulted and combined. This study provides an overview of physico-chemical waste characterisation data for individual waste material fractions available in literature and thereby aims to support the selection of data fitting to a specific scope and the selection of uncertainty ranges related...... to the data selection from literature. Overall, 97 publications were reviewed with respect to employed characterisation method, regional origin of the waste, number of investigated parameters and material fractions and other qualitative aspects. Descriptive statistical analysis of the reported physico...

Energetical fly ashes – separation and utilization of metallic valuable components

Directory of Open Access Journals (Sweden)

Michalíková Františka

2000-12-01

Full Text Available In the contribution, methods of separating metals – Fe, Al, Ge from energetic wastes – fly ashes are presented along with further possibilities of utilization of particular valuable components for industrial purposes.In the contribution, properties of energetic wastes are presented influencing the contents, separability, and utilizability of metal-bearing valuable components. From among physical properties these are grain size distribution and surface area. Chemical properties are characterized by elements contained in combusted coal whose content after combustion is increased 2 to 4 times, depending on the content of ash and combustible matters in original coal. Mineralogical properties of energetic wastes are determined by the combustion process conditions in the course of which mineral novelties are produced in concentrations suitable for separation.In the contribution, methods of separation and utilization of metals such as Fe, Al, Ge are described. From literature information on the processing of Fe component, as well as from results of experiments made at the Department of Mineral Processing and Environmental Protection, Technical University of Kosice follows that the highest concentration and mass yield of the component can be obtained from black coal fly ashes produced in smelting boilers. The content of Al in Slovak energetic wastes is lower than the 30 % Al2O3 limit that conditions an economic technological processing. Only in the case of black coal fly ash from TEKO Kosice and EVO Vojany was the Al2O3 content of 32.93 %. Therefore, in an indirect way – by separating the residues of uncombusted coal and magnetite Fe – the content of Al in fly ash was increased.For Ge, a principle of selective sizing has been utilized.A complex utilization of energetic wastes, that is the separation of metallic components, elimination of particular metals and the subsequent treatment of nonmetallic residue, should be an effective solution in various

Large-Scale Reactive Atomistic Simulation of Shock-induced Initiation Processes in Energetic Materials

Science.gov (United States)

Thompson, Aidan

2013-06-01

Initiation in energetic materials is fundamentally dependent on the interaction between a host of complex chemical and mechanical processes, occurring on scales ranging from intramolecular vibrations through molecular crystal plasticity up to hydrodynamic phenomena at the mesoscale. A variety of methods (e.g. quantum electronic structure methods (QM), non-reactive classical molecular dynamics (MD), mesoscopic continuum mechanics) exist to study processes occurring on each of these scales in isolation, but cannot describe how these processes interact with each other. In contrast, the ReaxFF reactive force field, implemented in the LAMMPS parallel MD code, allows us to routinely perform multimillion-atom reactive MD simulations of shock-induced initiation in a variety of energetic materials. This is done either by explicitly driving a shock-wave through the structure (NEMD) or by imposing thermodynamic constraints on the collective dynamics of the simulation cell e.g. using the Multiscale Shock Technique (MSST). These MD simulations allow us to directly observe how energy is transferred from the shockwave into other processes, including intramolecular vibrational modes, plastic deformation of the crystal, and hydrodynamic jetting at interfaces. These processes in turn cause thermal excitation of chemical bonds leading to initial chemical reactions, and ultimately to exothermic formation of product species. Results will be presented on the application of this approach to several important energetic materials, including pentaerythritol tetranitrate (PETN) and ammonium nitrate/fuel oil (ANFO). In both cases, we validate the ReaxFF parameterizations against QM and experimental data. For PETN, we observe initiation occurring via different chemical pathways, depending on the shock direction. For PETN containing spherical voids, we observe enhanced sensitivity due to jetting, void collapse, and hotspot formation, with sensitivity increasing with void size. For ANFO, we

Data on trapping and re-emission of energetic hydrogen isotopes and helium in materials, supplement 1

International Nuclear Information System (INIS)

Yamaguchi, Sadae; Sugizaki, Yasuaki; Ozawa, Kunio; Nakai, Yohta.

1984-05-01

This is the supplement to the data on trapping and re-emission of energetic hydrogen isotopes and helium in materials (JAERI-M 82-118). It contains 32 data up to end of 1982, dividing it into following 6 sections: 1) Dose Dependence, 2) Target Material Dependence, 3) Target Temperature Dependence, 4) Incident Energy Dependence, 5) Damage Effects and 6) Ion-Induced Release. (author)

Practice of the utilization of biomass from waste materials; Praxis der Verwertung von Biomasse aus Abfaellen

Energy Technology Data Exchange (ETDEWEB)

Wiemer, Klaus; Kern, Michael; Raussen, Thomas (eds.)

2010-07-01

(Martin Wellacher); (17) The Bio-QZ - an innovative process step for the increase of efficiency of biogas facilities (Karsten Mennerich); (18) Processing of biological wastes for the production of biogas (Thomas Authmann); (19) An example of a optimization measure in the area of processing biological wastes in the fermentation plant Leonberg (Rudi Sendersky); (20) The concept of materials management for municipal biological wastes and green waste in the administrative district Emsland (Heinz Boekers); (21) Cultivation of green waste places between material and energetic utilization (Leonhard Unterberg); (22) Construction and startup of a municipal thermal power station for fuels from green wastes (Guenter Hacklaender); (23) Biogas in Energy Verbund - Chances for municipal power suppliers (Thorsten Ebert); (24) New developments and perspectives in the hydrothermal carbonization (HTC) of biomass (Fritz Richarts).

Experimental Investigation of the Role of Defects in Detonation Sensitivity of Energetic Materials: Development of Techniques for Characterization

Science.gov (United States)

2009-12-31

materials. The initial work was focused on design and construction of an apparatus for injecting defects into the crystals using PZT ceramics ...in the energy partitioning (Table 2), which offers some insight into the nature of the energetic texture of crystalline materials not apparent in

Cementitions materials in nuclear waste management

International Nuclear Information System (INIS)

Roy, D.M.

1990-01-01

Cementitious materials have been investigated extensively to establish their role, and enable a prediction of their performance, when used for radioactive waste isolation. A number of applications have been addressed, ranging from those in high-level waste management, where their prime roles would be physical such as in sealing an underground waste repository, mechanical to serve as a protective cask for transport, or under certain conditions, both chemical and physical in the solidification of high-level waste. Cements also have been explored for their use in forming primary casks for containment of spent fuel assemblies. For the disposal of low-level (and in some countries, intermediate-level) waste, a cementitious matrix may be used to encapsulate the waste, thereby generating an integral waste form. In addition, concretes will be required to perform special structural roles, used to construct trenches, vaults, and other disposal units. Also, there are numerous applications where grouts are used for sealing purposes. This paper addresses each of these areas

Materials considerations relative to multibarrier waste isolation

International Nuclear Information System (INIS)

McCoy, H.E.; Griess, J.C.

1981-07-01

The environmental conditions associated with the storage of radioactive wastes are reviewed, and the corrosion of potential waste containment materials under these conditions is evaluated. The desired service life of about 1000 years is beyond the time period for which existing corrosion data can be extrapolated with certainty; however, titanium alloys seem to offer the most promise. The mechanical requirements for canisters and overpacks are considered and several candidate materials are selected. Designs for a canister and an overpack have been developed, and these are used to estimate the costs for three possible materials of construction

The application of waste fly ash and construction-waste in cement filling material in goaf

Science.gov (United States)

Chen, W. X.; Xiao, F. K.; Guan, X. H.; Cheng, Y.; Shi, X. P.; Liu, S. M.; Wang, W. W.

2018-01-01

As the process of urbanization accelerated, resulting in a large number of abandoned fly ash and construction waste, which have occupied the farmland and polluted the environment. In this paper, a large number of construction waste and abandoned fly ash are mixed into the filling material in goaf, the best formula of the filling material which containing a large amount of abandoned fly ash and construction waste is obtained, and the performance of the filling material is analyzed. The experimental results show that the cost of filling material is very low while the performance is very good, which have a good prospect in goaf.

Materials and Waste Management Research

Science.gov (United States)

EPA is developing data and tools to reduce waste, manage risks, reuse and conserve natural materials, and optimize energy recovery. Collaboration with states facilitates assessment and utilization of technologies developed by the private sector.

Compacting biomass waste materials for use as fuel

Science.gov (United States)

Zhang, Ou

Every year, biomass waste materials are produced in large quantity. The combustibles in biomass waste materials make up over 70% of the total waste. How to utilize these waste materials is important to the nation and the world. The purpose of this study is to test optimum processes and conditions of compacting a number of biomass waste materials to form a densified solid fuel for use at coal-fired power plants or ordinary commercial furnaces. Successful use of such fuel as a substitute for or in cofiring with coal not only solves a solid waste disposal problem but also reduces the release of some gases from burning coal which cause health problem, acid rain and global warming. The unique punch-and-die process developed at the Capsule Pipeline Research Center, University of Missouri-Columbia was used for compacting the solid wastes, including waste paper, plastics (both film and hard products), textiles, leaves, and wood. The compaction was performed to produce strong compacts (biomass logs) under room temperature without binder and without preheating. The compaction conditions important to the commercial production of densified biomass fuel logs, including compaction pressure, pressure holding time, back pressure, moisture content, particle size, binder effects, and mold conditions were studied and optimized. The properties of the biomass logs were evaluated in terms of physical, mechanical, and combustion characteristics. It was found that the compaction pressure and the initial moisture content of the biomass material play critical roles in producing high-quality biomass logs. Under optimized compaction conditions, biomass waste materials can be compacted into high-quality logs with a density of 0.8 to 1.2 g/cm3. The logs made from the combustible wastes have a heating value in the range 6,000 to 8,000 Btu/lb which is only slightly (10 to 30%) less than that of subbituminous coal. To evaluate the feasibility of cofiring biomass logs with coal, burn tests were

Anthropogenic materials and products containing natural radionuclides. Pt. 1a. Radiation properties of raw materials and waste materials. A literature study

International Nuclear Information System (INIS)

Reichelt, A.; Roehrer, J.; Lehmann, K.H.

1995-12-01

Cased on the literature study, the publication presents relevant data on raw materials and wastes containing natural radionuclides. The study is part 1a of the project on ''Anthropogenic materials and waste materials containing natural radionuclides''. Part 1 of the project gives data and information on about 100 different materials and wastes or products for household or industrial applications which contain significant amounts of natural radioactivity. In addition, part 1 presents for some of these materials information on their applications, consumption, radioactivity and resulting radiation doses. The raw materials and waste materials on the list in part 1 are characterised in this 1a report. Wherever appropriate, two or more materials are dealt with in one chapter, as e.g. felspar and felspar sands (pegmatite), talcum, and soapstone. The wastes are dealt with in the chapters discussing the relevant raw materials. The information given is as derived from the literature and does not include comments or evaluation by the authors of this report. Whenever the literature study did not yield information on radiological aspects of a material on the list, an appropriate notice is given. (Orig./DG) [de

Engineering materials for high level radioactive waste repository

International Nuclear Information System (INIS)

Wen Zhijian

2009-01-01

Radioactive wastes can arise from a wide range of human activities and have different physical and chemical forms with various radioactivity. The high level radioactive wastes (HLW)are characterized by nuclides of very high initial radioactivity, large thermal emissivity and the long life-term. The HLW disposal is highly concerned by the scientists and the public in the world. At present, the deep geological disposal is regarded as the most reasonable and effective way to safely dispose high-level radioactive wastes in the world. The conceptual model of HLW geological disposal in China is based on a multi-barrier system that combines an isolating geological environment with an engineering barrier system(EBS). The engineering materials in EBS include the vitrified HLW, canister, overpack, buffer materials and backfill materials. Referring to progress in the world, this paper presents the function, the requirement for material selection and design, and main scientific projects of R and D of engineering materials in HLW repository. (authors)

Modeling of high energy laser ignition of energetic materials

International Nuclear Information System (INIS)

Lee, Kyung-cheol; Kim, Ki-hong; Yoh, Jack J.

2008-01-01

We present a model for simulating high energy laser heating and ignition of confined energetic materials. The model considers the effect of irradiating a steel plate with long laser pulses and continuous lasers of several kilowatts and the thermal response of well-characterized high explosives for ignition. Since there is enough time for the thermal wave to propagate into the target and to create a region of hot spot in the high explosives, electron thermal diffusion of ultrashort (femto- and picosecond) lasing is ignored; instead, heat diffusion of absorbed laser energy in the solid target is modeled with thermal decomposition kinetic models of high explosives. Numerically simulated pulsed-laser heating of solid target and thermal explosion of cyclotrimethylenetrinitramine, triaminotrinitrobenzene, and octahydrotetranitrotetrazine are compared to experimental results. The experimental and numerical results are in good agreement

The low-level waste handling challenge at the Feed Materials Production Center

International Nuclear Information System (INIS)

Harmon, J.E.; Diehl, D.E.; Gardner, R.L.

1988-02-01

The management of low-level wastes from the production of depleted uranium at the Feed Materials Production Center presents an enormous challenge. The recovery of uranium from materials contaminated with depleted uranium is usually not economical. As a result, large volumes of wastes are generated. The Westinghouse Materials Company of Ohio has established an aggressive waste management program. Simple solutions have been applied to problems in the areas of waste handling and waste minimization. The success of this program has been demonstrated by the reduction of low-level waste inventory at the Feed Materials Production Center. 8 refs., 4 figs

The low-level waste handling challenge at the Feed Materials Production Center

International Nuclear Information System (INIS)

Harmon, J.E.; Diehl, D.E.; Gardner, R.L.

1988-01-01

The management of low-level wastes from the production of depleted uranium at the Feed Materials Production Center presents an enormous challenge. The recovery of uranium from materials contaminated with depleted uranium is usually not economical. As a result, large volumes of wastes are generated. The Westinghouse Materials Company of Ohio has established an aggressive waste management program. Simple solutions have been applied to problems in the areas of waste handling and waste minimization. The success of this program has been demonstrated by the reduction of low-level waste inventory at the Feed Materials Production Center

Immobilization of INEL low-level radioactive wastes in ceramic containment materials

International Nuclear Information System (INIS)

Seymour, W.C.; Kelsey, P.V.

1978-11-01

INEL low-level radioactive wastes have an overall chemical composition that lends itself to self-containment in a ceramic-based material. Fewer chemical additives would be needed to process the wastes than to process high-level wastes or use a mixture containment method. The resulting forms of waste material could include a basalt-type glass or glass ceramic and a ceramic-type brick. Expected leach resistance is discussed in relationshp to data found in the literature for these materials and appears encouraging. An overview of possible processing steps for the ceramic materials is presented

Survey of matrix materials for solidified radioactive high-level waste

Energy Technology Data Exchange (ETDEWEB)

Gurwell, W.E.

1981-09-01

Pacific Northwest Laboratory (PNL) has been investigating advanced waste forms, including matrix waste forms, that may provide a very high degree of stability under the most severe repository conditions. The purpose of this study was to recommend practical matrix materials for future development that most enhance the stability of the matrix waste forms. The functions of the matrix were reviewed. Desirable matrix material properties were discussed and listed relative to the matrix functions. Potential matrix materials were discussed and recommendations were made for future matrix development. The matrix mechanically contains waste cores, reduces waste form temperatures, and is capable of providing a high-quality barrier to leach waters. High-quality barrier matrices that separate and individually encapsulate the waste cores are fabricated by powder fabrication methods, such as sintering, hot pressing, and hot isostatic pressing. Viable barrier materials are impermeable, extremely corrosion resistant, and mechanically strong. Three material classes potentially satisfy the requirements for a barrier matrix and are recommended for development: titanium, glass, and graphite. Polymers appear to be marginally adequate, and a more thorough engineering assessment of their potential should be made.

Survey of matrix materials for solidified radioactive high-level waste

International Nuclear Information System (INIS)

Gurwell, W.E.

1981-09-01

Pacific Northwest Laboratory (PNL) has been investigating advanced waste forms, including matrix waste forms, that may provide a very high degree of stability under the most severe repository conditions. The purpose of this study was to recommend practical matrix materials for future development that most enhance the stability of the matrix waste forms. The functions of the matrix were reviewed. Desirable matrix material properties were discussed and listed relative to the matrix functions. Potential matrix materials were discussed and recommendations were made for future matrix development. The matrix mechanically contains waste cores, reduces waste form temperatures, and is capable of providing a high-quality barrier to leach waters. High-quality barrier matrices that separate and individually encapsulate the waste cores are fabricated by powder fabrication methods, such as sintering, hot pressing, and hot isostatic pressing. Viable barrier materials are impermeable, extremely corrosion resistant, and mechanically strong. Three material classes potentially satisfy the requirements for a barrier matrix and are recommended for development: titanium, glass, and graphite. Polymers appear to be marginally adequate, and a more thorough engineering assessment of their potential should be made

Energetics Laboratory Facilities

Data.gov (United States)

Federal Laboratory Consortium — These energetic materials laboratories are equipped with explosion proof hoods with blow out walls for added safety, that are certified for safe handling of primary...

Materials design considerations and selection for a large rad waste incinerator

International Nuclear Information System (INIS)

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

1997-01-01

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

The waste minimization program at the Feed Materials Production Center

International Nuclear Information System (INIS)

Blasdel, J.E.; Crotzer, M.E.; Gardner, R.L.; Kato, T.R.; Spradlin, C.N.

1987-01-01

A waste minimization program is being implemented at the Feed Materials Production Center to reduce the generation of uranium-contaminated wastes and to comply with existing and forthcoming regulations. Procedures and plans are described which deal with process and non-process trash, contaminated wood and metals, used metal drums, and major process wastes such as contaminated magnesium fluoride and neutralized raffinate. Waste minimization techniques used include segregation, source reduction, volume reduction, material substitution and waste/product recycle. The importance of training, communication, and incentives is also covered. 5 refs., 11 figs

Waste in Education: The Potential of Materiality and Practice

Science.gov (United States)

Jørgensen, Nanna Jordt; Madsen, Katrine Dahl; Laessøe, Jeppe

2018-01-01

This article explores how waste materials and waste practices figure in education, pointing to educational potentials of waste which have hitherto received little consideration in environmental and sustainability education practice and research. Building on empirical research on waste education in Danish schools and preschools, we discuss how an…

Removal of radioactive and other hazardous material from fluid waste

Science.gov (United States)

Tranter, Troy J [Idaho Falls, ID; Knecht, Dieter A [Idaho Falls, ID; Todd, Terry A [Aberdeen, ID; Burchfield, Larry A [W. Richland, WA; Anshits, Alexander G [Krasnoyarsk, RU; Vereshchagina, Tatiana [Krasnoyarsk, RU; Tretyakov, Alexander A [Zheleznogorsk, RU; Aloy, Albert S [St. Petersburg, RU; Sapozhnikova, Natalia V [St. Petersburg, RU

2006-10-03

Hollow glass microspheres obtained from fly ash (cenospheres) are impregnated with extractants/ion-exchangers and used to remove hazardous material from fluid waste. In a preferred embodiment the microsphere material is loaded with ammonium molybdophosphonate (AMP) and used to remove radioactive ions, such as cesium-137, from acidic liquid wastes. In another preferred embodiment, the microsphere material is loaded with octyl(phenyl)-N-N-diisobutyl-carbamoylmethylphosphine oxide (CMPO) and used to remove americium and plutonium from acidic liquid wastes.

Microwave reactor for utilizing waste materials

Directory of Open Access Journals (Sweden)

M. Pigiel

2010-01-01

Full Text Available The paper presents a designed and manufactured, semi-industrial microwave reactor for thermal utilization of asbestos-bearing wastes. Presented are also semi-industrial tests of utilizing such wastes. It was found that microwave heating can be applied for utilizing asbestos with use of suitable wetting agents. The wetting agents should ensure continuous heating process above 600 °C, as well as uniform heat distribution in the whole volume of the utilized material. Analysis of the neutralization process indicates a possibility of presenting specific, efficient and effective process parameters of utilizing some asbestos-bearing industrial wastes.

The function of packing materials in a high-level nuclear waste repository and some candidate materials: Salt Repository Project

International Nuclear Information System (INIS)

Bunnell, L.R.; Shade, J.W.

1987-03-01

Packing materials should be included in waste package design for a high-level nuclear waste repository in salt. A packing material barrier would increase confidence in the waste package by alleviating possible shortcomings in the present design and prolonging confinement capabilities. Packing materials have been studied for uses in other geologic repositories; appropriately chosen, they would enhance the confinement capabilities of salt repository waste packages in several ways. Benefits of packing materials include retarding or chemically modifying brines to reduce corrosion of the waste package, providing good thermal conductivity between the waste package and host rock, retarding or absorbing radionuclides, and reducing the massiveness of the waste package. These benefits are available at low percentage of total repository cost, if the packing material is properly chosen and used. Several candidate materials are being considered, including oxides, hydroxides, silicates, cement-based mixtures, and clay mixtures. 18 refs

Characterization study of industrial waste glass as starting material ...

African Journals Online (AJOL)

In present study, an industrial waste glass was characterized and the potential to assess as starting material in development of bioactive materials was investigated. A waste glass collected from the two different glass industry was grounded to fine powder. The samples were characterized using X-ray fluorescence (XRF), ...

State-of-the-art review of materials properties of nuclear waste forms

International Nuclear Information System (INIS)

Mendel, J.E.; Nelson, R.D.; Turcotte, R.P.; Gray, W.J.; Merz, M.D.; Roberts, F.P.; Weber, W.J.; Westsik, J.H. Jr.; Clark, D.E.

1981-04-01

The Materials Characterization Center (MCC) was established at the Pacific Northwest Laboratory to assemble a standardized nuclear waste materials data base for use in research, systems and facility design, safety analyses, and waste management decisions. This centralized data base will be provided through the means of a Nuclear Waste Materials Handbook. The first issue of the Handbook will be published in the fall of 1981 in looseleaf format so that it can be updated as additional information becomes available. To ensure utmost reliability, all materials data appearing in the Handbook will be obtained by standard procedures defined in the Handbook and approved by an independent Materials Review Board (MRB) comprised of materials experts from Department of Energy laboratories and from universities and industry. In the interim before publication of the Handbook there is need for a report summarizing the existing materials data on nuclear waste forms. This review summarizes materials property data for the nuclear waste forms that are being developed for immobilization of high-level radioactive waste. It is intended to be a good representation of the knowledge concerning the properties of HLW forms as of March 1981. The table of contents lists the following topics: introduction which covers waste-form categories, and important waste-form materials properties; physical properties; mechanical properties; chemical durability; vaporization; radiation effects; and thermal phase stability

Computational studies on energetic properties of nitrogen-rich ...

Indian Academy of Sciences (India)

Computational studies on energetic properties of nitrogen-rich energetic materials with ditetrazoles. LI XIAO-HONGa,b,∗ and ZHANG RUI-ZHOUa. aCollege of Physics and Engineering, Henan University of Science and Technology, Luoyang 471 003, China. bLuoyang Key Laboratory of Photoelectric Functional Materials, ...

Materials for high-level waste containment

International Nuclear Information System (INIS)

Marsh, G.P.

1982-01-01

The function of the high-level radioactive waste container in storage and of a container/overpack combination in disposal is considered. The consequent properties required from potential fabrication materials are discussed. The strategy adopted in selecting containment materials and the experimental programme underway to evaluate them are described. (U.K.)

Remote automated material handling of radioactive waste containers

International Nuclear Information System (INIS)

Greager, T.M.

1994-09-01

To enhance personnel safety, improve productivity, and reduce costs, the design team incorporated a remote, automated stacker/retriever, automatic inspection, and automated guidance vehicle for material handling at the Enhanced Radioactive and Mixed Waste Storage Facility - Phase V (Phase V Storage Facility) on the Hanford Site in south-central Washington State. The Phase V Storage Facility, scheduled to begin operation in mid-1997, is the first low-cost facility of its kind to use this technology for handling drums. Since 1970, the Hanford Site's suspect transuranic (TRU) wastes and, more recently, mixed wastes (both low-level and TRU) have been accumulating in storage awaiting treatment and disposal. Currently, the Hanford Site is only capable of onsite disposal of radioactive low-level waste (LLW). Nonradioactive hazardous wastes must be shipped off site for treatment. The Waste Receiving and Processing (WRAP) facilities will provide the primary treatment capability for solid-waste storage at the Hanford Site. The Phase V Storage Facility, which accommodates 27,000 drum equivalents of contact-handled waste, will provide the following critical functions for the efficient operation of the WRAP facilities: (1) Shipping/Receiving; (2) Head Space Gas Sampling; (3) Inventory Control; (4) Storage; (5) Automated/Manual Material Handling

Waste Package and Material Testing for the Proposed Yucca Mountain High Level Waste Repository

International Nuclear Information System (INIS)

Doering, Thomas; Pasupathi, V.

2002-01-01

Over the repository lifetime, the waste package containment barriers will perform various functions that will change with time. During the operational period, the barriers will function as vessels for handling, emplacement, and waste retrieval (if necessary). During the years following repository closure, the containment barriers will be relied upon to provide substantially complete containment, through 10,000 years and beyond. Following the substantially complete containment phase, the barriers and the waste package internal structures help minimize release of radionuclides by aqueous- and gaseous-phase transport. These requirements have lead to a defense-in-depth design philosophy. A multi-barrier design will result in a lower breach rate distributed over a longer period of time, thereby ensuring the regulatory requirements are met. The design of the Engineered Barrier System (EBS) has evolved. The initial waste package design was a thin walled package, 3/8 inch of stainless steel 304, that had very limited capacity, (3 PWR and 4 BWR assemblies) and performance characteristics, 300 to 1,000 years. This design required over 35,000 waste packages compared to today's design of just over 10,000 waste packages. The waste package designs are now based on a defense-in-depth/multi-barrier philosophy and have a capacity similar to the standard storage and rail transported spent nuclear fuel casks. Concurrent with the development of the design of the waste packages, a comprehensive waste package materials testing program has been undertaken to support the selection of containment barrier materials and to develop predictive models for the long-term behavior of these materials under expected repository conditions. The testing program includes both long-term and short-term tests and the results from these tests combination with the data published in the open literature are being used to develop models for predicting performance of the waste packages

Structure and Stability of Deflagrations in Porous Energetic Materials

Energy Technology Data Exchange (ETDEWEB)

stephen B. Margolis; Forman A. Williams

1999-03-01

Theoretical two-phase-flow analyses have recently been developed to describe the structure and stability of multi-phase deflagrations in porous energetic materials, in both confined and unconfined geometries. The results of these studies are reviewed, with an emphasis on the fundamental differences that emerge with respect to the two types of geometries. In particular, pressure gradients are usually negligible in unconfined systems, whereas the confined problem is generally characterized by a significant gas-phase pressure difference, or overpressure, between the burned and unburned regions. The latter leads to a strong convective influence on the burning rate arising from the pressure-driven permeation of hot gases into the solid/gas region and the consequent preheating of the unburned material. It is also shown how asymptotic models that are suitable for analyzing stability may be derived based on the largeness of an overall activation-energy parameter. From an analysis of such models, it is shown that the effects of porosity and two-phase flow are generally destabilizing, suggesting that degraded propellants, which exhibit greater porosity than their pristine counterparts, may be more readily subject to combustion instability and nonsteady deflagration.

Utilization of Construction Waste Composite Powder Materials as Cementitious Materials in Small-Scale Prefabricated Concrete

OpenAIRE

Cuizhen Xue; Aiqin Shen; Yinchuan Guo; Tianqin He

2016-01-01

The construction and demolition wastes have increased rapidly due to the prosperity of infrastructure construction. For the sake of effectively reusing construction wastes, this paper studied the potential use of construction waste composite powder material (CWCPM) as cementitious materials in small-scale prefabricated concretes. Three types of such concretes, namely, C20, C25, and C30, were selected to investigate the influences of CWCPM on their working performances, mechanical properties, ...

Feed Materials Production Center Waste Management Plan

International Nuclear Information System (INIS)

Watts, R.E.; Allen, T.; Castle, S.A.; Hopper, J.P.; Oelrich, R.L.

1986-01-01

In the process of producing uranium metal products used in Department of Energy (DOE) defense programs at other DOE facilities, various types of wastes are generated at the Feed Materials Production Center (FMPC). Process wastes, both generated and stored, are discussed in the Waste Management Plan and include low-level radioactive waste (LLW), mixed hazardous/radioactive waste, and sanitary/industrial waste. Scrap metal waste and wastes requiring special remediation are also addressed in the Plan. The Waste Management Plan identifies the comprehensive programs developed to address safe storage and disposition of all wastes from past, present, and future operations at the FMPC. Waste streams discussed in this Plan are representative of the waste generated and waste types that concern worker and public health and safety. Budgets and schedules for implementation of waste disposition are also addressed. The waste streams receiving the largest amount of funding include LLW approved for shipment by DOE/ORO to the Nevada Test Site (NTS) (MgF 2 , slag leach filter cake, and neutralized raffinate); remedial action wastes (waste pits, K-65 silo waste); thorium; scrap metal (contaminated and noncontaminated ferrous and copper scrap); construction rubble and soil generated from decontamination and decommissioning of outdated facilities; and low-level wastes that will be handled through the Low-Level Waste Processing and Shipping System (LLWPSS). Waste Management milestones are also provided. The Waste Management Plan is divided into eight major sections: Introduction; Site Waste and Waste Generating Process; Strategy; Projects and Operations; Waste Stream Budgets; Milestones; Quality Assurance for Waste Management; and Environmental Monitoring Program

Climate protection potential in the waste management sector. Examples: municipal waste and waste wood; Klimaschutzpotenziale der Abfallwirtschaft. Am Beispiel von Siedlungsabfaellen und Altholz

Energy Technology Data Exchange (ETDEWEB)

Dehoust, Guenter; Schueler, Doris [Oeko-Institut e.V. Institut fuer angewandte Oekologie, Darmstadt (Germany); Vogt, Regine; Giegrich, Juergen [IFEU Institut fuer Energie- und Umweltforschung Heidelberg GmbH (Germany)

2010-03-15

In the National Inventory Reports only the direct greenhouse gas emissions of the waste management sector are taken into account. The overall efforts of the waste management sector in terms of reducing greenhouse gas emissions in accordance with the Kyoto Protocol are not, therefore, represented. In particular the efforts related to the separate collection of recyclables from waste and the re-use or energetic use of such recyclables or residue are shown as the savings of other sectors of the production industry and energy industry. This research project has used the methodology of eco-balancing to examine the efforts of the municipal waste management sector - including the use of waste wood - in Germany, the 27 Member States as well as in Turkey, Tunisia and Mexico. The balances referred to the actual balance in 2006 and different optimisation scenarios for 2020. The expenditure resulting from collection, transport, treatment and recycling of waste after it has become available was compared to the savings arising from the secondary products and energy realised from waste. Since the landfilling of untreated municipal waste has been discontinued in Germany, the key potentials of the country have already been fully tapped. Indeed, the contribution of municipal waste management to the reduction of total greenhouse gas emissions amounted to approx. 18 million t CO{sub 2}-eq per annum in 2006 in Germany. In particular, these emission reductions have been brought about by improving treatment techniques (emission reductions in the biological processes and greater energy efficiency in the thermal processes) and by increases in the separate collection and use of recyclable materials stemming from municipal waste and waste wood. If both strategies are combined, there is still an optimisation potential for reducing greenhouse gas emissions of 10 million t CO{sub 2}-eq per annum. Compared to 1990 data taken from previous assessments, the overall reduction amounts to approx. 56

Processing method for liquid waste containing various kinds of radioactive material

International Nuclear Information System (INIS)

Toyabe, Keiji; Nabeshima, Masahiro; Ozeki, Noboru; Muraki, Tsutomu.

1996-01-01

Various kind of radioactive materials and heavy metal elements dissolved in liquid wastes are removed from the liquid wastes by adsorbing them on chitin or chitosan. In this case, a hydrogen ion concentration in the liquid wastes is adjusted to a pH value of from 1 to 3 depending on the kinds of the radioactive materials and heavy metal elements to be removed. Since chitin or chitosan has a special ion exchange performance or adsorbing performance, chemical species comprising radioactive materials or heavy metals dissolved in the liquid wastes are adsorbed thereto by ion adsorption or physical adsorption. With such procedures, radioactive materials and heavy metal elements are removed from the liquid wastes, and the concentration thereof can be reduced to such a level that they can be discharged into environments. On the other hand, since chitin or chitosan adsorbing the radioactive materials and heavy metal elements has a structure of polysaccharides, it is easily burnt into gaseous carbon dioxide. Accordingly, the amount of secondary wastes can remarkably be reduced. (T.M.)

Corrosion assessment of refractory materials for high temperature waste vitrification

International Nuclear Information System (INIS)

Marra, J.C.; Congdon, J.W.; Kielpinski, A.L.

1995-01-01

A variety of vitrification technologies are being evaluated to immobilize radioactive and hazardous wastes following years of nuclear materials production throughout the Department of Energy (DOE) complex. The compositions and physical forms of these wastes are diverse ranging from inorganic sludges to organic liquids to heterogeneous debris. Melt and off-gas products can be very corrosive at the high temperatures required to melt many of these waste streams. Ensuring material durability is required to develop viable treatment processes. Corrosion testing of materials in some of the anticipated severe environments is an important aspect of the materials identification and selection process. Corrosion coupon tests on typical materials used in Joule heated melters were completed using glass compositions with high salt contents. The presence of chloride in the melts caused the most severe attack. In the metal alloys, oxidation was the predominant corrosion mechanism, while in the tested refractory material enhanced dissolution of the refractory into the glass was observed. Corrosion testing of numerous different refractory materials was performed in a plasma vitrification system using a surrogate heterogeneous debris waste. Extensive corrosion was observed in all tested materials

Problematic issues of air protection during thermal processes related to the energetic uses of sewage sludge and other waste. Case study: Co-combustion in peaking power plant.

Science.gov (United States)

Hroncová, Emília; Ladomerský, Juraj; Musil, Juraj

2018-03-01

Currently, it is necessary to deal with issues related to the emissions as there is a constantly increasing interest in combusting sludge from sewage treatment plants in the boilers for wood. An analysis of the energetic importance of the combustion of sewage sludge has already been carried out, but the effects of various treatments of the sludge are not always clear, e.g. composting and subsequent combustion to the air pollution. Investments in other thermal processes of energetic utilisation of sewage sludge and organic waste are not always successfully implemented. The objective of this paper is to point out some problematic cases for acceptance of thermal processes related to energetic use of waste in terms of the air protection. The other aim is to mention the experience with solutions of such issues in Slovakia. There are mentioned first results of the operational validation experiments during the energy generation in circulating fluidized bed boiler in peaking power plant (Power 110MW) with the addition of the so-called alternative fuel based on wood and sewage sludge to the main fuel - black coal (anthracite). And there has already been achieved the highest share of 12.4%w. (dry matter) of sewage sludge in form of compost in blend with black coal, which is technologically viable. Moreover analyzed the problems of the authorization and operation of the co-combustion of sewage sludge and of combustion of products of various kinds of pyrolysis waste - pyrolysis gas and pyrolysis oil are analyzed. Copyright © 2017 Elsevier Ltd. All rights reserved.

Ferrocyanide Safety Program: Analysis of postulated energetic reactions and resultant aerosol generation in Hanford Site Waste Tanks

International Nuclear Information System (INIS)

Postma, A.K.; Dickinson, D.R.

1995-09-01

This report reviews work done to estimate the possible consequences of postulated energetic reactions in ferrocyanide waste stored in underground tanks at the Hanford Site. The issue of explosive reactions was raised in the 1987 Environmental Impact Statement (EIS), where a detonation-like explosion was postulated for the purpose of defining an upper bound on dose consequences for various disposal options. A review of the explosion scenario by the General Accounting Office (GAO) indicated that the aerosol generation and consequent radioactive doses projected for the explosion postulated in the EIS were understated by one to two orders of magnitude. The US DOE has sponsored an extensive study of the hazard posed by uncontrolled exothermic reactions in ferrocyanide waste, and results obtained during the past three years have allowed this hazard to be more realistically assessed. The objective of this report is to summarize the improved knowledge base that now indicates that explosive or vigorous chemical reactions are not credible in the ferrocyanide waste stored in underground tanks. This improved understanding supports the decision not to proceed with further analyses or predictions of the consequences of such an event or with aerosol tests in support of such predictions. 53 refs., 2 tabs

Risks associated with nuclear material recovery and waste preparation

Energy Technology Data Exchange (ETDEWEB)

Fullwood, R R; Erdmann, R C

1983-01-01

An analysis of the risk associated with nuclear material recovery and waste preparation is presented. The steps involve: reprocessing of spent fuel to recycle fissionable material, refabrication of the recovered material for use as reactor fuel, and the transportation links connecting these plants with the power plants and waste repositories. The risks considered are radiological and non-radiological, accident and routine effects on the public and workers during plant construction, operation and decommissioning.

Peer Review of the Waste Package Material Performance Interim Report

International Nuclear Information System (INIS)

J. A. Beavers; T. M. Devine, Jr.; G. S. Frankel; R. H. Jones; R. G. Kelly; R. M. Latanision; J. H. Payer

2001-01-01

At the request of the U.S. Department of Energy, Bechtel SAIC Company, LLC, formed the Waste Package Materials Performance Peer Review Panel (the Panel) to review the technical basis for evaluating the long-term performance of waste package materials in a proposed repository at Yucca Mountain, Nevada. This is the interim report of the Panel; a final report will be issued in February 2002. In its work to date, the Panel has identified important issues regarding waste package materials performance. In the remainder of its work, the Panel will address approaches and plans to resolve these issues. In its review to date, the Panel has not found a technical basis to conclude that the waste package materials are unsuitable for long-term containment at the proposed Yucca Mountain Repository. Nevertheless, significant technical issues remain unsettled and, primarily because of the extremely long life required for the waste packages, there will always be some uncertainty in the assessment. A significant base of scientific and engineering knowledge for assessing materials performance does exist and, therefore, the likelihood is great that uncertainty about the long-term performance can be substantially reduced through further experiments and analysis

PURIFIED WASTE FCC CATALYST AS A CEMENT REPLACEMENT MATERIAL

Directory of Open Access Journals (Sweden)

Danute Vaiciukyniene

2015-06-01

Full Text Available Zeolites are commonly used in the fluid catalytic cracking process. Zeolite polluted with oil products and became waste after some time used. The quantity of this waste inevitably rises by expanding rapidly oil industry. The composition of these catalysts depends on the manufacturer and on the process that is going to be used. The main factors retarding hydration process of cement systems and modifying them strength are organic compounds impurities in the waste FCC catalyst. The present paper shows the results of using purified waste FCC catalyst (pFCC from Lithuania oil refinery, as Portland cement replacement material. For this purpose, the purification of waste FCC catalyst (FCC samples was treated with hydrogen peroxide. Hydrogen peroxide (H2O2 is one of the most powerful oxidizers known. By acting of waste with H2O2 it can eliminate the aforementioned waste deficiency, and the obtained product becomes one of the most promising ingredients, in new advanced building materials. Hardened cement paste samples with FCC or pFCC were formed. It was observed that the pFCC blended cements developed higher strength, after 28 days, compared to the samples with FCC or reference samples. Typical content of Portland cement substituting does not exceed 30 % of mass of Portland cement in samples. Reducing the consumption of Portland cement with utilizing waste materials is preferred for reasons of environmental protection.

Calcium phosphate nuclear materials: apatitic ceramics for separated wastes

International Nuclear Information System (INIS)

Carpena, J.; Lacout, J.L.

2005-01-01

Is it feasible to elaborate conditioning materials for separated high activity nuclear wastes, as actinides or fission products? Specific materials have been elaborated so that the waste is incorporated within the crystalline structure of the most stable calcium phosphate, i.e. apatite. This mineral is able to sustain high irradiation doses assuming a well chosen chemical composition. Mainly two different ways of synthesis have been developed to produce hard apatite ceramics that can be used to condition nuclear wastes. Here we present a data synthesis regarding the elaboration of these apatite nuclear materials that includes experiments on crystallo-chemistry, chemical analysis, leaching and irradiation tests performed for the past fifteen years. (authors)

Seeded Reaction Waves in Composites: Fast Structure Transforming Materials that Respond to Energetic Stimuli

Science.gov (United States)

2016-10-21

change in the structure of the capsule system . The temperatures at which the capsules undergo transformation are in accordance with the results in DSC...Structure- Transforming Materials that Respond to Energetic Stimuli Sb. GRANT NUMBER N00014-13-1-0170 Sc. PROGRAM ELEMENT NUMBER 6. AUTHOR(S) Sd...encapsulated super- cooled fluids into a polymer matrix allows for rapid changes in mechanical properties. Frontal polymerization within a microvascular

Release of powdered material from waste packages

International Nuclear Information System (INIS)

Berg, H.P.; Gruendler, D.; Peiffer, F.; Seehars, H.D.

1990-01-01

Possible incidents in the operational phase of the planned German repository KONRAD for radioactive waste with negligible heat production were investigated to assess the radiological consequences. For these investigations release fractions of the radioactive materials are required. This paper deals with the determination of the release of powdered material from waste packages under mechanical stress. These determinations were based on experiments. The experimental procedure and the process parameters chosen in accordance with the conditions in the planned repository will be described. The significance of the experimental results is discussed with respect to incidents in the planned repository. 8 figs., 3 tabs

Production of renewable energy from biomass and waste materials using fluidized bed technologies

International Nuclear Information System (INIS)

Rozainee, M.; Rashid, M.; Looi, S.

2000-01-01

Malaysian industries generate substantial amount of biomass and waste materials such as wastes from agricultural and wood based industries, sludge waste from waste-water treatment plants and solid waste from municipals. Incinerating these waste materials not only produces renewable energy, but also solving their disposal problems. Fluidized bed combustors are widely used for incinerating these biomass materials. The significant advantages of fluidized bed incineration include simple design, efficient, and ability to reduce air pollution emissions. This paper discusses the opportunities and challenges of producing the green energy from biomass materials using the fluidized bed technologies. (Author)

Cementitious materials for radioactive waste management within IAEA coordinated research project - 59021

International Nuclear Information System (INIS)

Drace, Zoran; Ojovan, Michael I.

2012-01-01

The IAEA Coordinated Research Project (CRP) on cementitious materials for radioactive waste management was launched in 2007 [1, 2]. The objective of CRP was to investigate the behaviour and performance of cementitious materials used in radioactive waste management system with various purposes and included waste packages, waste-forms and backfills as well as investigation of interactions and interdependencies of these individual elements during long term storage and disposal. The specific research topics considered were: (i) cementitious materials for radioactive waste packaging: including radioactive waste immobilization into a solid waste form, (ii) waste backfilling and containers; (iii) emerging and alternative cementitious systems; (iv) physical-chemical processes occurring during the hydration and ageing of cement matrices and their influence on the cement matrix quality; (v) methods of production of cementitious materials for: immobilization into wasteform, backfills and containers; (vi) conditions envisaged in the disposal environment for packages (physical and chemical conditions, temperature variations, groundwater, radiation fields); (vii) testing and non-destructive monitoring techniques for quality assurance of cementitious materials; (viii) waste acceptance criteria for waste packages, waste forms and backfills; transport, long term storage and disposal requirements;and finally (ix) modelling or simulation of long term behaviours of cementations materials used for packaging, waste immobilization and backfilling, especially in the post-closure phase. The CRP has gathered overall 26 research organizations from 22 Member States aiming to share their research and practices on the use of cementitious materials [2]. The main research outcomes of the CRP were summarized in a summary report currently under preparation to be published by IAEA. The generic topical sections covered by report are: a) conventional cementitious systems; b) novel cementitious

Materials and wastes from power generation of nuclear origin

International Nuclear Information System (INIS)

Dessus, Benjamin; Guillemette, Andre; Laponche, Bernard; Zerbib, Jean-Claude

2014-01-01

In most countries, spent nuclear fuel is directly stored in pools and constitute the bulk of highly radioactive waste. In France, reprocessing separates spent fuel into three categories: uranium, plutonium, minor actinides and fission products. Hence, a vast amount of very diverse radioactive materials are stored in various sites and conditions, under two denominations: 'nuclear materials' (which can be or are partly recycled) and 'radioactive waste' which should be permanently disposed of. The production of highly radioactive and long-lived waste raise legitimate questions on the use of nuclear energy for power production and many people think that it's a sufficient reason for giving up this technique. Concerning existing radioactive waste, the alternative to deep disposal should be: a) dry storage of spent fuel and other existing waste in protected sites (bunkers or hills), and b) more active research on the possibilities to reduce both radioactivity and the lifetime of radioactive waste. (authors)

Molecular Theory of Detonation Initiation: Insight from First Principles Modeling of the Decomposition Mechanisms of Organic Nitro Energetic Materials.

Science.gov (United States)

Tsyshevsky, Roman V; Sharia, Onise; Kuklja, Maija M

2016-02-19

This review presents a concept, which assumes that thermal decomposition processes play a major role in defining the sensitivity of organic energetic materials to detonation initiation. As a science and engineering community we are still far away from having a comprehensive molecular detonation initiation theory in a widely agreed upon form. However, recent advances in experimental and theoretical methods allow for a constructive and rigorous approach to design and test the theory or at least some of its fundamental building blocks. In this review, we analyzed a set of select experimental and theoretical articles, which were augmented by our own first principles modeling and simulations, to reveal new trends in energetic materials and to refine known existing correlations between their structures, properties, and functions. Our consideration is intentionally limited to the processes of thermally stimulated chemical reactions at the earliest stage of decomposition of molecules and materials containing defects.

Product Control of Waste Products with New Coating Materials

International Nuclear Information System (INIS)

Krumbach, H.; Steinmetz, H.J.; Odoj, R.; Wartenberg, W.; Grunau, H.

2009-01-01

In Germany, with the shaft KONRAD a repository for low radioactive waste will be available at the earliest in the year 2013. The previously conditioned radioactive waste has to be suitable for a longer-term interim storage. They have to be treated in a way that they are chemically stable and that their integrity is guaranteed for a long time. That is why the waste product or the container is covered/ coated for special waste such as hygroscopic waste or waste that includes aluminium. The Product Control Group for radioactive waste (PKS) has to proof the suitability of the so-treated waste for the repository KONRAD on behalf of the Federal Office for Radiation Protection (BfS). This has to be done before the delivering. In this context the PKS also assesses the suitability of new coating materials for low radioactive waste products or containers and their correct technical application. The characteristics and the technical application of polyurethane coatings as well as the control of the so-coated waste for the disposal in the shaft KONRAD are described in this poster. The Poster shows the development stages of the coating and the filling. There are also shown the boundary conditions and the investigations of the Product Control Group for the use of the new coating material for radioactive waste. (authors)

Feasibility of Target Material Recycling as Waste Management Alternative

International Nuclear Information System (INIS)

El-Guebaly, L.; Wilson, P.; Henderson, D.; Varuttamaseni, A.

2004-01-01

The issue of waste management has been studied simultaneously along with the development of the ARIES heavy-ion-driven inertial fusion energy (IFE) concept. Options for waste management include disposal in repositories, recycling, or clearance from regulatory control, following a reasonable cooling period. This paper concerns the feasibility of recycling the heavy-ion-beam targets, in particular the hohlraum wall materials that include, for example, Au/Gd, Au, W, Pb, Hg, Ta, Pb/Ta/Cs, Hg/W/Cs, Pb/Hf, Hf, solid Kr, and solid Xe. The choice between target material disposal and recycling depends on the amount of waste generated relative to the nuclear island, the strategy to solve the recycling problem, and the impact of the additional cost and complexity of the recycling process on the overall machine. A detailed flow diagram for the elements of the recycling process was developed to analyze two extreme activation cases: (a) one-shot use and then disposal in a repository and (b) recycling continuously during plant life without removal of transmutation products. Metrics for comparing the two scenarios included waste level, dose to recycling equipment, additional cost, and design complexity. Comparing the two approaches indicated a preference for the one-shot scenario as it generates 1 m 3 /yr of extremely low-level waste (Class A) and offers attractive design and economics features. Recycling reduces the target waste stream by a factor of 10 or more but introduces additional issues. It may produce high-level waste, requires remote handling, adds radioactive storage facilities, and increases the cost and complexity of the plant. The inventory analysis indicated that the heavy-ion-beam (HIB) target materials represent a very small waste stream compared to that of the nuclear island (<1% of the total waste). This means recycling is not a 'must' requirement for IFE-HIB power plants unless the target materials have cost and/or resource problems (e.g., Au and Gd). In this

Producing glass-ceramics from waste materials

Energy Technology Data Exchange (ETDEWEB)

Boccaccini, A.R.; Rawlings, R.D. [Imperial College, London (United Kingdom)

2002-10-01

An overview is given of recent research at the Department of Materials of Imperial College, London, UK, concerning the production of useful glass-ceramic products from industrial waste materials. The new work, using controlled crystallisation to improve the properties of vitrified products, could help to solve the problem of what to do with increasing amounts of slag, fly ash and combustion dust. The results show, that it is possible to produce new materials with interesting magnetic and constructive properties.

Waste package materials testing for a salt repository: 1983 status summary report

International Nuclear Information System (INIS)

Moak, D.P.

1986-09-01

The United States plans to safely dispose of nuclear waste in deep, stable geologic formations. As part of these plans, the US Department of Energy is sponsoring research on the designing and testing of waste packages and waste package materials. This fiscal year 1983 status report summarizes recent results of waste package materials testing in a salt environment. The results from these tests will be used by waste package designers and performance assessment experts. Release characteristics data are available on two waste forms (spent fuel and waste-containing glass) that were exposed to leaching tests at various radiation levels, temperatures, pH, glass surface area to solution volume ratios, and brine solutions simulating expected salt repository conditions. Candidate materials tested for corrosion resistance and other properties include iron alloys; TI-CODE 12, the most promising titanium alloy for containment; and nickel alloys. In component interaction testing, synergistic effects have not ruled out any candidate material. 21 refs., 37 figs., 15 tabs

Importance of the gas phase role to the prediction of energetic material behavior: An experimental study

International Nuclear Information System (INIS)

Ali, A.N.; Son, S.F.; Asay, B.W.; Sander, R.K.

2005-01-01

Various thermal (radiative, conductive, and convective) initiation experiments are performed to demonstrate the importance of the gas phase role in combustion modeling of energetic materials (EM). A previously published condensed phase model that includes a predicted critical irradiance above which ignition is not possible is compared to experimental laser ignition results for octahydro-1,3,5,7-tetranitro-1,3,5,7-tetrazocine (HMX) and 2,4,6-trinitrotoluene (TNT). Experimental results conflict with the predicted critical irradiance concept. The failure of the model is believed to result from a misconception about the role of the gas phase in the ignition process of energetic materials. The model assumes that ignition occurs at the surface and that evolution of gases inhibits ignition. High speed video of laser ignition, oven cook-off and hot wire ignition experiments captures the ignition of HMX and TNT in the gas phase. A laser ignition gap test is performed to further evaluate the effect of gas phase laser absorption and gas phase disruption on the ignition process. Results indicate that gas phase absorption of the laser energy is probably not the primary factor governing the gas phase ignition observations. It is discovered that a critical gap between an HMX pellet and a salt window of 6 mm±0.4 mm exists below which ignition by CO 2 laser is not possible at the tested irradiances of 29 W/cm 2 and 38 W/cm 2 for HMX ignition. These observations demonstrate that a significant disruption of the gas phase, in certain scenarios, will inhibit ignition, independent of any condensed phase processes. These results underscore the importance of gas phase processes and illustrate that conditions can exist where simple condensed phase models are inadequate to accurately predict the behavior of energetic materials

Importance of the gas phase role to the prediction of energetic material behavior: An experimental study

Science.gov (United States)

Ali, A. N.; Son, S. F.; Asay, B. W.; Sander, R. K.

2005-03-01

Various thermal (radiative, conductive, and convective) initiation experiments are performed to demonstrate the importance of the gas phase role in combustion modeling of energetic materials (EM). A previously published condensed phase model that includes a predicted critical irradiance above which ignition is not possible is compared to experimental laser ignition results for octahydro-1,3,5,7-tetranitro-1,3,5,7-tetrazocine (HMX) and 2,4,6-trinitrotoluene (TNT). Experimental results conflict with the predicted critical irradiance concept. The failure of the model is believed to result from a misconception about the role of the gas phase in the ignition process of energetic materials. The model assumes that ignition occurs at the surface and that evolution of gases inhibits ignition. High speed video of laser ignition, oven cook-off and hot wire ignition experiments captures the ignition of HMX and TNT in the gas phase. A laser ignition gap test is performed to further evaluate the effect of gas phase laser absorption and gas phase disruption on the ignition process. Results indicate that gas phase absorption of the laser energy is probably not the primary factor governing the gas phase ignition observations. It is discovered that a critical gap between an HMX pellet and a salt window of 6mm±0.4mm exists below which ignition by CO2 laser is not possible at the tested irradiances of 29W /cm2 and 38W/cm2 for HMX ignition. These observations demonstrate that a significant disruption of the gas phase, in certain scenarios, will inhibit ignition, independent of any condensed phase processes. These results underscore the importance of gas phase processes and illustrate that conditions can exist where simple condensed phase models are inadequate to accurately predict the behavior of energetic materials.

Effect of Paper Waste Products as a Litter Material on Broiler Performance

Directory of Open Access Journals (Sweden)

Serdar Özlü

2017-12-01

Full Text Available This study conducted to determine the possibilities of using the paper waste products as a litter material in broiler production. A total of 468 Ross 308 broilers were used in this experiment. Litter materials were rice hulls (RH, waste paper (WP and mix of them (50 % RH + 50 % WP. BW was approximately 60 g heavier in waste paper group compare to other two litter groups at 42d of age. Type of litter material had no significant effects on feed conversion ratio, livability and leg defect. Therefore, paper waste products have potential as an alternative litter material for broiler production.

Influence of Handling Practices on Material Recovery from Residential Solid Waste

Directory of Open Access Journals (Sweden)

Jairo F. Pereira

2010-07-01

Full Text Available Material recovery from municipal solid waste (MSW is becoming widely adopted in several developing countries. Residential solid waste is one of the most important components of MSW and the handling practices of the MSW by the generators have a major impact on the quality and quantity of the materials for recovery. This article analyzes the generation and composition of residential solid waste and the handling practices by users in three municipalities in Colombia that have a solid waste management plant (SWMP. The findings show that, although there are significant amounts of useful materials, their handling of the materials as “garbage”, the low recognition of recovery work, and the inadequate storage and source management practices, affect material recovery and the operation of SWMPs. These results may be taken as a reference for this type of municipality, because the solid waste management system and the type of operation of the SWMPs analyzed is similar to all of the SWMPs in the country as well as in other countries in the region.

Waste glass as eco-friendly replacement material in construction products

Science.gov (United States)

Sharma, Gayatri; Sharma, Anu

2018-05-01

Atpresent time the biggest issue is increasing urban population, industrialization and development all over the world. The quantity of the raw materials of construction products like cement, concrete etc is gradually depleting. This is important because if we don't find the alternative material to accomplish need of this industry, with every year it will put pressure on natural resources which are limited in quantity. This major issue can be solved by partial replacing with waste glass of different construction products. This paper gives an overview of the current growth and recycling situation of waste glass and point out the direction for the proper use of waste glass as replacement of construction material. These will not only help in the reuse of waste glass but also create eco-friendly environment.

Analysis of waste coal from the enterprises of Kemerovo region as raw materials for production of ceramic materials

Science.gov (United States)

Stolboushkin, A. Yu; Akst, D. V.; Fomina, O. A.; Ivanov, A. I.; Syromyasov, V. A.

2017-09-01

The analysis of waste coal from mining enterprises of Kemerovo region as raw materials for production of building ceramics is given. The results of studies of material, chemical and mineralogical compositions of waste coal from Abashevskaya processing plant (Novokuznetsk) are presented. It was established that the chemical composition of waste coal refers to aluminosilicate raw materials with a high content of alumina and coloring oxides, the residual carbon content in the wastes is 12-25 %. According to the granulometric composition the waste coal is basically a sandy-dusty fraction with a small amount of clay particles (1-3 %). Additional grinding of coal waste and the introduction of a clay additive in an amount of up to 30 % are recommended. The results of the study of the mineral composition of waste coal are presented. Clay minerals are represented in the descending order by hydromuscovite, montmorillonite and kaolinite, minerals-impurities consist of quartz, feldspar fine-dispersed carbonates. The results of the investigation of ceramic-technological properties of waste coal, which belong to the group of moderately plastic low-melting raw materials, are given. As a result of a comprehensive study it was been established that with chemical, granulometric and mineralogical compositions waste coal with the reduced residual carbon can be used in the production of ceramic bricks.

Degradation modes of nickel-base alternate waste package overpack materials

International Nuclear Information System (INIS)

Pitman, S.G.

1988-07-01

The suitability of Ti Grade 12 for waste package overpacks has been questioned because of its observed susceptibility to crevice corrosion and hydrogen-assisted crack growth. For this reason, materials have been selected for evaluation as alternatives to Ti Grade 12 for use as waste package overpacks. These alternative materials, which are based on the nickel-chromium-molybdenum (Ni-Cr-Mo) alloy system, are Inconel 625, Hastelloy C-276, and Hastelloy C-22. The degradation modes of the Ni-base alternate materials have been examined at Pacific Northwest Laboratory to determine the suitability of these materials for waste package overpack applications in a salt repository. Degradation modes investigated included general corrosion, crevice corrosion, pitting, stress-corrosion cracking, and hydrogen embrittlement

Molecular Theory of Detonation Initiation: Insight from First Principles Modeling of the Decomposition Mechanisms of Organic Nitro Energetic Materials

Directory of Open Access Journals (Sweden)

Roman V. Tsyshevsky

2016-02-01

Full Text Available This review presents a concept, which assumes that thermal decomposition processes play a major role in defining the sensitivity of organic energetic materials to detonation initiation. As a science and engineering community we are still far away from having a comprehensive molecular detonation initiation theory in a widely agreed upon form. However, recent advances in experimental and theoretical methods allow for a constructive and rigorous approach to design and test the theory or at least some of its fundamental building blocks. In this review, we analyzed a set of select experimental and theoretical articles, which were augmented by our own first principles modeling and simulations, to reveal new trends in energetic materials and to refine known existing correlations between their structures, properties, and functions. Our consideration is intentionally limited to the processes of thermally stimulated chemical reactions at the earliest stage of decomposition of molecules and materials containing defects.

Screening tests for hazard classification of complex waste materials – Selection of methods

International Nuclear Information System (INIS)

Weltens, R.; Vanermen, G.; Tirez, K.; Robbens, J.; Deprez, K.; Michiels, L.

2012-01-01

In this study we describe the development of an alternative methodology for hazard characterization of waste materials. Such an alternative methodology for hazard assessment of complex waste materials is urgently needed, because the lack of a validated instrument leads to arbitrary hazard classification of such complex waste materials. False classification can lead to human and environmental health risks and also has important financial consequences for the waste owner. The Hazardous Waste Directive (HWD) describes the methodology for hazard classification of waste materials. For mirror entries the HWD classification is based upon the hazardous properties (H1–15) of the waste which can be assessed from the hazardous properties of individual identified waste compounds or – if not all compounds are identified – from test results of hazard assessment tests performed on the waste material itself. For the latter the HWD recommends toxicity tests that were initially designed for risk assessment of chemicals in consumer products (pharmaceuticals, cosmetics, biocides, food, etc.). These tests (often using mammals) are not designed nor suitable for the hazard characterization of waste materials. With the present study we want to contribute to the development of an alternative and transparent test strategy for hazard assessment of complex wastes that is in line with the HWD principles for waste classification. It is necessary to cope with this important shortcoming in hazardous waste classification and to demonstrate that alternative methods are available that can be used for hazard assessment of waste materials. Next, by describing the pros and cons of the available methods, and by identifying the needs for additional or further development of test methods, we hope to stimulate research efforts and development in this direction. In this paper we describe promising techniques and argument on the test selection for the pilot study that we have performed on different

Hazardous materials and waste management a guide for the professional hazards manager

CERN Document Server

Cheremisinoff, Nicholas P

1995-01-01

The management of hazardous materials and industrial wastes is complex, requiring a high degree of knowledge over very broad technical and legal subject areas. Hazardous wastes and materials are diverse, with compositions and properties that not only vary significantly between industries, but within industries, and indeed within the complexity of single facilities. Proper management not only requires an understanding of the numerous and complex regulations governing hazardous materials and waste streams, but an understanding and knowledge of the treatment, post-treatment, and waste minimizatio

Initial specifications for nuclear waste package external dimensions and materials

International Nuclear Information System (INIS)

Gregg, D.W.; O'Neal, W.C.

1983-09-01

Initial specifications of external dimensions and materials for waste package conceptual designs are given for Defense High Level Waste (DHLW), Commercial High Level Waste (CHLW) and Spent Fuel (SF). The designs have been developed for use in a high-level waste repository sited in a tuff media in the unsaturated zone. Drawings for reference and alternative package conceptual designs are presented for each waste form for both vertical and horizontal emplacement configurations. Four metal alloys: 304L SS, 321 SS, 316L SS and Incoloy 825 are considered for the canister or overpack; 1020 carbon steel was selected for horizontal borehole liners, and a preliminary packing material selection is either compressed tuff or compressed tuff containing iron bearing smectite clay as a binder

Composition of waste materials and recyclables

DEFF Research Database (Denmark)

Götze, Ramona

involves several steps to prepare the samples mechanically and/or chemically for final analysis. Not all sample preparation methods are equally well suited for specific waste characterization purposes. The correctness of results and practical feasibility of sample preparation was strongly affected...... for future modelling and assessment of waste management systems. The analyzed fractions were selected based on material properties with relevance for potential recycling processes. The physico-chemical analysis revealed chemical differences between residual and source-segregated samples for several fractions....... The results for parameters associated with organic matter confirmed the idea of cross-contaminated recyclables in residual waste, whereas the results for heavy metals and trace elements were more complex. For many fractions rather high metal contents were found to be intrinsic properties of the recyclables...

Unify a hazardous materials/waste program

International Nuclear Information System (INIS)

Carson, H.T.

1988-01-01

Efficiently managing a hazardous materials/waste program in a multi-facility, multi-product corporation is a major challenge. This paper describes several methods to help unify a program and gain maximum efficiency of manpower and to minimize risk

Data summary of municipal solid waste management alternatives. Volume 7, Appendix E -- Material recovery/material recycling technologies

Energy Technology Data Exchange (ETDEWEB)

None

1992-10-01

The enthusiasm for and commitment to recycling of municipal solid wastes is based on several intuitive benefits: Conservation of landfill capacity; Conservation of non-renewable natural resources and energy sources; Minimization of the perceived potential environmental impacts of MSW combustion and landfilling; Minimization of disposal costs, both directly and through material resale credits. In this discussion, ``recycling`` refers to materials recovered from the waste stream. It excludes scrap materials that are recovered and reused during industrial manufacturing processes and prompt industrial scrap. Materials recycling is an integral part of several solid waste management options. For example, in the preparation of refuse-derived fuel (RDF), ferrous metals are typically removed from the waste stream both before and after shredding. Similarly, composting facilities, often include processes for recovering inert recyclable materials such as ferrous and nonferrous metals, glass, Plastics, and paper. While these two technologies have as their primary objectives the production of RDF and compost, respectively, the demonstrated recovery of recyclables emphasizes the inherent compatibility of recycling with these MSW management strategies. This appendix discusses several technology options with regard to separating recyclables at the source of generation, the methods available for collecting and transporting these materials to a MRF, the market requirements for post-consumer recycled materials, and the process unit operations. Mixed waste MRFs associated with mass bum plants are also presented.

General Equilibrium Analysis of Economic Instruments in Materials-Product Chains with Materials Balance, Recycling and Waste Treatment

Energy Technology Data Exchange (ETDEWEB)

Kandelaars, P.A.A.H.; Van den Bergh, J.C.J.M. [Department of Spatial Economics, Faculty of Economics and Econometrics, Vrije Universiteit, Amsterdam (Netherlands)

1997-12-31

Optimal environmental taxation and subsidies in a materials-product (M-P) chain are examined. This incorporates the main economic activities extraction, production, consumption, recycling and waste treatment. A static general equilibrium model of this M-P chain is constructed, with environmental impacts represented as negative externalities generated by natural resource extraction and final dumping of waste. The model includes various environmental taxes and subsidies on products and materials to pay for these externalities. The originality of this analytical exercise is twofold: in all stages of the M-P chain materials balance conditions are satisfied; furthermore, recycling is explicitly included as a separate activity with inputs, outputs and objectives. Thus, the paper combines physical-environmental and welfare economic perspectives on materials flows. The results show that the externalities generated by extraction and harmful waste can only be optimized by imposing a direct tax on the new materials. In a second-best world the externalities may be sub-optimized by taxing the generation of harmful waste or by subsidizing the use of recycled materials. Changes in some variables causes a shift between the optimal taxes on new materials at the beginning and harmful waste at the end of the M-P chain. This linkage is interesting because it shows that the whole M-P chain needs to be considered instead of parts of this chain. 16 refs.

Materials selection for process equipment in the Hanford waste vitrification plant

Energy Technology Data Exchange (ETDEWEB)

Elmore, M R; Jensen, G A

1991-07-01

The Hanford Waste Vitrification Plant (HWVP) is being designed to vitrify defense liquid high-level wastes and transuranic wastes stored at Hanford. The HWVP Functional Design Criteria (FDC) requires that materials used for fabrication of remote process equipment and piping in the facility be compatible with the expected waste stream compositions and process conditions. To satisfy FDC requirements, corrosion-resistant materials have been evaluated under simulated HWVP-specific conditions and recommendations have been made for HWVP applications. The materials recommendations provide to the project architect/engineer the best available corrosion rate information for the materials under the expected HWVP process conditions. Existing data and sound engineering judgement must be used and a solid technical basis must be developed to define an approach to selecting suitable construction materials for the HWVP. This report contains the strategy, approach, criteria, and technical basis developed for selecting materials of construction. Based on materials testing specific to HWVP and on related outside testing, this report recommends for constructing specific process equipment and identifies future testing needs to complete verification of the performance of the selected materials. 30 refs., 7 figs., 11 tabs.

2009 National inventory of radioactive material and wastes. Synthesis report

International Nuclear Information System (INIS)

2009-01-01

Third edition of the ANDRA's national inventory report on radioactive wastes that are present on the French territory (as recorded until december, 2007). After a brief historical review of the national inventory and the way it is constructed, the report gives the basics on radioactive wastes, their classification, origins and management processes, followed by a general presentation and discussion of the inventory results (radioactive wastes and materials). Results are then detailed for the different activity sectors using radioactive materials (nuclear industry, medical domain, scientific research, conventional industry, Defense...). Information is also given concerning radioactive polluted areas (characterization and site management) and radioactive waste inventories in various foreign countries

Report on current research into organic materials in radioactive waste

International Nuclear Information System (INIS)

Norris, G.H.

1987-11-01

A preliminary review of relevant recent papers on organic materials in radioactive waste is presented. In particular, the effects of chelating or complexing agents, the influence of bacteria and the role of colloids are assessed. The requirement for further radioactive waste inventory detail is indicated. Potential problem areas associated with the presence of organic materials in radioactive waste are identified and appropriate experimental work to assess their significance is proposed. Recommendations for specific further work are made. A list and diagrams of some of the more important polymer structures likely to be present in radioactive waste and their possible degradation products are appended. (author)

Mechanism of lead removal by waste materials

International Nuclear Information System (INIS)

Qaiser, S.; Saleemi, A.R.; Ahmed, M.M.

2007-01-01

Heavy metal ions are priority pollutants, due to their toxicity and mobility in natural water ecosystems. The discharge of heavy metals into aquatic ecosystems has become a matter of concern in Pakistan over the last few decades. These contaminants are introduced into the aquatic systems significantly as a result of various industrial operations. The metals of concern include lead, chromium, zinc, copper, nickel and uranium. Lead is one of the most hazardous and toxic metals. It is used as industrial raw material in the manufacture of storage batteries, pigments, leaded glass, fuels, photographic materials, matches and explosives. Conventional methods for treatment of dissolved lead include precipitation, adsorption, coagulation/notation, sedimentation, reverse osmosis and ion exchange. Each process has its merits and limitations in applications. Adsorption by activated carbon and ion exchange using commercial ion exchange resins are very expensive processes, especially for a developing country like Pakistan. The present research was conducted to identify some waste materials, which can be utilized to remove lead from industrial wastewater. Natural wastes in the form of leaves and ash have considerable amounts of CaO, MgO, Na/sub 2/O, SiO/sub 2/ and Al/sub 2/O/sub 3/ which can be utilized for precipitation and adsorption. Utilization of waste materials to remove lead from industrial wastewater is the basic theme of this research. The waste materials used in this research were maple leaves, pongamia pinata leaves, coal ash and maple ago leave ash. Parameters studied were reaction time, precipitant dose, pH and temperature. It was found that maple leaves ash has maximum lead removal capacity 19.24 mg g/sup -1/ followed by coal ash 13.2 mg g/sup -1/. The optimal pH was 5 for maple leaves and pongamia Pinata leaves; and 4 for coal ash and maple leaves ash. Removal capacity decreased with increase in temperature. The major removal mechanisms were adsorption and

Tank waste remediation system (TWRS) privatization contractor samples waste envelope D material 241-C-106

Energy Technology Data Exchange (ETDEWEB)

Esch, R.A.

1997-04-14

This report represents the Final Analytical Report on Tank Waste Remediation System (TWRS) Privatization Contractor Samples for Waste Envelope D. All work was conducted in accordance with ''Addendum 1 of the Letter of Instruction (LOI) for TWRS Privatization Contractor Samples Addressing Waste Envelope D Materials - Revision 0, Revision 1, and Revision 2.'' (Jones 1996, Wiemers 1996a, Wiemers 1996b) Tank 241-C-1 06 (C-106) was selected by TWRS Privatization for the Part 1A Envelope D high-level waste demonstration. Twenty bottles of Tank C-106 material were collected by Westinghouse Hanford Company using a grab sampling technique and transferred to the 325 building for processing by the Pacific Northwest National Laboratory (PNNL). At the 325 building, the contents of the twenty bottles were combined into a single Initial Composite Material. This composite was subsampled for the laboratory-scale screening test and characterization testing, and the remainder was transferred to the 324 building for bench-scale preparation of the Privatization Contractor samples.

Material resources, energy, and nutrient recovery from waste: are waste refineries the solution for the future?

DEFF Research Database (Denmark)

Tonini, Davide; Martinez-Sanchez, Veronica; Astrup, Thomas Fruergaard

2013-01-01

Waste refineries focusing on multiple outputs of material resources, energy carriers, and nutrients may potentially provide more sustainable utilization of waste resources than traditional waste technologies. This consequential life cycle assessment (LCA) evaluated the environmental performance....... Overall, the waste refinery provided global warming (GW) savings comparable with efficient incineration, MBT, and bioreactor landfilling technologies. The main environmental benefits from waste refining were a potential for improved phosphorus recovery (about 85%) and increased electricity production (by...

Silver recovery from the waste materials by the method of flotation process

OpenAIRE

B. Oleksiak; G. Siwiec; A. Tomaszewska; D. Piękoś

2018-01-01

During the leaching process of zinc concentrates, the waste materials rich in various metals such as eg. silver are produced. So far no attempts of silver recovery from the mentioned waste materials have been made due to the lack of any method which would be both effective and beneficial. The paper presents some possibilities of application of flotation process in silver recovery form waste materials generated during zinc production.

Preliminary selection criteria for the Yucca Mountain Project waste package container material

International Nuclear Information System (INIS)

Halsey, W.G.

1991-01-01

The Department of Energy's Yucca Mountain Project (YMP) is evaluating a site at Yucca Mountain in Nevada for construction of a geologic repository for the storage of high-level nuclear waste. Lawrence Livermore National Laboratory's (LLNL) Nuclear Waste Management Project (NWMP) has the responsibility for design, testing, and performance analysis of the waste packages. The design is performed in an iterative manner in three sequential phases (conceptual design, advanced conceptual design, and license application design). An important input to the start of the advanced conceptual design is the selection of the material for the waste containers. The container material is referred to as the 'metal barrier' portion of the waste package, and is the responsibility of the Metal Barrier Selection and Testing task at LLNL. The selection will consist of several steps. First, preliminary, material-independent selection criteria will be established based on the performance goals for the container. Second, a variety of engineering materials will be evaluated against these criteria in a screening process to identify candidate materials. Third, information will be obtained on the performance of the candidate materials, and final selection criteria and quantitative weighting factors will be established based on the waste package design requirements. Finally, the candidate materials will be ranked against these criteria to determine whether they meet the mandated performance requirements, and to provide a comparative score to choose the material for advanced conceptual design activities. This document sets forth the preliminary container material selection criteria to be used in screening candidate materials. 5 refs

Fires at storage sites of organic materials, waste fuels and recyclables.

Science.gov (United States)

Ibrahim, Muhammad Asim; Alriksson, Stina; Kaczala, Fabio; Hogland, William

2013-09-01

During the last decade, the European Union has enforced the diversion of organic wastes and recyclables to waste management companies operating incineration plants, composting plants and recycling units instead of landfills. The temporary storage sites have been established as a buffer against fluctuations in energy demand throughout the year. Materials also need to be stored at temporary storage sites before recovery and recycling. However, regulations governing waste fuel storage and handling have not yet been developed, and, as a result, companies have engaged in risky practices that have resulted in a high number of fire incidents. In this study, a questionnaire survey was distributed to 249 of the 400 members of Avfall Sverige (Swedish Waste Management Association), which represents the waste management of 95% of the Swedish population. Information regarding 122 storage facilities owned by 69 companies was obtained; these facilities were responsible for the storage of 47% of the total treated waste (incineration + digestion + composting) in 2010 in Sweden. To identify factors related to fire frequency, the questionnaire covered the amounts of material handled and burnt per year, financial losses due to fires, storage duration, storage method and types of waste. The results show that 217 fire incidents corresponded to 170 kilotonnes of material burnt and cumulative losses of 49 million SEK (€4.3 million). Fire frequency and amount of material burnt per fire was found to be dependent upon type of management group (waste operator). Moreover, a correlation was found between fire frequency and material recycled during past years. Further investigations of financial aspects and externalities of fire incidents are recommended.

Molecular Environmental Science Using Synchrotron Radiation: Chemistry and Physics of Waste Form Materials

Energy Technology Data Exchange (ETDEWEB)

Lindle, Dennis W.

2011-04-21

Production of defense-related nuclear materials has generated large volumes of complex chemical wastes containing a mixture of radionuclides. The disposition of these wastes requires conversion of the liquid and solid-phase components into durable, solid forms suitable for long-term immobilization. Specially formulated glass compositions and ceramics such as pyrochlores and apatites are the main candidates for these wastes. An important consideration linked to the durability of waste-form materials is the local structure around the waste components. Equally important is the local structure of constituents of the glass and ceramic host matrix. Knowledge of the structure in the waste-form host matrices is essential, prior to and subsequent to waste incorporation, to evaluate and develop improved waste-form compositions based on scientific considerations. This project used the soft-x-ray synchrotron-radiation-based technique of near-edge x-ray-absorption fine structure (NEXAFS) as a unique method for investigating oxidation states and structures of low-Z elemental constituents forming the backbones of glass and ceramic host matrices for waste-form materials. In addition, light metal ions in ceramic hosts, such as titanium, are also ideal for investigation by NEXAFS in the soft-x-ray region. Thus, one of the main objectives was to understand outstanding issues in waste-form science via NEXAFS investigations and to translate this understanding into better waste-form materials, followed by eventual capability to investigate “real” waste-form materials by the same methodology. We conducted several detailed structural investigations of both pyrochlore ceramic and borosilicate-glass materials during the project and developed improved capabilities at Beamline 6.3.1 of the Advanced Light Source (ALS) to perform the studies.

Chemistry and Materials Science, 1990--1991. [Second annual report

Energy Technology Data Exchange (ETDEWEB)

Sugihara, T.T.; Bruner, J.M.; McElroy, L.A. [eds.

1991-12-31

This 2-year (FY 1990-91) contains 49 technical articles in ten sections: research sampler, metals and alloys, energetic materials, chemistry and physics of advanced materials, bonding and reactions at surfaces and interfaces, superconductivity, energy R and D, waste processing and management, characterization and analysis, and facilities and instrumentation. Two more sections list department personnel, their publications etc., consultants, and summary of department budgets. The articles are processed separately for the data base. (DLC)

Used nuclear materials at Savannah River Site: asset or waste?

International Nuclear Information System (INIS)

Magoulas, Virginia

2013-01-01

The nuclear industry, both in the commercial and the government sectors, has generated large quantities of material that span the spectrum of usefulness, from highly valuable ''assets'' to worthless ''wastes''. In many cases, the decision parameters are clear. Transuranic waste and high level waste, for example, have no value, and is either in a final disposition path today, or - in the case of high level waste - awaiting a policy decision about final disposition. Other materials, though discardable, have intrinsic scientific or market value that may be hidden by the complexity, hazard, or cost of recovery. An informed decision process should acknowledge the asset value, or lack of value, of the complete inventory of materials, and the structure necessary to implement the range of possible options. It is important that informed decisions are made about the asset value for the variety of nuclear materials available. For example, there is a significant quantity of spent fuel available for recycle (an estimated $4 billion value in the Savannah River Site's (SRS) L area alone); in fact, SRS has already blended down more than 300 metric tons of uranium for commercial reactor use. Over 34 metric tons of surplus plutonium is also on a path to be used as commercial fuel. There are other radiological materials that are routinely handled at the site in large quantities that should be viewed as strategically important and / or commercially viable. In some cases, these materials are irreplaceable domestically, and failure to consider their recovery could jeopardize our technological leadership or national defense. The inventories of nuclear materials at SRS that have been characterized as ''waste'' include isotopes of plutonium, uranium, americium, and helium. Although planning has been performed to establish the technical and regulatory bases for their discard and disposal, recovery of these materials is both economically attractive and in the national interest.

Source Characterization Model (SCM): A Predictive Capability for the Source Terms of Residual Energetic Materials from Burning and/or Detonation Activities

National Research Council Canada - National Science Library

Brown, Robert C; Kolb, Charles E; Conant, John A; Zhang, John; Dussault, David M; Rush, Tamera L; Conway, Brooke E; Morris, James W; Touma, Joe

2004-01-01

.... Detonation of energetic materials produces a wide range of air and surface pollutants, including carbon monoxide, nitrogen oxides, volatile organic compounds, acid gases, and particulate matter...

Lining materials for waste disposal containment and waste storage facilities. (Latest citations from the NTIS bibliographic database). Published Search

International Nuclear Information System (INIS)

1993-11-01

The bibliography contains citations concerning the design characteristics, performance, and materials used to make liners for the waste disposal and storage industry. Liners made of concrete, polymeric materials, compacted clays, asphalt, and in-situ glass are discussed. The use of these liners to contain municipal wastes, hazardous waste liquids, and both low-level and high-level radioactive wastes is presented. Liner permeability, transport, stability, construction, and design are studied. Laboratory field measurements for specific wastes are included. (Contains a minimum of 213 citations and includes a subject term index and title list.)

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

International Nuclear Information System (INIS)

2013-02-01

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

Criticality conditions of heterogeneous energetic materials under shock loading

Science.gov (United States)

Nassar, Anas; Rai, Nirmal Kumar; Sen, Oishik; Udaykumar, H. S.

2017-06-01

Shock interaction with the microstructural heterogeneities of energetic materials can lead to the formation of locally heated regions known as hot spots. These hot spots are the potential sites where chemical reaction may be initiated. However, the ability of a hot spot to initiate chemical reaction depends on its size, shape and strength (temperature). Previous study by Tarver et al. has shown that there exists a critical size and temperature for a given shape (spherical, cylindrical, and planar) of the hot spot above which reaction initiation is imminent. Tarver et al. assumed a constant temperature variation in the hot spot. However, the meso-scale simulations show that the temperature distribution within a hot spot formed from processes such as void collapse is seldom constant. Also, the shape of a hot spot can be arbitrary. This work is an attempt towards development of a critical hot spot curve which is a function of loading strength, duration and void morphology. To achieve the aforementioned goal, mesoscale simulations are conducted on porous HMX material. The process is repeated for different loading conditions and void sizes. The hot spots formed in the process are examined for criticality depending on whether they will ignite or not. The metamodel is used to obtain criticality curves and is compared with the critical hot spot curve of Tarver et al.

Silver recovery from the waste materials by the method of flotation process

Directory of Open Access Journals (Sweden)

B. Oleksiak

2018-01-01

Full Text Available During the leaching process of zinc concentrates, the waste materials rich in various metals such as eg. silver are produced. So far no attempts of silver recovery from the mentioned waste materials have been made due to the lack of any method which would be both effective and beneficial. The paper presents some possibilities of application of flotation process in silver recovery form waste materials generated during zinc production.

2009 National inventory of radioactive material and wastes. In short

International Nuclear Information System (INIS)

2009-01-01

This booklet gives a summary of the national inventory report on radioactive wastes that are present on the French territory (as recorded until december, 2007). Intended for public information, the booklet explains the basics of radioactive materials and wastes and waste management, and gives some data on present and future waste volumes, information about radioactive waste classification, the geographical distribution of waste sites in France, etc. The various types of radioactive wastes are described (classified by their lifetime and activity level) as well as historical storage sites, polluted areas where wastes are stored, radioactive objects, etc. and their respective management approaches are presented

Multiphase Combustion of Metalized Nanocomposite Energetic Materials

Science.gov (United States)

2014-12-19

on thermal conductivity and absorption coefficient for consolidated aluminum nanoparticles, International Journal of Heat and Mass Transfer, (06...28. Stacy, S.C., Zhang, X., Pantoya, M.L., Weeks, B., Effect of Density on Thermal Conductivity and Absorption Coefficient for Consolidated Aluminum...energetic powder to ESD stimuli generated from a piezo electric crystal ( PZT ). Results show that a high PZT dielectric strength leads to faster

Stability of quasi-steady deflagrations in confined porous energetic materials

Energy Technology Data Exchange (ETDEWEB)

Alexander M. Telengator; Stephen B. Margolis; Forman A. Williams

2000-03-01

Previous analyses have shown that unconfined deflagrations propagating through both porous and nonporous energetic materials can exhibit a thermal/diffusive instability that corresponds to the onset of various oscillatory modes of combustion. For porous materials, two-phase-flow effects, associated with the motion of the gas products relative to the condensed material, play a significant role that can shift stability boundaries with respect to those associated with the nonporous problem. In the present work, additional significant effects are shown to be associated with confinement, which produces an overpressure in the burned-gas region that leads to reversal of the gas flow and hence partial permeation of the hot gases into the unburned porous material. This results in a superadiabatic effect that increases the combustion temperature and, consequently, the burning rate. Under the assumption of gas-phase quasi-steadiness, an asymptotic model is presented that facilitates a perturbation analysis of both the basic solution, corresponding to a steadily propagating planar combustion wave, and its stability. The neutral stability boundaries collapse to the previous results in the absence of confinement, but different trends arising from the presence of the gas-permeation layer are predicted for the confined problem. Whereas two-phase-flow effects are generally destabilizing in the unconfined geometry, the effects of increasing overpressure and hence combustion temperature associated with confinement are shown to be generally stabilizing with respect to thermal/diffusive instability, analogous to the effects of decreasing heat losses on combustion temperature and stability in single-phase deflagrations.

Waste reduction by re-use of low activated material - 16035

International Nuclear Information System (INIS)

Ehrlicher, Ulrich; Pauli, Heinz

2009-01-01

A multidisciplinary institute, equipped with research reactors and accelerator-driven research installations produces and, in the case of PSI, collects radioactive waste on one hand and requires material, especially for shielding purpose, on the other hand. The legislative framework for radiation protection, financial reasons and limited storage capacity strongly force Paul Scherrer Institute and comparable facilities to minimize radioactive waste. Besides free release of inactive components, recycling and re-use of low-level radioactive material in controlled areas are the best means for waste minimization. The re-use of slightly activated steel plates as a shielding material and the recycling of irradiated reactor graphite as a filling material embedded in mortar may give examples and encouragement for similar activities. Besides the advantages for radiation protection, the financial benefit can be measured in millions of dollars. (authors)

Developing an institutional strategy for transporting defense transuranic waste materials

International Nuclear Information System (INIS)

Guerrero, J.V.; Kresny, H.S.

1986-01-01

In late 1988, the US Department of Energy (DOE) expects to begin emplacing transuranic waste materials in the Waste Isolation Pilot Plant (WIPP), an R and D facility to demonstrate the safe disposal of radioactive wastes resulting from defense program activities. Transuranic wastes are production-related materials, e.g., clothes, rags, tools, and similar items. These materials are contaminated with alpha-emitting transuranium radionuclides with half-lives of > 20 yr and concentrations > 100 nCi/g. Much of the institutional groundwork has been done with local communities and the State of New Mexico on the siting and construction of the facility. A key to the success of the emplacement demonstration, however, will be a qualified transportation system together with institutional acceptance of the proposed shipments. The DOE's Defense Transuranic Waste Program, and its contractors, has lead responsibility for achieving this goal. The Joint Integration Office (JIO) of the DOE, located in Albuquerque, New Mexico, is taking the lead in implementing an integrated strategy for assessing nationwide institutional concerns over transportation of defense transuranic wastes and in developing ways to resolve or mitigate these concerns. Parallel prototype programs are under way to introduce both the new packaging systems and the institutional strategy to interested publics and organizations

Waste-efficient materials procurement for construction projects: A structural equation modelling of critical success factors.

Science.gov (United States)

Ajayi, Saheed O; Oyedele, Lukumon O

2018-05-01

Albeit the understanding that construction waste is caused by activities ranging from all stages of project delivery process, research efforts have been concentrated on design and construction stages, while the possibility of reducing waste through materials procurement process is widely neglected. This study aims at exploring and confirming strategies for achieving waste-efficient materials procurement in construction activities. The study employs sequential exploratory mixed method approach as its methodological framework, using focus group discussion, statistical analysis and structural equation modelling. The study suggests that for materials procurement to enhance waste minimisation in construction projects, the procurement process would be characterised by four features. These include suppliers' commitment to low waste measures, low waste purchase management, effective materials delivery management and waste-efficient Bill of Quantity, all of which have significant impacts on waste minimisation. This implies that commitment of materials suppliers to such measures as take back scheme and flexibility in supplying small materials quantity, among others, are expected of materials procurement. While low waste purchase management stipulates the need for such measures as reduced packaging and consideration of pre-assembled/pre-cut materials, efficient delivery management entails effective delivery and storage system as well as adequate protection of materials during the delivery process, among others. Waste-efficient specification and bill of quantity, on the other hand, requires accurate materials take-off and ordering of materials based on accurately prepared design documents and bill of quantity. Findings of this study could assist in understanding a set of measures that should be taken during materials procurement process, thereby corroborating waste management practices at other stages of project delivery process. Copyright © 2018. Published by Elsevier Ltd.

Energetic materials research and development activities at Sandia National Laboratories supported under DP-10 programs

Energy Technology Data Exchange (ETDEWEB)

Ratzel, A.C. III

1998-09-01

This report provides summary descriptions of Energetic Materials (EM) Research and Development activities performed at Sandia National Laboratories and funded through the Department of Energy DP-10 Program Office in FY97 and FY98. The work falls under three major focus areas: EM Chemistry, EM Characterization, and EM Phenomenological Model Development. The research supports the Sandia component mission and also Sandia's overall role as safety steward for the DOE Nuclear Weapons Complex.

Standardization of waste acceptance test methods by the Materials Characterization Center

International Nuclear Information System (INIS)

Slate, S.C.

1985-01-01

This paper describes the role of standardized test methods in demonstrating the acceptability of high-level waste (HLW) forms for disposal. Key waste acceptance tests are standardized by the Materials Characterization Center (MCC), which the US Department of Energy (DOE) has established as the central agency in the United States for the standardization of test methods for nuclear waste materials. This paper describes the basic three-step process that is used to show that waste is acceptable for disposal and discusses how standardized tests are used in this process. Several of the key test methods and their areas of application are described. Finally, future plans are discussed for using standardized tests to show waste acceptance. 9 refs., 1 tab

Characterization and inventories of nuclear materials and wastes for possible future energy scenarios

International Nuclear Information System (INIS)

Arthur, E.D.

1997-10-01

Awareness of the total materials inventory and materials balance associated with differing methods for energy generation is part of present day concerns associated with disparate areas that include atmospheric emissions, resource utilization, health effects, and both current and long term hazards and risks. Nuclear energy, for a number of decades, has been the recipient of significant scrutiny concerning the materials and wastes it generates, particularly in the context of long term solutions to such issues. This paper examines the nuclear materials and waste generation for nuclear energy scenarios spanning the coming century. The paper also briefly addresses wastes (in the form of emissions) from other energy sources and examines requirements associated with backend energy system materials management. Possible future requirements pertaining to CO 2 management are found to place conditions upon waste management generally similar to those for nuclear waste. One example of material flows for the case of coal generation of electricity coupled with carbon sequestration is also given

Bioenergy, material, and nutrients recovery from household waste: Advanced material, substance, energy, and cost flow analysis of a waste refinery process

DEFF Research Database (Denmark)

Tonini, Davide; Dorini, Gianluca Fabio; Astrup, Thomas Fruergaard

2014-01-01

Energy, materials, and resource recovery from mixed household waste may contribute to reductions in fossil fuel and resource consumption. For this purpose, legislation has been enforced to promote energy recovery and recycling. Potential solutions for separating biogenic and recyclable materials...

Toxicity Determinations for Five Energetic Materials, Weathered and Aged in Soil, to the Collembolan Folsomia Candida

Science.gov (United States)

2015-03-01

obtained from the Soil Fauna and Ecotoxicology Research Unit, Department of Terrestrial Ecology, National Environmental Research Institute (Silkeborg...AND AGED IN SOIL , TO THE COLLEMBOLAN FOLSOMIA CANDIDA ECBC-TR-1273 Carlton T. Phillips Ronald T. Checkai Roman G. Kuperman Michael Simini...for Five Energetic Materials, Weathered and Aged in Soil , to the Collembolan Folsomia candida 5a. CONTRACT NUMBER 5b. GRANT NUMBER 5c

Method and apparatus for the management of hazardous waste material

Science.gov (United States)

Murray, Jr., Holt

1995-01-01

A container for storing hazardous waste material, particularly radioactive waste material, consists of a cylindrical body and lid of precipitation hardened C17510 beryllium-copper alloy, and a channel formed between the mated lid and body for receiving weld filler material of C17200 copper-beryllium alloy. The weld filler material has a precipitation hardening temperature lower than the aging kinetic temperature of the material of the body and lid, whereby the weld filler material is post weld heat treated for obtaining a weld having substantially the same physical, thermal, and electrical characteristics as the material of the body and lid. A mechanical seal assembly is located between an interior shoulder of the body and the bottom of the lid for providing a vacuum seal.

Nuclear waste package materials testing report: basaltic and tuffaceous environments

International Nuclear Information System (INIS)

Bradley, D.J.; Coles, D.G.; Hodges, F.N.; McVay, G.L.; Westerman, R.E.

1983-03-01

The disposal of high-level nuclear wastes in underground repositories in the continental United States requires the development of a waste package that will contain radionuclides for a time period commensurate with performance criteria, which may be up to 1000 years. This report addresses materials testing in support of a waste package for a basalt (Hanford, Washington) or a tuff (Nevada Test Site) repository. The materials investigated in this testing effort were: sodium and calcium bentonites and mixtures with sand or basalt as a backfill; iron and titanium-based alloys as structural barriers; and borosilicate waste glass PNL 76-68 as a waste form. The testing also incorporated site-specific rock media and ground waters: Reference Umtanum Entablature-1 basalt and reference basalt ground water, Bullfrog tuff and NTS J-13 well water. The results of the testing are discussed in four major categories: Backfill Materials: emphasizing water migration, radionuclide migration, physical property and long-term stability studies. Structural Barriers: emphasizing uniform corrosion, irradiation-corrosion, and environmental-mechanical testing. Waste Form Release Characteristics: emphasizing ground water, sample surface area/solution volume ratio, and gamma radiolysis effects. Component Compatibility: emphasizing solution/rock, glass/rock, glass/structural barrier, and glass/backfill interaction tests. This area also includes sensitivity testing to determine primary parameters to be studied, and the results of systems tests where more than two waste package components were combined during a single test

Compression device for feeding a waste material to a reactor

Science.gov (United States)

Williams, Paul M.; Faller, Kenneth M.; Bauer, Edward J.

2001-08-21

A compression device for feeding a waste material to a reactor includes a waste material feed assembly having a hopper, a supply tube and a compression tube. Each of the supply and compression tubes includes feed-inlet and feed-outlet ends. A feed-discharge valve assembly is located between the feed-outlet end of the compression tube and the reactor. A feed auger-screw extends axially in the supply tube between the feed-inlet and feed-outlet ends thereof. A compression auger-screw extends axially in the compression tube between the feed-inlet and feed-outlet ends thereof. The compression tube is sloped downwardly towards the reactor to drain fluid from the waste material to the reactor and is oriented at generally right angle to the supply tube such that the feed-outlet end of the supply tube is adjacent to the feed-inlet end of the compression tube. A programmable logic controller is provided for controlling the rotational speed of the feed and compression auger-screws for selectively varying the compression of the waste material and for overcoming jamming conditions within either the supply tube or the compression tube.

Chemical digestion of low level nuclear solid waste material

International Nuclear Information System (INIS)

Cooley, C.R.; Lerch, R.E.

1976-01-01

A chemical digestion for treatment of low level combustible nuclear solid waste material is provided and comprises reacting the solid waste material with concentrated sulfuric acid at a temperature within the range of 230 0 --300 0 C and simultaneously and/or thereafter contacting the reacting mixture with concentrated nitric acid or nitrogen dioxide. In a special embodiment spent ion exchange resins are converted by this chemical digestion to noncombustible gases and a low volume noncombustible residue. 6 claims, no drawings

ENVIRONMENTALLY SOUND DISPOSAL OF RADIOACTIVE MATERIALS AT A RCRA HAZARDOUS WASTE DISPOSAL FACILITY

International Nuclear Information System (INIS)

Romano, Stephen; Welling, Steven; Bell, Simon

2003-01-01

The use of hazardous waste disposal facilities permitted under the Resource Conservation and Recovery Act (''RCRA'') to dispose of low concentration and exempt radioactive materials is a cost-effective option for government and industry waste generators. The hazardous and PCB waste disposal facility operated by US Ecology Idaho, Inc. near Grand View, Idaho provides environmentally sound disposal services to both government and private industry waste generators. The Idaho facility is a major recipient of U.S. Army Corps of Engineers FUSRAP program waste and received permit approval to receive an expanded range of radioactive materials in 2001. The site has disposed of more than 300,000 tons of radioactive materials from the federal government during the past five years. This paper presents the capabilities of the Grand View, Idaho hazardous waste facility to accept radioactive materials, site-specific acceptance criteria and performance assessment, radiological safety and environmental monitoring program information

Assessing microbiologically induced corrosion of waste package materials in the Yucca Mountain repository

Energy Technology Data Exchange (ETDEWEB)

Horn, J. M., LLNL

1998-01-01

The contribution of bacterial activities to corrosion of nuclear waste package materials must be determined to predict the adequacy of containment for a potential nuclear waste repository at Yucca Mountain (YM), NV. The program to evaluate potential microbially induced corrosion (MIC) of candidate waste container materials includes characterization of bacteria in the post-construction YM environment, determination of their required growth conditions and growth rates, quantitative assessment of the biochemical contribution to metal corrosion, and evaluation of overall MIC rates on candidate waste package materials.

A case-study of landfill minimization and material recovery via waste co-gasification in a new waste management scheme.

Science.gov (United States)

Tanigaki, Nobuhiro; Ishida, Yoshihiro; Osada, Morihiro

2015-03-01

This study evaluates municipal solid waste co-gasification technology and a new solid waste management scheme, which can minimize final landfill amounts and maximize material recycled from waste. This new scheme is considered for a region where bottom ash and incombustibles are landfilled or not allowed to be recycled due to their toxic heavy metal concentration. Waste is processed with incombustible residues and an incineration bottom ash discharged from existent conventional incinerators, using a gasification and melting technology (the Direct Melting System). The inert materials, contained in municipal solid waste, incombustibles and bottom ash, are recycled as slag and metal in this process as well as energy recovery. Based on this new waste management scheme with a co-gasification system, a case study of municipal solid waste co-gasification was evaluated and compared with other technical solutions, such as conventional incineration, incineration with an ash melting facility under certain boundary conditions. From a technical point of view, co-gasification produced high quality slag with few harmful heavy metals, which was recycled completely without requiring any further post-treatment such as aging. As a consequence, the co-gasification system had an economical advantage over other systems because of its material recovery and minimization of the final landfill amount. Sensitivity analyses of landfill cost, power price and inert materials in waste were also conducted. The higher the landfill costs, the greater the advantage of the co-gasification system has. The co-gasification was beneficial for landfill cost in the range of 80 Euro per ton or more. Higher power prices led to lower operation cost in each case. The inert contents in processed waste had a significant influence on the operating cost. These results indicate that co-gasification of bottom ash and incombustibles with municipal solid waste contributes to minimizing the final landfill amount and has

Design of a deposit of waste materials coming from mining exploitations

International Nuclear Information System (INIS)

Castro, Alvaro; Pinzon, Hernan; Vargas, William; Pinzon, Andres

2005-01-01

This paper presents the design process and stability assessment of a waste backfill in a limestone quarry method. The study shows the geotechnical and mining features of waste and underground materials affected by backfill. The mainly waste materials are: clay, gravel, and blocks of clay stone, sandstone and limestone, all to be disposed by a layered embankment. The constructive method is selected and the stability analysis of deposit and soil foundation was made by equilibrium method without considering deformations

Catalytic applications of calcium rich waste materials for biodiesel: Current state and perspectives

International Nuclear Information System (INIS)

Shan, Rui; Zhao, Che; Lv, Pengmei; Yuan, Haoran; Yao, Jingang

2016-01-01

Highlights: • This review presents information related to waste derived Ca-based catalysts. • The materials described include eggshells, mollusk shells, bones, and so on. • The mechanism, future challenges and prospects of those catalysts are discussed. - Abstract: The synthesis of heterogeneous catalysts from waste materials has become increasingly popular over the past two decades. Among them, Ca-based catalysts have widely been tested in the transesterification reaction because of their relatively high catalytic activity and the large amount of feedstock (calcium rich waste materials) available. Those Ca-based catalysts can be simply prepared via the high temperature calcination and using these waste materials to generate the catalyst in addition to the target product makes the system more cost effective and environmentally friendly. This review presents general information related to the recent progress in the development of various Ca-based catalysts derived from waste materials for biodiesel production. The materials described include eggshells, mollusk shells, bones, large-scale industrial wastes and so on. Meanwhile, based on this collection of data and information, the catalytic activity mechanism, future challenges and prospects of renewable resources derived catalysts are also discussed.

Three-dimensional simulations of void collapse in energetic materials

Science.gov (United States)

Rai, Nirmal Kumar; Udaykumar, H. S.

2018-03-01

The collapse of voids in porous energetic materials leads to hot-spot formation and reaction initiation. This work advances the current knowledge of the dynamics of void collapse and hot-spot formation using 3D reactive void collapse simulations in HMX. Four different void shapes, i.e., sphere, cylinder, plate, and ellipsoid, are studied. For all four shapes, collapse generates complex three-dimensional (3D) baroclinic vortical structures. The hot spots are collocated with regions of intense vorticity. The differences in the vortical structures for the different void shapes are shown to significantly impact the relative sensitivity of the voids. Voids of high surface area generate hot spots of greater intensity; intricate, highly contorted vortical structures lead to hot spots of corresponding tortuosity and therefore enhanced growth rates of reaction fronts. In addition, all 3D voids are shown to be more sensitive than their two-dimensional (2D) counterparts. The results provide physical insights into hot-spot formation and growth and point to the limitations of 2D analyses of hot-spot formation.

Municipal wastes and landfield gases utilization - renewable resource of energy and materials

International Nuclear Information System (INIS)

Kuburovic, M.; Jovovic, A.

2002-01-01

Urbanization and industrialization, have been fundamental causes of environmental pollution (of water, air and land) which the cities were unable to handle. There is already enough evidence of the fact that the role of technology in environmental matters is moving in two important directions: sustainable development, dealing primary with global problems, and preventive technology, designed to reduce the environmental effects of processes, operations, and products. Treatment plants for industrial and municipal wastes, emission controls for incinerators, and safe landfills for waste disposal were developed to control air, water, and land pollution. Now, this 'end-of-pipe' treatment technologies are still the way of environmental protection philosophy, particularly in the developing countries. New environmental standards demand more and more rigorous preventive environmental protection technologies, therefore further development of industrial production requires the rational use of natural sources of raw materials and energy. Production and the use of goods with the minimum municipal and industrial wastes and the development of recycling technology provided closed cycle of materials. Main principles for the development and exploitation of the technology with the minimum or without waste materials and energy are: the use of renewable sources of material and energy, maximum use of waste materials and waste energy, waste minimisation and reduction of energy losses in the production, development of new industrial processes operating with minimum material and energy losses in products exploitation period and after that, and the responsible use of natural sources, products and energy in the field of industry and consumption. (author)

Material Recovery and Waste Form Development FY 2014 Accomplishments Report

Energy Technology Data Exchange (ETDEWEB)

Braase, Lori [Idaho National Lab. (INL), Idaho Falls, ID (United States)

2014-11-01

Develop advanced nuclear fuel cycle separation and waste management technologies that improve current fuel cycle performance and enable a sustainable fuel cycle, with minimal processing, waste generation, and potential for material diversion.

Raw-materials mixtures from waste of the coal industry for production of ceramic materials

Energy Technology Data Exchange (ETDEWEB)

Galpern, E I [Scientific-Manufacturing Enterprise ` ` Ceramics` ` , Donetsk (Ukraine); Pashchenko, L V [Inst. of Physical, Organic and Coal Chemistry of NASU, Donetsk (Ukraine)

1998-09-01

The liquidation of waste dumps on the surface of mining enterprises and realization of measures by environment protection of air and aquatic basins are connected to the complex processing of mining mass. The main directions of utilization of mining rocks and coal wastes realized in Ukraine industry are: - filling of mines worked-out area by grouting solutions; - ceramic brick, porous filling materials and binding materials production; - road-making, construction of hydrostructures and industrial objects; - output of concrete items predominantly for using in mining conditions. The peculiarity of wastes using in above-mentioned fields is the possibility of their mass application in quantities commensurable with valumes of their yields. The experience of enterprises work which process mining rocks into building materials by burning method (ceramic brick, porous aggregates of concretes as aggloporite, expanded clay aggregate) has shown that unconstant and, as the rule, exceeding norms content of carbon and sulphur in the rock results to deterioration of products quality and technological factors of production. Unstability of carbon content in raw material makes the burning process hardly operated. Obtained products having residual carbon in the view of coke residue are often characterized by lower physical-mechanical characteristics. (orig./SR)

Recycling ceramic industry wastes in sound absorbing materials

Directory of Open Access Journals (Sweden)

C. Arenas

2016-10-01

Full Text Available The scope of this investigation is to develop a material mainly composed (80% w/w of ceramic wastes that can be applied in the manufacture of road traffic noise reducing devices. The characterization of the product has been carried out attending to its acoustic, physical and mechanical properties, by measuring the sound absorption coefficient at normal incidence, the open void ratio, density and compressive strength. Since the sound absorbing behavior of a porous material is related to the size of the pores and the thickness of the specimen tested, the influence of the particle grain size of the ceramic waste and the thickness of the samples tested on the properties of the final product has been analyzed. The results obtained have been compared to a porous concrete made of crushed granite aggregate as a reference commercial material traditionally used in similar applications. Compositions with coarse particles showed greater sound absorption properties than compositions made with finer particles, besides presenting better sound absorption behavior than the reference porous concrete. Therefore, a ceramic waste-based porous concrete can be potentially recycled in the highway noise barriers field.

Demonstration of remotely operated TRU waste size reduction and material handling equipment

International Nuclear Information System (INIS)

Looper, M.G.; Charlesworth, D.L.

1988-01-01

The Savannah River Laboratory (SRL) is developing remote size reduction and material handling equipment to prepare 238 Pu contaminated waste for permanent disposal at the Waste Isolation Pilot Plant (WIPP) in New Mexico. The waste is generated at the Savannah River Plant (SRP) from normal operation and decommissioning activity and is retrievably stored onsite. A Transuranic Waste Facility for preparing, size-reducing, and packaging this waste for disposal is scheduled for completion in 1995. A cold test facility for demonstrating the size reduction and material handling equipment was built, and testing began in January 1987. 9 figs., 1 tab

PROCESS DEVELOPMENT FOR THE RECOVERY OF CRITICAL MATERIALS FROM ELECTRONIC WASTE

Energy Technology Data Exchange (ETDEWEB)

Lister, T. E.; Diaz, L. A.; Clark, G. G.; Keller, P.

2016-09-01

As electronic technology continues to evolve there is a growing need to develop processes which recover valuable material from antiquated technology. This need follows from the environmental challenges associated with the availability of raw materials and fast growing generation of electronic waste. Although just present in small quantities in electronic devices, the availability of raw materials, such as rare earths and precious metals, becomes critical for the production of high tech electronic devices and the development of green technologies (i.e. wind turbines, electric motors, and solar panels). Therefore, the proper recycling and processing of increasing volumes of electronic waste present an opportunity to stabilize the market of critical materials, reducing the demand of mined products, and providing a proper disposal and treatment of a hazardous waste stream. This paper will describe development and techno-economic assessment of a comprehensive process for the recovery of value and critical materials from electronic waste. This hydrometallurgical scheme aims to selectively recover different value segments in the materials streams (base metals, precious metals, and rare earths). The economic feasibility for the recovery of rare earths from electronic waste is mostly driven by the efficient recovery of precious metals, such as Au and Pd (ca. 80 % of the total recoverable value). Rare earth elements contained in magnets (speakers, vibrators and hard disk storage) can be recovered as a mixture of rare earths oxides which can later be reduced to the production of new magnets.

Prediction of detonation and JWL eos parameters of energetic materials using EXPLO5 computer code

CSIR Research Space (South Africa)

Peter, Xolani

2016-09-01

Full Text Available Ballistic Organization Cape Town, South Africa 27-29 September 2016 1 PREDICTION OF DETONATION AND JWL EOS PARAMETERS OF ENERGETIC MATERIALS USING EXPLO5 COMPUTER CODE X. Peter*, Z. Jiba, M. Olivier, I.M. Snyman, F.J. Mostert and T.J. Sono.... Nowadays many numerical methods and programs are being used for carrying out thermodynamic calculations of the detonation parameters of condensed explosives, for example a BKW Fortran (Mader, 1967), Ruby (Cowperthwaite and Zwisler, 1974) TIGER...

Forming artificial soils from waste materials for mine site rehabilitation

Science.gov (United States)

Yellishetty, Mohan; Wong, Vanessa; Taylor, Michael; Li, Johnson

2014-05-01

Surface mining activities often produce large volumes of solid wastes which invariably requires the removal of significant quantities of waste rock (overburden). As mines expand, larger volumes of waste rock need to be moved which also require extensive areas for their safe disposal and containment. The erosion of these dumps may result in landform instability, which in turn may result in exposure of contaminants such as trace metals, elevated sediment delivery in adjacent waterways, and the subsequent degradation of downstream water quality. The management of solid waste materials from industrial operations is also a key component for a sustainable economy. For example, in addition to overburden, coal mines produce large amounts of waste in the form of fly ash while sewage treatment plants require disposal of large amounts of compost. Similarly, paper mills produce large volumes of alkaline rejected wood chip waste which is usually disposed of in landfill. These materials, therefore, presents a challenge in their use, and re-use in the rehabilitation of mine sites and provides a number of opportunities for innovative waste disposal. The combination of solid wastes sourced from mines, which are frequently nutrient poor and acidic, with nutrient-rich composted material produced from sewage treatment and alkaline wood chip waste has the potential to lead to a soil suitable for mine rehabilitation and successful seed germination and plant growth. This paper presents findings from two pilot projects which investigated the potential of artificial soils to support plant growth for mine site rehabilitation. We found that pH increased in all the artificial soil mixtures and were able to support plant establishment. Plant growth was greatest in those soils with the greatest proportion of compost due to the higher nutrient content. These pot trials suggest that the use of different waste streams to form an artificial soil can potentially be used in mine site rehabilitation

Thermodynamic model of natural, medieval and nuclear waste glass durability

International Nuclear Information System (INIS)

Jantzen, C.M.; Plodinec, M.J.

1983-01-01

A thermodynamic model of glass durability based on hydration of structural units has been applied to natural glass, medieval window glasses, and glasses containing nuclear waste. The relative durability predicted from the calculated thermodynamics correlates directly with the experimentally observed release of structural silicon in the leaching solution in short-term laboratory tests. By choosing natural glasses and ancient glasses whose long-term performance is known, and which bracket the durability of waste glasses, the long-term stability of nuclear waste glasses can be interpolated among these materials. The current Savannah River defense waste glass formulation is as durable as natural basalt from the Hanford Reservation (10 6 years old). The thermodynamic hydration energy is shown to be related to the bond energetics of the glass. 69 references, 2 figures, 1 table

Validation of new ceramic materials from tungsten mining wastes. Mechanical properties

International Nuclear Information System (INIS)

Duran Suarez, J. A.; Montoya Herrera, J.; Silva, A. P.; Peralbo Cano, R.; Castro-Gomes, J. P.

2014-01-01

New ceramic materials obtained from tungsten mining wastes, from region of Beira Interior in Portugal, with no commercial use, responsible for landscape and environmental problems are presented. These preshaped new ceramic products, prepared in a wide thermal range (800 degree centigrade to 1300 degree centigrade) was evaluated by mechanical test, but also was characterized the starting raw materials: tungsten wastes mining and industrial kaolin. Results, which also include a mineralogical characterization of ceramic products and morphologic evaluation of neoformed by scanning electron microscopy, show firstly, the feasibility of converting a large number of these wastes in marketable ceramics. Thanks to the experimentation carried out, the ability to generate ceramic materials is emphasized, without the presence of mineral clay, due to the particular composition of these waste of mining with content of acid, neutral and basic oxides. (Author)

New Porous Material Made from Industrial and Municipal Waste for Building Application

Directory of Open Access Journals (Sweden)

Diana BAJARE

2014-09-01

Full Text Available The aim of this study was to find a new method for usage of the hazardous waste coming from recycling industry. Two hazardous wastes – aluminium recycling final dross or non-metallic product (NMP and lead – silica glass (LSG were investigated. It is generally considered that NMP is a process waste and subject to disposal after residual metal has been recovered from primary dross. NMP is impurities which are removed from the molten metal in dross recycling process and it could be defined as a hazardous waste product in aluminium recycling industry. LSG comes from fluorescence lamp recycling plant and could be classified as hazardous waste due to high amount of lead in the composition and re-melting problems. The new alkali activated material, which can be defined as porous building material, was created. Composition of this material consisted of aluminium recycling waste, recycled fluorescent lamp LSG, sintered kaolin clay as well as commercially available alkali flakes (NaOH and liquid glass (Na2SiO3 + nH2O. Physical and mechanical properties of the obtained material were tested. Density of the obtained material was from (460 – 550 kg/m3 and the total porosity was from 82 % – 83 %. The compressive strength of the material was in range from 1.1 MPa to 2.3 MPa. The thermal conductivity was determined. The pore microstructure was investigated and the mineralogical composition of porous material was determined. DOI: http://dx.doi.org/10.5755/j01.ms.20.3.4330

Melting behaviour of raw materials and recycled stone wool waste

DEFF Research Database (Denmark)

Schultz-Falk, Vickie; Agersted, Karsten; Jensen, Peter Arendt

2018-01-01

Stone wool is a widely used material for building insulation, to provide thermal comfort along with fire stability and acoustic comfort for all types of buildings. Stone wool waste generated either during production or during renovation or demolition of buildings can be recycled back into the sto...... wool melt production. This study investigates and compares the thermal response and melting behaviour of a conventional stone wool charge and stone wool waste. The study combines differential scanning calorimetry (DSC), hot stage microscopy (HSM) and X-ray diffraction (XRD). DSC reveals...... that the conventional charge and stone wool waste have fundamentally different thermal responses, where the charge experiences gas release, phase transition and melting of the individual raw materials. The stone wool waste experiences glass transition, crystallization and finally melting. Both DSC and HSM measurements...

Phosphate bonded ceramics as candidate final-waste-form materials

International Nuclear Information System (INIS)

Singh, D.; Wagh, A.S.; Cunnane, J.; Sutaria, M.; Kurokawa, S.; Mayberry, J.

1994-04-01

Room-temperature setting phosphate-bonded ceramics were studied as candidate materials for stabilization of DOE low-level problem mixed wastes which cannot be treated by other established stabilization techniques. Phosphates of Mg, Mg-Na, Al and Zr were studied to stabilize ash surrogate waste containing RCRA metals as nitrates and RCRA organics. We show that for a typical loading of 35 wt.% of the ash waste, the phosphate ceramics pass the TCLP test. The waste forms have high compression strength exceeding ASTM recommendations for final waste forms. Detailed X-ray diffraction studies and differential thermal analyses of the waste forms show evidence of chemical reaction of the waste with phosphoric acid and the host matrix. The SEM studies show evidence of physical bonding. The excellent performance in the leaching tests is attributed to a chemical solidification and physical as well as chemical bonding of ash wastes in these phosphate ceramics

Characteristics and advantages of the HTW process for efficient recycling of the energetic and material fraction of waste materials; Merkmale und Vorzuege des Hochtemperatur-Winkler (HTW)-Verfahrens zur effizienten energetischen und stofflichen Nutzung von Abfaellen

Energy Technology Data Exchange (ETDEWEB)

Wischnewski, R; Mittelstaedt, A; Renzenbrink, W [Rheinbraun AG, Koeln (Germany); Luetge, C; Abraham, R [Krupp Uhde GmbH, Dortmund (Germany)

1998-09-01

Co-gasification of DSD mixed plastics in the HTW demonstration plant led to the following results: Co-gasification of preprocessed waste materials poses no technical problems - the performance of the gasifier and its downstream components is not affected - the synthesis gas quality remains unchanged - changes in trace element behaviour can be accounted for by design modifications - the large volume of the fluidized bed neutralizes the effects of waste material inhomogeneities and foreign materials - the conversion yield is high - there are well-established ways of disposal of residual material, i.e. bottom deposits and hot-gas filter dust. (orig./SR) [Deutsch] Die Ergebnisse der Mitvergasung von DSD-Mischkunststoffen an der HTW-Demonstrationsanlage haben zusammenfassend gezeigt: - der Abfallstoff laesst sich nach einer Aufbereitung problemlos in den Vergaser eintragen - es tritt keine Beeintraechtigung des Betriebsverhaltens des Vergasers und der nachgeschalteten Teilanlagen auf - die Synthesegasqualitaet veraendert sich nicht - Aenderungen am Spurstoffverhalten sind durch entsprechende Auslegung beherrschbar - der grosse Wirbelbettinhalt fuehrt zu einer Unempfindlichkeit gegenueber Inhomogenitaeten des Reststoffes sowie Fremdeinschluessen - die Umsetzung fuehrt zu einer hohen Ausbeute des Abfallstoffes - fuer die Reststoffe Bodenprodukt und Warmgasfilterstaub gibt es geklaerte Entsorgungswege. (orig./SR)

National inventory of radioactive wastes and valorizable materials. Synthesis report

International Nuclear Information System (INIS)

2004-01-01

This national inventory of radioactive wastes is a reference document for professionals and scientists of the nuclear domain and also for any citizen interested in the management of radioactive wastes. It contains: 1 - general introduction; 2 - the radioactive wastes: definition, classification, origin and management; 3 - methodology of the inventory: organization, accounting, prospective, production forecasting, recording of valorizable materials, exhaustiveness, verification tools; 4 - general results: radioactive waste stocks recorded until December 31, 2002, forecasts for the 2003-2020 era, post-2020 prospects: dismantling operations, recording of valorizable materials; 5 - inventory per producer or owner: front-end fuel cycle facilities, power generation nuclear centers, back-end fuel cycle facilities, waste processing or maintenance facilities, civil CEA research centers, non-CEA research centers, medical activities (diagnostics, therapeutics, analyses), various industrial activities (sources fabrication, control, particular devices), military research and experiment centers, storage and disposal facilities; 6 - elements about radioactive polluted sites; 7 - examples of foreign inventories; 8 - conclusion and appendixes. (J.S.)

Mechanical degradation temperature of waste storage materials

International Nuclear Information System (INIS)

Fink, M.C.; Meyer, M.L.

1993-01-01

Heat loading analysis of the Solid Waste Disposal Facility (SWDF) waste storage configurations show the containers may exceed 90 degrees C without any radioactive decay heat contribution. Contamination containment is primarily controlled in TRU waste packaging by using multiple bag layers of polyvinyl chloride and polyethylene. Since literature values indicate that these thermoplastic materials can begin mechanical degradation at 66 degrees C, there was concern that the containment layers could be breached by heating. To better define the mechanical degradation temperature limits for the materials, a series of heating tests were conducted over a fifteen and thirty minute time interval. Samples of a low-density polyethylene (LDPE) bag, a high-density polyethylene (HDPE) high efficiency particulate air filter (HEPA) container, PVC bag and sealing tape were heated in a convection oven to temperatures ranging from 90 to 185 degrees C. The following temperature limits are recommended for each of the tested materials: (1) low-density polyethylene -- 110 degrees C; (2) polyvinyl chloride -- 130 degrees C; (3) high-density polyethylene -- 140 degrees C; (4) sealing tape -- 140 degrees C. Testing with LDPE and PVC at temperatures ranging from 110 to 130 degrees C for 60 and 120 minutes also showed no observable differences between the samples exposed at 15 and 30 minute intervals. Although these observed temperature limits differ from the literature values, the trend of HDPE having a higher temperature than LDPE is consistent with the reference literature. Experimental observations indicate that the HDPE softens at elevated temperatures, but will retain its shape upon cooling. In SWDF storage practices, this might indicate some distortion of the waste container, but catastrophic failure of the liner due to elevated temperatures (<185 degrees C) is not anticipated

Advanced Thermoelectric Materials for Efficient Waste Heat Recovery in Process Industries

Energy Technology Data Exchange (ETDEWEB)

Adam Polcyn; Moe Khaleel

2009-01-06

The overall objective of the project was to integrate advanced thermoelectric materials into a power generation device that could convert waste heat from an industrial process to electricity with an efficiency approaching 20%. Advanced thermoelectric materials were developed with figure-of-merit ZT of 1.5 at 275 degrees C. These materials were not successfully integrated into a power generation device. However, waste heat recovery was demonstrated from an industrial process (the combustion exhaust gas stream of an oxyfuel-fired flat glass melting furnace) using a commercially available (5% efficiency) thermoelectric generator coupled to a heat pipe. It was concluded that significant improvements both in thermoelectric material figure-of-merit and in cost-effective methods for capturing heat would be required to make thermoelectric waste heat recovery viable for widespread industrial application.

Characterization of solid wastes from kraft pulp industry for ceramic materials development purposes

International Nuclear Information System (INIS)

Rodrigues, L.R.; Francisco, M.A.C.O.; Sagrillo, V.P.D.; Louzada, D.M.; Entringer, J.M.S.

2016-01-01

The Kraft pulp industry generates a large amount of solid wastes. Due this large quantity, the target of this study is characterize inorganic solid wastes, dregs, grits and lime mud, from the step of reagents recovery of Kraft process, aiming evaluate the potentiality of their use as alternative raw material on development of ceramic materials. Initially, the wastes were dried and ground, then they were subjected to the following characterization techniques: pH analysis, particle size analysis, X ray fluorescence, X ray diffraction, differential thermal analysis and thermogravimetric analysis and scanning electron microscopy. According to the results, it may be concluded that these wastes could be used as raw material in production of red ceramic and luting materials. (author)

Materials Characterization Center meeting on impact testing of waste forms. Summary report

International Nuclear Information System (INIS)

Merz, M.D.; Atteridge, D.; Dudder, G.

1981-10-01

A meeting was held on March 25-26, 1981 to discuss impact test methods for waste form materials to be used in nuclear waste repositories. The purpose of the meeting was to obtain guidance for the Materials Characterization Center (MCC) in preparing the MCC-10 Impact Test Method to be approved by the Materials Review Board. The meeting focused on two essential aspects of the test method, namely the mechanical process, or impact, used to effect rapid fracture of a waste form and the analysis technique(s) used to characterize particulates generated by the impact

Radioactive material inventory control at a waste characterization facility

International Nuclear Information System (INIS)

Yong, L.K.; Chapman, J.A.; Schultz, F.J.

1996-01-01

Due to the recent introduction of more stringent Department of Energy (DOE) regulations and requirements pertaining to nuclear and criticality safety, the control of radioactive material inventory has emerged as an important facet of operations at DOE nuclear facilities. In order to comply with nuclear safety regulations and nuclear criticality requirements, radioactive material inventories at each nuclear facility have to be maintained below limits specified for the facility in its safety authorization basis documentation. Exceeding these radioactive material limits constitutes a breach of the facility's nuclear and criticality safety envelope and could potentially result in an accident, cause a shut-down of the facility, and bring about imminent regulatory repercussions. The practice of maintaining control of radioactive material, especially sealed and unsealed sources, is commonplace and widely implemented; however, the requirement to track the entire radioactivity inventory at each nuclear facility for the purpose of ensuring nuclear safety is a new development. To meet the new requirements, the Applied Radiation Measurements Department at Oak Ridge National Laboratory (ORNL) has developed an information system, called the open-quotes Radioactive Material Inventory Systemclose quotes (RMIS), to track the radioactive material inventory at an ORNL facility, the Waste Examination and Assay Facility (WEAF). The operations at WEAF, which revolve around the nondestructive assay and nondestructive examination of waste and related research and development activities, results in an ever-changing radioactive material inventory. Waste packages and radioactive sources are constantly being brought in or taken out of the facility; hence, use of the RMIS is necessary to ensure that the radioactive material inventory limits are not exceeded

Transport packages for nuclear material and waste

International Nuclear Information System (INIS)

1997-01-01

The regulations and responsibilities concerning the transport packages of nuclear materials and waste are given in the guide. The approval procedure, control of manufacturing, commissioning of the packaging and the control of use are specified. (13 refs.)

RDF to energy plant for a central Italian region SUW management system: Energetic and economical analysis

International Nuclear Information System (INIS)

Di Maria, Francesco; Pavesi, Gregorio

2006-01-01

It is well known that a rise in a country's prosperity is parallel to an increase in the amount of waste produced by the population. The specific solid urban waste production off a European citizen is actually about 500 kg per inhabitant per year. In reference to the whole European population, the global solid urban waste production requires an adequate management system, able to satisfy economical, social and environmental needs. Before final disposal (i.e. sanitary landfill), wastes need some kind of recovery, reuse and ad hoc treatments operation, in compliance with European state laws. The aim of these rules is to achieve an environmentally sound waste management system, that allows to reduce raw materials and fossil fuel consumption, dangerous waste production and the amount of disposed materials. Among the technologies available for the different treatments, incineration with energy recovery seems to have many advantages mainly because it reduces waste volume and fossil fuel consumption, and because its sterilization effects are achieved on the inlet substances. The main drawbacks of such plants are represented by the emission off gaseous pollutant, thus requiring important exhaust gasses treatment systems, by producing a non-negligible amount of dangerous substances, and by high capital and operating costs. In this paper the solid urban waste production of a central Italian region and the amount of available residual derived fuel for thermal treatment has been assessed. Then, the possibility of exploiting a fluid bed combustor based power plant, able to treat the residual derive fuel fraction produced through the years, has been analyzed both from an energetic and an economical point of view

Sustainable construction : towards a strategic approach to construction material management for waste reduction

OpenAIRE

Abarca Guerrero, L.; Scheublin, F.J.M.; Egmond - de Wilde De Ligny, van, E.L.C.; Lambert, A.J.D.

2008-01-01

The construction sector plays a key role in shaping and developing the built environment. It also has an undisputed and significant impact on it due to the amounts of materials extracted and produced as waste. The construction industry has emphasized to recycling construction waste (CW), however, relatively less emphasis has been paid on construction waste minimization. CW reduction can be achieved through changes in design concepts, material and construction methods selection and material ma...

Materials And Carbon Flow In A Waste Refinery Process Using Enzymes

DEFF Research Database (Denmark)

Tonini, Davide; Woods, M.; Astrup, Thomas

2011-01-01

Recovery of resources from mixed Municipal Solid Waste (MSW) is a crucial aspect of waste management practices. In this paper the materials and carbon flows of an innovative waste refinery process using enzymes are presented. Through enzymatic treatment the process produces two main streams from...... the initial mixed MSW: a bioslurry (liquefied paper and organics) and a solid fraction (non-degradable materials). The discussion is based on the performance of the process in separating recyclables and recovery Cbiogenic as well as nutrients from the input MSW. The results of MFA and SFA illustrate...... that the waste refinery has great potential for resource recovery: about 100% of the Cbiogenic and up to 90% of N and P can potentially be recovered in the bioslurry and returned to land after anaerobic digestion. Recovery of ferrous and non-ferrous material is estimated double compared to recovering the same...

Material Not Categorized As Waste (MNCAW) data report. Radioactive Waste Technical Support Program

Energy Technology Data Exchange (ETDEWEB)

Casey, C.; Heath, B.A.

1992-11-01

The Department of Energy (DOE), Headquarters, requested all DOE sites storing valuable materials to complete a questionnaire about each material that, if discarded, could be liable to regulation. The Radioactive Waste Technical Support Program entered completed questionnaires into a database and analyzed them for quantities and type of materials stored. This report discusses the data that TSP gathered. The report also discusses problems revealed by the questionnaires and future uses of the data. Appendices contain selected data about material reported.

DOE progress in assessing the long term performance of waste package materials

International Nuclear Information System (INIS)

Berusch, A.; Gause, E.

1987-01-01

Under the Nuclear Waste Policy Act of 1982 (NWPA)[1], the US Dept. of Energy (DOE) is conducting activities to select and characterize candidate sites suitable for the construction and operation of a geologic repository for the disposal of high-level nuclear wastes. DOE is funding three first repository projects: Basalt Waste Isolation Project, BWIP; Nevada Nuclear Waste Isolation Project, NNWSI; and Salt Repository Project Office, SRPO. It is essential in the licensing process that DOE demonstrate to the NRC that the long-term performance of the materials and design will be in compliance with the requirements of 10 CFR 60.113 on substantially complete containment within the waste packages for 300 to 1000 years and a controlled release rate from the engineered barrier system (EBS) for 10,000 years of 1 part in 10 5 per year for radionuclides present in defined quantities 100 years after permanent closure. Obviously, the time spans involved make it impractical to base the assessment of the long term performance of waste package materials on real time, prototypical testing. The assessment of performance will be implemented by the use of models that are supported by real time field and laboratory tests, monitoring, and natural analog studies. Each of the repository projects is developing a plan for demonstrating long-term waste package material performance depending on the particular materials and the package-perturbed, time-dependent environment under which the materials must function. An overview of progress in each of these activities for each of the projects is provided in the following

Physical and mechanical properties of degraded waste surrogate material

International Nuclear Information System (INIS)

Hansen, F.D.; Mellegard, K.D.

1998-03-01

This paper discusses rock mechanics testing of surrogate materials to provide failure criteria for compacted, degraded nuclear waste. This daunting proposition was approached by first assembling all known parameters such as the initial waste inventory and rock mechanics response of the underground setting after the waste is stored. Conservative assumptions allowing for extensive degradation processes helped quantify the lowest possible strength conditions of the future state of the waste. In the larger conceptual setting, computations involve degraded waste behavior in transient pressure gradients as gas exits the waste horizon into a wellbore. Therefore, a defensible evaluation of tensile strength is paramount for successful analyses and intentionally provided maximal failed volumes. The very conservative approach assumes rampant degradation to define waste surrogate composition. Specimens prepared from derivative degradation product were consolidated into simple geometries for rock mechanics testing. Tensile strength thus derived helped convince a skeptical peer review panel that drilling into the Waste Isolation Pilot Plant (WIPP) would not likely expel appreciable solids via the drill string

Use of waste materials in rubber matrix

Directory of Open Access Journals (Sweden)

Pajtášová Mariana

2018-01-01

Full Text Available The presented paper deals with the use of waste materials as ecological fillers into rubber matrix. Waste materials were used as partial replacement of the commercial filler – carbon black, designated as N339. These prepared rubber compounds were characterized on the basis of the rheology and vulcanization characteristics – minimum torque (ML, maximum torque (MH, optimum time of vulcanization (t(c90, processing safety of compound (ts, rate coefficient of vulcanization (Rv. In the case of the prepared vulcanizates, physical-mechanical properties (tensile strength, tensibility and hardness and dynamic-mechanical properties (storage modulus, loss modulus, loss angle tan δ were investigated. Using the dependency of loss angle on temperature, the selected properties for tyre tread vulcanizates were evaluated, including traction on snow and ice, traction on the wet surface and rolling resistance.

Corrosion of canister materials for radioactive waste disposal

International Nuclear Information System (INIS)

Kienzler, Bernhard

2017-01-01

In the period between 1980 and 2004, corrosion studies on various metallic materials have been performed at the Research Center Karlsruhe. The objectives of these experimental studies addressed mainly the performance of canister materials for heat producing, high-level wastes and spent nuclear fuels for a repository in a German salt dome. Additional studies covered the performance of steels for packaging wastes with negligible heat production under conditions to be expected in rocksalt and in the Konrad iron ore mine. The results of the investigations have been published in journals and conference proceedings but also in ''grey literature''. This paper presents a summary of the results of corrosion experiments with fine-grained steels and nodular cast steel.

Investigations on deflagration to detonation transition in porous energetic materials. Final report

Energy Technology Data Exchange (ETDEWEB)

Stewart, D.S. [Univ. of Illinois, Urbana, IL (United States)

1999-07-01

The research carried out by this contract was part of a larger effort funded by LANL in the areas of deflagration to detonation in porous energetic materials (DDT) and detonation shock dynamics in high explosives (DSD). In the first three years of the contract the major focus was on DDT. However, some researchers were carried out on DSD theory and numerical implementation. In the last two years the principal focus of the contract was on DSD theory and numerical implementation. However, during the second period some work was also carried out on DDT. The paper discusses DDT modeling and DSD modeling. Abstracts are included on the following topics: modeling deflagration to detonation; DSD theory; DSD wave front tracking; and DSD program burn implementation.

Waste Plastic Converting into Hydrocarbon Fuel Materials

Energy Technology Data Exchange (ETDEWEB)

Sarker, Moinuddin; Mamunor Rashid, Mohammad; Molla, Mohammad

2010-09-15

The increased demand and high prices for energy sources are driving efforts to convert organic compounds into useful hydrocarbon fuels. Although much of this work has focused on biomass, there are strong benefits to deriving fuels from waste plastic material. Natural State Research Inc. (NSR) has invented a simple and economically viable process to decompose the hydrocarbon polymers of waste plastic into the shorter chain hydrocarbon of liquid fuel (patent pending). The method and principle of the production / process will be discussed. Initial tests with several widely used polymers indicate a high potential for commercialization.

Radioactive waste - a select list of material

International Nuclear Information System (INIS)

Lambert, C.M.

1982-01-01

A chronological bibliography is presented of literature relating to radioactive waste management in the United Kingdom concentrating on material published since 1978. The main sections include Dept. of Environ. and Official publications, administrative and environmental concerns, technological and scientific considerations, including publications on geological aspects, deep-sea bed and ocean-dumping and salt domes, with general background material and further sources of information listed at the end. (U.K.)

Shaft-retort for treating waste materials, like washery waste, bituminous shale, oil-bearing sands and the like

Energy Technology Data Exchange (ETDEWEB)

Koppers, H

1916-10-29

A shaft-retort for converting waste materials, like washery waste, bituminous shale, oil-bearing sands, brown coal and non-coking mineral coal to oil and tar by supplying heat through the shaft wall formed of an iron-sheet to the material, which is forced through a feeding member perforated for the removal of gases and vapors, and moved downward in a thin layer on the shaft wall; that is characterized by the fact that the iron heating sheet is made rotatable for the purpose of equalizing overheating of itself and the material to be treated.

Leaching tests as a tool in waste management to evaluate the potential for utilization of waste materials

Energy Technology Data Exchange (ETDEWEB)

Sloot, H.A. van der [Netherlands Energy Research Foundation (ECN), Petten (Netherlands); Kosson, D.S. [Rutgers Univ., Piscataway, NJ (United States)

1995-12-01

Several waste materials from large scale industrial processes possess technical properties that would allow their use in certain construction applications, e.g. coal fly ash, slags from large scale industrial melting and ore processing, and incinerator residues. The disposal of such materials requires space and controlled landfills to minimize long term environmental risks. The beneficial use of such bulk materials is an attractive alternative, if it can be shown that such applications are environmentally acceptable. For this management of wastes and the decision to either dispose or use, information on the environmental properties of materials is needed. Leaching tests have been developed to assess such properties. These have been designed typically in relation to regulatory tools, not as instruments to guide the management of wastes and the possibilities to improve material properties. New methods have been designed to address this aspect, in which maximum benefit can be derived from knowledge of the systematic behaviour of materials and the already existing knowledge in other countries producing similar residues. After initial detailed characterization, concise procedures can be used for control purposes focused on the typical aspects of a certain residue stream. Examples of existing knowledge in this field will be presented.

Direct waste heat recovery via thermoelectric materials - chosen issues of the thermodynamic description

International Nuclear Information System (INIS)

Kolasiński, Piotr; Kolasińska, Ewa

2016-01-01

The effective waste heat recovery is one of the present-day challenges in the industry and power engineering. The energy systems dedicated for waste heat conversion into electricity are usually characterized by low efficiency and are complicated in the design. The possibility of waste heat recovery via thermoelectric materials may be an interesting alternative to the currently used technologies. In particular, due to their material characteristics, conducting polymers may be competitive when compared with the power machinery and equipment. These materials can be used in a wide range of the geometries e.g. the bulk products, thin films, pristine form or composites and the others. In this article, the authors present selected issues related to the mathematical and thermodynamic description of the heat transfer processes in the thermoelectric materials dedicated for the waste heat recovery. The link of these models with electrical properties of the material and a material solution based on a conducting polymer have also been presented in this paper. (paper)

A case-study of landfill minimization and material recovery via waste co-gasification in a new waste management scheme

Energy Technology Data Exchange (ETDEWEB)

Tanigaki, Nobuhiro, E-mail: tanigaki.nobuhiro@eng.nssmc.com [NIPPON STEEL & SUMIKIN ENGINEERING CO., LTD., (EUROPEAN OFFICE), Am Seestern 8, 40547 Dusseldorf (Germany); Ishida, Yoshihiro [NIPPON STEEL & SUMIKIN ENGINEERING CO., LTD., 46-59, Nakabaru, Tobata-ku, Kitakyushu, Fukuoka 804-8505 (Japan); Osada, Morihiro [NIPPON STEEL & SUMIKIN ENGINEERING CO., LTD., (Head Office), Osaki Center Building 1-5-1, Osaki, Shinagawa-ku, Tokyo 141-8604 (Japan)

2015-03-15

Highlights: • A new waste management scheme and the effects of co-gasification of MSW were assessed. • A co-gasification system was compared with other conventional systems. • The co-gasification system can produce slag and metal with high-quality. • The co-gasification system showed an economic advantage when bottom ash is landfilled. • The sensitive analyses indicate an economic advantage when the landfill cost is high. - Abstract: This study evaluates municipal solid waste co-gasification technology and a new solid waste management scheme, which can minimize final landfill amounts and maximize material recycled from waste. This new scheme is considered for a region where bottom ash and incombustibles are landfilled or not allowed to be recycled due to their toxic heavy metal concentration. Waste is processed with incombustible residues and an incineration bottom ash discharged from existent conventional incinerators, using a gasification and melting technology (the Direct Melting System). The inert materials, contained in municipal solid waste, incombustibles and bottom ash, are recycled as slag and metal in this process as well as energy recovery. Based on this new waste management scheme with a co-gasification system, a case study of municipal solid waste co-gasification was evaluated and compared with other technical solutions, such as conventional incineration, incineration with an ash melting facility under certain boundary conditions. From a technical point of view, co-gasification produced high quality slag with few harmful heavy metals, which was recycled completely without requiring any further post-treatment such as aging. As a consequence, the co-gasification system had an economical advantage over other systems because of its material recovery and minimization of the final landfill amount. Sensitivity analyses of landfill cost, power price and inert materials in waste were also conducted. The higher the landfill costs, the greater the

PRODUCTION OF AN INSULATION MATERIAL FROM CARPET AND BORON WASTES

OpenAIRE

Yasin ERDOĞAN

2016-01-01

Buildings are large consumers of energy in all countries. In regions with harsh climatic conditions, a substantial share of energy goes to heat and cool buildings. This paper reports an investigation of the insulation materials made from mixing carpet wastes with a solution with added crude colemanite ore, one of boron minerals, and a solution with added colemanite wastes from a barrage. A new building insulation material was produced which is name, Halibor. Optimum mixing ratios were determi...

Yugoslav central disposal system or rad waste materials: necessity and justification of construction

International Nuclear Information System (INIS)

Peric, A.; Plecas, I.; Pavlovic, R.

1995-01-01

Decision on searching for the location and the choice of appropriate type of system for final disposal of low and intermediate level rad waste materials should be made urgently in Yugoslavia. capacities for further storing of such waste materials on the site of the Vinca Institute will be full in the next few years, following the trend of present rad waste generation and delivery. Selection of the location and type of the disposal system in Yugoslavia is of crucial importance from the point of view of conservation of environment quality level and enabling permanent control of disposed immobilized rad waste materials and its impact on the environment. (author)

Elaboration and characterisation of plutonium waste reference materials

International Nuclear Information System (INIS)

Perolat, J.P.

1990-01-01

The Analysis Methods Establishment Commission (CETAMA) has set up a program for the elaboration and characterisation of plutonium waste reference materials. The object of this program is to give laboratories the possibility to test and calibrate apparatus used in non-destructive methods for the analysis of plutonium waste. The different parameters of this program are presented: - characterisation of plutonium, - type and number of containers, - plutonium distribution inside the different containers, - description of the matrix

Utilization of Blended Waste Materials in Bricks

Directory of Open Access Journals (Sweden)

Muhammad Ekhlasur Rahman

2018-01-01

Full Text Available Cement is considered a key raw material for brick production. However, excessive use of cement leads to a negative environment impact. Cement replaced with locally available waste materials has a significant potential to address this environmental impact, especially in the construction industry by contributing to cleaner production. The objective of this research is to investigate the performance of brick where cement is replaced by fly ash and palm oil fuel ash, waste materials typically available in Malaysia, where the construction industry is on the rise. To determine the performance of these bricks, a compressive strength test, a water absorption test, and a thermogravimetric analysis were carried out at different percentage combinations of fly ash and palm oil fuel ash. The results from the tests reveal that both fly ash and palm oil fuel ash incorporated bricks satisfy Class 1 and Class 2 load-bearing brick requirements according to the Malaysian Standard MS76:1972 along with water absorption requirements as per ASTM C55-11. The thermogravimetric analysis study confirms that the Ca(OH2 gradually decreases due to the increase of pozzolanic material contents (fly ash and palm oil fuel ash. Moreover, these newly developed bricks cost less than the conventional bricks.

Material Not Categorized As Waste (MNCAW) data report

International Nuclear Information System (INIS)

Casey, C.; Heath, B.A.

1992-11-01

The Department of Energy (DOE), Headquarters, requested all DOE sites storing valuable materials to complete a questionnaire about each material that, if discarded, could be liable to regulation. The Radioactive Waste Technical Support Program entered completed questionnaires into a database and analyzed them for quantities and type of materials stored. This report discusses the data that TSP gathered. The report also discusses problems revealed by the questionnaires and future uses of the data. Appendices contain selected data about material reported

Concept of an integrated waste economy represented on the example of recycling of valuable materials

Energy Technology Data Exchange (ETDEWEB)

Wender, H

1980-08-01

The historical development of waste elimination is discussed, followed by the waste problem in an environmental discussion, the possibilities of recycling within the framework of a waste industry, and the solution of the waste problem from a waste-economy viewpoint, including the definition of 'waste' and the grouping by types of waste, their amounts and increase rates, composition and valuable materials in community wastes with a review of waste technologies under waste-economy viewpoints. This is followed by a discussion of the sales possibilities for valuable components from mechanical sorting facilities, including used paper, old glass, hard substances, metals, plastics, succeeded by a comparative evaluation method, and the national economy aspect of the waste industry, with the savings effect in raw materials for different branches, effects on raw material reserves, the problem of dependence on imports, waste rates and living standard, and the importance of environmental instruments which are discussed in detail.

Electronic waste (e-waste): Material flows and management practices in Nigeria

International Nuclear Information System (INIS)

Nnorom, Innocent Chidi; Osibanjo, Oladele

2008-01-01

The growth in electrical and electronic equipment (EEE) production and consumption has been exponential in the last two decades. This has been as a result of the rapid changes in equipment features and capabilities, decrease in prices, and the growth in internet use. This creates a large volume of waste stream of obsolete electrical and electronic devices (e-waste) in developed countries. There is high level of trans-boundary movement of these devices as secondhand electronic equipment into developing countries in an attempt to bridge the 'digital divide'. The past decade has witnessed a phenomenal advancement in information and communication technology (ICT) in Nigeria, most of which rely on imported secondhand devices. This paper attempts to review the material flow of secondhand/scrap electronic devices into Nigeria, the current management practices for e-waste and the environmental and health implications of such low-end management practices. Establishment of formal recycling facilities, introduction of legislation dealing specifically with e-waste and the confirmation of the functionality of secondhand EEE prior to importation are some of the options available to the government in dealing with this difficult issue

Characteristics of and sorption to biochars derived from waste material

Science.gov (United States)

Sun, Huichao; Kah, Melanie; Sigmund, Gabriel; Hofmann, Thilo

2015-04-01

Biochars can exhibit a high sorption potential towards heavy metals and organic contaminants in various environmental matrices (e.g., water, soil). They have therefore been proposed for environmental remediation purposes to sequester contaminants. To date, most studies have focused on the physicochemical and sorption properties of mineral phases poor biochars, which are typically produced from plant residues. Only little knowledge is available for biochars derived from human and animal waste material, which are typically characterized by high mineral contents (e.g., sewage sludge, manure). Using human and animal waste as source material to produce biochars would support the development of attractive combined strategies for waste management and remediation. The potential impact of mineral phases on the physicochemical and sorption properties of biochars requires further studies so that the potential as sorbent material can be evaluated. With this purpose, different source material biochars were produced at 200°C, 350°C and 500°C, to yield a series of biochars representing a range of mineral content. The derived biochars from wood shavings (sludge (50-70% ash) and pig manure (30-60% ash), as well as a commercial biochar derived from grain husks (40% ash), were extensively characterized (e.g., element composition, surface area, porosity, Fourier transform infrared spectroscopy). The contents of potentially toxic elements (i.e., heavy metals and polycyclic aromatic hydrocarbons) of all materials were within the guidelines values proposed by the International Biochar Initiative, indicating their suitability for environmental application. Single point sorption coefficients for the model sorbate pyrene were measured to investigate the effect of mineral content, feedstock, pyrolysis temperature, particle size fractions and acid demineralization on sorption behavior. Overall, sorption of pyrene was strong for all materials (4 waste material and exhibiting high mineral

Compatibility study of trans-1,4,5,8-tetranitro-1,4,5,8-tetraazadecalin (TNAD) with some energetic components and inert materials

International Nuclear Information System (INIS)

Yan Qilong; Li Xiaojiang; Zhang Laying; Li Jizhen; Li Hongli; Liu Ziru

2008-01-01

The compatibility of trans-1,4,5,8-tetranitro-1,4,5,8-tetraazadecalin (TNAD) with some energetic components and inert materials of solid propellants was studied by using the pressure DSC method where, cyclotetramethylenetetranitroamine (HMX), cyclotrimethylenetrinitramine (RDX), 1,4-dinitropiperazine (DNP), 1.25/1-NC/NG mixture, lead 3-nitro-1,2,4-triazol-5-onate (NTO-Pb), aluminum powder (Al, particle size = 13.6 μm) and N-nitrodihydroxyethylaminedinitrate (DINA) were used as energetic components and polyethylene glycol (PEG), polyoxytetramethylene-co-oxyethylene (PET), addition product of hexamethylene diisocyanate and water (N-100), 2-nitrodianiline (2-NDPA), 1,3-dimethyl-1,3-diphenyl urea (C 2 ), carbon black (C.B.), aluminum oxide (Al 2 O 3 ), cupric 2,4-dihydroxy-benzoate (β-Cu), cupric adipate (AD-Cu) and lead phthalate (φ-Pb) were used as inert materials. It was concluded that the binary systems of TNAD with NTO-Pb, RDX, PET and Al powder are compatible, and systems of TNAD with DINA and HMX are slightly sensitive, and with 2-NDPA, φ-Pb, β-Cu, AD-Cu and Al 2 O 3 are sensitive, and with PEG, N-100, C 2 and C.B. are incompatible. The impact and friction sensitivity data of the TNAD and TNAD in combination with the other energetic materials under present study was also obtained, and there was no consequential affiliation between sensitivity and compatibility

Corrosion of canister materials for radioactive waste disposal

Energy Technology Data Exchange (ETDEWEB)

Kienzler, Bernhard [KIT Karlsruhe (Germany). Institut fuer Nukleare Entsorgung (INE)

2017-08-15

In the period between 1980 and 2004, corrosion studies on various metallic materials have been performed at the Research Center Karlsruhe. The objectives of these experimental studies addressed mainly the performance of canister materials for heat producing, high-level wastes and spent nuclear fuels for a repository in a German salt dome. Additional studies covered the performance of steels for packaging wastes with negligible heat production under conditions to be expected in rocksalt and in the Konrad iron ore mine. The results of the investigations have been published in journals and conference proceedings but also in ''grey literature''. This paper presents a summary of the results of corrosion experiments with fine-grained steels and nodular cast steel.

Pilot experiment on utilization of vegetable biomass in Umbria. Part 2. Anaerobic digestion of the wastes coming from the maintenance activity of the lake Trasimeno and the working of energetic cultures

International Nuclear Information System (INIS)

Poletti, A.; Selvaggi, R.; Poletti, L.

2000-01-01

In this work the energetic exploitation has been assessed of the vegetable biomasses available in the region Umbria, derived both from the maintenance operation of Lake Trasimeno and energetic cultures. Biomethanation experiments have been carried out both on laboratory scale, by preparing anaerobic digestion tests in batch and in continuous, and on pilot scale, through the use of a 2000 litres digest or. Throughout the experiment the main chemical and physical process parameters have been monitored and the process efficiency assessed. The experimental values, measured for the anaerobic digestion process, have shown that both types of biomass can be very good substrated for the production of biogas. Their energetic re-use, when considering the broad and complex problems posed by breeding wastes disposal, could positively contribute to a rational sustainability scheme of the activities operating in the territory [it

ERG review of waste package container materials selection and corrosion

International Nuclear Information System (INIS)

Moak, D.P.; Perrin, J.S.

1986-07-01

The Engineering Review Group (ERG) was established by the Office of Nuclear Waste Isolation (ONWI) to help evaluate engineering-related issues in the US Department of Energy's nuclear waste repository program. The October 1984 meeting of the ERG reviewed the waste package container materials selection and corrosion. This report documents the ERG's comments and recommendations on these subjects and the ONWI response to the specific points raised by the ERG

Molecular Environmental Science Using Synchrotron Radiation: Chemistry and Physics of Waste Form Materials. Final Report

International Nuclear Information System (INIS)

Lindle, Dennis W.

2011-01-01

Production of defense-related nuclear materials has generated large volumes of complex chemical wastes containing a mixture of radionuclides. The disposition of these wastes requires conversion of the liquid and solid-phase components into durable, solid forms suitable for long-term immobilization. Specially formulated glass compositions and ceramics such as pyrochlores and apatites are the main candidates for these wastes. An important consideration linked to the durability of waste-form materials is the local structure around the waste components. Equally important is the local structure of constituents of the glass and ceramic host matrix. Knowledge of the structure in the waste-form host matrices is essential, prior to and subsequent to waste incorporation, to evaluate and develop improved waste-form compositions based on scientific considerations. This project used the soft-x-ray synchrotron-radiation-based technique of near-edge x-ray-absorption fine structure (NEXAFS) as a unique method for investigating oxidation states and structures of low-Z elemental constituents forming the backbones of glass and ceramic host matrices for waste-form materials. In addition, light metal ions in ceramic hosts, such as titanium, are also ideal for investigation by NEXAFS in the soft-x-ray region. Thus, one of the main objectives was to understand outstanding issues in waste-form science via NEXAFS investigations and to translate this understanding into better waste-form materials, followed by eventual capability to investigate 'real' waste-form materials by the same methodology. We conducted several detailed structural investigations of both pyrochlore ceramic and borosilicate-glass materials during the project and developed improved capabilities at Beamline 6.3.1 of the Advanced Light Source (ALS) to perform the studies.

Preliminary Hazard Analysis of Supercritical Fluid Separation of Energetic Materials

National Research Council Canada - National Science Library

1997-01-01

.... Army Research Laboratory (ARL) and elsewhere, particularly at the Phasex Corporation, Lawrence, MA, has demonstrated the feasibility of separating the energetic moieties by use of supercritical CO2...

Recycling and reuse of chosen kinds of waste materials in a building industry

Science.gov (United States)

Ferek, B.; Harasymiuk, J.; Tyburski, J.

2016-08-01

The article describes the current state of knowledge and practice in Poland concerning recycling as a method of reuse of chosen groups of waste materials in building industry. The recycling of building scraps is imposed by environmental, economic and technological premises. The issue of usage of sewage residues is becoming a problem of ever -growing gravity as the presence of the increasing number of pernicious contaminants makes their utilization for agricultural purposes more and more limited. The strategies of using waste materials on Polish building sites were analyzed. The analysis of predispositions to salvage for a group of traditional materials, such as: timber, steel, building debris, insulation materials, plastics, and on the example of new materials, such as: artificial light aggregates made by appropriate mixing of siliceous aggregates, glass refuses and sewage residues in order to obtain a commodity which is apt for economic usage also was made in the article. The issue of recycling of waste materials originating from building operations will be presented in the context of the binding home and EU legal regulations. It was proved that the level of recycling of building wastes in Poland is considerably different from one which is achieved in the solid market economies, both in quantity and in assortment. The method of neutralization of building refuses in connection with special waste materials, which are sewage sludge that is presented in the article may be one of the alternative solutions to the problem of recycling of these wastes not only on the Polish scale.

Low-temperature setting phosphate ceramics for stabilization of DOE problem low level mixed-waste: I. Material and waste form development

International Nuclear Information System (INIS)

Singh, D.; Wagh, A.; Knox, L.; Mayberry, J.

1994-03-01

Chemically bonded phosphate ceramics are proposed as candidates for solidification and stabilization of some of the open-quotes problemclose quotes DOE low-level mixed wastes at low-temperatures. Development of these materials is crucial for stabilization of waste streams which have volatile species and any use of high-temperature technology leads to generation of off-gas secondary waste streams. Several phosphates of Mg, Al, and Zr have been investigated as candidate materials. Monoliths of these phosphates were synthesized using chemical routes at room or slightly elevated temperatures. Detailed physical and chemical characterizations have been conducted on some of these phosphates to establish their durability. Magnesium ammonium phosphate has shown to possess excellent mechanical and as well chemical properties. These phosphates were also used to stabilize a surrogate ash waste with a loading ranging from 25-35 wt.%. Characterization of the final waste forms show that waste immobilization is due to both chemical stabilization and physical encapsulation of the surrogate waste which is desirable for waste immobilization

POLYMER COMPOSITES MODIFIED BY WASTE MATERIALS CONTAINING WOOD FIBRES

Directory of Open Access Journals (Sweden)

Bernardeta Dębska

2016-11-01

Full Text Available In recent years, the idea of sustainable development has become one of the most important require-ments of civilization. Development of sustainable construction involves the need for the introduction of innovative technologies and solutions that will combine beneficial economic effects with taking care of the health and comfort of users, reducing the negative impact of the materials on the environment. Composites obtained from the use of waste materials are part of these assumptions. These include modified epoxy mortar containing waste wood fibres, described in this article. The modification consists in the substitution of sand by crushed waste boards, previously used as underlays for panels, in quantities of 0%, 10%, 20%, 35% and 50% by weight, respectively. Composites containing up to 20% of the modifier which were characterized by low water absorption, and good mechanical properties, also retained them after the process of cyclic freezing and thawing.

Laboratory-performance criteria for in situ waste-stabilization materials

International Nuclear Information System (INIS)

Shaw, P.; Weidner, J.

1996-01-01

The Department of Energy (DOE) Landfill Stabilization Focus Area is investigating a variety of in situ placement methods, grout materials, and characterization techniques for the stabilization of buried low-level transuranic-contaminated waste at Department of Energy sites. In situ stabilization involves underground injection or placement of substances to isolate, treat, or contain buried contaminants. Performance criteria were developed to evaluate various candidate stabilization materials for both long-term stabilization and interim stabilization or retrieval. The criteria are go/no-go, ready, and preliminary. The criterion go/no-go eliminates technologies that are not applicable for in situ treatment of buried waste. The criterion ready indicates that the technology is sufficiently developed and proven to be field demonstrated full-scale. The criterion preliminary indicates the prospective technologies to be potentially applicable to in situ buried waste stabilization, but further development is needed before the technology is ready for field-scale demonstration

Package materials, waste form

International Nuclear Information System (INIS)

Anon.

1980-01-01

The schedules for waste package development for the various host rocks were presented. The waste form subtask activities were reviewed, with the papers focusing on high-level waste, transuranic waste, and spent fuel. The following ten papers were presented: (1) Waste Package Development Approach; (2) Borosilicate Glass as a Matrix for Savannah River Plant Waste; (3) Development of Alternative High-Level Waste Forms; (4) Overview of the Transuranic Waste Management Program; (5) Assessment of the Impacts of Spent Fuel Disassembly - Alternatives on the Nuclear Waste Isolation System; (6) Reactions of Spent Fuel and Reprocessing Waste Forms with Water in the Presence of Basalt; (7) Spent Fuel Stabilizer Screening Studies; (8) Chemical Interactions of Shale Rock, Prototype Waste Forms, and Prototype Canister Metals in a Simulated Wet Repository Environment; (9) Impact of Fission Gas and Volatiles on Spent Fuel During Geologic Disposal; and (10) Spent Fuel Assembly Decay Heat Measurement and Analysis

Prevention of spontaneous combustion of backfilled plant waste material.

CSIR Research Space (South Africa)

Adamski, SA

2003-06-01

Full Text Available Since Grootegeluk Coal Mine commenced operation in 1980 all plant discards and inter-burden material have been stacked on discards dumps, a practice that has led to the spontaneous combustion of the waste material on these dumps. From 1980 to 1988...

Use of industrial waste for the manufacturing of sustainable building materials.

Science.gov (United States)

Sugrañez, Rafael; Cruz-Yusta, Manuel; Mármol, Isabel; Martín, Francisco; Morales, Julián; Sánchez, Luis

2012-04-01

Presently, appropriate waste management is one of the main requisites for sustainable development; this task is tackled by the material construction industry. The work described herein is focused on the valorization of granite waste through incorporation, as a filler-functional admixture, into cement-based mortar formulations. The main components of the waste are SiO(2) (62.1 %), Al(2)O(3) (13.2 %), Fe(2)O(3) (10.1 %), and CaO (4.6 %). The presence of iron oxides is used to develop the photocatalytic properties of the waste. Following heating at 700 °C, α-Fe(2)O(3) forms in the waste. The inclusion of the heated sample as a filler admixture in a cement-based mortar is possible. Moreover, this sample exhibits a moderate ability in the photodegradation of organic dye solutions. Also, the plastering mortars, in which the heated samples have been used, show self-cleaning properties. The preparation of sustainable building materials is demonstrated through the adequate reuse of the granite waste. Copyright © 2012 WILEY-VCH Verlag GmbH & Co. KGaA, Weinheim.

Feed Materials Production Center Waste Management: Annual report for fiscal year 1986

International Nuclear Information System (INIS)

Watts, R.E.; Kottner, S.A.

1986-01-01

During FY-1986, the Westinghouse Materials Company of Ohio (WMCO) and the Department of Energy focused on safe storage and disposition of all wastes at the Feed Materials Production Center (FMPC) in compliance with federal and state regulations concerning waste management and worker health and safety. The Waste Management Annual Report identifies the comprehensive programs developed to achieve WMCO goals at the FMPC. The programs address waste issues which concern worker and public health and safety. Among those programs discussed are the decontamination, safe storage, and disposition of low-level and mixed hazardous radioactive waste. Principal attention and resources were allocated to programs which identify the largest waste streams (both currently generated and inventory backlogged). The most voluminous waste streams include low-level waste approved for shipment to the Nevada Test Site (MgF 2 slag, slag leach filter cake, and neutralized raffinate); remedial action wastes (K-65, stormwater runoff/effluent, and waste pits); thorium; and contaminated construction rubble and soil. Goals were established and met for the Waste Management Section in the form of completed milestones. The completed milestones involved such activities as characterization studies for the waste pits, K-65 Silos and adjacent areas; issuance of the Waste Management Plan required by DOE; analysis of decontamination alternatives for copper scrap; and analysis of silo structural integrity and remedial action alternatives

EXPERIMENTAL INVESTIGATION ON PREFABRICATED ROAD PANEL BY USING WASTE MATERIALS

OpenAIRE

M. Aravinth; P. Arun Kumar; R. Aravind Kumar; S. Arun Kumar

2018-01-01

Plastics are user friendly but not eco-friendly as they are non-biodegradable. Generally it is disposed by way of land filling or incineration of materials which are hazardous. The better binding property of plastics in its molten state has helped in finding out a method of safe disposal of waste plastics, by using them in road laying. Use of plastic waste (HDPE) and Crumb Rubber. This not only allows us to collect modifier raw material at low cost, but also provides a solution towards ecolog...

Materials characterization center workshop on the irradiation effects in nuclear waste forms

International Nuclear Information System (INIS)

Roberts, F.P.; Turcotte, R.P.; Weber, W.J.

1981-01-01

The Workshop on Irradiation Effects in Nuclear Waste Forms sponsored by the Materials Characterization Center (MCC) brought together experts in radiation damage in materials and waste-management technology to review the problems associated with irradiation effects on waste-form integrity and to evaluate standard methods for generating data to be included in the Nuclear Waste Materials Handbook. The workshop reached the following conclusions: the concept of Standard Test for the Effects of Alpha-Decay in Nuclear Waste Solids, (MCC-6) for evaluating the effects of alpha decay is valid and useful, and as a result of the workshop, modifications to the proposed procedure will be incorpoated in a revised version of MCC-6; the MCC-6 test is not applicable to the evaluation of radiation damage in spent fuel; plutonium-238 is recommended as the dopant for transuranic and defense high-level waste forms, and when high doses are required, as in the case of commercial high-level waste forms, 244 Cm can be used; among the important property changes caused by irradiation are those that lead to greater leachability, and additionally, radiolysis of the leachant may increase leach rates; research is needed in this area; ionization-induced changes in physical properties can be as important as displacement damage in some materials, and a synergism is also likely to exist from the combined effects of ionization and displacement damage; and the effect of changing the temperature and dose rates on property changes induced by radiation damage needs to be determined

Material Balance Assessment for Double-Shell Tank Waste Pipeline Transfer

International Nuclear Information System (INIS)

Onishi, Yasuo; Wells, Beric E; Hartley, Stacey A; Enderlin, Carl W

2001-01-01

PNNL developed a material balance assessment methodology based on conservation of mass for detecting leaks and mis-routings in pipeline transfer of double-shell tank waste at Hanford. The main factors causing uncertainty in these transfers are variable property and tank conditions of density, existence of crust, and surface disturbance due to mixer pump operation during the waste transfer. The methodology was applied to three waste transfers from Tanks AN-105 and AZ-102

Synthesis and Investigation of Advanced Energetic Materials Based on Bispyrazolylmethanes.

Science.gov (United States)

Fischer, Dennis; Gottfried, Jennifer L; Klapötke, Thomas M; Karaghiosoff, Konstantin; Stierstorfer, Jörg; Witkowski, Tomasz G

2016-12-23

Herein we present the preparation and characterization of three new bispyrazolyl-based energetic compounds with great potential as explosive materials. The reaction of sodium 4-amino-3,5-dinitropyrazolate (5) with dimethyl iodide yielded bis(4-amino-3,5-dinitropyrazolyl)methane (6), which is a secondary explosive with high heat resistance (T dec =310 °C). The oxidation of this compound afforded bis(3,4,5-trinitropyrazolyl)methane (7), which is a combined nitrogen- and oxygen-rich secondary explosive with very high theoretical and estimated experimental detonation performance (V det (theor)=9304 m s -1 versus V det (exp)=9910 m s -1 ) in the range of that of CL-20. Also, the thermal stability (T dec =205 °C) and sensitivities of 7 are auspicious. The reaction of 6 with in situ generated nitrous acid yielded the primary explosive bis(4-diazo-5-nitro-3-oxopyrazolyl)methane (8), which showed superior properties to those of currently used diazodinitrophenol (DDNP). © 2016 Wiley-VCH Verlag GmbH & Co. KGaA, Weinheim.

Application of the US decision support tool for materials and waste management

International Nuclear Information System (INIS)

Thorneloe, Susan A.; Weitz, Keith; Jambeck, Jenna

2007-01-01

The US Environmental Protection Agency (US EPA) launched the Resource Conservation Challenge (RCC) in 2002 to help reduce waste and move towards more sustainable resource consumption. The objective of the RCC is to help communities, industries, and the public think in terms of materials management rather than waste disposal. Reducing cost, finding more efficient and effective strategies to manage municipal waste, and thinking in terms of materials management requires a holistic approach that considers life-cycle environmental tradeoffs. The US EPA's National Risk Management Research Laboratory has led the development of a municipal solid waste decision support tool (MSW-DST). The computer software can be used to calculate life-cycle environmental tradeoffs and full costs of different waste management or materials recovery programs. The environmental methodology is based on the use of life-cycle assessment and the cost methodology is based on the use of full-cost accounting. Life-cycle inventory (LCI) environmental impacts and costs are calculated from the point of collection, handling, transport, treatment, and disposal. For any materials that are recovered for recycling, offsets are calculated to reflect potential emissions savings from use of virgin materials. The use of the MSW-DST provides a standardized format and consistent basis to compare alternatives. This paper provides an illustration of how the MSW-DST can be used by evaluating ten management strategies for a hypothetical medium-sized community to compare the life-cycle environmental and cost tradeoffs. The LCI results from the MSW-DST are then used as inputs into another US EPA tool, the Tool for the reduction and assessment of chemical and other environmental impacts, to convert the LCI results into impact indicators. The goal of this paper is to demonstrate how the MSW-DST can be used to identify and balance multiple criteria (costs and environmental impacts) when evaluating options for materials and

Materials interactions relating to long-term geologic disposal of nuclear waste glass

International Nuclear Information System (INIS)

Bibler, N.E.; Jantzen, C.M.

1987-01-01

In the geologic disposal of nuclear waste glass, the glass will eventually interact with groundwater in the repository system. Interactions can also occur between the glass and other waste package materials that are present. These include the steel canister that holds the glass, the metal overpack over the canister, backfill materials that may be used, and the repository host rock. This review paper systematizes the additional interactions that materials in the waste package will impose on the borosilicate glass waste form-groundwater interactions. The repository geologies reviewed are tuff, salt, basalt, and granite. The interactions emphasized are those appropriate to conditions expected after repository closure, e.g. oxic vs anoxic conditions. Whenever possible, the effect of radiation from the waste form on the interactions is examined. The interactions are evaluated based on their effect on the release and speciation of various elements including radionuclides from the glass. It is noted when further tests of repository interactions are needed before long-term predictions can be made. 63 references, 1 table

Power plant wastes capitalization as geopolymeric building materials

Science.gov (United States)

Ciobanu, Gabriela; Litu, Loredana; Harja, Maria

2017-11-01

In this innovative study, we are present an investigation over the properties of geopolymeric materials prepared using ash supplied by power plant Iasi, Romania and sodium hydroxide solutions/pellets. Having as objective a minimum consumption of energy and materials was developed a class of advanced eco-materials. New synthesized materials can be used as a binder for cement replacement or for the removal/immobilization of pollutants from waste waters or soils. It offers an advanced and low cost-effective solution too many problems, where waste must be capitalized. The geopolymer formation, by hydrothermal method, is influenced by: temperature (20-600°C), alkali concentration (2M-6M), solid /liquid ratio (1-2), ash composition, time of heating (2-48 h), etc. The behaviour of the FTIR peak of 6M sample indicated upper quantity of geopolymer formation at the first stage of the reaction. XRD spectra indicated phases like sodalite, faujasite, Na-Y, which are known phases of geopolymer/zeolite. Advanced destroyed of ash particles due to geopolymerisation reaction were observed when the temperature was higher. At the constant temperature the percentage of geopolymer increases with increasing of curing time, from 4-48 h. Geopolymer materials are environmentally friendly, for its obtaining energy consumption, and CO2 emission is reduced compared to cement binder.

Optimizing Urban Material Flows and Waste Streams in Urban Development through Principles of Zero Waste and Sustainable Consumption

Directory of Open Access Journals (Sweden)

Steffen Lehmann

2011-01-01

Full Text Available Beyond energy efficiency, there are now urgent challenges around the supply of resources, materials, energy, food and water. After debating energy efficiency for the last decade, the focus has shifted to include further resources and material efficiency. In this context, urban farming has emerged as a valid urban design strategy, where food is produced and consumed locally within city boundaries, turning disused sites and underutilized public space into productive urban landscapes and community gardens. Furthermore, such agricultural activities allow for effective composting of organic waste, returning nutrients to the soil and improving biodiversity in the urban environment. Urban farming and resource recovery will help to feed the 9 billion by 2050 (predicted population growth, UN-Habitat forecast 2009. This paper reports on best practice of urban design principles in regard to materials flow, material recovery, adaptive re-use of entire building elements and components (‘design for disassembly’; prefabrication of modular building components, and other relevant strategies to implement zero waste by avoiding waste creation, reducing wasteful consumption and changing behaviour in the design and construction sectors. The paper touches on two important issues in regard to the rapid depletion of the world’s natural resources: the built environment and the education of architects and designers (both topics of further research. The construction and demolition (C&D sector: Prefabricated multi-story buildings for inner-city living can set new benchmarks for minimizing construction wastage and for modular on-site assembly. Today, the C&D sector is one of the main producers of waste; it does not engage enough with waste minimization, waste avoidance and recycling. Education and research: It’s still unclear how best to introduce a holistic understanding of these challenges and to better teach practical and affordable solutions to architects, urban

Tests with ceramic waste form materials made by pressureless consolidation

International Nuclear Information System (INIS)

Lewis, M. A.; Hash, M. C.; Hebden, A. S.; Ebert, W. L.

2002-01-01

A multiphase waste form referred to as the ceramic waste form (CWF) will be used to immobilize radioactively contaminated salt wastes recovered after the electrometallurgical treatment of spent sodium-bonded nuclear fuel. The CWF is made by first occluding salt in zeolite and then encapsulating the zeolite in a borosilicate binder glass. A variety of surrogate CWF materials were made using pressureless consolidation (PC) methods for comparison with CWF consolidated using a hot isostatic press (HIP) method and to study the effects of glass/zeolite batching ratio and processing conditions on the physical and chemical properties of the resulting materials. The data summarized in this report will also be used to support qualification of the PC CWF for disposal in the proposed federal high-level radioactive waste repository at Yucca Mountain. The phase composition and microstructure of HIP CWF and PC CWF are essentially identical: both are composed of about 70% sodalite, 25% binder glass, and a 5% total of inclusion phases (halite, nepheline, and various oxides and silicates). The primary difference is that PC CWF materials have higher porosities than HIP CWFs. The product consistency test (PCT) that was initially developed to monitor homogeneous glass waste forms was used to measure the chemical durabilities of the CWF materials. Series of replicate tests with several PC CWF materials indicate that the PCT can be conducted with the same precision with CWF materials as with borosilicate glasses. Short-term (7-day) PCTs were used to evaluate the repeatability of making the PC CWF and the effects of the glass/zeolite mass ratio, process temperature, and processing time on the chemical durability. Long-term (up to 1 year) PCTs were used to compare the durabilities of HIP and PC CWFs and to estimate the apparent solubility limit for the PC CWF that is needed for modeling. The PC and HIP CWF materials had similar disabilities, based on the release of silicon in long

Ultrafast Laser Diagnostics for Energetic-Material Ignition Mechanisms: Tools for Physics-Based Model Development.

Energy Technology Data Exchange (ETDEWEB)

Kearney, Sean Patrick; Jilek, Brook Anton; Kohl, Ian Thomas; Farrow, Darcie; Urayama, Junji

2014-11-01

We present the results of an LDRD project to develop diagnostics to perform fundamental measurements of material properties during shock compression of condensed phase materials at micron spatial scales and picosecond time scales. The report is structured into three main chapters, which each focus on a different diagnostic devel opment effort. Direct picosecond laser drive is used to introduce shock waves into thin films of energetic and inert materials. The resulting laser - driven shock properties are probed via Ultrafast Time Domain Interferometry (UTDI), which can additionally be used to generate shock Hugoniot data in tabletop experiments. Stimulated Raman scattering (SRS) is developed as a temperature diagnostic. A transient absorption spectroscopy setup has been developed to probe shock - induced changes during shock compressio n. UTDI results are presented under dynamic, direct - laser - drive conditions and shock Hugoniots are estimated for inert polystyrene samples and for the explosive hexanitroazobenzene, with results from both Sandia and Lawrence Livermore presented here. SRS a nd transient absorption diagnostics are demonstrated on static thin - film samples, and paths forward to dynamic experiments are presented.

Approved reference and testing materials for use in Nuclear Waste Management Research and Development Programs

International Nuclear Information System (INIS)

Mellinger, G.B.; Daniel, J.L.

1984-12-01

This document, addressed to members of the waste management research and development community summarizes reference and testing materials available from the Nuclear Waste Materials Characterization Center (MCC). These materials are furnished under the MCC's charter to distribute reference materials essential for quantitative evaluation of nuclear waste package materials under development in the US. Reference materials with known behavior in various standard waste management related tests are needed to ensure that individual testing programs are correctly performing those tests. Approved testing materials are provided to assist the projects in assembling materials data base of defensible accuracy and precision. This is the second issue of this publication. Eight new Approved Testing Materials are listed, and Spent Fuel is included as a separate section of Standard Materials because of its increasing importance as a potential repository storage form. A summary of current characterization information is provided for each material listed. Future issues will provide updates of the characterization status of the materials presented in this issue, and information about new standard materials as they are acquired. 7 references, 1 figure, 19 tables

Treatment of contaminated waste plastics material

International Nuclear Information System (INIS)

Sims, J.; Hitchcock, J.W.

1984-01-01

Radioactive contaminated plastics material is treated by reducing it to uniform-sized debris and extruding it from a heated extruder into a sealed container in monolithic block form or as an in-fill matrix for other contaminated waste articles to create a substantially void-free sealed mass for disposal. Density adjusting fillers may be included. Extrusion may alternatively take place into a clean sealable plastics tube. (author)

REMOTE MATERIAL HANDLING IN THE YUCCA MOUNTAIN WASTE PACKAGE CLOSURE CELL AND SUPPORT AREA GLOVEBOX

International Nuclear Information System (INIS)

K.M. Croft; S.M. Allen; M.W. Borland

2005-01-01

The Yucca Mountain Waste Package Closure System (WPCS) cells provide for shielding of highly radioactive materials contained in unsealed waste packages. The purpose of the cells is to provide safe environments for package handling and sealing operations. Once sealed, the packages are placed in the Yucca Mountain Repository. Closure of a typical waste package involves a number of remote operations. Those involved typically include the placement of matched lids onto the waste package. The lids are then individually sealed to the waste package by welding. Currently, the waste package includes three lids. One lid is placed before movement of the waste package to the closure cell; the final two are placed inside the closure cell, where they are welded to the waste package. These and other important operations require considerable remote material handling within the cell environment. This paper discusses the remote material handling equipment, designs, functions, operations, and maintenance, relative to waste package closure

Management of radioactive wastes produced by users of radioactive materials

International Nuclear Information System (INIS)

1985-01-01

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

Preliminary corrosion models for BWIP [Basalt Waste Isolation Project] canister materials

International Nuclear Information System (INIS)

Fish, R.L.; Anantatmula, R.P.

1983-01-01

Waste package development for the Basalt Waste Isolation Project (BWIP) requires the generation of materials degradation data under repository relevant conditions. These data are used to develop predictive models for the behavior of each component of waste package. The component models are exercised in performance analyses to optimize the waste package design. This document presents all repository relevant canister materials corrosion data that the BWIP and others have developed to date, describes the methodology used to develop preliminary corrosion models and provides the mathematical description of the models for both low carbon steel and Fe9Cr1Mo steel. Example environment/temperature history and model application calculations are presented to aid in understanding the models. The models are preliminary in nature and will be updated as additional corrosion data become available. 6 refs., 5 tabs

The 2016-2018 National Plan of Management of Radioactive Materials and Wastes - Project

International Nuclear Information System (INIS)

Gazzo, Alexis; Robert, Jean-Gabriel; Abraham, Christophe; Benaze, Manon de

2015-01-01

A first document contains the project of the National Plan of Management of Radioactive Materials and Wastes (PNGMDR) for the period 2016-2018: principles and objectives (presentation of radioactive materials and wastes, principles to be taken into account to define pathways of management of radioactive wastes, legal and institutional framework, information transparency), the management of radioactive materials (context and challenges, management pathways, works on fast breeder reactors of fourth generation), assessment and perspectives of existing pathways of management of radioactive wastes (management of historical situations, management of residues of mining and sterile processing, management of waste with a high natural radioactivity, management of very short life waste, of very low activity wastes, and low and medium activity wastes), needs and perspectives regarding management processes to be implemented for the different types of radioactive wastes. Appendices to this document contain a recall of the content of previous PNGMDR since 2007, a synthesis of realisations and researches performed abroad, research orientations for the concerned period, and international agreement on spent fuel and radioactive waste management. A second document, released by the ASN, proposes an environmental and strategic assessment of the plan. A third one and a fourth one contain the opinion of the Environmental Authority, respectively on the plan preliminary focus, and on the plan itself. An answer to this last one is then proposed, followed by a synthesis of the plan project and the text of the corresponding decree

Materials evaluation programs at the Defense Waste Processing Facility

International Nuclear Information System (INIS)

Gee, J.T.; Iverson, D.C.; Bickford, D.F.

1992-01-01

The Savannah River Site (SRS) has been operating a nuclear fuel cycle since the 1950s to produce nuclear materials in support of the national defense effort. About 83 million gallons of high-level waste produced since operations began has been consolidated by evaporation into 33 million gallons at the waste tank farm. The Department of Energy authorized the construction of the Defense Waste Processing Facility (DWPF), the function of which is to immobilize the waste as a durable borosilicate glass contained in stainless steel canisters prior to the placement of the canisters in a federal repository. The DWPF is now mechanically complete and is undergoing commissioning and run-in activities. A brief description of the DWPF process is provided

Thermogravimetric Analysis and Kinetic Study on Pyrolysis of Veteri-narian Solid Waste

Directory of Open Access Journals (Sweden)

Andrés Felipe Rojas González

2016-10-01

Full Text Available Context: Institutional waste from clinical centers can be classified as those coming from health institutions dedicated to human attention and those coming from centers for animal veterinary care. The latter are mainly hazardous wastes, hence their disposal requires incineration. Most of such waste is organic, and it is possible, therefore, to take advantage of their energetic power in combustion or pyrolysis processes. This work is motivated because no literature was found on the pyrolysis kinetics veterinary waste, as this kind of studies are mainly focused on hospital waste of human health care. Method: The kinetics of pyrolysis is characterized and studied by means of thermogravimetric analysis of 6 major veterinary waste (gauze, cotton swabs, cotton, nails, hair, plastic syringes. The characterization is performed by proximate and elemental analysis, and thermogravimetric analysis. Reactivity characteristics and pyrolytic capability of wastes are established. The kinetics study on pyrolysis was carried out by determining the kinetic triplet by isoconversional Starink method. Results: It was established that the pyrolysis index increases with the heating rate and that the thermal degradation depends on the material type of the waste. Similarly, it was found that the temperature (ΔT = Tf - Ti for the thermal decomposition of veterinary waste is: ΔTnails> ΔThair > ΔTcotton swabs > ΔTgauze > ΔTcotton > ΔTplastic syringes; the activation energy is Enails> E hair > Eplastic syringes > Ecotton swabs > E gauze > Ecotton, and the reaction order is: n hair > nnails > ncotton swabs > ncotton > n gauze > n plastic syringes. Conclusions: These results suggest the possibility of using veterinary wastes for power generation, providing an alternative for sustainable energy development to cities in continuous growth, from both, energetic and environmental points of view.

Utilizing waste materials to enhance mechanical and durability characteristics of concrete incorporated with silica fume

Directory of Open Access Journals (Sweden)

Hamza Ali

2017-01-01

Full Text Available Construction and demolition wastes are increasing significantly due to augmented boom of modern construction. Although the partial cement replacement materials do promote the idea of sustainable construction, the use of construction and demolition waste can also be considered to be viable option to advance the sustainability in modern construction practices. This paper investigates the use of industrial waste materials namely marble dust and crushed bricks as replacement of natural fine aggregates along with the use of silica fume as a partial cement replacement on the mechanical properties and durability characteristics of concrete. Partial replacement levels of waste materials were 10 and 20 percent by volume while the partial replacement level of silica fume was kept to 20 percent at all concrete samples. The results reported in this paper show that the use of marble dust as a replacement material to the natural fine aggregates resulted in an increase in the mechanical properties of concrete. However, the use of crushed bricks did not substantially contribute in the development of strength. Water permeability of concrete incorporated with both silica fume and waste materials (marble dust and crushed bricks decreased significantly. The decrease in water permeability of concrete was attributed to the pozzolanic reaction of silica fume with calcium hydroxide of cement and the filler effect of the waste materials of marble dust and crushed bricks. The use of waste materials also enhance the freeze and thaw resistance of concrete. Authors strongly suggest that the pozzolanic reaction and the development of the microstructure of the concrete through the use of waste materials are largely responsible from the advances in the durability of concrete.

Environmentally sound management of hazardous waste and hazardous recyclable materials

International Nuclear Information System (INIS)

Smyth, T.

2002-01-01

Environmentally sound management or ESM has been defined under the Basel Convention as 'taking all practicable steps to ensure that hazardous wastes and other wastes are managed in a manner which will protect human health and the environment against the adverse effects which may result from such wastes'. An initiative is underway to develop and implement a Canadian Environmentally Sound Management (ESM) regime for both hazardous wastes and hazardous recyclable materials. This ESM regime aims to assure equivalent minimum environmental protection across Canada while respecting regional differences. Cooperation and coordination between the federal government, provinces and territories is essential to the development and implementation of ESM systems since waste management is a shared jurisdiction in Canada. Federally, CEPA 1999 provides an opportunity to improve Environment Canada's ability to ensure that all exports and imports are managed in an environmentally sound manner. CEPA 1999 enabled Environment Canada to establish criteria for environmentally sound management (ESM) that can be applied by importers and exporters in seeking to ensure that wastes and recyclable materials they import or export will be treated in an environmentally sound manner. The ESM regime would include the development of ESM principles, criteria and guidelines relevant to Canada and a procedure for evaluating ESM. It would be developed in full consultation with stakeholders. The timeline for the development and implementation of the ESM regime is anticipated by about 2006. (author)

Pyrolysis of plastic packaging waste: A comparison of plastic residuals from material recovery facilities with simulated plastic waste

International Nuclear Information System (INIS)

Adrados, A.; Marco, I. de; Caballero, B.M.; López, A.; Laresgoiti, M.F.; Torres, A.

2012-01-01

Highlights: ► Pyrolysis of plastic waste. ► Comparison of different samples: real waste, simulated and real waste + catalyst. ► Study of the effects of inorganic components in the pyrolysis products. - Abstract: Pyrolysis may be an alternative for the reclamation of rejected streams of waste from sorting plants where packing and packaging plastic waste is separated and classified. These rejected streams consist of many different materials (e.g., polyethylene (PE), polypropylene (PP), polystyrene (PS), polyvinyl chloride (PVC), polyethylene terephthalate (PET), acrylonitrile butadiene styrene (ABS), aluminum, tetra-brik, and film) for which an attempt at complete separation is not technically possible or economically viable, and they are typically sent to landfills or incinerators. For this study, a simulated plastic mixture and a real waste sample from a sorting plant were pyrolyzed using a non-stirred semi-batch reactor. Red mud, a byproduct of the aluminum industry, was used as a catalyst. Despite the fact that the samples had a similar volume of material, there were noteworthy differences in the pyrolysis yields. The real waste sample resulted, after pyrolysis, in higher gas and solid yields and consequently produced less liquid. There were also significant differences noted in the compositions of the compared pyrolysis products.

Radiation effects on ion exchange materials used in waste management

International Nuclear Information System (INIS)

Pillay, K.K.S.

1982-01-01

Radiation damage to process materials used in radioactive waste management has been a topic of little interest in the past. In recent years, as a result of the increasing number of accidents reported in the open literature, there has been some desire to examine the radiation decomposition of ion exchange materials and its consequences to the interim and long-term management of radioactive wastes. Extensive literature surveys and some confirmatory laboratory investigations conducted conclusively demonstrate that radiation damage to ion exchangers has the potential to cause problems of corrosion, elution of adsorbed ionic species, generation of flammable and explosive gaseous products and agglomeration of particulates to form rigid monoliths. This paper is an overview of present knowledge and a presentation of the results of our investigations of this phenomenon. The distinct lack of systematic studies to evaluate the problems of radiation damage to process materials used in the consolidation and isolation of high specific activity radionuclides still leaves considerable gaps in our knowledge of the processes and consequences of radiation effects on ion exchangers used in radioactive waste management

French National Plan for the Management of Radioactive Materials and Waste (PNGMDR) - 2010-2012

International Nuclear Information System (INIS)

2009-01-01

Faced with the high diversity of radioactive materials and waste, it may be difficult to grasp the relevance and consistency of the installed management framework. The purpose of the National Plan for the Management of Radioactive Materials and Waste (PNGMDR) is to clarify this management framework and improve it. To this end, it draws up an assessment of the management policy, evaluates the needs and determines the objectives to be attained in the future. The PNGMDR's usefulness was confirmed by Parliament. The evaluation report of the PNGMDR 2007-2009 by the Parliamentary Office for Evaluation of Scientific and Technological Options thus indicates that 'the interest of a summary document exposing all the problems and the solutions related to the management of radioactive waste was underlined a number of times by the Office. Since such a plan can allow achieving exhaustiveness and introducing a consistency in the management of radioactive waste, the Office deemed it necessary that it be linked to the law in one way or another. Conforming to the Office's recommendations, the Act of 28 June 2006 related to the sustainable management of radioactive waste stipulated that such a plan must be elaborated, updated every three years and published, extending its scope to reusable radioactive materials'. Thus, the PNGMDR provides the public with a global vision of the management of radioactive materials and waste, concerning both topics 'in the news' and those less publicised. Some waste, in fact, attracts momentarily particular attention, for example, on the occasion of a search for a disposal site, such as in 2008-2009, for so-called low level and long lived ('LL-LL') waste. The media also broadcast in 2008 and 2009 special enquiries on the management of mining residues and on reprocessed uranium; all these topics are discussed in detail in the PNGMDR. Other waste topics attract less attention, such as sealed radioactive sources, which are more dispersed throughout France

Management of radioactive materials and wastes: status, stakes and perspectives

International Nuclear Information System (INIS)

Champion, Didier; Devin, Patrick; Tanguy, Loic; Bernard, Herve; Minon, Jean-Paul; Leclaire, Arnaud; Gilli, Ludivine; Lheureux, Yves; Pescatore, Claudio; Barbey, Pierre; Schneider, Thierry; Gay, Didier; Forest, Isabelle; Hemidy, Pierre-Yves; Baglan, Nicolas; Desnoyers, Bruno; Pieraccini, Michel; Poncet, Philippe; Seguin, Bertille; Calvez, Marianne; Leclerc, Elisabeth; Bancelin, Estelle; Fillion, Eric; Segura, Yannick; Vernaz, Etienne; Granier, Guy; De Preter, Peter; Petitfrere, Michael; Laye, Frederic; Nakamura, Takashi; Gin, Stephane; Lebaron-Jacobs, Laurence; Dinant, Sophie; Vacquier, Blandine; Crochon, Philippe; Griffault, Lise; Smith, Graham

2013-10-01

These technical days were organized by the Environment section of the French Society of Radiation Protection (SFRP). Time was given to some exchange about the societal aspects of radioactive waste management as well as about the legal context but the most part of the debates delt with the actual management modalities of the different types of wastes, both in France and in foreign countries, and with the related stakes, in particular in terms of impact. This document brings together the presentations (slides) of the following talks: - Contributions of radiation protection to the long-term safety management of radioactive wastes (Jean-Paul MINON - ONDRAF); - The national inventory of radioactive materials and wastes (Arnaud LECLAIRE - ANDRA); - The high activity, medium activity-long living wastes in debate - a co-building approach (ANCCLI/Clis of Bure/IRSN) to share stakes, enlighten, and develop thought (Ludivine GILLI - IRSN, Yves LHEUREUX - ANCCLI); - Social aspects of Radioactive Waste Management - The International Learning (Claudio PESCATORE - AEN/OCDE); - Citizens involvement and ACRO's point of view on radioactive wastes management (Pierre BARBEY - ACRO); - New CIPR recommendations about the geologic disposal of long-living radioactive wastes (Thierry SCHNEIDER - CEPN); - Overview of processes under the views of radiation protection principles (Didier GAY - IRSN); - The national plan of radioactive materials and wastes management (Loic TANGUY - ASN); - Joint convention on spent fuel management safety and on radioactive waste management safety - status and main stakes (Isabelle FOREST - ASN); - Transport of radioactive wastes (Bruno DESNOYERS - AREVA); - Optimisation and limitation of the environmental impacts of very-low level wastes - valorisation and processes selection (Michel PIERACCINI - EDF), Philippe PONCET - AREVA); - Management of hospital wastes - Example of Montpellier's University Regional Hospital (Bertille SEGUIN - CHRU de Montpellier); - Waste

Qualification test of packages for transporting radioactive materials and wastes

International Nuclear Information System (INIS)

Oliveira Santos, P. de; Miaw, S.T.W.

1990-01-01

Since 1979 the Waste Treatment Division of Nuclear Tecnology Development Center has been developed and tested packagings for transporting radioactive materials and wastes. The Division has designed facilities for testing Type A packages in accordance with the adopted regulations. The Division has tested several packages for universities, research centers, industries, INB, FURNAS, etc. (author) [pt

Alkaline degradation of organic materials contained in TRU wastes under repository conditions

International Nuclear Information System (INIS)

Otsuka, Yoshiki; Banba, Tsunetaka

2007-09-01

Alkaline degradation tests for 9 organic materials were conducted under the conditions of TRU waste disposal: anaerobic alkaline conditions. The tests were carried out at 90degC for 91 days. The sample materials for the tests were selected from the standpoint of constituent organic materials of TRU wastes. It has been found that cellulose and plastic solidified products are degraded relatively easily and that rubbers are difficult to degrade. It could be presumed that the alkaline degradation of organic materials occurs starting from the functional group in the material. Therefore, the degree of degradation difficulty is expected to be dependent on the kinds of functional group contained in the organic material. (author)

Recovering energy and materials from hazardous waste

Energy Technology Data Exchange (ETDEWEB)

Anon.

2003-12-01

The tannery industry faces growing environmental concerns because of the high hazardous metal content of its process waste. The formation, during the tanning process, of the highly toxic hexavalent chromium precludes the use of conventional thermal incineration processes. Borge Tannery in Norway, which processes 600 cattle hides per day, has solved the problem by using new PyroArc technology. The PyroArc waste processing plant can treat all of the tannery's production wastes, transforming them into useful products such as fuel gas and re-usable metal. The fuel gas consists mainly of carbon monoxide, hydrogen and nitrogen, and has a calorific value of about 4 MJ/Nm{sub 3}. About 65-70% of the energy content of the source material (waste or biomass) is recovered in the gas, and this is used to produce steam and/or electricity in a gas engine with a capacity of 580 kW. A further 20-25% of the initial energy content is recovered as heat or low-pressure steam. The plant is designed to be self-sufficient in energy (1.5 MW) and to meet the tannery's maximum requirements for hot water and steam. (UK)

Permanent disposal of radioactive particulate waste in cartridge containing ferromagnetic material

International Nuclear Information System (INIS)

Troy, M.

1986-01-01

This patent describes a cartridge for permanent disposal of solid radioactive particulate waste, comprising; a liquid impervious casing having an upper end cover, a lower end cover and a side wall extending between the covers, the casing enclosing a waste storage region; ferromagnetic fibrous material defining a waste retaining matrix and filling a major portion of the waste storage region; means defining an inlet conduit extending through the upper end cover and axially of the casing through the waste storage region, and opening into the waste storage region in the vicinity of the lower and end cover; and means defining first and second outlet conduits extending through the upper end cover and opening into the waste storage region in the vicinity of the upper end cover

Materials interactions test methods to measure radionuclide release from waste forms under repository-relevant conditions

International Nuclear Information System (INIS)

Strickert, R.G.; Erikson, R.L.; Shade, J.W.

1984-10-01

At the request of the Basalt Waste Isolation Project, the Materials Characterization Center has collected and developed a set of procedures into a waste form compliance test method (MCC-14.4). The purpose of the test is to measure the steady-state concentrations of specified radionuclides in solutions contacting a waste form material. The test method uses a crushed waste form and basalt material suspended in a synthetic basalt groundwater and agitated for up to three months at 150 0 C under anoxic conditions. Elemental and radioisotopic analyses are made on filtered and unfiltered aliquots of the solution. Replicate experiments are performed and simultaneous tests are conducted with an approved test material (ATM) to help ensure precise and reliable data for the actual waste form material. Various features of the test method, equipment, and test conditions are reviewed. Experimental testing using actinide-doped borosilicate glasses are also discussed. 9 references, 2 tables

Potential applications of nanostructured materials in nuclear waste management.

Energy Technology Data Exchange (ETDEWEB)

Braterman, Paul S. (The University of North Texas, Denton, TX); Phol, Phillip Isabio; Xu, Zhi-Ping (The University of North Texas, Denton, TX); Brinker, C. Jeffrey; Yang, Yi (University of New Mexico, Albuquerque, NM); Bryan, Charles R.; Yu, Kui; Xu, Huifang (University of New Mexico, Albuquerque, NM); Wang, Yifeng; Gao, Huizhen

2003-09-01

This report summarizes the results obtained from a Laboratory Directed Research & Development (LDRD) project entitled 'Investigation of Potential Applications of Self-Assembled Nanostructured Materials in Nuclear Waste Management'. The objectives of this project are to (1) provide a mechanistic understanding of the control of nanometer-scale structures on the ion sorption capability of materials and (2) develop appropriate engineering approaches to improving material properties based on such an understanding.

Disposal of radwastes and recycling of wastes and structural materials -fundamental principles, concepts, results

International Nuclear Information System (INIS)

Schaller, G.; Arens, G.; Brennecke, P.; Goertz, R.; Poschner, J.; Thieme, M.

1997-01-01

This report describes the German concept for the disposal of radioactive waste, and the re-use or recycling of contaminated materials. All radioactive waste can be disposed of in deep geological formations (practised at ERAM disposal site, planned for Konrad disposal site). Radioactively contaminated material below clearance levels can proceed for disposal at waste disposal sites and incineration plants, or for re-use and recycling, especially where the material consists of contaminated steel and of buildings. The basic principles (dose limits and model structures for deriving recommendations), reference values, or limits are described. The latest concepts are described in greater detail. Waste management in Germany is compared with international concepts. (orig.) [de

Transportation of radioactive, hazardous, and mixed wastes: Material identification is the key

International Nuclear Information System (INIS)

Stancell, D.F.; Willaford, D.M.

1992-01-01

This paper will discuss how material identification and classification will result in an accurate determination of regulatory requirements, and will assure safe and compliant shipment of radioactive, hazardous, and mixed wastes. The primary focus of the paper is a discussion of lessons learned by the Department of Energy in making waste shipments, and how this can be applied to future mixed waste shipments. There will be a brief discussion of the Department's regulatory compliance program, including a presentation of compliance audit results, and how regulatory issues are addressed through effective information exchange, technical assistance, and compliance training. A detailed discussion will follow, which describes cases involving material identification and classification problems. Examples will include both RCRA waste and uranium mill tailings shipments. The paper will conclude with a discussion concerning the application of these lessons to future mixed waste shipments proposed by the Department. (author)

Final disposal of the rad waste materials - question of the nuclear energy implementation and application perspectives

International Nuclear Information System (INIS)

Plecas, I.

1995-01-01

Two main problems that are denying and slowing down the development of nuclear energy are safe work of the nuclear power facilities (NEF) and disposal of the radioactive waste materials, produced from the NEF and infrastructure facilities of the nuclear fuel cycle (NFC). Although nowadays worldwide knowledge, based on the 45 year of experiences in handling the radioactive waste materials, do not treat the problems of final disposal of the rad waste materials as a task of the primary importance in NFC, this subject still engage experts from this field of investigations, especially in the countries that developed all aspects of the nuclear fuel cycle. Techniques for final disposal of low and intermediate level rad waste materials, are well known and are in state of implementation. The importance of the fundamental safety principles, implemented in the IAEA documents, concerning handling, treatment and final disposal of the rad waste materials, is presented. Future usage of nuclear energy, taking into account all the facts that are dealing with problems of the rad waste materials produced in the NFC, can be a reality. (author.)

Energetic use of the tomato plant waste

Energy Technology Data Exchange (ETDEWEB)

Encinar, Jose M.; Martinez, Gloria [Dpto. de Ingenieria Quimica y Quimica Fisica. UEX. Avda de Elvas s/n. 06071 Badajoz, Tf. 34 924 289672 (Spain); Gonzalez, Juan F. [Dpto. de Fisica Aplicada. UEX. Avda de Elvas s/n 06071 Badajoz (Spain)

2008-11-15

A study of the conventional pyrolysis of the tomato plant waste has been carried out. The objective of this work was to characterize the solid, liquid and gaseous phases obtained in the process for their possible utilization in energy generation. Also, a study of the influence of operation variables has been performed, determining the optimal conditions in which the process can be accomplished. The operation variables studied were temperature (400-800 C), the initial sample mass (2.5-10 g of tomato plant waste) and the particle size (0.63-2.00 mm). Under the conditions studied here, an increase in reaction temperature leads to a decrease in solid and liquid yields and to an increase in gas phase yield. However the variation in the initial sample mass and the particle size does not seem to exert a defined influence in the yield of the different phases. The higher heating value (HHV) of solids and liquids was determined; also the immediate analysis of the solid phase was carried out. The gas phase, mainly composed of H{sub 2}, CO, CH{sub 4}, CO{sub 2} and traces of ethane and ethylene, was analyzed chromatographically. The solid phase is constituted for a charcoal with an average higher heating value of 26 MJ kg{sup -} {sup 1}, the liquid phase presents a HHV of 7.8 MJ kg{sup -} {sup 1} at 400 C, this value diminishes when the temperature is increased, and the gas phase has an HHV between 0.5 and 8.0 MJ (kg of raw material){sup -} {sup 1}. According to their characteristics and energy contents, the solid phase can be used as fuel or precursor for the manufacture of activated carbons. The liquid phase could be used as liquid fuel or as organic-compounds source. The gas phase could be used to heat the pyrolysis reactor or to generate heat and electricity in a gas-turbine/vapour-turbine combined cycle. Finally, as previous step to the design of the industrials equipments, a kinetic study of the process, based in the generation of the principal gases, has been carried

Handbook of solid waste disposal: materials and energy recovery

Energy Technology Data Exchange (ETDEWEB)

Pavoni, J L; Heer, Jr, J E; Hagerty, D J

1975-01-01

Traditional and innovative solid waste disposal techniques and new developments in materials and energy recovery systems are analyzed. Each method is evaluated in terms of system methodology, controlling process parameters, and process requirements, by-products, economics, and case histories. Medium and high temperature incineration; wet pulping; landfill with leachate recirculation; the Hercules, Inc., system; USBM front-end and back-end systems; pyrolysis; waste heat utilization, the Combustion Power Unit-400; use of refuse as a supplementary fuel; and methane production from anaerobic fermentation systems are considered, as well as sanitary landfilling, incineration, and composting. European solid waste management techniques are evaluated for their applicability to the US.

A multi-scale methodology to model damage, deformation and ignition of highly-filled energetic materials

Energy Technology Data Exchange (ETDEWEB)

Vivier, G. [Paris Univ., Paris (France). LMT Cachan; CEA Le Ripault, Monts (France); Trumel, H. [CEA Le Ripault, Monts (France); Hild, F. [Paris Univ., Paris (France). LMT Cachan

2009-07-01

The kinetic energy that occurs when energetic materials are impacted can be converted to heat through dissipative deformation processes while the macroscopic temperature remains unaffected. In this study, a thermodynamics-based approach was used to model the elasto-plastic behaviour that occurs during the deformation process of microstructures. Macroscopic material was modelled as a statistical distribution of unit cells containing a crack grain embedded in an elastic mortar-like matrix. A mesoscopic unit cell model was also developed under confined shear. The study demonstrated that stored energy is a non-negligible part of the total energy of the system, and that stored energy can be released during the unloading process. It was concluded that the mesoscopic analysis of the cracked cell demonstrates that continuum thermodynamics can be used to predict hot spots induced by friction. 7 refs., 7 figs.

Energetic balance and air pollutant emissions estimates in the Aburra Valley, 1999: A preliminary approximation

International Nuclear Information System (INIS)

Molina Perez; Francisco; Saavedra Duque, Marcela; Obregon Cardona Mauricio

2003-01-01

Based on the application of Material Fluxes Analysis, this paper presents the composition of the energetic basket in Valle de Aburra during 1999 and the atmospheric emissions caused by the consumption of those energetic materials. Basically, it was found that the daily energetic consumption of the system was 43,2 Tcal that generated 716 ton. by day of atmospheric contaminants as an output. The results show that the main energetic materials that participate in the global metabolism of the system, was those consumed in the transportation sector (gasoline and diesel). Therefore transportation sector contributes with the principal load of contaminants represented by carbon monoxide that overtake the 77,6% of the whole emissions

Apparatus and method for treating waste material

International Nuclear Information System (INIS)

Allison, W.

1981-01-01

Apparatus is described for the packaging of waste material in a vessel, comprising: a vessel entry station having inlet and outlet doors; a filling station downstream of the vessel entry station and having a filling position to which vessels are transferred from the entry station through the outlet door, the filling station having filling means for introducing radioactive waste into the vessel; a mixing station having a mixing position to which a vessel is transferred from the filling position; a capping station having a capping position to which a vessel is transferred from the mixing position; and means for effecting transfer of a vessel through the apparatus. Radiation shielding is provided. (U.K.)

Radiolytic gas generation in plutonium contaminated waste materials

International Nuclear Information System (INIS)

Kazanjian, A.R.

1976-01-01

Many plutonium contaminated waste materials decompose into gaseous products because of exposure to alpha radiation. The gases generated (usually hydrogen) over long-storage periods may create hazardous conditions. To determine the extent of such hazards, knowing the gas generation yields is necessary. These yields were measured by contacting some common Rocky Flats Plant waste materials with plutonium and monitoring the enclosed atmospheres for extensive periods of time. The materials were Plexiglas, polyvinyl chloride, glove-box gloves, machining oil, carbon tetrachloride, chlorothene VG solvent, Kimwipes (dry and wet), polyethylene, Dowex-1 resin, and surgeon's gloves. Both 239 Pu oxide and 238 Pu oxide were used as radiation sources. The gas analyses were made by mass spectrometry and the results obtained were the total gas generation, the hydrogen generation, the oxygen consumption rate, and the gas composition over the entire storage period. Hydrogen was the major gas produced in most of the materials. The total gas yields varied from 0.71 to 16 cm 3 (standard temperature pressure) per day per curie of plutonium. The oxygen consumption rates varied from 0.0088 to 0.070 millimoles per day per gram of plutonium oxide-239 and from 0.0014 to 0.0051 millimoles per day per milligram 238 Pu

The Civilisation Biorefinery - A Future Approach for Material and Energy Recovery from Regional Organic Waste

International Nuclear Information System (INIS)

Koerner, I.

2010-01-01

The future shortage of energy and raw materials as well as the problems on climate protection are challenges for which a solution is imperative. For efficient utilizing organic liquid and solid wastes which are generated in a city, a city itself could become a civilisation biorefinery. The output will be various energetic and material products, which can be used in the city or in the surrounding of the city. Depending on the nature of the various urban input materials, they need to be fed in to biorefineries adapted to the substrate type. The separate substrate-specific biorefineries may be at central or decentralised locations within the city. Moreover, since the residues from one system can be used in others as input, mutual networking is of importance. To facilitate efficient valorification, bioresources and the type of biorefinery need to be optimally matched. That also means that at the collection stage already, the material properties of the bioresource must be taken into account and where appropriate, new collection systems introduced, or consideration should be given to technical processes for separation of mixtures of materials. Extremely differing cascades will be appropriate for the various regional situations. For this reason, the evaluation of alternative schemes will be seen as very significant. Additional important points are the suitability of new measures or processes for integration into existing regional structures, as well as the logistics aspects, including the question of whether bioconversion processes should be conducted centrally or in decentralised locations. In Germany, considerable amounts of biowaste are available today and in the future which, until now, were almost entirely composted. The possibilities of anaerobic fermentation are gaining more and more in importance. Aerobic and anaerobic treatments of biowaste are more and more combined within the scope of a win-win situation. These technologies will be important parts of a

Organic fraction of solid waste in biodigester; Fracao organica de lixo urbano como substrato para biodigestor

Energy Technology Data Exchange (ETDEWEB)

Gorgati, Claudia Q. [UNESP, Botucatu, SP (Brazil). Faculdade de Ciencias Agronomicas. Curso de Pos-graduacao em Energia na Agricultura; Lucas Junior, Jorge de [UNESP, Jaboticabal, SP (Brazil). Faculdade de Ciencias Agrarias e Veterinarias. Dept. de Engenharia Rural

1999-12-01

The study of the anaerobic digestion was accomplished with the organic fraction of urban solid waste collected at the composting plant - CONSTRUFERT- from the municipal district of Sao Jose do Rio Preto - SP. The essay was conducted in six bio digesters at the Rural Engineering Department of the Faculdade de Ciencias Agrarias e Veterinarias, in Jaboticabal/SP, three of them with fresh urban organic waste and remaining ones with dried and ground material. With regard to the anaerobic digestion the biogas production was monitored and the data indicated the energetic potential of urban waste, which was found to be 0.1034 - 0.1395 m{sup 3}/Kg of raw urban waste with reduction of volatile solids between 56 and 66.50%. (author)

Container material and design considerations for storage of low-level radioactive waste

International Nuclear Information System (INIS)

Temus, C.J.

1987-01-01

With the threat of increased burial site restrictions and increased surcharges; the ease with which waste is sent to the burial site has been reduced. For many generators of waste the only alternative after maximizing volume reduction efforts is to store the waste. Even after working through the difficult decision of deciding what type of storage facility to have, the decision of what type of container to store the waste in has to still be made. This paper explores the many parameters that affect not only the material selection but also the design. The proper selection of materials affect the ability of the container to survive the storage period. The material selection also directly affects the design and utilization of the storage facility. The impacts to the facility include the functional aspects as well as its operational cost and liability as related to such things as fire insurance and active environmental control systems. The advantages and disadvantages of many of the common systems such as carbon steel, various coatings, polyethylene, stainless steel, composites and concrete will be discussed and evaluated. Recognizing that the waste is to be disposed of in the future differentiates it from waste that is shipped directly to the disposal site. The stored waste has to have the capability to be handled not only once like the disposal site waste but potentially several times before ultimate disposal. This handling may be by several different systems both at the storage facility and the burial site. Some of these systems due to ALARA considerations are usually remote requiring various interfaces, while not interfering with handling, transportation or disposal operations

Plant waste materials from restaurants as the adsorbents for dyes

Directory of Open Access Journals (Sweden)

Pavlović Marija D.

2015-01-01

Full Text Available This paper has demonstrated the valorization of inexpensive and readily available restaurant waste containing most consumed food and beverage residues as adsorbents for methylene blue dye. Coffee, tea, lettuce and citrus waste have been utilized without any pre-treatment, thus the adsorption capacities and dye removal efficiency were determined. Coffee waste showed highest adsorbent capacity, followed by tea, lettuce and citrus waste. The dye removal was more effective as dye concentration increases from 5 up to 60 mg/L. The favorable results obtained for lettuce waste have been especially encouraged, as this material has not been commonly employed for sorption purposes. Equilibrium data fitted very well in a Freundlich isotherm model, whereas pseudo-second-order kinetic model describes the process behavior. Restaurant waste performed rapid dye removal at no cost, so it can be adopted and widely used in industries for contaminated water treatment.

Bentonite as a waste isolation pilot plant shaft sealing material

International Nuclear Information System (INIS)

Daemen, J.; Ran, Chongwei

1996-12-01

Current designs of the shaft sealing system for the Waste Isolation Pilot Plant (WIPP) propose using bentonite as a primary sealing component. The shaft sealing designs anticipate that compacted bentonite sealing components can perform through the 10,000-year regulatory period and beyond. To evaluate the acceptability of bentonite as a sealing material for the WIPP, this report identifies references that deal with the properties and characteristics of bentonite that may affect its behavior in the WIPP environment. This report reviews published studies that discuss using bentonite as sealing material for nuclear waste disposal, environmental restoration, toxic and chemical waste disposal, landfill liners, and applications in the petroleum industry. This report identifies the physical and chemical properties, stability and seal construction technologies of bentonite seals in shafts, especially in a saline brine environment. This report focuses on permeability, swelling pressure, strength, stiffness, longevity, and densification properties of bentonites

Bentonite as a waste isolation pilot plant shaft sealing material

Energy Technology Data Exchange (ETDEWEB)

Daemen, J.; Ran, Chongwei [Univ. of Nevada, Reno, NV (United States)

1996-12-01

Current designs of the shaft sealing system for the Waste Isolation Pilot Plant (WIPP) propose using bentonite as a primary sealing component. The shaft sealing designs anticipate that compacted bentonite sealing components can perform through the 10,000-year regulatory period and beyond. To evaluate the acceptability of bentonite as a sealing material for the WIPP, this report identifies references that deal with the properties and characteristics of bentonite that may affect its behavior in the WIPP environment. This report reviews published studies that discuss using bentonite as sealing material for nuclear waste disposal, environmental restoration, toxic and chemical waste disposal, landfill liners, and applications in the petroleum industry. This report identifies the physical and chemical properties, stability and seal construction technologies of bentonite seals in shafts, especially in a saline brine environment. This report focuses on permeability, swelling pressure, strength, stiffness, longevity, and densification properties of bentonites.

Optimising material procurement for construction waste minimization: An exploration of success factors

OpenAIRE

Ajayi, SO; Oyedele, LO; Akinade, OO; Bilal, M; Alaka, HA; Owolabi, HA

2017-01-01

Although construction waste occurs during the actual construction activities, there is an understanding that it is caused by activities and actions at design, materials procurement and construction stages of project delivery processes. This study investigates the material procurement and logistics measures for mitigating waste generated by construction activities. In a bid to explore the phenomenon from the perspectives of experts from the construction industry, this study used a combination ...

Optimization of Waste and Materials Disposition in France - Policy, Strategies, and Techniques

International Nuclear Information System (INIS)

DUTZER, Michel; Rives, Jean Francois

2014-01-01

The general legal and regulatory framework for waste management in France is described in the 'Code for the Environment'. A specificity of the French regulation is that it prescribes the implementation within nuclear facilities of a waste zoning to segregate areas where waste cannot be contaminated or activated and areas where waste are or may have an added radioactive content. The first category may be managed in conventional routes; the second category (nuclear waste) requires a dedicated management in licensed facilities with a reinforced traceability. The purpose of this regulation is to prevent a misdirection of waste from the very large French nuclear fleet without a need of an increased control by the regulatory body. Furthermore there is a reluctance of some stakeholders for free release of materials. As a consequence disposal for very low level waste must have an economical relevance in comparison with conventional waste disposal. The regulation includes principles that are provided by the Planning Act of June 2006, 28, related to the sustainable management of radioactive Materials and waste. In particular this act sets a schedule for research into high level waste and intermediate level long-lived waste and confirms the implementation of a national plan for the management of radioactive materials and waste (PNGMDR). This plan, which is chaired by the ministry of energy and the nuclear regulatory body (ASN) involves elected officials, waste generators, the national waste management agency and members of the civil society. It is updated every three years. The plan deals with all types of radioactive waste and materials, with already available management routes and routes under development. It identifies areas to be improved and makes recommendations. It describes the research works to be performed. The follow up is done through periodical meetings, the conclusions of which are used to update the plan. The first version of PNGMDR was published in

Institute of Energy and Climate Research IEK-6. Nuclear Waste Management report 2011/2012. Material science for nuclear waste management

International Nuclear Information System (INIS)

Klinkenberg, M.; Neumeier, S.; Bosbach, D.

2013-01-01

The nuclear waste management section of the Institute of Energy and Climate Research IEK-6 in Juelich is focused on research on radiochemistry aspects/materials science relevant for the long-term safety of nuclear waste storage and disposal. Studies on innovative waste management strategies include partitioning o actinides and the development of ceramic waste forms. Structural research is covering solid state chemistry, crystallography and computational science to model actinide containing compounds. With respect to waste management concepts nondestructive essay techniques, waste treatment procedures and product quality control strategies were developed.

Compost feedstock characteristics and ratio modelling for organic waste materials co-composting in Malaysia.

Science.gov (United States)

Chai, E W; H'ng, P S; Peng, S H; Wan-Azha, W M; Chin, K L; Chow, M J; Wong, W Z

2013-01-01

In Malaysia, large amounts of organic materials, which lead to disposal problems, are generated from agricultural residues especially from palm oil industries. Increasing landfill costs and regulations, which limit many types of waste accepted at landfills, have increased the interest in composting as a component of waste management. The objectives of this study were to characterize compost feedstock properties of common organic waste materials available in Malaysia. Thus, a ratio modelling of matching ingredients for empty fruit bunches (EFBs) co-composting using different organic materials in Malaysia was done. Organic waste materials with a C/N ratio of composting. The outcome of this study suggested that the percentage of EFB ranged between 50% and 60%, which is considered as the ideal mixing ratio in EFB co-composting. Conclusively, EFB can be utilized in composting if appropriate feedstock in term of physical and chemical characteristics is coordinated in the co-composting process.

Utilization of waste of chicken feathers and waste of cardboard as the material of acoustic panel maker

Science.gov (United States)

Ansarullah; Rahim, Ramli; Kusno, Asniawaty; Baharuddin; Jamala, Nurul

2018-03-01

In The existence of chicken fur is a waste of chicken slaughterhouse Which is produced daily and still not widely used. Likewise cartons everywhere we can see its being because its function is so great in all human activities In the fulfillment of the need for storage and packaging of goods for human purposes such as electronic goods, commodity, Because it has a relatively large thickness of paper. Several studies have proven that Quill and cardboard can be used for acoustic materials. This study aims to identify the potential of chicken fur and cardboard to be created as panel materials Which acts as an acoustic panel. . This study uses an experimental method by combining two materials, Including waste Quill and carton waste by performing several stages in the formation of panels, Such as the selection of chicken fur material and cardboard cleaning process, drying process, enumeration process, panel modeling process. The result of this research is acoustic panel model with size 20x20cm2 with thickness 9 and 18 mm, The study also produced a Ø9,8 cm diameter-shaped panel model with 1.5cm, 2.5cm, and 5cm thickness for use in testing absorption coefficients using impedance tubes.

Evaluation of municipal solid waste management performance by material flow analysis: Theoretical approach and case study.

Science.gov (United States)

Zaccariello, Lucio; Cremiato, Raffaele; Mastellone, Maria Laura

2015-10-01

The main role of a waste management plan is to define which is the combination of waste management strategies and method needed to collect and manage the waste in such a way to ensure a given set of targets is reached. Objectives have to be sustainable and realistic, consistent with the environmental policies and regulations and monitored to verify the progressive achievement of the given targets. To get the aim, the setting up and quantification of indicators can allow the measurement of efficiency of a waste management system. The quantification of efficiency indicators requires the developing of a material flow analysis over the system boundary, from waste collection to secondary materials selling, processing and disposal. The material flow analysis has been carried out with reference to a case study for which a reliable, time- and site-specific database was available. The material flow analysis allowed the evaluation of the amount of materials sent to recycling, to landfilling and to waste-to-energy, by highlighting that the sorting of residual waste can further increase the secondary materials amount. The utilisation of energy recovery to treat the low-grade waste allows the maximisation of waste diversion from landfill with a low production of hazardous ash. A preliminary economic balance has been carried out to define the gate fee of the waste management system that was in the range of 84-145 € t(-1) without including the separate collection cost. The cost of door-by-door separate collection, designed to ensure the collection of five separate streams, resulted in 250 € t(-1) ±30%. © The Author(s) 2015.

Utilization of Construction Waste Composite Powder Materials as Cementitious Materials in Small-Scale Prefabricated Concrete

Directory of Open Access Journals (Sweden)

Cuizhen Xue

2016-01-01

Full Text Available The construction and demolition wastes have increased rapidly due to the prosperity of infrastructure construction. For the sake of effectively reusing construction wastes, this paper studied the potential use of construction waste composite powder material (CWCPM as cementitious materials in small-scale prefabricated concretes. Three types of such concretes, namely, C20, C25, and C30, were selected to investigate the influences of CWCPM on their working performances, mechanical properties, and antipermeability and antifrost performances. Also the effects of CWCPM on the morphology, hydration products, and pore structure characteristics of the cement-based materials were analyzed. The results are encouraging. Although CWCPM slightly decreases the mechanical properties of the C20 concrete and the 7 d compressive strengths of the C25 and C30 concretes, the 28 d compressive strength and the 90 d flexural strength of the C25 and C30 concretes are improved when CWCPM has a dosage less than 30%; CWCPM improves the antipermeability and antifrost performances of the concretes due to its filling and pozzolanic effects; the best improvement is obtained at CWCPM dosage of 30%; CWCPM optimizes cement hydration products, refines concrete pore structure, and gives rise to reasonable pore size distribution, therefore significantly improving the durability of the concretes.

Textural development and hydrogen adsorption of carbon materials from PET waste

International Nuclear Information System (INIS)

Parra, J.B.; Ania, C.O.; Arenillas, A.; Rubiera, F.; Palacios, J.M.; Pis, J.J.

2004-01-01

Polyethyleneterephthalate (PET) has become one of the major post-consumer plastic wastes. PET products present a problem of considerable concern due to the huge amount of solid waste produced. The disposal of this waste, together with its low bio- and photo-degradability represents a serious challenge for industrial countries all over the world. Pyrolysis could provide an alternative and economically viable route for processing PET waste due to the potential uses of different by-products: energy from the pyrolysis gases (58% yield in this work), recovery of terephthalic acid and other subproducts (20%), and a solid residue (22%), which has shown a high textural development after activation. The pyrolysis of PET waste was performed in a quartz reactor (i.d. 35 mm) under an inert atmosphere. Further activation was carried out at a temperature of 925 deg. C, with a flow rate of 10 ml min -1 of CO 2 . A series of carbon materials with different burn-off degrees was obtained. Textural characterisation of the samples was carried out by performing N 2 adsorption isotherms at -196 deg. C. Changes in the morphological and structural properties of chars were studied by scanning electron microscopy (SEM) and X-ray diffraction (XRD). The carbons obtained were isotropic and highly microporous materials with apparent BET surface areas of up to 2500 m 2 g -1 . The suitability of the samples for hydrogen storage was studied by performing H 2 adsorption measurements in the 0-1 bar pressure range. Adsorption-desorption experiments showed that reversible physisorption takes place in all the samples. The hydrogen adsorption capacities of the activated PET waste compare favourably well with those attained with high-value carbon materials

The 2016-2018 National Plan of Management of Radioactive Materials and Wastes. Final report

International Nuclear Information System (INIS)

2017-01-01

A first document contains the final version of the French National Plan of Management of Radioactive Materials and Wastes (PNGMDR) for the period 2016-2018: principles and objectives (presentation of radioactive materials and wastes, principles to be taken into account to define pathways of management of radioactive wastes, legal and institutional framework, information transparency), the management of radioactive materials (context and challenges, management pathways, works on fast breeder reactors of fourth generation), assessment and perspectives of existing pathways of management of radioactive wastes (management of historical situations, management of residues of mining and sterile processing, management of waste with a high natural radioactivity, management of very short life waste, of very low activity wastes, and low and medium activity wastes), needs and perspectives regarding management processes to be implemented for the different types of radioactive wastes. Appendices to this document contain: a recall of the content of previous PNGMDR since 2007, a synthesis of realisations and researches performed abroad, research orientations for the concerned period, and international agreement on spent fuel and radioactive waste management. A second document, released by the ASN, proposes an environmental and strategic assessment of the plan. A third one and a fourth one contain the opinion of the Environmental Authority on the plan preliminary focus and the answer to the Environmental Authority by the ASN. Finally, a synthesis of the remarks made by the public about the PNGMDR and the answers to these remarks conclude the document

National Inventory of radioactive materials and wastes: statement at the end of 2015

International Nuclear Information System (INIS)

2016-12-01

As part of its general interest mission described in the French law from June 28, 2006, the French national agency of radioactive wastes is responsible of the annual inventory of all radioactive materials and wastes present on the French territory in order to have a vision of their nature, amount and localization as comprehensive as possible. This document presents the inventory of existing radioactive materials and wastes at December 31, 2015, according to the declarations made by their owners. These data are compared to the projected data established at the end of 2013

Graphite matrix materials for nuclear waste isolation

International Nuclear Information System (INIS)

Morgan, W.C.

1981-06-01

At low temperatures, graphites are chemically inert to all but the strongest oxidizing agents. The raw materials from which artificial graphites are produced are plentiful and inexpensive. Morover, the physical properties of artificial graphites can be varied over a very wide range by the choice of raw materials and manufacturing processes. Manufacturing processes are reviewed herein, with primary emphasis on those processes which might be used to produce a graphite matrix for the waste forms. The approach, recommended herein, involves the low-temperature compaction of a finely ground powder produced from graphitized petroleum coke. The resultant compacts should have fairly good strength, low permeability to both liquids and gases, and anisotropic physical properties. In particular, the anisotropy of the thermal expansion coefficients and the thermal conductivity should be advantageous for this application. With two possible exceptions, the graphite matrix appears to be superior to the metal alloy matrices which have been recommended in prior studies. The two possible exceptions are the requirements on strength and permeability; both requirements will be strongly influenced by the containment design, including the choice of materials and the waste form, of the multibarrier package. Various methods for increasing the strength, and for decreasing the permeability of the matrix, are reviewed and discussed in the sections in Incorporation of Other Materials and Elimination of Porosity. However, it would be premature to recommend a particular process until the overall multi-barrier design is better defined. It is recommended that increased emphasis be placed on further development of the low-temperature compacted graphite matrix concept

Positive utilization of waste materials from mines and quarries

International Nuclear Information System (INIS)

Blunden, J.R.

1980-01-01

World mineral waste production together with its backlog accumulation is reviewed with particular emphasis upon the situation in North America and the UK. The common problems of conventional waste dumping in relation to its propensity to create land dereliction, are discussed before considering the positive ways of utilizing such material. Upgrading to a saleable product has not resulted in the significant utilization of currently produced waste or stockpiles, whilst processing and transport costs are unlikely in the near future to permit any reduction in on-site tipping through this mode of use. Amenity uses are related to the availability of quantities of waste. Where small amounts are concerned opportunities exist for the backfilling of old excavations, rolling restoration and the construction of amenity backs; the technical and economic problems of each of these is considered. Large scale waste production cannot be similarly contained. Thus the problems of backfilling old workings and long distance transport for reclamation or public works schemes are examined in relation to cost factors. The limitations of conventional economics in dealing with the environmental problems posed by waste are stressed and the possible supportive role of governments in this respect is examined

Method of encapsulating solid radioactive waste material for storage

International Nuclear Information System (INIS)

Bunnell, L.R.; Bates, J.L.

1976-01-01

High-level radioactive wastes are encapsulated in vitreous carbon for long-term storage by mixing the wastes as finely divided solids with a suitable resin, formed into an appropriate shape and cured. The cured resin is carbonized by heating under a vacuum to form vitreous carbon. The vitreous carbon shapes may be further protected for storage by encasement in a canister containing a low melting temperature matrix material such as aluminum to increase impact resistance and improve heat dissipation. 8 claims

Trapping and re-emission of energetic hydrogen and helium ions in materials

International Nuclear Information System (INIS)

Yamaguchi, Sadae

1981-01-01

The experimental results on the trapping and re-emission of energetic hydrogen and helium ions in materials are explained. The trapping of deuterium and helium in graphite saturates at the concentration of 10 18 ions/cm 2 . The trapping rate of hydrogen depends on the kinds of target materials. In the case of the implantation in Mo over 3 x 10 16 H/cm 2 , hydrogen is hardly trapped. On the other hand, the trapping of hydrogen in Ti, Zr and Ta which form solid solution is easily made. The hydrogen in these metals can diffuse toward the inside of metals. The deuterium retained in 316 SS decreased with time. The trapping rate reached saturation more rapidly at higher implantation temperature. The effective diffusion constant for the explanation of the re-emission process is 1/100 as small as the ordinary value. The radiation damage due to helium irradiation affects on the trapping of deuterium in Mo. The temperature dependence of the trapping rate can be explained by the diffusion model based on the Sievert's law. The re-emission of helium was measured at various temperature. At low temperature, the re-emission was low at first, then the rate increased. At high temperature, the re-emission rate was high from the beginning. (Kato, T.)

Analysis of energetic and exergetic efficiency, and environmental benefits of biomass integrated gasification combined cycle technology.

Science.gov (United States)

Mínguez, María; Jiménez, Angel; Rodríguez, Javier; González, Celina; López, Ignacio; Nieto, Rafael

2013-04-01

The problem of the high carbon dioxide emissions linked to power generation makes necessary active research on the use of biofuels in gas turbine systems as a promising alternative to fossil fuels. Gasification of biomass waste is particularly of interest in obtaining a fuel to be run in gas turbines, as it is an efficient biomass-to-biofuel conversion process, and an integration into a combined cycle power plant leads to a high performance with regard to energetic efficiency. The goal of this study was to carry out an energetic, exergetic and environmental analysis of the behaviour of an integrated gasification combined cycle (IGCC) plant fuelled with different kinds of biomass waste by means of simulations. A preliminary economic study is also included. Although a technological development in gasification technology is necessary, the results of simulations indicate a high technical and environmental interest in the use of biomass integrated gasification combined cycle (BioIGCC) systems for large-scale power generation from biomass waste.

Processing agricultural and industrial waste materials to fodder

Energy Technology Data Exchange (ETDEWEB)

Varga, J; Baintner, F; Schmidt, J

1977-11-28

Unstable agricultural and industrial waste materials containing proteins and less than or equal to 80% H/sub 2/O, e.g. feathers, entrails, blood, malt, malt husks, whey, skim milk, cheese wastes, starch, malt residues, marc, broken and bloody eggs, lucerne liquor, etc. were homogenized with fodder containing carbohydrates or inert materials, as well as additives, e.g., AcOH, ascorbic acid, cysteine, NaNO/sub 2/, etc. to give a products containing less than or equal to 60% H/sub 2/O, pH 4.6 to 4.8, storable for shorter periods and useful for further processing. Thus, a homogenized mixture of 60 parts lard cake and 40 parts corn grits was homogenized with a 2:1 mixture of EtCO/sub 2/H and HCO/sub 2/H 1.5, NaNO/sub 2/ 0.05, and vitamin C 0.2% by weight to give a product with 32% protein content, useful for further processing.

PRODUCTION OF AN INSULATION MATERIAL FROM CARPET AND BORON WASTES

Directory of Open Access Journals (Sweden)

Yasin ERDOĞAN

2016-12-01

Full Text Available Buildings are large consumers of energy in all countries. In regions with harsh climatic conditions, a substantial share of energy goes to heat and cool buildings. This paper reports an investigation of the insulation materials made from mixing carpet wastes with a solution with added crude colemanite ore, one of boron minerals, and a solution with added colemanite wastes from a barrage. A new building insulation material was produced which is name, Halibor. Optimum mixing ratios were determined for mass production and the physical properties of the product were established. In addition, the material produced was compared with similar products used in buildings in terms of physical properties. As a result of the investigations, it was established that the product provides high heat and sound insulation and can be used easily in building and construction industry.

The influence of organic materials on the near field of an intermediate level waste radioactive waste repository

International Nuclear Information System (INIS)

Wilkins, J.D.

1988-02-01

The influence of organic materials, which are present in some intermediate level wastes, on the chemistry of the near field of a radioactive waste repository is discussed. Particular attention is given to the possible formation of water soluble complexing agents formed as a result of the radiation field and chemical conditions. The present state of the research is reviewed. (author)

The useful application of sulphur-bound waste materials

NARCIS (Netherlands)

Alkemade, M.M.C.; Koene, J.I.A.

1996-01-01

An immobilization process is described which is based on sulphur (instead of cement) as a binding agent for the treatment of hazardous waste materials. Elemental sulphur is able to bind chemically metals such as mercury and, to a lesser extent, lead as metal sulphides. Furthermore, sulphur forms a

Organic waste processing using molten salt oxidation

Energy Technology Data Exchange (ETDEWEB)

Adamson, M. G., LLNL

1998-03-01

Molten Salt Oxidation (MSO) is a thermal means of oxidizing (destroying) the organic constituents of mixed wastes, hazardous wastes, and energetic materials while retaining inorganic and radioactive constituents in the salt. For this reason, MSO is considered a promising alternative to incineration for the treatment of a variety of organic wastes. The U. S. Department of Energy`s Office of Environmental Management (DOE/EM) is currently funding research that will identify alternatives to incineration for the treatment of organic-based mixed wastes. (Mixed wastes are defined as waste streams which have both hazardous and radioactive properties.) One such project is Lawrence Livermore National Laboratory`s Expedited Technology Demonstration of Molten Salt Oxidation (MSO). The goal of this project is to conduct an integrated demonstration of MSO, including off-gas and spent salt treatment, and the preparation of robust solid final forms. Livermore National Laboratory (LLNL) has constructed an integrated pilot-scale MSO treatment system in which tests and demonstrations are presently being performed under carefully controlled (experimental) conditions. The system consists of a MSO process vessel with dedicated off-gas treatment, a salt recycle system, feed preparation equipment, and equipment for preparing ceramic final waste forms. In this paper we describe the integrated system and discuss its capabilities as well as preliminary process demonstration data. A primary purpose of these demonstrations is to identify the most suitable waste streams and waste types for MSO treatment.

Using thermal power plants waste for building materials

Science.gov (United States)

Feduik, R. S.; Smoliakov, A. K.; Timokhin, R. A.; Batarshin, V. O.; Yevdokimova, Yu G.

2017-10-01

The recycled use of thermal power plants (TPPs) wastes in the building materials production is formulated. The possibility of using of TPPs fly ash as part of the cement composite binder for concrete is assessed. The results of X-ray diffraction and differential thermal analysis as well as and materials photomicrographs are presented. It was revealed that the fly ash of TPPs of Russian Primorsky Krai is suitable for use as a filler in cement binding based on its chemical composition.

Nano-Aluminum Reaction with Nitrogen in the Burn Front of Oxygen-Free Energetic Materials

International Nuclear Information System (INIS)

Tappan, B. C.; Son, S. F.; Moore, D. S.

2006-01-01

Nano-particulate aluminum metal was added to the high nitrogen energetic material triaminoguanidium azotetrazolate (TAGzT) in order to determine the effects on decomposition behavior. Standard safety testing (sensitivity to impact, spark and friction) are reported and show that the addition of nano-Al actually decreases the sensitivity of the pure TAGzT. Thermo-equilibrium calculations (Cheetah) indicate that the all of the Al reacts to form AlN in TAGzT decomposition, and the calculated specific impulses are reported. T-Jump/FTIR spectroscopy was performed on the neat TAGzT. Emission spectra were collected to determine the temperature of AlN formation in combustion. Burning rates were also collected, and the effects of nano-Al on rates are discussed

Gas generation by self-radiolysis of tritiated waste materials

International Nuclear Information System (INIS)

Tadlock, W.E.; Abell, G.C.; Steinmeyer, R.H.

1980-01-01

Studies simulating the effect of self-radiolysis in disposal packages containing tritiated waste materials show hydrogen to be the dominant gas-phase product. Pressure buildup and gas composition over various tritiated octane and tritiated water samples are designed to give worst case results. One effect of tritium fixation agents is to reduce pressure buildup. The results show that development of explosive gas mixtures is unlikely and that maximum pressure buildup in typical Mound Facility waste packages can be expected to be <0.25 MPa

Potential of Electronic Plastic Waste as a Source of Raw Material and Energy Recovery

International Nuclear Information System (INIS)

Norazli Othman; Nor Ezlin Ahmad Basri; Lariyah Mohd Sidek

2009-01-01

Nowadays, the production of electronic equipment is one of the fastest growing industrial activities in this world. The increase use of plastic in this sector resulted in an increase of electronic plastic waste. Basically, electronic plastic material contains various chemical elements which act as a flame retardant when electronic equipment is operated. In general, the concept of recycling electronic plastic waste should be considered in order to protect the environment. For this purpose, research has been conducted to different resins of electronic plastic waste to identify the potential of electronic plastic waste as a source of raw material and energy recovery. This study was divided into two part for example determination of physical and chemical characteristics of plastic resins and calculation of heating value for plastic resins based on Dulong formula. Results of this research show that the average calorific value of electronic waste is 30,872.42 kJ/ kg (7,375 kcal/ kg). The emission factor analysis showed that the concentration of emission value that might occur during waste management activities is below the standard set by the Environment Quality Act 1974. Basically, this research shows that electronic plastic waste has the potential to become the source of raw material and energy recovery. (author)

Textural development and hydrogen adsorption of carbon materials from PET waste

Energy Technology Data Exchange (ETDEWEB)

Parra, J.B.; Ania, C.O.; Arenillas, A.; Rubiera, F.; Palacios, J.M.; Pis, J.J

2004-10-06

Polyethyleneterephthalate (PET) has become one of the major post-consumer plastic wastes. PET products present a problem of considerable concern due to the huge amount of solid waste produced. The disposal of this waste, together with its low bio- and photo-degradability represents a serious challenge for industrial countries all over the world. Pyrolysis could provide an alternative and economically viable route for processing PET waste due to the potential uses of different by-products: energy from the pyrolysis gases (58% yield in this work), recovery of terephthalic acid and other subproducts (20%), and a solid residue (22%), which has shown a high textural development after activation. The pyrolysis of PET waste was performed in a quartz reactor (i.d. 35 mm) under an inert atmosphere. Further activation was carried out at a temperature of 925 deg. C, with a flow rate of 10 ml min{sup -1} of CO{sub 2}. A series of carbon materials with different burn-off degrees was obtained. Textural characterisation of the samples was carried out by performing N{sub 2} adsorption isotherms at -196 deg. C. Changes in the morphological and structural properties of chars were studied by scanning electron microscopy (SEM) and X-ray diffraction (XRD). The carbons obtained were isotropic and highly microporous materials with apparent BET surface areas of up to 2500 m{sup 2} g{sup -1}. The suitability of the samples for hydrogen storage was studied by performing H{sub 2} adsorption measurements in the 0-1 bar pressure range. Adsorption-desorption experiments showed that reversible physisorption takes place in all the samples. The hydrogen adsorption capacities of the activated PET waste compare favourably well with those attained with high-value carbon materials.

Chemotoxic materials in a final repository for high-level radioactive wastes. CHEMOTOX concept for defence in depth concerning ground water protection from chemotoxic materials in a final high-level waste repository

International Nuclear Information System (INIS)

Alt, Stefan; Sailer, Michael; Schmidt, Gerhard; Herbert, Horst-Juergen; Krone, Juergen; Tholen, Marion

2009-01-01

The disposal of high-level radioactive wastes in a final repository includes chemotoxic materials. The chemotoxic materials are either part of the radioactive material or part of the packaging material, or the structures within the repository. In the frame of the licensing procedure it has to be demonstrated that no hazardous pollution of the ground water or other disadvantageous changes can occur. The report describes the common project of the Oeko-Institut e.V., the DBE Technology GmbH and the GRS mbH concerning the possible demonstration of a systematic protection of the groundwater against chemotoxic materials in case of a final high-level-radioactive waste repository in the host materials salt and clay stone.

Standard practice for prediction of the long-term behavior of materials, including waste forms, used in engineered barrier systems (EBS) for geological disposal of high-level radioactive waste

CERN Document Server

American Society for Testing and Materials. Philadelphia

2007-01-01

1.1 This practice describes test methods and data analyses used to develop models for the prediction of the long-term behavior of materials, such as engineered barrier system (EBS) materials and waste forms, used in the geologic disposal of spent nuclear fuel (SNF) and other high-level nuclear waste in a geologic repository. The alteration behavior of waste form and EBS materials is important because it affects the retention of radionuclides by the disposal system. The waste form and EBS materials provide a barrier to release either directly (as in the case of waste forms in which the radionuclides are initially immobilized), or indirectly (as in the case of containment materials that restrict the ingress of groundwater or the egress of radionuclides that are released as the waste forms and EBS materials degrade). 1.1.1 Steps involved in making such predictions include problem definition, testing, modeling, and model confirmation. 1.1.2 The predictions are based on models derived from theoretical considerat...

Preliminary concepts: materials management in an internationally safeguarded nuclear-waste geologic repository

International Nuclear Information System (INIS)

Ostenak, C.A.; Whitty, W.J.; Dietz, R.J.

1979-11-01

Preliminary concepts of materials accountability are presented for an internationally safeguarded nuclear-waste geologic repository. A hypothetical reference repository that receives nuclear waste for emplacement in a geologic medium serves to illustrate specific safeguards concepts. Nuclear wastes received at the reference repository derive from prior fuel-cycle operations. Alternative safeguards techniques ranging from item accounting to nondestructive assay and waste characteristics that affect the necessary level of safeguards are examined. Downgrading of safeguards prior to shipment to the repository is recommended whenever possible. The point in the waste cycle where international safeguards may be terminate depends on the fissile content, feasibility of separation, and practicable recoverability of the waste: termination may not be possible if spent fuels are declared as waste

Waste management, waste resource facilities and waste conversion processes

International Nuclear Information System (INIS)

Demirbas, Ayhan

2011-01-01

In this study, waste management concept, waste management system, biomass and bio-waste resources, waste classification, and waste management methods have been reviewed. Waste management is the collection, transport, processing, recycling or disposal, and monitoring of waste materials. A typical waste management system comprises collection, transportation, pre-treatment, processing, and final abatement of residues. The waste management system consists of the whole set of activities related to handling, treating, disposing or recycling the waste materials. General classification of wastes is difficult. Some of the most common sources of wastes are as follows: domestic wastes, commercial wastes, ashes, animal wastes, biomedical wastes, construction wastes, industrial solid wastes, sewer, biodegradable wastes, non-biodegradable wastes, and hazardous wastes.

Characterization of the material produced using marble waste and reagents aiminig production of rock wool

International Nuclear Information System (INIS)

Rodrigues, Girley Ferreira; Espinosa, Denise Crocce Romano; Tenorio, Jorge Alberto Soares; Alves, Joner Oliveira

2010-01-01

The aim of this work was to characterize materials produced from the mixture of marble waste and chemical reagents. The materials were homogenized, melted and cooled in order to obtain materials with similar characteristics of rock wools. The batch was poured in a water-filled recipient and also in a Herty viscometer at three temperatures. Samples of produced materials were characterized by X-ray diffraction, scanning electron microscopy and differential thermal analysis. Results of this study indicate that it is possible the incorporation of marble waste in the production process of rock wool, replacing approximately 15% of the raw material used to fabricate this material. This process represents a technological breakthrough since it allows the reuse of marble waste, and also represents a possible decrease in rock wool production cost, which is a material with a growing market as thermo acoustic insulator. (author)

1-Amine-1,2,3-triazolium salts with oxidizing anions: A new family of energetic materials with good performance

Science.gov (United States)

Zhang, Zhi-Bin; Zhang, Jian-Guo

2018-04-01

A series of 1-amino-1,2,3-triazole (ATZ) based energetic nitrogen-rich salts are prepared by using acid-base neutralization reaction (1:1 M ratio), and fully characterized. Structures of the salts are recrystallized and determined by single-crystal X-ray diffraction, which dominated by a strong hydrogen-bond influence with the densities ranging from 1.692 to 1.868 g cm-3. Thermal behaviors have characterized by using the DSC and TG-DTG technologies. The enthalpies of formation have calculated by using Gaussian 03. The detonation parameters of the salts are determined by using the K-J method, and most salts show promising detonation performances (D: 6699-8231 m s-1, P: 19.2-30.7 GPa), among which the salt of 1-amino-1,2,3-triazolium trinitrophloroglucinate has a detonation properties comparable to RDX. The sensitivities results provided the salts as insensitive energetic materials.

DOE materials program supporting immobilization of radioactive wastes

International Nuclear Information System (INIS)

Oertel, G.K.; Scheib, W.S. Jr.

1979-01-01

A summary is presented of the DOE program for developing waste-form criteria, immobilization processes, and generation and evaluation of performance characterization data. Interrelationships are discussed among repository design, materials requirements, immobilization process definition, quality assurance, and risk analysis as part of the National Environmental Policy Act and regulatory processes

Institute of Energy and Climate Research IEK-6. Nuclear waste management report 2013/2014. Material science for nuclear waste management

Energy Technology Data Exchange (ETDEWEB)

Neumeier, S.; Klinkenberg, M.; Bosbach, D. (eds.)

2016-07-01

This is the third bi-annual report of the Nuclear Waste Management section of the Institute of Energy and Climate Research (IEK-6) at Forschungszentrum Juelich since 2009 - almost a tradition. Our institute has seen two more years with exciting scientific work, but also major changes regarding nuclear energy in Germany and beyond. After the reactor accident in Fukushima (Japan) in 2011, it was decided in Germany to phase out electricity production by nuclear energy by 2022. It seems clear, that the decommissioning of the nuclear power plants will take several decades. The German nuclear waste repository Konrad for radioactive waste with negligible heat generation (all low level and some of the intermediate level radioactive waste) will start operation in the next decade. The new site selection act from 2013 re-defines the selection procedure for the German high level nuclear waste repository. Independently of the decision to stop electricity production by nuclear energy, Germany has to manage and ultimately dispose of its nuclear waste in a safe way. Our basic and applied research for the safe management of nuclear waste is focused on radiochemistry and materials chemistry aspects - it is focused on the behaviour of radionuclides and radioactive waste materials within the back-end of the nuclear fuel cycle. Itis organized in four areas: (1) research supporting the scientific basis of the safety case of a deep geological repository for high level nuclear waste, (2) fundamental structure research of radionuclide containing (waste) materials (3) R and D for waste management concepts for special nuclear wastes and (4) international safeguards. A number of excellent scientific results have been published in more than 80 papers in international peer-reviewed scientific journals in 2013 - 2014. Here, I would like to mention four selected scientific highlights - more can be found in this report: (1) The retention of radionuclides within a nuclear waste repository system by

Institute of Energy and Climate Research IEK-6. Nuclear waste management report 2013/2014. Material science for nuclear waste management