Hanford's self-assessment of the solid waste forecast process

International Nuclear Information System (INIS)

Hauth, J.; Skumanich, M.; Morgan, J.

1996-01-01

In fiscal year (FY) 1995 the forecast process used at Hanford to project future solid waste volumes was evaluated. Data on current and future solid waste generation are used by Hanford site planners to determine near-term and long-term planning needs. Generators who plan to ship their waste to Hanford's Solid Waste Program for treatment, storage, and disposal provide volume information on the types of waste that could be potentially generated, waste characteristics, and container types. Generators also provide limited radionuclide data and supporting assumptions. A self-assessment of the forecast process identified many effective working elements, including a well-established and systematic process for data collection, analysis and reporting; sufficient resources to obtain the necessary information; and dedicated support and analytic staff. Several areas for improvement were identified, including the need to improve confidence in the forecast data, integrate forecast data with other site-level and national data calls, enhance the electronic data collection system, and streamline the forecast process

Problems in shallow land disposal of solid low-level radioactive waste in the united states

Science.gov (United States)

Stevens, P.R.; DeBuchananne, G.D.

1976-01-01

Disposal of solid low-level wastes containing radionuclides by burial in shallow trenches was initiated during World War II at several sites as a method of protecting personnel from radiation and isolating the radionuclides from the hydrosphere and biosphere. Today, there are 11 principal shallow-land burial sites in the United States that contain a total of more than 1.4 million cubic meters of solid wastes contaminated with a wide variety of radionuclides. Criteria for burial sites have been few and generalized and have contained only minimal hydrogeologic considerations. Waste-management practices have included the burial of small quantities of long-lived radionuclides with large volumes of wastes contaminated with shorter-lived nuclides at the same site, thereby requiring an assurance of extremely long-time containment for the entire disposal site. Studies at 4 of the 11 sites have documented the migration of radionuclides. Other sites are being studied for evidence of containment failure. Conditions at the 4 sites are summarized. In each documented instance of containment failure, ground water has probably been the medium of transport. Migrating radionuclides that have been identified include90Sr,137Cs,106Ru,239Pu,125Sb,60Co, and3H. Shallow land burial of solid wastes containing radionuclides can be a viable practice only if a specific site satisfies adequate hydrogeologic criteria. Suggested hydrogeologic criteria and the types of hydrogeologic data necessary for an adequate evaluation of proposed burial sites are given. It is mandatory that a concomitant inventory and classification be made of the longevity, and the physical and chemical form of the waste nuclides to be buried, in order that the anticipated waste types can be matched to the containment capability of the proposed sites. Ongoing field investigations at existing sites will provide data needed to improve containment at these sites and help develop hydrogeologic criteria for new sites. These

Consequence ranking of radionuclides in Hanford tank waste

International Nuclear Information System (INIS)

Schmittroth, F.A.; De Lorenzo, T.H.

1995-09-01

Radionuclides in the Hanford tank waste are ranked relative to their consequences for the Low-Level Tank Waste program. The ranking identifies key radionuclides where further study is merited. In addition to potential consequences for intrude and drinking-water scenarios supporting low-level waste activities, a ranking based on shielding criteria is provided. The radionuclide production inventories are based on a new and independent ORIGEN2 calculation representing the operation of all Hanford single-pass reactors and the N Reactor

Assessment of environmental impact models in natural occurring radionuclides solid wastes disposal from the mineral industry

International Nuclear Information System (INIS)

Pontedeiro, Elizabeth May Braga Dulley

2006-07-01

This work evaluates the behavior of wastes with naturally occurring radionuclides as generated by the mineral industry and their final disposal in landfills. An integrated methodology is used to predict the performance of an industrial landfill for disposal of wastes containing NORM/TENORM, and to define acceptable amounts that can be disposed at the landfill using long-term environmental assessment. The governing equations for radionuclide transport are solved analytically using the generalized integral transform technique. Results obtained for each compartment of the biogeosphere are validated with experimental results or compared to other classes of solutions. An impact analysis is performed in order to define the potential consequences of a landfill to the environment, considering not only the engineering characteristics of the waste deposit but also the exposure pathways and plausible scenarios in which the contaminants could migrate and reach the environment and the human population. The present work permits the development of a safety approach that can be used to derive quantitative waste acceptance criteria for the disposal of NORM/TENORM waste in landfills. (author)

Storing solid radioactive wastes at the Savannah River Plant

International Nuclear Information System (INIS)

Horton, J.H.; Corey, J.C.

1976-06-01

The facilities and the operation of solid radioactive waste storage at the Savannah River Plant (SRP) are discussed in the report. The procedures used to segregate and the methods used to store radioactive waste materials are described, and the monitoring results obtained from studies of the movement of radionuclides from buried wastes at SRP are summarized. The solid radioactive waste storage site, centrally located on the 192,000-acre SRP reservation, was established in 1952 to 1953, before any radioactivity was generated onsite. The site is used for storage and burial of solid radioactive waste, for storage of contaminated equipment, and for miscellaneous other operations. The solid radioactive waste storage site is divided into sections for burying waste materials of specified types and radioactivity levels, such as transuranium (TRU) alpha waste, low-level waste (primarily beta-gamma), and high-level waste (primarily beta-gamma). Detailed records are kept of the burial location of each shipment of waste. With the attention currently given to monitoring and controlling migration, the solid wastes can remain safely in their present location for as long as is necessary for a national policy to be established for their eventual disposal. Migration of transuranium, activation product, and fission product nuclides from the buried wastes has been negligible. However, monitoring data indicate that tritium is migrating from the solid waste emplacements. Because of the low movement rate of ground water, the dose-to-man projection is less than 0.02 man-rem for the inventory of tritium in the burial trenches. Limits are placed on the amounts of beta-gamma waste that can be stored so that the site will require minimum surveillance and control. The major portion (approximately 98 percent) of the transuranium alpha radioactivity in the waste is stored in durable containers, which are amenable to recovery for processing and restorage should national policy so dictate

Solid waste

International Nuclear Information System (INIS)

1995-01-01

The article drawn up within the framework of 'the assessment of the state of the environment in Lebanon' provides an overview of solid waste management, and assesses future wastes volume and waste disposal issues.In particular it addresses the following concerns: - Long term projections of solid waste arisings (i.e. domestic, industrial, such commercial wastes, vehicle types, construction waste, waste oils, hazardous toxic wastes and finally hospital and clinical wastes) are described. - Appropriate disposal routes, and strategies for reducing volumes for final disposal - Balance between municipal and industrial solid waste generation and disposal/treatment and - environmental impacts (aesthetics, human health, natural environment )of existing dumps, and the potential impact of government plans for construction of solid waste facilities). Possible policies for institutional reform within the waste management sector are proposed. Tables provides estimations of generation rates and distribution of wastes in different regions of Lebanon. Laws related to solid waste management are summarized

Performance assessment for continuing and future operations at solid waste storage area 6. Appendices

International Nuclear Information System (INIS)

1997-09-01

This appendix provides the radionuclide inventory data used for the Solid Waste Storage Area (SWSA) 6 Performance Assessment (PA). The uncertainties in the radionuclide inventory data are also provided, along with the descriptions of the methods used to estimate the uncertainties. of the methods used to estimate the uncertainties

Evaluation of radionuclide concentrations in high-level radioactive wastes

International Nuclear Information System (INIS)

Fehringer, D.J.

1985-10-01

This report describes a possible approach for development of a numerical definition of the term ''high-level radioactive waste.'' Five wastes are identified which are recognized as being high-level wastes under current, non-numerical definitions. The constituents of these wastes are examined and the most hazardous component radionuclides are identified. This report suggests that other wastes with similar concentrations of these radionuclides could also be defined as high-level wastes. 15 refs., 9 figs., 4 tabs

Solid waste containing method and solid waste container

International Nuclear Information System (INIS)

Sawai, Takeshi.

1997-01-01

Solid wastes are filled in a sealed vessel, and support spacers are inserted to the gap between the inner wall of a vessel main body and the solid wastes. The solid wastes comprise shorn pieces (crushed pieces) of spent fuel rod cladding tubes, radioactively contaminated metal pieces and miscellaneous solids pressed into a disk-like shape. The sealed vessel comprises, for example, a stainless steel. The solid wastes are filled while being stacked in a plurality of stages. A solidifying filler is filled into the gap between the inner wall and the solid wastes in the vessel main body by way of an upper opening, and the upper opening is closed by a closing lid to provide an entirely sealed state. Alumina particles having high heat conductivity and excellent heat durability are used for the solid filler. It is preferable to fill an inert gas such as a dried nitrogen gas in the sealed vessel. (I.N.)

Identification of key radionuclides in a nuclear waste repository in basalt

International Nuclear Information System (INIS)

Barney, G.S.; Wood, B.J.

1980-05-01

Radionuclides were identified which appear to pose the greatest potential hazard to man during long-term storage of nuclear waste in a repository mined in the Columbia Plateau basalt formation. The criteria used to select key radionuclides were as follows: quantity of radionuclide in stored waste; biological toxicity; leach rate of the wastes into groundwater; and transport rate via groundwater flow. The waste forms were assumed to be either unreprocessed spent fuel or borosilicate glass containing reprocessed high-level waste. The nuclear waste composition was assumed to be that from a light water reactor. Radionuclides were ranked according to quantity, toxicity, and release rate from the repository. These rankings were combined to obtain a single list of key radionuclides. The ten most important radionuclides in order of decreasing hazard are: 99 Tc, 129 I, 237 Np, 226 Ra, 107 Pd, 230 Th, 210 Pb, 126 Sn, 79 Se, and 242 Pu. Safety assessment studies and the design of engineered barriers should concentrate on containment of radionuclides in this list

Solid waste management

OpenAIRE

Srebrenkoska, Vineta; Golomeova, Saska; Zhezhova, Silvana

2013-01-01

Waste is unwanted or useless materials from households, industry, agriculture, hospitals. Waste materials in solid state are classified as solid waste. Increasing of the amount of solid waste and the pressure what it has on the environment, impose the need to introduce sustainable solid waste management. Advanced sustainable solid waste management involves several activities at a higher level of final disposal of the waste management hierarchy. Minimal use of material and energy resources ...

Regulation Concepts for Clearance Level of Radionuclide in Solid Materials

International Nuclear Information System (INIS)

Nanang Triagung Edi Hermawan

2008-01-01

Practices of nuclear energy have expanded in some fields such as researches and development, educations, agricultures, medicines and industries. Every practice beside give much benefit, could generate residue or waste. Radioactive waste needs management to ensure the safety of workers, member of the public, and for the eternal of environment. The product of radioactive waste management, in generally, is some containment of radionuclide concentration in solid matrix material after immobilization or conditioning process. Some kind of processed radioactive wastes with short half live then decay faster to stabile condition. The decay will reach clearance level in sometimes, so from the radiation protection views is harmless. This materials above didn’t need control and must be cleared from all determinate and regulation aspects of radioactive material practices. There is clearance for harmless material off course will be simplify management task and efficiency of money. So the regulation about clearance levels will be important as law basic for technical practices in field. (author)

Chemical durability of slag produced by thermal plasma melting of low-level miscellaneous solid wastes. Effects of slag composition

International Nuclear Information System (INIS)

Amakawa, Tadashi; Yasui, Shinji

2001-01-01

Low-level radioactive miscellaneous solid wastes are generated from commercial operation of nuclear power plants and will be generated from decommissioning of nuclear power plants in future. Static leaching tests were carried out in deionized water of 10degC on slag obtained by thermal plasma melting of simulating materials of the miscellaneous solids wastes with surrogate elements of radionuclides. It is found that logarithm of normalized elemental mass loss from the slag is proportional to the basicity represented by mole fractions of main structural oxides of the slag, such as SiO 2 , Al 2 O 3 , CaO, FeO and MgO. The range of static leaching rates from the slag is determined based on the above results and the basicity range of the miscellaneous solid wastes. Then we compared the leaching rates form the slag and from high level waste glasses. On these grounds, we concluded that the slag obtained by thermal plasma melting of miscellaneous solid wastes can stabilize radio-nuclides in it by no means inferior to the high level waste glasses. (author)

Hydrology of the solid waste burial ground as related to potential migration of radionuclides, Idaho National Engineering Laboratory

Science.gov (United States)

Barraclough, Jack T.; Robertson, J.B.; Janzer, V.J.; Saindon, L.G.

1976-01-01

A study was made (1970-1974) to evaluate the geohydrologic and geochemical controls on subsurface migration of radionuclides from pits and trenches in the Idaho National Engineering Laboratory (INEL) solid waste burial ground and to determine the existence and extent of radionuclide migration from the burial ground. A total of about 1,700 sediment, rock, and water samples were collected from 10 observation wells drilled in and near the burial ground of Idaho National Engineering Laboratory, formerly the National Reactor Testing Station (NRTS). Within the burial ground area, the subsurface rocks are composed principally of basalt. Wind- and water-deposited sediments occur at the surface and in beds between the thicker basalt zones. Two principal sediment beds occur at about 110 feet and 240 feet below the land surface. The average thickness of the surficial sedimentary layer is about 15 feet while that of the two principal subsurface layers is 13 and 14 feet, respectively. The water table in the aquifer beneath the burial ground is at a depth of about 580 feet. Fission, activation, and transuranic elements were detected in some of the samples from the 110- and 240-foot sedimentary layers. (Woodard-USGS)

Ecological vectors of radionuclide transport at a solid radioactive waste disposal facility in southeastern Idaho

International Nuclear Information System (INIS)

Arthur, W.J.; Markham, O.D.

1983-01-01

Radioecological research conducted at the Idaho National Engineering Laboratory Subsurface Disposal Area (SDA) has estimated the quantity of radionuclides transported by various ecosystem components and evaluated the impact of subsurface disposal of radioactive waste on biotic species inhabiting the area. Radiation dose rates received by small mammals ranged from 0.4 to 41790 mrad/day. Small mammal soil burrowing was an upward transport mechanism for transuranic radionuclides. Seventy-seven uCi of radioactivity occurred in SDA vegetation annually. None of these ecological vectors contributed appreciable quantities of radioactive contamination to the environment surrounding the SDA

Solid radioactive waste: evaluation of residual activity in nuclear medicine services

International Nuclear Information System (INIS)

Alabarse, Frederico G.; Xavier, Ana M.; Magalhaes, Maisa H.; Guerrero, Jesus S.P.

2009-01-01

An experimental programme to estimate, with a better degree of accuracy, the activity that remains adsorbed in flasks and syringes used in Nuclear Medicine Services for the administration of radionuclides to patients submitted to diagnostic or therapy is been conducted under the coordination of the Radioactive Waste Division of the Brazilian Nuclear Energy Commission, CNEN. The adopted recommendation in Brazil to allow an expedite solid waste management in nuclear medicine facilities, up to the present, is to consider that 2% of the initial activity remains adsorbed in the solid waste, which easily allows the calculation of the storage time to achieve regulatory clearance levels by decay. This research evaluates 17 different kinds of radiopharmaceuticals and three radioisotopes: 99m Tc, 67 Ga and 201 Tl. Results obtained by means of a weighting method to estimate the residual mass in flasks show that the ratio of the mass of the liquid that remains in the solid waste to the mass of the empty flask is constant. This suggests that the residual activity depends on the initial activity concentration of radiopharmaceutical contained in each flask, as assumed by the regulatory body. Additionally, results obtained by determining the remaining activity in flasks, shortly after the injection of its radionuclide contents in patients, indicate that an average value for the residual activity of the order of 10% of the initial activity contained in the flasks or syringes should be adopted to determine the decay storage time before the release of solid waste in the urban conventional land fill disposal system. The 'rule of thumb' of 10 half-lives for storage before clearance is also discussed in the present work. (author)

Radionuclide concentrations in raw and purified phosphoric acids from Brazil and their processing wastes: implications for radiation exposures.

Science.gov (United States)

da Conceição, Fabiano Tomazini; Antunes, Maria Lúcia Pereira; Durrant, Steven F

2012-02-01

Radionuclides from the U and Th natural series are present in alkaline rocks, which are used as feedstock in Brazil for the production of raw phosphoric acid, which can be considered as a NORM (naturally occurring radioactive material). As a result of the purification of raw phosphoric acid to food-grade phosphoric acid, two by-products are generated, i.e., solid and liquid wastes. Taking this into account, the main aim of this study was to evaluate the fluxes of natural radionuclide in the production of food-grade phosphoric acids in Brazil, to determine the radiological impact caused by ingestion of food-grade phosphoric acid, and to evaluate the solid waste environmental hazards caused by its application in crop soils. Radiological characterization of raw phosphoric acid, food-grade phosphoric acid, solid waste, and liquid waste was performed by alpha and gamma spectrometry. The (238)U, (234)U, (226)Ra, and (232)Th activity concentrations varied depending on the source of raw phosphoric acid. Decreasing radionuclides activity concentrations in raw phosphoric acids used by the producer of the purified phosphoric acid were observed as follows: Tapira (raw phosphoric acid D) > Catalão (raw phosphoric acids B and C) > Cajati (raw phosphoric acid A). The industrial purification process produces a reduction in radionuclide activity concentrations in food-grade phosphoric acid in relation to raw phosphoric acid produced in plant D and single raw phosphoric acid used in recent years. The most common use of food-grade phosphoric acid is in cola soft drinks, with an average consumption in Brazil of 72 l per person per year. Each liter of cola soft drink contains 0.5 ml of food-grade phosphoric acid, which gives an annual average intake of 36 ml of food-grade phosphoric acid per person. Under these conditions, radionuclide intake through consumption of food-grade phosphoric acid per year per person via cola soft drinks is not hazardous to human health in Brazil

Uptake by plants of radionuclides from FUSRAP waste materials

International Nuclear Information System (INIS)

Knight, M.J.

1983-04-01

Radionuclides from FUSRAP wastes potentially may be taken up by plants during remedial action activities and permanent near-surface burial of contaminated materials. In order to better understand the propensity of radionuclides to accumulate in plant tissue, soil and plant factors influencing the uptake and accumulation of radionuclides by plants are reviewed. In addition, data describing the uptake of the principal radionuclides present in FUSRAP wastes (uranium-238, thorium-230, radium-226, lead-210, and polonium-210) are summarized. All five radionuclides can accumulate in plant root tissue to some extent, and there is potential for the translocation and accumulation of these radionuclides in plant shoot tissue. Of these five radionuclides, radium-226 appears to have the greatest potential for translocation and accumulation in plant shoot tissue. 28 references, 1 figure, 3 tables

Uptake by plants of radionuclides from FUSRAP waste materials

Energy Technology Data Exchange (ETDEWEB)

Knight, M.J.

1983-04-01

Radionuclides from FUSRAP wastes potentially may be taken up by plants during remedial action activities and permanent near-surface burial of contaminated materials. In order to better understand the propensity of radionuclides to accumulate in plant tissue, soil and plant factors influencing the uptake and accumulation of radionuclides by plants are reviewed. In addition, data describing the uptake of the principal radionuclides present in FUSRAP wastes (uranium-238, thorium-230, radium-226, lead-210, and polonium-210) are summarized. All five radionuclides can accumulate in plant root tissue to some extent, and there is potential for the translocation and accumulation of these radionuclides in plant shoot tissue. Of these five radionuclides, radium-226 appears to have the greatest potential for translocation and accumulation in plant shoot tissue. 28 references, 1 figure, 3 tables.

Hydrologic transport of radionuclides from low-level waste burial grounds

International Nuclear Information System (INIS)

Duguid, J.O.

1979-01-01

The physical characteristics of the virgin site and of the disturbed site after burial drastically affect the transport of radionuclides from buried waste. The disturbance of the land surface during the waste burial operation causes changes in the local ground-water regimen. These changes can increase the water table elevation and cause the occurrence of perched water in burial trenches. The combination of these changes may lead to submersion of the waste and to increased radionuclide transport from the burial site in both surface and groundwater. Factors such as ion exchange can retard or in some cases, with competing ions, can also mobilize radionuclides and increase their discharge into ground and surface water. Because of complexing agents (organics) contained in the waste, increased mobility of some radionuclides can be expected. The chemical form of radionuclides in the water, the ground-water quality, and the chemistry of the geologic formation in which the waste is buried all influence the movement of radionuclides in the hydrologic system. For the assessment of the environmental impact of low-level waste burial, models capable of simulating both the chemical and the physical factors that affect hydrologic transport must be available. Several models for conducting such simulation are presently available. However, the input parameters used in these models are highly variable; and the accuracy of parameter measurement must be considered in evaluating the reliability of simulated results

Significance of radiation effects in solid radioactive waste

International Nuclear Information System (INIS)

Permar, P.H.; McDonell, W.R.

1980-01-01

Proposed NRC criteria for disposal of high-level nuclear waste require development of waste packages to contain radionuclide for at least 1000 years, and design of repositories to prevent radionuclide release at an annual rate greater than 1 part in 100,000 of the total activity. The high-level wastes that are now temporarily stored as aqueous salts, sludges, and calcines must be converted to high-integrity solid forms that resist deterioration from radiation and other effects of long-term storage. Spent fuel may be encapsulated for similar long-term storage. Candidate waste forms beside the spent fuel elements themselves, include borosilicate and related glasses, mineral-like crystalline ceramics, concrete formulations, and metal-matrix glass or ceramic composites. these waste forms will sustain damage produced by beta-gamma radiation up to 10 12 rads, by alpha radiation up to 10 19 particles/g, by internal helium generation greater than about 0.1 atom percent, and by the atom transmutations accompanying radioactive decay. Current data indicate that under these conditions the glass forms suffer only minor volume changes, stored energy deposition, and leachability effects. The crystalline ceramics appear susceptible to the potentially more severe alterations accompanying metamictization and natural analogs of candidate materials are being examined to establish their suitability as waste forms. Helium concentrations in the waste forms are generally below thresholds for severe damage in either glass or crystalline ceramics at low temperatures, but microstructural effects are not well characterized. Transmutation effects remain to be established

Effects of radionuclide decay on waste glass behavior: A critical review

International Nuclear Information System (INIS)

Wronkiewicz, D.J.

1993-12-01

This paper is an extension of a chapter in an earlier report [1] that provides an updated review on the status of radiation damage problems in nuclear waste glasses. This report will focus on radiation effects on vitrified borosilicate nuclear waste glasses under conditions expected in the proposed Yucca mountain repository. Radiation effects on high-level waste glasses and their surrounding repository environment are important considerations for radionuclide immobilization because of the potential to alter the glass stability and thereby influence the radionuclide retentive properties of this waste form. The influence of radionuclide decay on vitrified nuclear waste may be manifested by several changes, including volume, stored energy, structure, microstructure, mechanical properties, and phase separation. Radiation may also affect the composition of aqueous fluids and atmospheric gases in relatively close proximity to the waste form. What is important to the radionuclide retentive properties of the repository is how these radiation effects collectively or individually influence the durability and radionuclide release from the glass in the event of liquid water contact

Hydrologic transport of radionuclides from low-level waste burial grounds

International Nuclear Information System (INIS)

Duguid, J.O.

1977-01-01

The physical characteristics of the virgin site and of the disturbed site after burial drastically affect the transport of radionuclides from buried waste. The disturbance of the land surface during the waste burial operation causes changes in the local ground-water regimen. These changes can increase the water table elevation and cause the occurrence of perched water in burial trenches. The combination of these changes may lead to submersion of the waste and to increased radionuclide transport from the burial site in both surface and ground water. Factors such as ion exchange can retard or in some cases, with competing ions, can also mobilize radionuclides and increase their discharge into ground and surface water. Because of complexing agents (organics) contained in the waste, increased mobility of some radionuclides can be expected. The chemical form of radionuclides in the water, the ground-water quality, and the chemistry of the geologic formation in which the waste is buried all influence the movement of radionuclides in the hydrologic system. For the assessment of the environmental impact of low-level waste burial, models capable of simulating both the chemical and the physical factors that affect hydrologic transport must be available. Several models for conducting such simulation are presently available. However,the input parameters used in these models are highly variable, and the accuracy of parameter measurement must be considered in evaluating the reliability of simulated results

Radionuclide - Soil Organic Matter Interactions

DEFF Research Database (Denmark)

Carlsen, Lars

1985-01-01

Interactions between soil organic matter, i.e. humic and fulvic acids, and radionuclides of primary interest to shallow land burial of low activity solid waste have been reviewed and to some extent studied experimentally. The radionuclides considered in the present study comprise cesium, strontium...

Estimates of the solubilities of waste element radionuclides in waste isolation pilot plant brines: A report by the expert panel on the source term

International Nuclear Information System (INIS)

Hobart, D.E.; Bruton, C.J.; Trauth, K.M.; Anderson, D.R.

1996-05-01

Evaluation of the long-term performance of the WIPP includes estimation of the cumulative releases of radionuclide elements to the accessible environment. Nonradioactive lead is added because of the large quantity expected in WIPP wastes. To estimate the solubilities of these elements in WIPP brines, the Panel used the following approach. Existing thermodynamic data were used to identify the most likely aqueous species in solution through the construction of aqueous speciation diagrams. Existing thermodynamic data and expert judgment were used to identify potential solubility-limiting solid phases. Thermodynamic data were used to calculate the activities of the radionuclide aqueous species in equilibrium with each solid. Activity coefficients of the radionuclide-bearing aqueous species were estimated using Pitzer's equations. These activity coefficients were then used to calculate the concentration of each radionuclide at the 0.1 and 0.9 fractiles. The 0.5 fractile was chosen to represent experimental data with activity coefficient corrections as described above. Expert judgment was used to develop the 0.0, 0.25, 0.75, and 1.0 fractiles by considering the sensitivity of solubility to the potential variability in the composition of brine and gas, and the extent of waste contaminants, and extending the probability distributions accordingly. The results were used in the 1991 and 1992 performance assessment calculations. 68 refs

Estimates of the solubilities of waste element radionuclides in waste isolation pilot plant brines: A report by the expert panel on the source term

Energy Technology Data Exchange (ETDEWEB)

Hobart, D.E. [Sandia National Labs., Albuquerque, NM (United States)]|[Glenn T. Seaborg Inst. for Transactinium Science, Livermore, CA (United States); Bruton, C.J. [Sandia National Labs., Albuquerque, NM (United States)]|[Lawrence Livermore National Lab., CA (United States). Earth Sciences Dept.; Millero, F.J. [Sandia National Labs., Albuquerque, NM (United States)]|[Univ. of Miami, FL (United States). Rosenstiel School of Marine and Atmospheric Science; Chou, I.M. [Sandia National Labs., Albuquerque, NM (United States)]|[Geological Survey, Reston, VA (United States); Trauth, K.M.; Anderson, D.R. [Sandia National Labs., Albuquerque, NM (United States)

1996-05-01

Evaluation of the long-term performance of the WIPP includes estimation of the cumulative releases of radionuclide elements to the accessible environment. Nonradioactive lead is added because of the large quantity expected in WIPP wastes. To estimate the solubilities of these elements in WIPP brines, the Panel used the following approach. Existing thermodynamic data were used to identify the most likely aqueous species in solution through the construction of aqueous speciation diagrams. Existing thermodynamic data and expert judgment were used to identify potential solubility-limiting solid phases. Thermodynamic data were used to calculate the activities of the radionuclide aqueous species in equilibrium with each solid. Activity coefficients of the radionuclide-bearing aqueous species were estimated using Pitzer`s equations. These activity coefficients were then used to calculate the concentration of each radionuclide at the 0.1 and 0.9 fractiles. The 0.5 fractile was chosen to represent experimental data with activity coefficient corrections as described above. Expert judgment was used to develop the 0.0, 0.25, 0.75, and 1.0 fractiles by considering the sensitivity of solubility to the potential variability in the composition of brine and gas, and the extent of waste contaminants, and extending the probability distributions accordingly. The results were used in the 1991 and 1992 performance assessment calculations. 68 refs.

Effects of sorption hysteresis on radionuclide releases from waste packages

International Nuclear Information System (INIS)

Barney, G.S.; Reed, D.T.

1985-01-01

A one-dimensional, numerical transport model was used to calculate radionuclide releases from waste packages emplaced in a nuclear waste repository in basalt. The model incorporates both sorption and desorption isotherm parameters measured previously for sorption of key radionuclides on the packing material component of the waste package. Sorption hysteresis as described by these isotherms lowered releases of some radionuclides by as much as two orders of magnitude. Radionuclides that have low molar inventories (relative to uranium), high solubility, and strongly sorbed, are most affected by sorption hysteresis. In these cases, almost the entire radionuclide inventory is sorbed on the packing material. The model can be used to help optimize the thickness of the packing material layer by comparing release rate versus packing material thickness curves with Nuclear Regulatory Commission (NRC) and Environmental Protection Agency (EPA) release limits

Removal of radionuclides from the water-soluble fraction of Hanford nuclear defense wastes

International Nuclear Information System (INIS)

Strachan, D.M.; Schulz, W.W.

1980-01-01

The current Hanford Waste Management Program has operated since 1968 to remove the bulk of the long-lived heat emitters /sup 90/Sr and /sup 137/Cs from stored high-level wastes. The liquid waste remaining after removal of /sup 90/Sr and /sup 137/Cs is returned to underground tanks for eventual evaporation to damp solid salt cake. Approximately 95,000 m/sup 3/ of salt cake and 49,000 m/sup 3/ of ''sludge'' will eventually accumulate in approximately 50 underground single-shell tanks. One alternative for long-term management of high-level Hanford wastes involves retrieval, after a yet-to-be determined interim storage time, conversion to more immobile forms, and terminal storage in a suitable geologic repository. Another alternative for long-term management of salt cake and residual liquid involves removing most of the long-lived radionuclides and many of the shorter-lived ones from these wastes. This paper describes conditions and results of recent hot cell tests of the complete Hanford Radionuclide Removal Process. These advanced tests, made with actual residual liquid containing large concentrations of ethylenediaminetetracetic acid (EDTA) and other organic compounds, provided a rigorous and convincing proof of the process flowsheet. 16 refs

Theoretical approach in optimization of stability of the multicomponent solid waste form

International Nuclear Information System (INIS)

Raicevic, S.; Plecas, I.; Mandic, M.

1998-01-01

Chemical precipitation of radionuclides and their immobilization into the solid matrix represents an important approach in the radioactive wastewater treatment. Unfortunately, because of the complexity of the system, optimization of this process in terms of its efficacy and safety represents a serious practical problem, even in treatment of the monocomponent nuclear waste. This situation is additionally complicated in the case of the polycomponent nuclear waste because of the synergic effects of interactions between the radioactive components and the solid matrix. Recently, we have proposed a general theoretical approach for optimization of the process of precipitation and immobilization of metal impurities by the solid matrix. One of the main advantages of this approach represents the possibility of treatment of the multicomponent liquid waste, immobilized by the solid matrix. This approach was used here for investigation of the stability of the system hydroxyapatite (HAP) - Pb/Cd, which was selected as a model multicomponent waste system. In this analysis, we have used a structurally dependent term of the cohesive energy as a stability criterion. (author)

FY 1996 solid waste integrated life-cycle forecast characteristics summary. Volumes 1 and 2

Energy Technology Data Exchange (ETDEWEB)

Templeton, K.J.

1996-05-23

For the past six years, a waste volume forecast has been collected annually from onsite and offsite generators that currently ship or are planning to ship solid waste to the Westinghouse Hanford Company`s Central Waste Complex (CWC). This document provides a description of the physical waste forms, hazardous waste constituents, and radionuclides of the waste expected to be shipped to the CWC from 1996 through the remaining life cycle of the Hanford Site (assumed to extend to 2070). In previous years, forecast data has been reported for a 30-year time period; however, the life-cycle approach was adopted this year to maintain consistency with FY 1996 Multi-Year Program Plans. This document is a companion report to two previous reports: the more detailed report on waste volumes, WHC-EP-0900, FY1996 Solid Waste Integrated Life-Cycle Forecast Volume Summary and the report on expected containers, WHC-EP-0903, FY1996 Solid Waste Integrated Life-Cycle Forecast Container Summary. All three documents are based on data gathered during the FY 1995 data call and verified as of January, 1996. These documents are intended to be used in conjunction with other solid waste planning documents as references for short and long-term planning of the WHC Solid Waste Disposal Division`s treatment, storage, and disposal activities over the next several decades. This document focuses on two main characteristics: the physical waste forms and hazardous waste constituents of low-level mixed waste (LLMW) and transuranic waste (both non-mixed and mixed) (TRU(M)). The major generators for each waste category and waste characteristic are also discussed. The characteristics of low-level waste (LLW) are described in Appendix A. In addition, information on radionuclides present in the waste is provided in Appendix B. The FY 1996 forecast data indicate that about 100,900 cubic meters of LLMW and TRU(M) waste is expected to be received at the CWC over the remaining life cycle of the site. Based on

FY 1996 solid waste integrated life-cycle forecast characteristics summary. Volumes 1 and 2

International Nuclear Information System (INIS)

Templeton, K.J.

1996-01-01

For the past six years, a waste volume forecast has been collected annually from onsite and offsite generators that currently ship or are planning to ship solid waste to the Westinghouse Hanford Company's Central Waste Complex (CWC). This document provides a description of the physical waste forms, hazardous waste constituents, and radionuclides of the waste expected to be shipped to the CWC from 1996 through the remaining life cycle of the Hanford Site (assumed to extend to 2070). In previous years, forecast data has been reported for a 30-year time period; however, the life-cycle approach was adopted this year to maintain consistency with FY 1996 Multi-Year Program Plans. This document is a companion report to two previous reports: the more detailed report on waste volumes, WHC-EP-0900, FY1996 Solid Waste Integrated Life-Cycle Forecast Volume Summary and the report on expected containers, WHC-EP-0903, FY1996 Solid Waste Integrated Life-Cycle Forecast Container Summary. All three documents are based on data gathered during the FY 1995 data call and verified as of January, 1996. These documents are intended to be used in conjunction with other solid waste planning documents as references for short and long-term planning of the WHC Solid Waste Disposal Division's treatment, storage, and disposal activities over the next several decades. This document focuses on two main characteristics: the physical waste forms and hazardous waste constituents of low-level mixed waste (LLMW) and transuranic waste (both non-mixed and mixed) (TRU(M)). The major generators for each waste category and waste characteristic are also discussed. The characteristics of low-level waste (LLW) are described in Appendix A. In addition, information on radionuclides present in the waste is provided in Appendix B. The FY 1996 forecast data indicate that about 100,900 cubic meters of LLMW and TRU(M) waste is expected to be received at the CWC over the remaining life cycle of the site. Based on

Removal and recovery of radionuclides and toxic metals from wastes, soils and materials

International Nuclear Information System (INIS)

Francis, A.J.

1993-07-01

A process has been developed at Brookhaven National Laboratory (BNL) for the removal of metals and radionuclides from contaminated materials, soils, and waste sites (Figure 1). In this process, citric acid, a naturally occurring organic complexing agent, is used to extract metals such as Ba, Cd, Cr, Ni, Zn, and radionuclides Co, Sr, Th, and U from solid wastes by formation of water soluble, metal-citrate complexes. Citric acid forms different types of complexes with the transition metals and actinides, and may involve formation of a bidentate, tridentate, binuclear, or polynuclear complex species. The extract containing radionuclide/metal complex is then subjected to microbiological degradation followed by photochemical degradation under aerobic conditions. Several metal citrate complexes are biodegraded and the metals are recovered in a concentrated form with the bacterial biomass. Uranium forms binuclear complex with citric acid and is not biodegraded. The supernatant containing uranium citrate complex is separated and upon exposure to light, undergoes rapid degradation resulting in the formation of an insoluble, stable polymeric form of uranium. Uranium is recovered as a precipitate (uranium trioxide) in a concentrated form for recycling or for appropriate disposal. This treatment process, unlike others which use caustic reagents, does not create additional hazardous wastes for disposal and causes little damage to soil which can then be returned to normal use

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

International Nuclear Information System (INIS)

Brown, D.F.

1994-01-01

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

Selected radionuclides important to low-level radioactive waste management

International Nuclear Information System (INIS)

1996-11-01

The purpose of this document is to provide information to state representatives and developers of low level radioactive waste (LLW) management facilities about the radiological, chemical, and physical characteristics of selected radionuclides and their behavior in the environment. Extensive surveys of available literature provided information for this report. Certain radionuclides may contribute significantly to the dose estimated during a radiological performance assessment analysis of an LLW disposal facility. Among these are the radionuclides listed in Title 10 of the Code of Federal Regulations Part 61.55, Tables 1 and 2 (including alpha emitting transuranics with half-lives greater than 5 years). This report discusses these radionuclides and other radionuclides that may be significant during a radiological performance assessment analysis of an LLW disposal facility. This report not only includes essential information on each radionuclide, but also incorporates waste and disposal information on the radionuclide, and behavior of the radionuclide in the environment and in the human body. Radionuclides addressed in this document include technetium-99, carbon-14, iodine-129, tritium, cesium-137, strontium-90, nickel-59, plutonium-241, nickel-63, niobium-94, cobalt-60, curium -42, americium-241, uranium-238, and neptunium-237

Selected radionuclides important to low-level radioactive waste management

Energy Technology Data Exchange (ETDEWEB)

NONE

1996-11-01

The purpose of this document is to provide information to state representatives and developers of low level radioactive waste (LLW) management facilities about the radiological, chemical, and physical characteristics of selected radionuclides and their behavior in the environment. Extensive surveys of available literature provided information for this report. Certain radionuclides may contribute significantly to the dose estimated during a radiological performance assessment analysis of an LLW disposal facility. Among these are the radionuclides listed in Title 10 of the Code of Federal Regulations Part 61.55, Tables 1 and 2 (including alpha emitting transuranics with half-lives greater than 5 years). This report discusses these radionuclides and other radionuclides that may be significant during a radiological performance assessment analysis of an LLW disposal facility. This report not only includes essential information on each radionuclide, but also incorporates waste and disposal information on the radionuclide, and behavior of the radionuclide in the environment and in the human body. Radionuclides addressed in this document include technetium-99, carbon-14, iodine-129, tritium, cesium-137, strontium-90, nickel-59, plutonium-241, nickel-63, niobium-94, cobalt-60, curium -42, americium-241, uranium-238, and neptunium-237.

The radionuclide content of radioactive wastes

International Nuclear Information System (INIS)

1988-06-01

This report presents the radionuclide content of stocks and arisings of radioactive wastes in the United Kingdom. Operational and decommissioning wastes are considered for both committed and prospective plant. Arisings are from power reactors, commercial reprocessing, fuel manufacture, medical and industrial sources and research and development. Data is included from Amersham International, British Nuclear Fuels, Central Electricity Generating Board, South of Scotland Electricity Board, United Kingdom Atomic Energy Authority and minor waste producers. (author)

Assessment of waste management of volatile radionuclides

International Nuclear Information System (INIS)

Altomare, P.M.; Barbier, M.; Lord, N.; Nainan, D.

1979-05-01

This document presents a review of the Technologies for Waste Management of the Volatile Radionuclides of iodine-129, krypton-85, tritium, and carbon-14. The report presents an estimate of the quantities of these volatile radionuclides as are produced in the nuclear power industry. The various technologies as may be used, or which are under investigation, to immobilize these nuclides and to contain them during storage and in disposal are discussed. Also, the alternative disposal options as may be applied to isolate these radioactive wastes from the human environment are presented. The report contains information which was available through approximately January 1978

Characterization of the near-surface radionuclide contamination associated with the bathtub effect at Solid Waste Storage Area 4, Oak Ridge National Laboratory, Tennessee

International Nuclear Information System (INIS)

Melroy, L.A.; Huff, D.D.; Farrow, N.D.

1986-06-01

Solid Waste Storage Area 4 (SWSA-4) at the Oak Ridge National Laboratory (ORNL) was studied to determine the extent of near-surface radionuclide contamination associated with the bathtub effect in low-lying trenches. A surface survey of the low-elevation portion of the burial ground was conducted to identify areas where the bathtub effect had resulted in surface contamination. Using this initial survey as a guide, 15 soil cores, each approximately 3 m deep, were taken to determine the depth to which contamination had spread and to help identify an contamination plumes. Results showed that two areas of surface radionuclide contamination exist, one located between the western end of the SWSA-4 tributary and the edge of the burial ground, the other located just north of the tributary below the central paved runoff channel. In addition, some downward migration of the solutes has occurred. However, the penetration depth for 90 Sr seems to be generally less than 2.7 m

Multibarrier system preventing migration of radionuclides from radioactive waste repository

Directory of Open Access Journals (Sweden)

Olszewska Wioleta

2015-09-01

Full Text Available Safety of radioactive waste repositories operation is associated with a multibarrier system designed and constructed to isolate and contain the waste from the biosphere. Each of radioactive waste repositories is equipped with system of barriers, which reduces the possibility of release of radionuclides from the storage site. Safety systems may differ from each other depending on the type of repository. They consist of the natural geological barrier provided by host rocks of the repository and its surroundings, and an engineered barrier system (EBS. The EBS may itself comprise a variety of sub-systems or components, such as waste forms, canisters, buffers, backfills, seals and plugs. The EBS plays a major role in providing the required disposal system performance. It is assumed that the metal canisters and system of barriers adequately isolate waste from the biosphere. The evaluation of the multibarrier system is carried out after detailed tests to determine its parameters, and after analysis including mathematical modeling of migration of contaminants. To provide an assurance of safety of radioactive waste repository multibarrier system, detailed long term safety assessments are developed. Usually they comprise modeling of EBS stability, corrosion rate and radionuclide migration in near field in geosphere and biosphere. The principal goal of radionuclide migration modeling is assessment of the radionuclides release paths and rate from the repository, radionuclides concentration in geosphere in time and human exposure to ionizing radiation

Direct measurement of γ-emitting radionuclides in waste drum

International Nuclear Information System (INIS)

Ma Ruwei; Mao Yong; Zhang Xiuzhen; Xia Xiaobin; Guo Caiping; Han Yueqin

1993-01-01

The low-level rad waste produced from nuclear power plant, nuclear facilities, and in the process of their decommissioning is stored in waste depository. For the safety of transport and storage of these wastes, some test must be done. One of them is to analyse the kinds and activities of radionuclides in each waste drum. Segmented scanning gamma spectrum analysis can be used for direct measurement of gamma-emitting radionuclides in drum. Gamma emitters such as Co-60, Cs-137, Ra-226 can be measured directly from outside of drum. A method and system for direct measuring gamma emitters in waste drum are described, and measuring apparatus and measurement results as well

Selective separation of radionuclides from nuclear waste solutions with inorganic ion exchangers

International Nuclear Information System (INIS)

Lehto, J.; Harjula, R.

1999-01-01

Nuclear industry produces and stores large volumes of radioactive waste solutions. Removal of radionuclides from the solutions is an important and challenging task for two main reasons: reductions in the volumes of solidified waste, which have to be disposed of, and reductions in the radioactive discharges into the environment. Since the radioactive elements in most waste solutions are in trace concentrations and the waste solutions contain large excesses of inactive metal ions, highly selective separation methods are needed for the removal of radionuclides. A number of inorganic ion exchange materials are very selective to key radionuclides and they can play an important role in solving these problems. The spectrum of nuclear waste solutions is rather wide considering their radionuclide contents, concentrations of interfering salts and acidity/alkalinity. Therefore, several inorganic ions exchangers are needed for the removal of most harmful radionuclides from a variety of solutions. This paper discusses the use and requirements of inorganic ion exchange materials in nuclear waste management. Special attention is paid to the novel ion exchange materials developed in the Laboratory of Radiochemistry, University of Helsinki. (orig.)

Assessment of solid low-level waste management at the Savannah River Plant

International Nuclear Information System (INIS)

Fenimore, J.W.; Hooker, R.L.

1977-08-01

Site description, facilities, operating practices, and assessment of solid low-level waste management at the Savannah River Plant are covered. The following recommendations are made. Programs to reduce the volume of waste generated at the source should be continued. Planning to utilize volume reduction by compaction and/or incineration should be continued and adopted when practical technology is available. Utilization of grading and ditching to reduce water infiltration into trenches and to control erosion should be continued. Burial ground studies should be continued to: measure Kd's of all important radionuclides in burial ground sediments; measure hydraulic conductivities in disturbed backfill and underlying undisturbed sediments at sufficient locations to give a statistically significant sampling; and measure water flow rates better, so that individual radionuclide rates can be computed

Radionuclide distributions in sediments of marine areas used for dumping solidified radioactive wastes

International Nuclear Information System (INIS)

Bowen, V.T.; Livingston, H.D.

A number of sediment samples, collected both by coring and by grabbing, from the shallow Pacific solid waste radioactive dump site and from the Atlantic dump site, have been analyzed carefully for a number of long-lived radionuclides. Both dump sites yielded samples that were expected to serve as controls, collected at considerable distance from any visually-located waste containers, as well as other samples that were collected close to identified waste drums, some of which showed evidence of physical disintegration. The Atlantic site shows evidence of wide-spread, general contamination, with 137 Cs and possibly with 241 Am. The Pacific site is perhaps less generally contaminated with 137 Cs, but shows evidence of widespread general contamination with several transuranic nuclides. Samples collected near to identified waste containers, at both sites, show that significant portions of leached radioactivity ( 137 Cs, 239 240 Pu, 238 Pu, 241 Am, 242 Cm, and 244 Cm) are immobilized by the sediments within very short distances, possibly measured in meters or tens of meters. The data also suggest considerable differences among the horizontal trajectories of the various leached transuranic elements. It is argued that careful study of nuclide distributions around such old waste containers would provide data of great value in helping to predict long-term behavior of radionuclides released to marine environments

Prediction of radionuclide inventory for the low-and intermediated-level radioactive waste disposal facility the radioactive waste classification

International Nuclear Information System (INIS)

Jung, Kang Il; Jeong, Noh Gyeom; Moon, Young Pyo; Jeong, Mi Seon; Park, Jin Beak

2016-01-01

To meet nuclear regulatory requirements, more than 95% individual radionuclides in the low- and intermediate-level radioactive waste inventory have to be identified. In this study, the radionuclide inventory has been estimated by taking the long-term radioactive waste generation, the development plan of disposal facility, and the new radioactive waste classification into account. The state of radioactive waste cumulated from 2014 was analyzed for various radioactive sources and future prospects for predicting the long-term radioactive waste generation. The predicted radionuclide inventory results are expected to contribute to secure the development of waste disposal facility and to deploy the safety case for its long-term safety assessment

Criteria of reference radionuclides for safety analysis of spent fuel waste disposal

International Nuclear Information System (INIS)

Suryanto

1998-01-01

Study on the criteria for reference radionuclides selection for assessment on spent fuel disposal have done. The reference radionuclides in this study means radionuclides are predicted to contribute of the most radiological effect for man if spent fuel waste are discharged on deep geology formation. The research was done by investigate critically of parameters were used on evaluation a kind of radionuclide. Especially, this research study of parameter which relevant disposal case and or spent fuel waste on deep geology formation . The research assumed that spent fuel discharged on deep geology by depth 500-1000 meters from surface of the land. The migration scenario Radionuclides from waste form to man was assumed particularly for normal release in which Radionuclides discharge from waste form in a series thorough container, buffer, geological, rock, to fracture(fault) and move together with ground water go to biosphere and than go into human body. On this scenario, the parameter such as radionuclides inventory, half life, heat generation, hazard index based on maximum permissible concentration (MPC) or annual limit on intake (ALI) was developed as criteria of reference radionuclides selection. The research concluded that radionuclides inventory, half live, heat generated, hazard index base on MPC or ALI can be used as criteria for selection of reference Radionuclide. The research obtained that the main radionuclides are predicted give the most radiological effect to human are as Cs-137, Sr-90, I-129, Am-243, Cm-244, Pu-238, Pu-239, Pu-240. The radionuclides reasonable to be used as reference radionuclides in safety analysis at spent fuel disposal. (author)

Volume reduction technology development for solid wastes from the nuclear fuel cycle

International Nuclear Information System (INIS)

Oh, Won Zin; Lee, Kune Woo; Song, Kee Chan; Choi, Wang Kyu; Kim, Young Min

1998-07-01

A great deal of solid wastes, which have various physical, chemical, and radiological characteristics, are generated from the nuclear fuel cycle facility as well as radioactive gaseous and liquid wastes. The treatment of the large quantity of solid wastes from the nuclear fuel cycle have great technical, economical and social effects on the domestic policy decision on the nuclear fuel cycle, such as operation and maintenance of the facility, waste disposal, etc. Cement immobilization, super compaction, and electrochemical dissolution were selected as the volume reduction technologies for solid wastes, which will generated from the domestic nuclear fuel cycle facility in the future. And the assessment of annual arisings and the preliminary conceptual design of volume reduction processes were followed. Electrochemical decontamination of α-radionuclides from the spent fuel hulls were experimentally investigated, and showed the successful results. However, β/γ radioactivity did not reduce to the level below which hulls can be classified as the low-level radioactive waste and sent to the disposal site for the shallow land burial. The effects of the various process variables in the electrochemical decontamination were experimentally analysed on the process. (author). 32 refs., 32 tabs., 52 figs

Geochemical behavior of disposed radioactive waste

International Nuclear Information System (INIS)

Barney, G.S.; Navratil, J.D.; Schulz, W.W.

1984-01-01

The papers in this book are organized to cover the chemical aspects that are important to understanding the behavior of disposed radioactive wastes. These aspects include radionuclide sorption and desorption, solubility of radionuclide compounds, chemical species of radionuclides in natural waters, hydrothermal geochemical reactions, measurements of radionuclide migration, solid state chemistry of wastes, and waste-form leaching behavior. The information in each of the papers is necessary to predict the transport of radionuclides from wastes via natural waters and thus to predict the safety of the disposed waste. Radionuclide transport in natural waters is strongly dependent on sorption, desorption, dissolution, and precipitation processes. The first two papers discuss laboratory investigations of these processes. Descriptions of sorption and desorption behavior of important radionuclides under a wide range of environmental conditions are presented in the first section. Among the sorbents studied are basalt interbed solids, granites, clays, sediments, hydrous oxides, and pure minerals. Effects of redox conditions, groundwater composition and pH on sorption reactions are described

Utilisation of solid waste

Energy Technology Data Exchange (ETDEWEB)

Balu, K

1978-07-01

The prime solution to the present energy crisis is the recovery of latent energy from waste materials, for solid waste contains recoverable energy and it merely needs to be released. The paper is concerned with classification of solid waste, energy content of waste, methods of solid waste disposal, and chemical processing of solid waste. Waste disposal must be performed in situ with energy recovery. Scarcity of available land, pollution problem, and unrecovered latent energy restrict the use of the land-filling method. Pyrolysis is an effective method for the energy recovery and disposal problems. Chemical processing is suitable for the separated cellulosic fraction of the waste material.

Integrated performance assessment model for waste package behavior and radionuclide release

International Nuclear Information System (INIS)

Kossik, R.; Miller, I.; Cunnane, M.

1992-01-01

Golder Associates Inc. (GAI) has developed a probabilistic total system performance assessment and strategy evaluation model (RIP) which can be applied in an iterative manner to evaluate repository site suitability and guide site characterization. This paper describes one component of the RIP software, the waste package behavior and radionuclide release model. The waste package component model considers waste package failure by various modes, matrix alteration/dissolution, and radionuclide mass transfer. Model parameters can be described as functions of local environmental conditions. The waste package component model is coupled to component models for far-field radionuclide transport and disruptive events. The model has recently been applied to the proposed repository at Yucca Mountain

Radionuclide migration through porous cement-waste composition in semi-real conditions

International Nuclear Information System (INIS)

Plecas, I.; Peric, A.; Kostadinovic, A.

1989-01-01

In this paper, result of examination of Leakage rate or radionuclides Co-60 and Cs-137 in semi-real conditions are given. Radionuclides Co-60 and Cs-137 were immobilized by cement process and conditioned in concrete containers trying to make similar scenario for storing radioactive waste materials as in engineering trench system, repository. Experiments were realized with two waste water, evaporator bottom and reactor cooling system, (EB) and (RCS), from Nuclear Power Plants Krsko, in which the main radionuclides are Co-60 and Cs-137. These results will be used for future Yugoslav radioactive waste storing center (author)

Determining the release of radionuclides from tank waste residual solids. FY2015 report

Energy Technology Data Exchange (ETDEWEB)

King, William D. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL); Hobbs, David T. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL)

2015-09-11

Methodology development for pore water leaching studies has been continued to support Savannah River Site High Level Waste tank closure efforts. For FY2015, the primary goal of this testing was the achievement of target pH and Eh values for pore water solutions representative of local groundwater in the presence of grout or grout-representative (CaCO₃ or FeS) solids as well as waste surrogate solids representative of residual solids expected to be present in a closed tank. For oxidizing conditions representative of a closed tank after aging, a focus was placed on using solid phases believed to be controlling pH and E_h at equilibrium conditions. For three pore water conditions (shown below), the target pH values were achieved to within 0.5 pH units. Tank 18 residual surrogate solids leaching studies were conducted over an E_h range of approximately 630 mV. Significantly higher Eh values were achieved for the oxidizing conditions (ORII and ORIII) than were previously observed. For the ORII condition, the target Eh value was nearly achieved (within 50 mV). However, E_h values observed for the ORIII condition were approximately 160 mV less positive than the target. E_h values observed for the RRII condition were approximately 370 mV less negative than the target. Achievement of more positive and more negative E_h values is believed to require the addition of non-representative oxidants and reductants, respectively. Plutonium and uranium concentrations measured during Tank 18 residual surrogate solids leaching studies under these conditions (shown below) followed the general trends predicted for plutonium and uranium oxide phases, assuming equilibrium with dissolved oxygen. The highest plutonium and uranium concentrations were observed for the ORIII condition and the lowest concentrations were observed for the RRII condition. Based on these results, it is recommended that these test methodologies be used to

Radionuclide Inventories for DOE SNF Waste Stream and Uranium/Thorium Carbide Fuels

International Nuclear Information System (INIS)

K.L. Goluoglu

2000-01-01

The objective of this calculation is to generate radionuclide inventories for the Department of Energy (DOE) spent nuclear fuel (SNF) waste stream destined for disposal at the potential repository at Yucca Mountain. The scope of this calculation is limited to the calculation of two radionuclide inventories; one for all uranium/thorium carbide fuels in the waste stream and one for the entire waste stream. These inventories will provide input in future screening calculations to be performed by Performance Assessment to determine important radionuclides

Classification of solid wastes as non-radioactive wastes

International Nuclear Information System (INIS)

Suzuki, Masahiro; Tomioka, Hideo; Kamike, Kozo; Komatu, Junji

1995-01-01

The radioactive wastes generally include nuclear fuels, materials contaminated with radioactive contaminants or neutron activation to be discarded. The solid wastes arising from the radiation control area in nuclear facilities are used to treat and stored as radioactive solid wastes at the operation of nuclear facilities in Japan. However, these wastes include many non-radioactive wastes. Especially, a large amount of wastes is expected to generate at the decommissioning of nuclear facilities in the near future. It is important to classify these wastes into non-radioactive and radioactive wastes. The exemption or recycling criteria of radioactive solid wastes is under discussion and not decided yet in Japan. Under these circumstances, the Nuclear Safety Committee recently decided the concept on the category of non-radioactive waste for the wastes arising from decommissioning of nuclear facilities. The concept is based on the separation and removal of the radioactively contaminated parts from radioactive solid wastes. The residual parts of these solid wastes will be treated as non-radioactive waste if no significant difference in radioactivity between the similar natural materials and materials removed the radioactive contaminants. The paper describes the procedures of classification of solid wastes as non-radioactive wastes. (author)

LA-ICP-MS for Trace Analysis of Long-Lived Radionuclides in Solid Non-conducting Radioactive Waste Samples

International Nuclear Information System (INIS)

Becker, J.S.; Gastel, M.; Tenzler, D.; Dietze, H.J.

1999-01-01

The characterization of radioactive waste materials from nuclear reactors for recycling and final storage requires fast, sensitive and precise analytical methods, which are able to determine long-lived radionuclidic ultra traces in a short time. For the determination of long-lived α and β ray-emitting nuclides besides the classical radiochemical methods which are mostly include time-consuming radiochemical separation procedures, to an increasing extent inductively coupled plasma mass spectrometry (ICP-MS) has been used successfully as a powerful trace, ultra trace and isotopic analytical method for the determination of long-lived radionuclides in aqueous solutions [1-3

Radionuclide-migration model for buried waste at the Savannah River Plant

International Nuclear Information System (INIS)

King, C.M.; Root, R.W. Jr.

1982-01-01

Solid waste has been buried at the Savannah River Plant burial ground since 1953. The solid waste is contaminated with alpha-emitting transuranium (TRU) nuclides, with beta-gamma-emitting activation and fission products, and with tritium. To provide guidance for the current use and eventual permanent retirement of the burial site from active service, a radionuclide environmental transport model has been used to project the potential influence on man if the burial site were occupied after decommissioning. The model used to simulate nuclide migration includes the various hydrological, animal, vegetative, atmospheric, and terrestrial pathways in estimating dose to man as a function of time. Specific scenarios include a four-person home farm on the 195-acre burial ground. Key input to the model includes site-specific nuclide migration rates through soil, nuclide distribution coefficients, and site topography. Coupled with literature data on plant and animal concentration factors, transfer coefficients reflecting migration routes are input to a set of linear differential equations for subsequent matrix solution. Output from the model is the nuclide-specific decayed curie intake by man. To discern principal migration routes, model-compartment inventories with time can also be displayed. Dose projections subsequently account for organ concentrations in man for the nuclide of interest. Radionuclide migration has been examined in depth with the dose-to-man model. Movement by vegetative pathways is the primary route for potential dose to man for short-lived isotopes. Hydrological routes provide a secondary scheme for long-lived nuclides. Details of model methodology are reviewed

Characterization of 618-11 solid waste burial ground, disposed waste, and description of the waste generating facilities

International Nuclear Information System (INIS)

Hladek, K.L.

1997-01-01

The 618-11 (Wye or 318-11) burial ground received transuranic (TRTJ) and mixed fission solid waste from March 9, 1962, through October 2, 1962. It was then closed for 11 months so additional burial facilities could be added. The burial ground was reopened on September 16, 1963, and continued operating until it was closed permanently on December 31, 1967. The burial ground received wastes from all of the 300 Area radioactive material handling facilities. The purpose of this document is to characterize the 618-11 solid waste burial ground by describing the site, burial practices, the disposed wastes, and the waste generating facilities. This document provides information showing that kilogram quantities of plutonium were disposed to the drum storage units and caissons, making them transuranic (TRU). Also, kilogram quantities of plutonium and other TRU wastes were disposed to the three trenches, which were previously thought to contain non-TRU wastes. The site burial facilities (trenches, caissons, and drum storage units) should be classified as TRU and the site plutonium inventory maintained at five kilograms. Other fissile wastes were also disposed to the site. Additionally, thousands of curies of mixed fission products were also disposed to the trenches, caissons, and drum storage units. Most of the fission products have decayed over several half-lives, and are at more tolerable levels. Of greater concern, because of their release potential, are TRU radionuclides, Pu-238, Pu-240, and Np-237. TRU radionuclides also included slightly enriched 0.95 and 1.25% U-231 from N-Reactor fuel, which add to the fissile content. The 618-11 burial ground is located approximately 100 meters due west of Washington Nuclear Plant No. 2. The burial ground consists of three trenches, approximately 900 feet long, 25 feet deep, and 50 feet wide, running east-west. The trenches constitute 75% of the site area. There are 50 drum storage units (five 55-gallon steel drums welded together

Characterization of 618-11 solid waste burial ground, disposed waste, and description of the waste generating facilities

Energy Technology Data Exchange (ETDEWEB)

Hladek, K.L.

1997-10-07

The 618-11 (Wye or 318-11) burial ground received transuranic (TRTJ) and mixed fission solid waste from March 9, 1962, through October 2, 1962. It was then closed for 11 months so additional burial facilities could be added. The burial ground was reopened on September 16, 1963, and continued operating until it was closed permanently on December 31, 1967. The burial ground received wastes from all of the 300 Area radioactive material handling facilities. The purpose of this document is to characterize the 618-11 solid waste burial ground by describing the site, burial practices, the disposed wastes, and the waste generating facilities. This document provides information showing that kilogram quantities of plutonium were disposed to the drum storage units and caissons, making them transuranic (TRU). Also, kilogram quantities of plutonium and other TRU wastes were disposed to the three trenches, which were previously thought to contain non-TRU wastes. The site burial facilities (trenches, caissons, and drum storage units) should be classified as TRU and the site plutonium inventory maintained at five kilograms. Other fissile wastes were also disposed to the site. Additionally, thousands of curies of mixed fission products were also disposed to the trenches, caissons, and drum storage units. Most of the fission products have decayed over several half-lives, and are at more tolerable levels. Of greater concern, because of their release potential, are TRU radionuclides, Pu-238, Pu-240, and Np-237. TRU radionuclides also included slightly enriched 0.95 and 1.25% U-231 from N-Reactor fuel, which add to the fissile content. The 618-11 burial ground is located approximately 100 meters due west of Washington Nuclear Plant No. 2. The burial ground consists of three trenches, approximately 900 feet long, 25 feet deep, and 50 feet wide, running east-west. The trenches constitute 75% of the site area. There are 50 drum storage units (five 55-gallon steel drums welded together

Management of solid waste

Science.gov (United States)

Thompson, W. T.; Stinton, L. H.

1980-04-01

Compliance with the latest regulatory requirements addressing disposal of radioactive, hazardous, and sanitary solid waste criteria in the selection, design, and operation of solid waste management facilities. Due to the state of flux of these regulatory requirements from EPA and NRC, several waste management options were of solid waste. The current regulatory constraints and the design and operational requirements for construction of both storage and disposal facilities for use in management of DOE-ORO solid waste are highlighted. Capital operational costs are included for both disposal and storage options.

Management of solid wastes

Energy Technology Data Exchange (ETDEWEB)

Williams, D.J. [University of Queensland, St. Lucia, Qld. (Australia). Dept. of Civil Engineering

1996-12-31

This chapter introduces the range of solid waste materials produced in the mining and mineral processing industries, with particular reference to Australia. The waste materials are characterised and their important geotechnical engineering properties are discussed. Disposal management techniques for metalliferous, coal, heavy mineral sand, fly ash and bauxite solid wastes are described. Geo-technical techniques for the management of potential contaminants are presented. Minimisation and utilisation of solid wastes, and the economics of solid waste management, are discussed from the perspectives of policy, planning, costing and rehabilitation. 19 figs., 2 tabs.

National low-level waste management program radionuclide report series, Volume 15: Uranium-238

International Nuclear Information System (INIS)

Adams, J.P.

1995-09-01

This report, Volume 15 of the National Low-Level Waste Management Program Radionuclide Report Series, discusses the radiological and chemical characteristics of uranium-238 ( 238 U). The purpose of the National Low-Level Waste Management Program Radionuclide Report Series is to provide information to state representatives and developers of low-level radioactive waste disposal facilities about the radiological, chemical, and physical characteristics of selected radionuclides and their behavior in the waste disposal facility environment. This report also includes discussions about waste types and forms in which 238 U can be found, and 238 U behavior in the environment and in the human body

Relative contributions of natural and waste-derived organics to the subsurface transport of radionuclides

International Nuclear Information System (INIS)

Toste, A.P.; Myers, R.B.

1985-06-01

Our laboratory is studying the role of organic compounds in the subsurface transport of radionuclides at shallow-land burial sites of low-level nuclear waste, including a commercial site at Maxey Flats, Kentucky, and an aqueous waste disposal site. At the Maxey Flats site, several radionuclides, notably Pu and 60 Co, appear to exist as anionic, organic complexes. Waste-derived organics, particularly chelating agents such as EDTA, HEDTA and associated degradation products (e.g., ED3A), are abundant in aqueous waste leachates and appear to account for the complexation. EDTA, and probably other waste-derived chelating agents as well, are chelated to the Pu and 60 Co in the leachates, potentially mobilizing these radionuclides. In contrast, at the low-level aqueous waste disposal site, naturally-occurring organics, ranging from low molecular weight (MW) acids to high MW humic acids, account for the bulk of the groundwater's organic content. Certain radionuclides, notably 60 Co, 103 Ru and 125 Sb, are mobile as anionic complexes. These radionuclides are clearly associated with higher MW organics, presumably humic and fulvic acids with nominal MW's > 1000. It is clear, therefore, that naturally-occurring organics may play an important role in radionuclide transport, particularly at nuclear waste burial sites containing little in the way of waste-derived organics

New approach and methodology for radionuclide researches of oil industry wastes

International Nuclear Information System (INIS)

Humbatov, F.; Lisanova, E.; Suleymanov, B.; Ahmedov, M.

2005-01-01

/treaters, storage tanks, and any other equipment where produced water is handled. In addition to their radioactive characteristics, NORM wastes also have physical and chemical characteristics.The waste stream going to a disposal cavern consists of accumulated heavy hydrocarbons, paraffins, inorganic solids, and heavy emulsions. In the submitted article are investigated radionuclide structure, radioactivity and parameters characterizing ground waters, which can influence on process of dissolution of minerals, precipitation and accumulation radionuclides. For definition dependence of radioactive pollution on characteristic parameters ground waters we took samples from chinks and oil field lake taking place on territory Surachany region. In each sample are measured a radioactivity, concentration of heavy metals, PH, TDS, sulphate, carbonates, nitrates, chlorine, etc. For concentration of radionuclides in water are usually used of evaporation of a water sample up to certain volume. There is other more effective method - pass the water through MnO2 impregnated fibre. The effective simple way of separation of radioactive substances from volumes of tests of water representing alternative to traditional ways is developed. Concentration of radium isotopes is possible to carry out by precipitation of radium isotopes on a surface of filters or disks, and measurement radioactivity by alpha-spectrometer

Barriers to migration of radionuclides from radioactive waste repositories

International Nuclear Information System (INIS)

Stefanova, I.

1999-01-01

Natural inorganic sorbents are known as effective barriers that reduce the migration of radionuclides from radioactive waste repositories and contaminated sites. They could be used as buffer, backfill and sealing materials in the repository and their presence in the host rock and the surrounding geological formations increases the retention properties of the strata. Natural occurring minerals from local origin are used in the study - zeolites (clinoptilolite and mordenite), celadonite and loess. Sorption of wide range of radionuclides is studies. Batch capacity is determined. Sorption of radionuclides from simulated natural solution is studied. Distribution coefficients are calculated from sorption isotherms. Desorption in presence of different natural solutions is studied. Sorption properties are compared. It is shown that clinoptilolite acts as effective barrier against migration of radionuclides from repositories. The presence of celadonite in the clinoptilolite rock increases the retention of polyvalent ions. The retention of radionuclides on loess samples fulfils the requirements for host media for repository for low and intermediate level waste. A method for construction of additional barrier to the existing in the country disposal vault for spent sealed sources is proposed

Solid waste as an energy source

International Nuclear Information System (INIS)

Armenski, Slave

2004-01-01

The solid wastes as sources of heat and electrical energy were analysed. Typical structure of solid waste and organic products from: municipal solid wastes, industrial wastes and agricultural wastes for some developed countries are presented. Some dates of agricultural wastes for R. Macedonia are presented. The structure and percentage of organic products and energy content of solid wastes are estimated. The quantity of heat from solid wastes depending of the waste mass is presented. The heat quantity of some solid wastes component and the mixed municipal waste is presented. (Original)

Application of two-barrier model of radioactive agent transport in sea water for analyzing artificial radionuclide release from containers with radioactive waste dumped in Kara Sea

Energy Technology Data Exchange (ETDEWEB)

Grishin, Denis S.; Laykin, Andrey I.; Kuchin, Nickolay L.; Platovskikh, Yuri A. [Krylov State Research Center, Saint Petersburg, 44 Moskovskoe shosse, 196158 (Russian Federation)

2014-07-01

Modeling of artificial radionuclide transport in sea water is crucial for prognosis of radioecological situation in regions where dumping of radioactive waste had been made and/or accidents with nuclear submarines had taken place. Distribution of artificial radionuclides in bottom sediments can be a detector of radionuclide release from dumped or sunk objects to marine environment. Proper model can determine the dependence between radionuclide distribution in sediments and radionuclide release. Following report describes two-barrier model of radioactive agent transport in sea water. It was tested on data from 1994 - 2013 expeditions to Novaya Zemlya bays, where regular dumping of solid radioactive waste was practiced by the former USSR from the early 1960's until 1990. Two-barrier model agrees with experimental data and allows more accurate determination of time and intensity of artificial radionuclide release from dumped containers. (authors)

Effect of Concrete Waste Form Properties on Radionuclide Migration

International Nuclear Information System (INIS)

Mattigod, Shas V.; Bovaird, Chase C.; Wellman, Dawn M.; Skinner, De'Chauna J.; Cordova, Elsa A.; Wood, Marcus I.

2009-01-01

Assessing long-term performance of Category 3 waste cement grouts for radionuclide encasement requires knowledge of the radionuclide-cement interactions and mechanisms of retention (i.e., sorption or precipitation) the mechanism of contaminant release, the significance of contaminant release pathways, how waste form performance is affected by the full range of environmental conditions within the disposal facility, the process of waste form aging under conditions that are representative of processes occurring in response to changing environmental conditions within the disposal facility, the effect of waste form aging on chemical, physical, and radiological properties and the associated impact on contaminant release. This knowledge will enable accurate prediction of radionuclide fate when the waste forms come in contact with groundwater. Numerous sets of tests were initiated in fiscal years (FY) 2006-2009 to evaluate (1) diffusion of iodine (I) and technetium (Tc) from concrete into uncontaminated soil after 1 and 2 years, (2) I and rhenium (Re) diffusion from contaminated soil into fractured concrete, (3) I and Re (set 1) and Tc (set 2) diffusion from fractured concrete into uncontaminated soil, (4) evaluate the moisture distribution profile within the sediment half-cell, (5) the reactivity and speciation of uranium (VI) (U(VI)) compounds in concrete porewaters, (6) the rate of dissolution of concrete monoliths, and (7) the diffusion of simulated tank waste into concrete.

Radionuclide release from low-level waste in field lysimeters

International Nuclear Information System (INIS)

Oblath, S.B.

1986-01-01

A field program has been in operation for 8 years at the Savannah River Plant (SRP) to determine the leaching/migration behavior of low-level radioactive waste using lysimeters. The lysimeters are soil-filled caissons containing well characterized wastes, with each lysimeter serving as a model of a shallow land burial trench. Sampling and analysis of percolate water and vegetation from the lysimeters provide a determination of the release rates of the radionuclides from the waste/soil system. Vegetative uptake appears to be a major pathway for migration. Fractional release rates from the waste/soil system are less than 0.01% per year. Waste-to-soil leach rates up to 10% per year have been determined by coring several of the lysimeters. The leaching of solidified wasteforms under unsaturated field conditions has agreed well with static, immersion leaching of the same type waste in the laboratory. However, releases from the waste/soil system in the lysimeter may be greater than predicted based on leaching alone, due to complexation of the radionuclides by other components leached from the wastes to form mobile, anionic species

Integrated performance assessment model for waste policy package behavior and radionuclide release

International Nuclear Information System (INIS)

Kossik, R.; Miller, I.; Cunnane, M.

1992-01-01

Golder Associates Inc. (GAI) has developed a probabilistic total system performance assessment and strategy evaluation model (RIP) which can be applied in an iterative manner to evaluate repository site suitability and guide site characterization. This paper describes one component of the RIP software, the waste package behavior and radionuclide release model. The waste package component model considers waste package failure by various modes, matrix alteration/dissolution, and radionuclide mass transfer. Model parameters can be described as functions of local environmental conditions. The waste package component model is coupled to component models for far-field radionuclide transport and disruptive events. The model has recently been applied to the proposed repository at Yucca Mountain

Management of solid waste

International Nuclear Information System (INIS)

Thompson, W.T.; Stinton, L.H.

1980-01-01

Compliance with the latest regulatory requirements addressing disposal of radioactive, hazardous, and sanitary solid waste requires the application of numerous qualitative and quantitative criteria in the selection, design, and operation of solid waste management facilities. Due to the state of flux of these regulatory requirements from EPA and NRC, several waste management options were identified as being applicable to the management of the various types of solid waste. This paper highlights the current regulatory constraints and the design and operational requirements for construction of both storage and disposal facilities for use in management of DOE-ORO solid waste. Capital and operational costs are included for both disposal and storage options

Management of solid waste

International Nuclear Information System (INIS)

Thompson, W.T.; Stinton, L.H.

1980-01-01

Compliance with the latest regulatory requirements addressing disposal of radioactive, hazardous, and sanitary solid waste requires the application of numerous qualitative and quantitative criteria in the selection, design, and operation of solid waste management facilities. Due to the state of flux of these regulatory requirements from EPA and NRC several waste management options were identified as being applicable to the management of the various types of solid waste. This paper highlights the current regulatory constraints and the design and operational requirements for construction of both storage and disposal facilities for use in management of DOE-ORO solid waste. Capital and operational costs are included for both disposal and storage options

Solid waste management in Malaysia

International Nuclear Information System (INIS)

Nadzri Yahaya

2010-01-01

All of the countries over the world have their own policies about how waste were managed. Malaysia as one of the developing country also faces this problems. So, the government was established Department of National Solid Waste Management under Ministry of Housing and Local Government to control and make sure all of these problem on waste will managed systematically. Guiding principle on these issues was mentioned in 3rd Outline Perspective Plan (2000 until 2010), National Policy on Solid Waste Management, National Strategic Plan on Solid Waste Management and also 10th Malaysian Plan. In 10th Malaysian Plan, the government will complete restructuring efforts in this Solid Waste Management sector with the federalization of solid waste management and public cleansing and full enforcement of the Solid Waste and Public Cleansing Management Act 2007. The key outcomes of these efforts will include providing support to local authorities, delivering comprehensive and sanitary services and ensuring that waste is managed in a sustainable manner. These presentations cover all aspect of solid waste management in Malaysia. What are guiding principle, paradigm shift, strategies approach, monitoring and enforcement and also mention about some issues and constraint that appear in Solid waste management in Malaysia.

The principal radionuclides in high level radioactive waste management

International Nuclear Information System (INIS)

Mulyanto

1998-01-01

The principal radionuclides in high level radioactive waste management. The selection of the principal radionuclides in the high level waste (HLW) management was developed in order to improve the disposal scenario of HLW. In this study the unified criteria for selection of the principal radionuclides were proposed as; (1) the value of hazard index estimated by annual limit of intake (ALI) for long-term tendency,(2) the relative dose factor related to adsorbed migration rate transferred by ground water, and (3) heat generation in the repository. From this study it can be concluded that the principal radionuclides in the HLW management were minor actinide (MA=Np, Am, Cm, etc), Tc, I, Cs and Sr, based on the unified basic criteria introduced in this study. The remaining short-lived fission product (SLFPs), after the selected nuclides are removed, should be immobilized and solidified in a glass matrix. Potential risk due to the remaining SLFPs can be lower than that of uranium ore after about 300 year. (author)

Exhumation test with aged radioactive solid wastes

International Nuclear Information System (INIS)

Horton, J.H.

1977-01-01

The deterioration of solid radioactive waste buried in soil is an important consideration when estimating the migration of radionuclides from the burial site, planning procedures for exhuming buried waste, and evaluating hazards caused by intentional or unintentional uncovering of the waste. This report presents observations during the excavation of low-level waste buried for 14 years in the humid environment of the Savannah River Plant. The radiation dose rates that were used to define the limits for low-level beta-gamma wastes were <50 mR/hr from an unshielded package or <50 mR/hr at 10 feet from a truck load. The waste was buried in sandy clay soil trenches more than 20 feet above the water table and covered with soil soon after burial. Rainfall for the area averages 47 inches per year. Because of the higher water permeability in backfilled soil than in undisturbed soil, perched water was sometimes found in the bottom of some trenches. However, the duration and/or extent of perched water is limited so that most waste is not subjected to water-saturated soil. The waste uncovered included wood, steel, plastics, cotton cloth, rubber, and paper. Cardboard boxes not enclosed in plastic were the only materials that deteriorated visibly. Apparently, decades would be required for all cellulose materials to decompose; plastics, rubber, and metals will probably survive indefinitely

Decontamination of organic wastes containing radionuclides

International Nuclear Information System (INIS)

Unsworth, T.J.; Pimblott, S.M.; Brown, N.W.

2015-01-01

An electrochemical oxidation treatment has been developed by Arvia Technology for organic wastes containing radionuclides, in which GIC-bisulphate is used as an adsorbent and electrode. Significant work has been carried out in the irradiation of graphite for medical and nuclear applications and in the use of carbonaceous adsorbents but knowledge of the applicability of graphite intercalation compounds (GICs) in these roles is limited. This project will attempt to fill this gap. It will investigate the suitability of GIC-bisulphate as an adsorbent in an electrochemical treatment process for radioactive organic liquids. The process was initially used to treat waste-water from non-nuclear operations and now requires technical knowledge and research to adapt the treatment for the nuclear industry. Adsorption processes involving organic wastes containing mobile radionuclides such as 137 Cs are difficult to understand. The effects of gamma radiation on the chemistry of water and organics could complicate the treatment process further. To ensure the suitability and effectiveness of the electrochemical oxidation treatment for radioactive organic wastes, the following effects are being investigated: -) radiolytic degradation of GIC-bisulphate in solution, -) leaching of intercalated ions due to gamma radiation, -) effect of gamma radiation on the adsorption of organics by GIC-bisulphate, -) changes in the sorption behaviour of radioactive contaminants, -) distribution coefficients of contaminants in organic and aqueous phases, and -) selective or competitive adsorption on graphite surface sites

Characterization of Discharge Areas of Radionuclides Originating From Nuclear Waste Repositories

Science.gov (United States)

Marklund, L.; Xu, S.; Worman, A.

2009-05-01

If leakages in nuclear waste repositories located in crystalline bedrock arise, radionuclides will reach the biosphere and cause a risk of radiological impact. The extent of the radiological impact depends on in which landscape elements the radionuclides emerge. In this study, we investigate if there are certain landscape elements that generally will act as discharge areas for radionuclides leaking from subsurface deposits. We also characterize the typical properties that distinguish these areas from others. In humid regions, landscape topography is the most important driving force for groundwater flow. Because groundwater is the main transporting agent for migrating radionuclides, the topography will determine the flowpaths of leaking radionuclides. How topography and heterogeneities in the subsurface affect the discharge distribution of the radionuclides is therefore an important scope of this study. To address these issues, we developed a 3-D transport model. Our analyses are based on site-specific data from two different areas in Sweden, Forsmark, Uppland, and Oskarshamn, Småland. The Swedish Nuclear Waste Management Company (SKB) has selected these two areas as candidate areas for a deep repository of nuclear waste and the areas are currently subject to site investigations. Our results suggest that there are hot-spots in the landscape i.e. areas with high probability of receiving large amounts of radionuclides from a leaking repository of nuclear waste. The hot-spots concentrate in the sea, streams, lakes and wetlands. All these elements are found at lower elevations in the landscape. This pattern is mostly determined by the landscape topography and the locations of fracture zones. There is a relationship between fracture zones and topography, and therefore the importance of the topography for the discharge area distribution is not contradicted by the heterogeneity in the bedrock. The varieties of landscape elements which have potential for receiving

Development of a separatif microsystem for radionuclides analysis in nitric acid media

OpenAIRE

Losno , Marion

2017-01-01

Radionuclides analysis is a key point for nuclear waste management and nuclear material control. Several steps of sample modification have to be carried out before measurements in order to avoid any interferences and improve measurement precision. However those different steps are long, irradiant and difficult to achieve in gloveboxes. Moreover they produce liquid and solid waste. The goal of the study is to offer a new alternative to the use of solid phase extraction column for radionuclides...

National Low-Level Waste Management Program Radionuclide Report Series

International Nuclear Information System (INIS)

Rudin, M.J.; Garcia, R.S.

1992-02-01

This report, Volume 3 of the National Low-Level Radioactive Waste Management Program Radionuclide Report Series, discusses the radiological and chemical characteristics of carbon-14. The report also discusses waste streams that contain carbon-14, waste forms that contain carbon-14, and carbon-14 behavior in the environment and in the human body

Airborne radionuclide waste-management reference document

International Nuclear Information System (INIS)

Brown, R.A.; Christian, J.D.; Thomas, T.R.

1983-07-01

This report provides the detailed data required to develop a strategy for airborne radioactive waste management by the Department of Energy (DOE). The airborne radioactive materials of primary concern are tritium (H-3), carbon-14 (C-14), krypton-85 (Kr-85), iodine-129 (I-129), and radioactive particulate matter. The introductory section of the report describes the nature and broad objectives of airborne waste management. The relationship of airborne waste management to other waste management programs is described. The scope of the strategy is defined by considering all potential sources of airborne radionuclides and technologies available for their management. Responsibilities of the regulatory agencies are discussed. Section 2 of this document deals primarily with projected inventories, potential releases, and dose commitments of the principal airborne wastes from the light water reactor (LWR) fuel cycle. In Section 3, dose commitments, technologies, costs, regulations, and waste management criteria are analyzed. Section 4 defines goals and objectives for airborne waste management

National Low-Level Waste Management Program Radionuclide Report Series

International Nuclear Information System (INIS)

Rudin, M.J.; Stanton, C.; Patterson, R.G.; Garcia, R.S.

1992-02-01

This report, Volume 2 of the National Low-Level Radioactive Waste Management Program Radionuclide Report Series, discusses radiological and chemical characteristics of technetium-99. This report also includes discussions about waste streams in which technetium-99 can be found, waste forms that contain technetium-99, and technetium-99's behavior in the environment and in the human body

Characterization of the solid low level mixed waste inventory for the solid waste thermal treatment activity - III

Energy Technology Data Exchange (ETDEWEB)

Place, B.G., Westinghouse Hanford

1996-09-24

The existing thermally treatable, radioactive mixed waste inventory is characterized to support implementation of the commercial, 1214 thermal treatment contract. The existing thermally treatable waste inventory has been identified using a decision matrix developed by Josephson et al. (1996). Similar to earlier waste characterization reports (Place 1993 and 1994), hazardous materials, radionuclides, physical properties, and waste container data are statistically analyzed. In addition, the waste inventory data is analyzed to correlate waste constituent data that are important to the implementation of the commercial thermal treatment contract for obtaining permits and for process design. The specific waste parameters, which were analyzed, include the following: ``dose equivalent`` curie content, polychlorinated biphenyl (PCB) content, identification of containers with PA-related mobile radionuclides (14C, 12 79Se, 99Tc, and U isotopes), tritium content, debris and non-debris content, container free liquid content, fissile isotope content, identification of dangerous waste codes, asbestos containers, high mercury containers, beryllium dust containers, lead containers, overall waste quantities, analysis of container types, and an estimate of the waste compositional split based on the thermal treatment contractor`s proposed process. A qualitative description of the thermally treatable mixed waste inventory is also provided.

Pacific Northwest Laboratory's Solid Waste Initiative

International Nuclear Information System (INIS)

Holter, G.M.

1993-09-01

In fiscal year 1992 (FY-92), a Solid Waste Initiative was undertaken within the Pacific Northwest Laboratory (PNL). This action was partly in response to a perceived increase in the frequency and severity of impacts associated with solid waste issues at all levels. It also recognized the limited attention of previous efforts in addressing the broader impacts resulting from solid waste and, thus, dealing with solid waste issues in a holistic fashion. This paper provides a description of the Solid Waste Initiative at PNL, including a historical perspective on PNL's involvement in solid waste issues, the goals and objectives of the Solid Waste Initiative, and a discussion of selected activities being conducted under the Initiative

Operating limit study for the proposed solid waste landfill at Paducah Gaseous Diffusion Plant

Energy Technology Data Exchange (ETDEWEB)

Lee, D.W.; Wang, J.C.; Kocher, D.C.

1995-06-01

A proposed solid waste landfill at Paducah Gaseous Diffusion Plant (PGDP) would accept wastes generated during normal operations that are identified as non-radioactive. These wastes may include small amounts of radioactive material from incidental contamination during plant operations. A site-specific analysis of the new solid waste landfill is presented to determine a proposed operating limit that will allow for waste disposal operations to occur such that protection of public health and the environment from the presence of incidentally contaminated waste materials can be assured. Performance objectives for disposal were defined from existing regulatory guidance to establish reasonable dose limits for protection of public health and the environment. Waste concentration limits were determined consistent with these performance objectives for the protection of off-site individuals and inadvertent intruders who might be directly exposed to disposed wastes. Exposures of off-site individuals were estimated using a conservative, site-specific model of the groundwater transport of contamination from the wastes. Direct intrusion was analyzed using an agricultural homesteader scenario. The most limiting concentrations from direct intrusion or groundwater transport were used to establish the concentration limits for radionuclides likely to be present in PGDP wastes.

Operating limit study for the proposed solid waste landfill at Paducah Gaseous Diffusion Plant

International Nuclear Information System (INIS)

Lee, D.W.; Wang, J.C.; Kocher, D.C.

1995-06-01

A proposed solid waste landfill at Paducah Gaseous Diffusion Plant (PGDP) would accept wastes generated during normal operations that are identified as non-radioactive. These wastes may include small amounts of radioactive material from incidental contamination during plant operations. A site-specific analysis of the new solid waste landfill is presented to determine a proposed operating limit that will allow for waste disposal operations to occur such that protection of public health and the environment from the presence of incidentally contaminated waste materials can be assured. Performance objectives for disposal were defined from existing regulatory guidance to establish reasonable dose limits for protection of public health and the environment. Waste concentration limits were determined consistent with these performance objectives for the protection of off-site individuals and inadvertent intruders who might be directly exposed to disposed wastes. Exposures of off-site individuals were estimated using a conservative, site-specific model of the groundwater transport of contamination from the wastes. Direct intrusion was analyzed using an agricultural homesteader scenario. The most limiting concentrations from direct intrusion or groundwater transport were used to establish the concentration limits for radionuclides likely to be present in PGDP wastes

Waste Form and Indrift Colloids-Associated Radionuclide Concentrations: Abstraction and Summary

International Nuclear Information System (INIS)

Aguilar, R.

2003-01-01

This Model Report describes the analysis and abstractions of the colloids process model for the waste form and engineered barrier system components of the total system performance assessment calculations to be performed with the Total System Performance Assessment-License Application model. Included in this report is a description of (1) the types and concentrations of colloids that could be generated in the waste package from degradation of waste forms and the corrosion of the waste package materials, (2) types and concentrations of colloids produced from the steel components of the repository and their potential role in radionuclide transport, and (3) types and concentrations of colloids present in natural waters in the vicinity of Yucca Mountain. Additionally, attachment/detachment characteristics and mechanisms of colloids anticipated in the repository are addressed and discussed. The abstraction of the process model is intended to capture the most important characteristics of radionuclide-colloid behavior for use in predicting the potential impact of colloid-facilitated radionuclide transport on repository performance

Waste Form and Indrift Colloids-Associated Radionuclide Concentrations: Abstraction and Summary

Energy Technology Data Exchange (ETDEWEB)

R. Aguilar

2003-06-24

This Model Report describes the analysis and abstractions of the colloids process model for the waste form and engineered barrier system components of the total system performance assessment calculations to be performed with the Total System Performance Assessment-License Application model. Included in this report is a description of (1) the types and concentrations of colloids that could be generated in the waste package from degradation of waste forms and the corrosion of the waste package materials, (2) types and concentrations of colloids produced from the steel components of the repository and their potential role in radionuclide transport, and (3) types and concentrations of colloids present in natural waters in the vicinity of Yucca Mountain. Additionally, attachment/detachment characteristics and mechanisms of colloids anticipated in the repository are addressed and discussed. The abstraction of the process model is intended to capture the most important characteristics of radionuclide-colloid behavior for use in predicting the potential impact of colloid-facilitated radionuclide transport on repository performance.

Solid waste management: an overview

International Nuclear Information System (INIS)

Ayoub, G.M.

1995-01-01

The source, effect and characterization of solid wastes are discussed. Constituents of municipal solid wastes and a comparative compositions of municipal solid waste with some data on Lebanon are given. Collection, transport and processing practices are next introduced. Finally treatment and disposal techniques are presented with emphasis on the solid waste as energy source and as material source. Methods of recycling are evaluated in respect with their environmental impact. 7 refs. 2 tabs

Solid waste study

International Nuclear Information System (INIS)

Ortiz, Paul G.

1995-01-01

The purpose of this document is to study the solid waste issues brought about by a Type C Investigation; ''Disposal of Inappropriate Material in the Los Alamos County Landfill'' (May 28, 1993). The study was completed in August 1995 by Coleman Research Corporation, under subcontract number 405810005-Y for Los Alamos National Laboratory (LANL). The study confirmed the issues identified in the Type C investigation, and also ascertained further issues or problems. During the course of this study two incidents involving hazardous waste resulted in the inappropriate disposal of the waste. An accidental spill, on June 8, 1995, at one of Laboratory buildings was not handled correctly, and ended up in the LAC Landfill. Hazardous waste was disposed of in a solid waste container and sent to the Los Alamos County Landfill. An attempt to locate the hazardous waste at the LAC Landfill was not successful. The second incident involving hazardous waste was discovered by the FSS-8, during a random dumpster surveillance. An interim dumpster program managed by FSS-8 discovered hazardous waste and copper chips in the solid waste, on August 9, 1995. The hazardous waste and copper chips would have been transported to the LAC Landfill if the audit team had not brought the problem to the awareness of the facility waste management personnel

SOLID WASTE STUDY

Energy Technology Data Exchange (ETDEWEB)

PAUL G. ORTIZ - COLEMAN RESEARCH CORP/COMPA INDUSTRIES

1995-08-01

The purpose of this document is to study the solid waste issues brought about by a Type C Investigation; ``Disposal of Inappropriate Material in the Los Alamos County Landfill'' (May 28, 1993). The study was completed in August 1995 by Coleman Research Corporation, under subcontract number 405810005-Y for Los Alamos National Laboratory (LANL). The study confirmed the issues identified in the Type C investigation, and also ascertained further issues or problems. During the course of this study two incidents involving hazardous waste resulted in the inappropriate disposal of the waste. An accidental spill, on June 8, 1995, at one of Laboratory buildings was not handled correctly, and ended up in the LAC Landfill. Hazardous waste was disposed of in a solid waste container and sent to the Los Alamos County Landfill. An attempt to locate the hazardous waste at the LAC Landfill was not successful. The second incident involving hazardous waste was discovered by the FSS-8, during a random dumpster surveillance. An interim dumpster program managed by FSS-8 discovered hazardous waste and copper chips in the solid waste, on August 9, 1995. The hazardous waste and copper chips would have been transported to the LAC Landfill if the audit team had not brought the problem to the awareness of the facility waste management personnel.

Simulating Radionuclide Migrations of Low-level Wastes in Nearshore Environment

Science.gov (United States)

Lu, C. C.; Li, M. H.; Chen, J. S.; Yeh, G. T.

2016-12-01

Tunnel disposal into nearshore mountains was tentatively selected as one of final disposal sites for low-level wastes in Taiwan. Safety assessment on radionuclide migrations in far-filed may involve geosphere processes under coastal environments and into nearshore ocean. In this study the 3-D HYDROFEOCHE5.6 numerical model was used to perform simulations of groundwater flow and radionuclide transport with decay chains. Domain of interest on the surface includes nearby watersheds delineated by digital elevation models and nearshore seabed. As deep as 800 m below the surface and 400 m below sea bed were considered for simulations. The disposal site was located at 200m below the surface. Release rates of radionuclides from near-field was estimated by analytical solutions of radionuclide diffusion with decay out of engineered barriers. Far-field safety assessments were performed starting from the release of radionuclides out of engineered barriers to a time scale of 10,000 years. Sensitivity analyses of geosphere and transport parameters were performed to improve our understanding of safety on final disposal of low-level waste in nearshore environments.

Process and research method of radionuclide migration in high level radioactive waste geological disposal system

International Nuclear Information System (INIS)

Chen Rui; Zhang Zhanshi

2014-01-01

Radionuclides released from waste can migrate from the repository to the rock and soil outside. On the other hand, nuclides also are retarded by the backfill material. Radionuclide migration is the main geochemical process of the waste disposal. This paper introduces various methods for radionuclide migration research, and give a brief analysis of the geochemical process of radionuclide migration. Finally, two of the most important processes of the radionuclide migration have been instanced. (authors)

Overview of the waste/barrier/rock interactions program of the basalt waste isolation project

International Nuclear Information System (INIS)

Salter, P.F.; Burnell, J.R.; Lane, D.L.

1986-01-01

The waste package waste/barrier/rock interactions testing program of the Basalt Waste Isolation Project is designed to assess the interactions between nuclear waste forms, other waste package components, and the environment in order to evaluate long-term waste package isolation (radionuclide release) behavior. The program involves reacting fully radioactive waste forms with combinations of steel or copper container material and basalt/bentonite packing material in site-specific ground water under anticipated repository conditions to obtain the steady state radionuclide concentrations required to predictively model waste package radionuclide concentrations required to predictively model waste package radionuclide releases. Both static and flow-through autoclaves are being used in the test program to determine radionuclide concentrations as a function of time and groundwater flow rate, and to evaluate the solid phase and water chemistry changes that control those concentrations. This test program, when combined with project hydrologic and geochemical testing and modeling efforts, and natural analog studies, provides the information required to evaluate long-term radionuclide mobility within a waste package emplaced in a basalt repository

Integrated report on radionuclide migration at the Savannah River shallow land burial site

International Nuclear Information System (INIS)

Towler, O.A. Jr.

1989-03-01

The impact of the SRP Solid Radioactive Waste Burial Ground on the environment has been studied since the early 1970s in four subtasks: subsurface monitoring of groundwater, lysimeter tests of waste, soil-water chemistry effects, and radionuclide transport modeling. This document summarizes and integrates the results of the four subtasks. More information has been gathered on the behavior of radionuclides in a solid waste disposal facility located in a humid region than from any other waste disposal site in the world. The design of closure for the SRP Burial Ground has been given a firm technical basis. The limiting pathways for radionuclide migration have been determined to be infiltrating rainwater and root penetration. Closure designs must therefore address both these factors. The designs for new storage/disposal facilities have also been given a firm technical basis. The major conclusions are that tritium will be stored for decay and not allowed to contact the groundwater, waste containing long-lived radionuclides such as iodine-129 must be stored for later geologic disposal, and above and below ground concrete vaults should be used for disposal of other low-level radioactive waste. 61 refs., 18 figs. 8 tabs

The main rules regarding the management of solid waste and liquid effluent contaminated during use at nuclear medicine departments

International Nuclear Information System (INIS)

Boudouin, E.

2011-01-01

This article describes the key requirements applicable to the management of contaminated medical waste and effluent from hospitals and health care centres, and more especially from nuclear medicine departments that use radionuclides for the purposes of diagnosis (in vivo or in vitro) or in patient treatment. It also presents the key management regulations, making a distinction between contaminated solid waste and contaminated liquid waste from such nuclear medicine departments. (author)

Hanford Site solid waste acceptance criteria

International Nuclear Information System (INIS)

Willis, N.P.; Triner, G.C.

1991-09-01

Westinghouse Hanford Company manages the Hanford Site solid waste treatment, storage, and disposal facilities for the US Department of Energy Field Office, Richland under contract DE-AC06-87RL10930. These facilities include radioactive solid waste disposal sites, radioactive solid waste storage areas and hazardous waste treatment, storage, and/or disposal facilities. This manual defines the criteria that must be met by waste generators for solid waste to be accepted by Westinghouse Hanford Company for treatment, storage and/or disposal facilities. It is to be used by all waste generators preparing radioactive solid waste for storage or disposal at the Hanford Site facilities and for all Hanford Site generators of hazardous waste. This manual is also intended for use by Westinghouse Hanford Company solid waste technical staff involved with approval and acceptance of solid waste. The criteria in this manual represent a compilation of state and federal regulations; US Department of Energy orders; Hanford Site requirements; and other rules, regulations, guidelines, and standards as they apply to management of solid waste. Where appropriate, these requirements are included in the manual by reference. It is the intent of this manual to provide guidance to the waste generator in meeting the applicable requirements

Evaluation of residual activity of solid waste generated in nuclear medicine services of Porto Alegre - Brazil

International Nuclear Information System (INIS)

Xavier, Ana M.; Alabarse, Frederico Gil; Magalhaes, Maisa Haiidamus; Guerrero, Jesus Salvador Perez

2008-01-01

An experimental programme to estimate, with a better degree of accuracy, the activity that remains adsorbed in flasks and syringes used in Nuclear Medicine Services for the administration of radionuclides to patients submitted to diagnostic or therapy was conducted under the coordination of the Radioactive Waste Division of the Brazilian Nuclear Energy Commission. The adopted recommendation in Brazil to allow an expedite solid waste management in nuclear medicine facilities, up to the present, is to consider that 2% of the initial activity remains adsorbed in the solid waste, which easily allows the calculation of the storage time to achieve regulatory clearance levels by decay. This research evaluates 17 different kinds of radio pharmaceuticals and three radioisotopes: 99m Tc, 67 Ga and 201 Tl. Results obtained by means of a weighting method to estimate the residual mass in flasks show that the ratio of the mass of the liquid that remains in the solid waste to the mass of the empty flask is constant. This suggests that the residual activity depends on the initial activity concentration of radiopharmaceutical contained in each flask, as assumed by the regulatory body. Additionally, results obtained by determining the remaining activity in flasks, shortly after the injection of its radionuclides contents in patients, indicate that an average value for the residual activity of the order of 10% of the initial activity contained in the flasks or syringes can be adopted instead of the previously assumed 2%. It is suggested that the more conservative average value obtained in the present work for the activity that remains in flasks and syringes, that is, 10% of the initial activity, could be adopted to determine the decay storage time before the release of solid waste in the urban conventional land fill disposal system. (author)

Effect on localized waste-container failure on radionuclide transport from an underground nuclear waste vault

International Nuclear Information System (INIS)

Cheung, S.C.H.; Chan, T.

1983-07-01

In the geological disposal of nuclear fuel waste, one option is to emplace the waste container in a borehole drilled into the floor of the underground vault. In the borehole, the waste container is surrounded by a compacted soil material known as the buffer. A finite-element simulation has been performed to study the effect of localized partial failure of the waste container on the steady-state radionuclide transport by diffusion from the container through the buffer to the surrounding rock and/or backfill. In this study, the radionuclide concentration at the buffer-backfill interface is assumed to be zero. Two cases are considered at the interface between the buffer and the rock. In case 1, a no-flux boundary condition is used to simulate intact rock. In case 2, a constant radionuclide concentration condition is used to simulate fractured rock with groundwater flow. The results show that the effect of localized partial failure of the waste container on the total flux is dependent on the boundary condition at the buffer-rock interface. For the intact rock condition, the total flux is mainly dependent on the location of the failure. The total flux increases as the location changes from the bottom to the top of the emplaced waste container. For a given localized failure of the waste container, the total flux remains unaffected by the area of failed surface below the top of the failure. For fractured rock, the total flux is directly proportional to the failed surface area of the waste container regardless of the failure location

Determining the Release of Radionuclides from Tank 18F Waste Residual Solids: FY2016 Report

Energy Technology Data Exchange (ETDEWEB)

King, William D. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL); Hobbs, David T. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL)

2016-08-12

Pore water leaching studies were conducted on actual Savannah River Site (SRS) Tank 18F residual waste solids to support Liquid Waste tank closure efforts. A test methodology was developed during previous simulant testing to produce slurries of tank residual solids and grout-representative solids in grout pore water solutions (based on SRS groundwater compositions) with pH and E_h values expected during the aging of the closed waste tank. The target conditions are provided below where the initial pore water has a reducing potential and a relatively high pH (Reducing Region II). The pore water is expected to become increasingly oxidizing with time (Oxidizing Region II) and during the latter stages of aging (Oxidizing Region III) the pH is expected to decrease. For the reducing case, tests were conducted with both unwashed and washed Tank 18F residual solids. For the oxidizing cases (Oxidizing Regions II and III), all samples were washed with simulated grout pore water solutions prior to testing, since it is expected that these conditions will occur after considerable pore water solution has passed through the system. For the reducing case, separate tests were conducted with representative ground grout solids and with calcium carbonate reagent, which is the grout phase believed to be controlling the pH. Ferrous sulfide (FeS) solids were also added to the reducing samples to lower the slurry E_h value. Calcium carbonate solids were used as the grout-representative solid phase for each of the oxidizing cases. Air purge-gas with and without CO₂ removed was transferred through the oxidizing test samples and nitrogen purge-gas was transferred through the reducing test samples during leach testing. The target pH values were achieved to within 0.5 pH units for all samples. Leaching studies were conducted over an E_h range of approximately 0.7 V. However, the highest and lowest E_h values achieved of ~+0.5 V and ~-0.2 V were

Hydrology of the solid waste burial ground, as related to the potential migration of radionuclides, Idaho National Engineering Laboratory

International Nuclear Information System (INIS)

Barraclough, J.T.; Robertson, J.B.; Janzer, V.J.; Saindon, L.G.

1976-08-01

This report describes a study conducted by the U. S. Geological Survey with the following objectives: to evaluate the hydrologic, radiologic and geochemical variables that control the potential for subsurface migration of waste radionuclides from the burial trenches to the Snake River Plain aquifer; to determine the extent of radionuclide migration, if any; and, to construct monitoring wells into the aquifer. Statistically significant trace amounts of radioactivity were found in about one-half of the 44 sedimentary samples from the six holes core drilled inside the burial ground and from all water samples from one hole tapping a perched water table. These very low levels of radioactivity are detectable only with the most sensitive of analytical equipment and techniques. The levels of radioactivity detected were, in most cases, less than the amounts found in surface soils in this region resulting from world-wide fallout. This radioactivity found in the cores could have been introduced naturally by migration by infiltrating water which had made contact with buried waste or could have been introduced artificially during drilling and sampling. The available data from the four peripheral monitoring wells do not indicate that radionuclide constituents from the burial ground have migrated into the underlying Snake River Plain aquifer. The low concentrations of radionuclides detected in samples taken from the sedimentary layers are not expected to migrate to the Snake River Plain aquifer. Water samples from the peripheral wells and one core hole inside the burial ground will continue to be collected and analyzed for radioactivity semi-annually

Characterization of radionuclide-chelating agent complexes found in low-level radioactive decontamination waste. Literature review

International Nuclear Information System (INIS)

Serne, R.J.; Felmy, A.R.; Cantrell, K.J.; Krupka, K.M.; Campbell, J.A.; Bolton, H. Jr.; Fredrickson, J.K.

1996-03-01

The US Nuclear Regulatory Commission is responsible for regulating the safe land disposal of low-level radioactive wastes that may contain organic chelating agents. Such agents include ethylenediaminetetraacetic acid (EDTA), diethylenetriaminepentaacetic acid (DTPA), picolinic acid, oxalic acid, and citric acid, and can form radionuclide-chelate complexes that may enhance the migration of radionuclides from disposal sites. Data from the available literature indicate that chelates can leach from solidified decontamination wastes in moderate concentration (1--100 ppm) and can potentially complex certain radionuclides in the leachates. In general it appears that both EDTA and DTPA have the potential to mobilize radionuclides from waste disposal sites because such chelates can leach in moderate concentration, form strong radionuclide-chelate complexes, and can be recalcitrant to biodegradation. It also appears that oxalic acid and citric acid will not greatly enhance the mobility of radionuclides from waste disposal sites because these chelates do not appear to leach in high concentration, tend to form relatively weak radionuclide-chelate complexes, and can be readily biodegraded. In the case of picolinic acid, insufficient data are available on adsorption, complexation of key radionuclides (such as the actinides), and biodegradation to make definitive predictions, although the available data indicate that picolinic acid can chelate certain radionuclides in the leachates

Characterization of radionuclide-chelating agent complexes found in low-level radioactive decontamination waste. Literature review

Energy Technology Data Exchange (ETDEWEB)

Serne, R.J.; Felmy, A.R.; Cantrell, K.J.; Krupka, K.M.; Campbell, J.A.; Bolton, H. Jr.; Fredrickson, J.K. [Pacific Northwest National Lab., Richland, WA (United States)

1996-03-01

The US Nuclear Regulatory Commission is responsible for regulating the safe land disposal of low-level radioactive wastes that may contain organic chelating agents. Such agents include ethylenediaminetetraacetic acid (EDTA), diethylenetriaminepentaacetic acid (DTPA), picolinic acid, oxalic acid, and citric acid, and can form radionuclide-chelate complexes that may enhance the migration of radionuclides from disposal sites. Data from the available literature indicate that chelates can leach from solidified decontamination wastes in moderate concentration (1--100 ppm) and can potentially complex certain radionuclides in the leachates. In general it appears that both EDTA and DTPA have the potential to mobilize radionuclides from waste disposal sites because such chelates can leach in moderate concentration, form strong radionuclide-chelate complexes, and can be recalcitrant to biodegradation. It also appears that oxalic acid and citric acid will not greatly enhance the mobility of radionuclides from waste disposal sites because these chelates do not appear to leach in high concentration, tend to form relatively weak radionuclide-chelate complexes, and can be readily biodegraded. In the case of picolinic acid, insufficient data are available on adsorption, complexation of key radionuclides (such as the actinides), and biodegradation to make definitive predictions, although the available data indicate that picolinic acid can chelate certain radionuclides in the leachates.

Integrated solid waste management in megacities

Directory of Open Access Journals (Sweden)

M.A. Abdoli

2016-05-01

Full Text Available Rapid urbanization and industrialization, population growth and economic growth in developing countries make management of municipal solid waste more complex comparing with developed countries. Furthermore, the conventional municipal solid waste management approach often is reductionists, not tailored to handle complexity. Therefore, the need to a comprehensive and multi-disciplinary approach regarding the municipal solid waste management problems is increasing. The concept of integrated solid waste management is accepted for this aim all over the world. This paper analyzes the current situation as well as opportunities and challenges regarding municipal solid waste management in Isfahan according to the integrated solid waste management framework in six aspects: environmental, political/legal, institutional, socio-cultural, financial/economic, technical and performance aspects. Based on the results obtained in this analysis, the main suggestions for future integrated solid waste management of Isfahan are as i promoting financial sustainability by taking the solid waste fee and reducing the expenses through the promoting source collection of recyclable materials, ii improving compost quality and also marketing the compost products simultaneously, iii promoting the private sector involvements throughout the municipal solid waste management system.

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

International Nuclear Information System (INIS)

Plodinec, M.J.

1993-01-01

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

Energy and solid/hazardous waste

Energy Technology Data Exchange (ETDEWEB)

None

1981-12-01

This report addresses the past and potential future solid and hazardous waste impacts from energy development, and summarizes the major environmental, legislation applicable to solid and hazardous waste generation and disposal. A glossary of terms and acronyms used to describe and measure solid waste impacts of energy development is included. (PSB)

Energy and solid/hazardous waste

International Nuclear Information System (INIS)

1981-12-01

This report addresses the past and potential future solid and hazardous waste impacts from energy development, and summarizes the major environmental, legislation applicable to solid and hazardous waste generation and disposal. A glossary of terms and acronyms used to describe and measure solid waste impacts of energy development is included

Shallow land burial of solid low-level radioactive wastes - 30 years of experience at the Savannah River Plant

International Nuclear Information System (INIS)

Stone, J.A.; Fenimore, J.W.; Hawkins, R.H.; Oblath, S.B.; Ryan, J.P. Jr.

1983-01-01

Solid radioactive wastes from production of nuclear materials at the Savannah River Plant (SRP) are buried in shallow trenches on a 79-hectare plot within the SRP site. The SRP burial ground, in use since 1953, has provided containment for about 370,000 m 3 of waste containing 10 7 Ci that have been buried through 1982. Site characteristics, operating practices, and monitoring results are described. Extensive field and laboratory studies aimed at developing a fundamental understanding of the soil/waste/water system of the SRP burial ground are discussed. Leaching and migration of buried radionuclides have been monitored by assays of soil cores and by periodic sampling of numerous groundwater wells. Except for tritium, none of the radionuclides have migrated significantly from the waste. Generally, traces of alpha and nonvolatile beta/gamma emitters that have entered the groundwater can be detected only by ultra-low-level radiochemical analyses. Current research efforts include: (1) migration of individual radionuclides such as 60 Co, 90 Sr, 99 Tc, 106 Ru, 129 I, 137 Cs, 238 Pu, and 239 Pu (plus nonradioactive materials such as mercury); (2) groundwater chemistry under buried waste, to determine fundamental transport mechanisms; (3) radionuclide migration from well characteized sources emplaced in lysimeters; (4) laboratory measurements of sorption on burial ground soil. In addition to ensuring continued safe operation, the ongoing waste migration studies provide technical guidance for site operations and decommissioning

Direct conversion of radioactive and chemical waste containing metals, ceramics, amorphous solids, and organics to glass

International Nuclear Information System (INIS)

Forsberg, C.W.; Beahm, E.C.; Parker, G.W.

1994-01-01

The Glass Material Oxidation and Dissolution System (CMODS) is a new process for direct conversion of radioactive, mixed, and chemical wastes to glass. The wastes can be in the chemical forms of metals, ceramics, amorphous solids, and organics. GMODS destroys organics and it incorporates heavy metals and radionuclides into a glass. Processable wastes may include miscellaneous spent fuels (SF), SF hulls and hardware, plutonium wastes in different forms, high-efficiency particulate air (HEPA) filters, ion-exchange resins, failed equipment, and laboratory wastes. Thermodynamic calculations indicate theoretical feasibility. Small-scale laboratory experiments (< 100 g per test) have demonstrated chemical laboratory feasibility for several metals. Additional work is needed to demonstrate engineering feasibility

Idaho radionuclide exposure study: Literature review

International Nuclear Information System (INIS)

Baker, E.G.; Freeman, H.D.; Hartley, J.N.

1987-10-01

Phosphate ores contain elevated levels of natural radioactivity, some of which is released to the environment during processing or use of solid byproducts. The effect of radionuclides from Idaho phosphate processing operations on the local communities has been the subject of much research and study. The literature is reviewed in this report. Two primary radionuclide pathways to the environment have been studied in detail: (1) airborne release of volatile radionuclides, primarily 210 Po, from calciner stacks at the two elemental phosphorus plants; and (2) use of byproduct slag as an aggregate for construction in Soda Springs and Pocatello. Despite the research, there is still no clear understanding of the population dose from radionuclide emissions, effluents, and solid wastes from phosphate processing plants. Two other potential radionuclide pathways to the environment have been identified: radon exhalation from phosphogypsum and ore piles and contamination of surface and ground waters. Recommendations on further study needed to develop a data base for a complete risk assssment are given in the report

Management of solid wastes during decommissioning of research reactors. Evaluation of gross clearance levels and mathematical simulation of solid waste assay techniques

International Nuclear Information System (INIS)

Gopalakrishnan, R.K.; Sobhan Babu, K.; Sharma, D.N.

2008-01-01

Full text: Decommissioning of nuclear facilities constitute a challenge mainly due to the huge and complex nature of radioactive waste generated during this process. In the context of management and disposal of waste and reuse/recycle of usable materials during decommissioning of reactors, clearance levels for relevant radio nuclides are of vital importance. Radionuclide specific clearance levels are developed by IAEA and such levels allow the facility for free release of materials to the environment without further regulatory consideration. An effort has been made in this paper to establish clearance levels for radionuclides associated with various system and structural components of a research reactor and rather than radionuclide specific clearance levels, these values are derived for gross activity concentration, which is more practical for radioactive waste categorization, disposal and reuse or recycle of usable materials. The first step towards the derivation of clearance levels is the calculation of annual doses relating to unit activity concentration for each nuclide using various enveloping scenarios. After the estimation of doses, the limiting enveloping scenario (the one that gives the highest dose) is identified. The clearance levels are then derived by dividing the reference dose level (10 μSv/y) by the annual dose calculated per unit activity concentration for the limiting enveloping scenario The clearance level for gross beta-gamma activity concentration is then evaluated as the product of the limiting clearance level and the number of radionuclides characterized for the structural components. Simulation studies were also carried out for the design of a monitoring system for estimation of activity concentration of the decommissioned materials, especially rubbles/ concrete, using mathematical models. Conventional solid waste assay techniques would not suffice to the requirement of decommissioning waste categorization since very low level activity

Sorption-capacity limited retardation of radionuclides transport in water-saturated packing materials

International Nuclear Information System (INIS)

Pescatore, C.; Sullivan, T.

1984-01-01

Radionuclides breakthrough times as calculated through constant retardation factors obtained in dilute solutions are non-conservative. The constant retardation approach regards the solid as having infinite sorption capacity throughout the solid. However, as the solid become locally saturated, such as in the proximity of the waste form-packing materials interface, it will exhibit no retardation properties, and transport will take place as if the radionuclides were locally non-reactive. The magnitude of the effect of finite sorption capacity of the packing materials on radionuclide transport is discussed with reference to high-level waste package performance. An example based on literature sorption data indicated that the breakthrough time may be overpredicted by orders of magnitude using a constant retardation factor as compared to using the entire sorption isotherm to obtain a concentration-dependent retardation factor. 8 refs., 3 figs., 3 tabs

Sorption-capacity limited retardation of radionuclides transport in water-saturated packing materials

International Nuclear Information System (INIS)

Pescatore, C.; Sullivan, T.

1984-01-01

Radionuclides breakthrough times as calculated through constant retardation factors obtained in dilute solutions are non-conservative. The constant retardation approach regards the solid as having infinite sorption capacity throughout the solid. However, as the solid becomes locally saturated, such as in the proximity of the waste form-packing materials interface, it will exhibit no retardation properties, and transport will take place as if the radionuclides were locally non-reactive. The magnitude of the effect of finite sorption capacity of the packing materials on radionuclide transport is discussed with reference to high-level waste package performance. An example based on literature sorption data indicates that the breakthrough time may be overpredicted by orders of magnitude using a constant retardation factor as compared to using the entire sorption isotherm to obtain a concentration-dependent retardation factor. 8 references, 3 figures, 3 tables

Radionuclide transport from near-surface repository for radioactive waste - The unsaturated zone approach

Energy Technology Data Exchange (ETDEWEB)

Jakimaviciute-Maseliene, V. [Vilnius University (Lithuania); Mazeika, J. [Nature Research Centre (Lithuania); Motiejunas, S. [Radioactive Waste Management Agency (Lithuania)

2014-07-01

About 100 000 m{sup 3} of solid conditioned Low and Intermediate Level Waste (LILW), generated during operation and decommissioning of the Ignalina nuclear power plant (INPP), are to be disposed of in a near-surface repository (NSR) - a 'hill'-type repository with reinforced concrete vaults and with engineered and natural barriers. The northeastern Lithuania and the environment of the INPP in particular were recognized as the areas most suitable for a near-surface repository (Stabatiske Site). The engineered barriers of the repository consist of concrete cells surrounded by clay-based material of low permeability with about the same isolating capacity in all directions. The clay materials must be effectively compactable so that required hydraulic conductivity is reached. The Lithuanian Triassic clay turned out to be sufficiently rich in smectites and was proposed as main candidate for sealing of the repository. When the concrete vaults are filled, the repository cover will be constructed. The surface of the mound will be planted with grass. In this study a computer code FEFLOW 5.0 was applied for simulating the transport of the most mobile radionuclides ({sup 3}H, {sup 14}C, {sup 59}Ni and {sup 94}Nb) with moisture through an unsaturated vault of the near-surface repository in Stabatiske Site. The HYDRUS-1D analysis was used to assess the radionuclide transport in the repository and to estimate initial activity concentrations of radionuclides transported from the cemented waste matrix. Radionuclide release from the vault in the unsaturated conditions after closure of the repository and consequent contaminant plume transport has been assessed taking into account site-specific natural and engineering conditions and based on a normal evolution scenario. The highest peak radionuclide activity concentrations were estimated applying the FEFLOW code. The highest value of {sup 14}C activity concentration(about 1.3x10{sup 8} Bq/m{sup 3}) at the groundwater table

SOLID WASTE INTEGRATED FORECAST TECHNICAL (SWIFT) REPORT FY2005 THRU FY2035 VERSION 2005.0 VOLUME 1

Energy Technology Data Exchange (ETDEWEB)

BARCOT, R.A.

2005-04-13

The SWIFT Report provides up-to-date life cycle information about the radioactive solid waste expected to be managed by Hanford's Waste Management (WM) Project from onsite and offsite generators. This report is an annual update to the SWIFT 2004.1 report that was published in August 2004. The SWIFT Report is published in two volumes. SWIFT Volume II provides detailed analyses of the data, graphical representation, comparison to previous years, and waste generator specific information. The data contained in this report are the official data for solid waste forecasting. In this revision, the volume numbers have been switched to reflect the timing of their release. This particular volume provides the following data reports: (1) Summary volume data by DOE Office, company, and location; (2) Annual volume data by waste generator; (3) Annual waste specification record and physical waste form volume; (4) Radionuclide activities and dose-equivalent curies; and (5) Annual container type data by volume and count.

SOLID WASTE INTEGRATED FORECAST TECHNICAL (SWIFT) REPORT FY2005 THRU FY2035 VERSION 2005.0 VOLUME 1

International Nuclear Information System (INIS)

BARCOT, R.A.

2005-01-01

The SWIFT Report provides up-to-date life cycle information about the radioactive solid waste expected to be managed by Hanford's Waste Management (WM) Project from onsite and offsite generators. This report is an annual update to the SWIFT 2004.1 report that was published in August 2004. The SWIFT Report is published in two volumes. SWIFT Volume II provides detailed analyses of the data, graphical representation, comparison to previous years, and waste generator specific information. The data contained in this report are the official data for solid waste forecasting. In this revision, the volume numbers have been switched to reflect the timing of their release. This particular volume provides the following data reports: (1) Summary volume data by DOE Office, company, and location; (2) Annual volume data by waste generator; (3) Annual waste specification record and physical waste form volume; (4) Radionuclide activities and dose-equivalent curies; and (5) Annual container type data by volume and count

Radionuclide compositions of spent fuel and high level waste from commercial nuclear reactors

International Nuclear Information System (INIS)

Goodill, D.R.; Tymons, B.J.

1984-10-01

This report provides information on radionuclide compositions of spent fuel and high level waste produced during reprocessing. The reactor types considered are Magnox, AGR, PWR and CFR. The activities of the radionuclides are calculated using the FISPIN code. The results are presented in a form suitable for radioactive waste management calculations. (author)

36 CFR 13.1118 - Solid waste disposal.

Science.gov (United States)

2010-07-01

... 36 Parks, Forests, and Public Property 1 2010-07-01 2010-07-01 false Solid waste disposal. 13.1118... Provisions § 13.1118 Solid waste disposal. (a) A solid waste disposal site may accept non-National Park Service solid waste generated within the boundaries of the park area. (b) A solid waste disposal site may...

36 CFR 13.1008 - Solid waste disposal.

Science.gov (United States)

2010-07-01

... 36 Parks, Forests, and Public Property 1 2010-07-01 2010-07-01 false Solid waste disposal. 13.1008... § 13.1008 Solid waste disposal. (a) A solid waste disposal site may accept non-National Park Service solid waste generated within the boundaries of the park area. (b) A solid waste disposal site may be...

36 CFR 13.1912 - Solid waste disposal.

Science.gov (United States)

2010-07-01

... 36 Parks, Forests, and Public Property 1 2010-07-01 2010-07-01 false Solid waste disposal. 13.1912....1912 Solid waste disposal. (a) A solid waste disposal site may accept non-National Park Service solid waste generated within the boundaries of the park area. (b) A solid waste disposal site may be located...

36 CFR 13.1604 - Solid waste disposal.

Science.gov (United States)

2010-07-01

... 36 Parks, Forests, and Public Property 1 2010-07-01 2010-07-01 false Solid waste disposal. 13.1604... Solid waste disposal. (a) A solid waste disposal site may accept non-National Park Service solid waste generated within the boundaries of the park area. (b) A solid waste disposal site may be located within one...

Modeling of container failure and radionuclide release from a geologic nuclear waste repository

International Nuclear Information System (INIS)

Kim, Chang Lak; Kim, Jhin Wung; Choi, Kwang Sub; Cho, Chan Hee

1989-02-01

Generally, two processes are involved in leaching and dissolution; (1) chemical reactions and (2) mass transfer by diffusion. The chemical reaction controls the dissolution rates only during the early stage of exposure to groundwater. The exterior-field mass transfer may control the long-term dissolution rates from the waste solid in a geologic repository. Masstransfer analyses rely on detailed and careful application of the governing equations that describe the mechanistic processes of transport of material between and within phases. We develop analytical models to predict the radionuclide release rate into the groundwater with five different approaches: a measurement-based model, a diffusion model, a kinetics model, a diffusion-and-kinetics model, and a modified diffusion model. We also collected experimental leaching data for a partial validation of the radionuclide release model based on the mass transfer theory. Among various types of corrosions, pitting is the most significant because of its rapid growth. The failure time of the waste container, which also can be interpreted as the containment time, is a milestone of the performance of a repository. We develop analytical models to predict the pit growth rate on the container surface with three different approaches: an experimental method, a statistical method, and a mathematical method based on the diffusion theory. (Author)

Solid waste management in Khartoum industrial area

International Nuclear Information System (INIS)

Elsidig, N. O. A.

2004-05-01

This study was conducted in Khartoum industrial area (KIA). The study discusses solid waste generation issues in KIA as well as solid waste collection, storage, transport and final disposal methods. A focus on environmental impact resulting from the accumulation of solid waste was presented by reviewing solid waste management in developed as well as developing countries starting from generation to final disposal. Environmental health legislation in Sudan was investigated. The study covers all the (eight) industrial sub-sectors presented in KIA. The main objective of the study is to assess the situation of solid waste in KIA. To fulfill the objectives of the study the researcher deemed it necessary to explore problems related to solid waste generation and solid waste arrangement with special emphasis on final disposal methods. Practically, 31 (thirty-one) factories representing the different industrial sub-sectors in KIA were studied. This represents 25% of the total number of factories located in KIA. Data were obtained by, questionnaires, interviews and observations mainly directed to concerned officials, solid waste workers, pickers and brokers. Obtained data were stored, coded, tabulated and analyzed using the computer systems (excel and SPSS programmes). The obtained results should clear deficiency in the management of solid waste which led to great environmental deterioration in KIA and neighboring residential areas. The environment in studied area is continuously polluted due to high pollution loads and unproved solid waste management. In order to maintain health environment operating factories have to pretreated their solid waste according to the recognized standards and waste minimization techniques such as recycling and re use should be widely applied, moreover, running crash programme for environmental sanitation in Khartoum state should be expanded and improved to include special characteristics of solid waste from industries. Finally, increase awareness

Transuranic solid waste management programs. Progress report, July--December 1975

International Nuclear Information System (INIS)

1976-09-01

Progress is reported for three transuranic solid waste management programs funded at the Los Alamos Scientific Laboratory (LASL) by the Energy Research and Development Administration (ERDA) Division of Fuel Cycle and Production (NFCP). Under the Transuranic Waste Research and Development Program, continued studies have shown the potential attractiveness of fiber drums as an acceptable substitute for the current mild steel storage containers. Various fire retardants have been evaluated, with one indicating significant ability to inhibit fire propagation. Continued radiolysis studies, under laboratory and field conditions, continue to reaffirm earlier LASL results indicating no significant hazard from radiolytic reactions, assuming no change in current allowable loadings. Care must be exercised to differentiate between radiolytic and chemical reactions. Other efforts have identified a modification of chemical processing to reduce the amounts of plutonium requiring retrievable storage. Studies are also in progress to enhance the sensitivity of the LASL MEGAS assay system. The Transuranic-Contaminated Solid Waste Treatment Development Facility building was 72 percent complete as of December 31, 1975, which is in accord with the existing schedule. Procurement of process components is also on schedule. Certain modifications to the facility have been made, and various pre-facility experiments on waste container handling and processing have been completed. The program for the Evaluation of Transuranic-Contaminated Radioactive Waste Disposal Areas continued development of various computer modules for simulation of radionuclide transport within the biosphere. In addition, program staff contributed to an ERDA document on radioactive waste management through the preparation of a report on burial of radioactive waste at ERDA-contractor and commercial sites

Transuranic solid waste management programs. Progress report, July--December 1975

Energy Technology Data Exchange (ETDEWEB)

1976-09-01

Progress is reported for three transuranic solid waste management programs funded at the Los Alamos Scientific Laboratory (LASL) by the Energy Research and Development Administration (ERDA) Division of Fuel Cycle and Production (NFCP). Under the Transuranic Waste Research and Development Program, continued studies have shown the potential attractiveness of fiber drums as an acceptable substitute for the current mild steel storage containers. Various fire retardants have been evaluated, with one indicating significant ability to inhibit fire propagation. Continued radiolysis studies, under laboratory and field conditions, continue to reaffirm earlier LASL results indicating no significant hazard from radiolytic reactions, assuming no change in current allowable loadings. Care must be exercised to differentiate between radiolytic and chemical reactions. Other efforts have identified a modification of chemical processing to reduce the amounts of plutonium requiring retrievable storage. Studies are also in progress to enhance the sensitivity of the LASL MEGAS assay system. The Transuranic-Contaminated Solid Waste Treatment Development Facility building was 72 percent complete as of December 31, 1975, which is in accord with the existing schedule. Procurement of process components is also on schedule. Certain modifications to the facility have been made, and various pre-facility experiments on waste container handling and processing have been completed. The program for the Evaluation of Transuranic-Contaminated Radioactive Waste Disposal Areas continued development of various computer modules for simulation of radionuclide transport within the biosphere. In addition, program staff contributed to an ERDA document on radioactive waste management through the preparation of a report on burial of radioactive waste at ERDA-contractor and commercial sites.

Treatment of solid non-active wastes

International Nuclear Information System (INIS)

Chmielewska, E.

2008-01-01

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

Application of dispersion and dose assessment models to the solid and liquid wastes facilities of Ezeiza radioactive waste management area

International Nuclear Information System (INIS)

Amado, Valeria A.; Lopez, Fabio O.

2007-01-01

This paper provides a dose assessment of the critic group from the near surface facility for solid and liquid waste, located at Ezeiza Atomic Center in Argentina (Ezeiza Radioactive Waste Management Area-AGE). The calculations were made using several approaches about source term. The activities for each radionuclide and facility were taken from the National Atomic Energy Commission's Inventory that corresponds to the first trimester of 2005. The radioactive decay of each radionuclide was considered. The work was performed in two steps. In the first step, using the Nuclide Dispersion in Phreatic Aquifer Model (DRAF), the dispersion of the contaminants into the phreatic aquifer until the discharge point at a superficial water course was considered. In the second step, the Consequences of Releases to the Environment Assessment Methodology Program (PC CREAM) was used for the study of radionuclides dispersion in superficial water course and dose calculations. The results from this paper show that, for every studied radionuclide, the doses involved are significantly lower than the values established by current regulations. On the other hand, those results put in evidence the utility of simple models in estimating the order of magnitude of expected concentrations and doses. It is important to highlight that the obtained results can be used only in the context of the suppositions that were made. (author) [es

Characteristics of wastes and soils which affect transport of radionuclides through the soil and their relationship to waste management. Annual report FY78

International Nuclear Information System (INIS)

Polzer, W.L.; Fowler, E.B.; Essington, E.H.

1979-04-01

Soil samples were collected from Beatty, NV, the University of California, Los Angeles/University of California, Berkeley (UCLA/UCB) project, California and Nebraska. Results of waste/soil interaction studies indicate that waste radionuclides can be categorized into three broad forms; filterable (insoluble) and sorbable and nonsorbable (soluble). The relative distribution of the three depends on the storage time of the waste and on the soil which is interacted with the waste. In the filterable (insoluble) fraction the radionuclides are associated with both organic and inorganic particulates. The primary inorganic particulate was identified as calcium carbonate. The soluble nonsorbable waste radionuclides possess a negative charge with the exception of 137 Cs; that species is positively charged. The presence of negatively charged species is attributed to complexing with either carbonate or chelating compounds. Changes in the soluble fraction of waste radionuclides on storage of waste are attributed in part to the dissolution or precipitation of calcium carbonate and perhaps the degradation of organic material or growth of microorganisms in the waste. 11 figures, 31 tables

Modeling of radionuclide migration and a temperature dynamics in underground disposal of liquid radioactive waste

International Nuclear Information System (INIS)

Larin, V.K.; Zubkov, A.A.; Balakhonov, V.G.; Sukhorukov, V.A.; Zhiganov, A.N.; Noskov, M.D.; Istomin, A.D.; Kesler, A.G.

2002-01-01

Mathematical model of radionuclide migration and temperature field dynamics during underground disposal of liquid radioactive wastes is presented. The model involves the description of filtration, convective-dispersion mass transfer, sorption and desorption of radionuclides, radioactive decay, convective heat transport and hear transfer. Software making possible to conduct prognosis calculations of changing state of stratum-collector of radioactive wastes was made. Results of the simulation of temperature field dynamics and behaviour of radionuclides on underground disposal of liquid radioactive wastes of the Siberian chemical plant are performed [ru

Melt-processing method for radioactive solid wastes

International Nuclear Information System (INIS)

Kobayashi, Hiroaki

1998-01-01

Radioactive solid wastes are charged into a water-cooled type cold crucible induction melting furnace disposed in high frequency coils, and high frequency currents are supplied to high frequency coils which surround the melting furnace to melt the solid wastes by induction-heating. In this case, heat plasmas are jetted from above the solid wastes to the solid wastes to conduct initial heating to melt a portion of the solid wastes. Then, high frequency currents are supplied to the high frequency coils to conduct induction heating. According to this method, even when waste components of various kinds of materials are mixed, a portion of the solid wastes in the induction melting furnace can be melted by the initial heating by jetting heat plasmas irrespective of the kinds and the electroconductivity of the materials of the solid wastes. With such procedures, entire solid wastes in the furnace can be formed into a molten state uniformly and rapidly. (T.M.)

Integrated solid waste management: a palliative to existing waste ...

African Journals Online (AJOL)

As a concept, Integrated Solid Waste Management (ISWM) is a sustainable ... on the perspective of consumers on waste generation, collection and disposal. ... to effective solid waste management in the case study area; non-sorting and ...

Solid radwaste processing and conditioning. The SGN experience

International Nuclear Information System (INIS)

Tucoulat, D.; Tchemitcheff, E.

1993-01-01

Solid wastes are generated in the operation of the installations in France. These solid wastes display different levels of radioactivity. Some of them arising from research centres or reprocessing plants even contain relatively significant quantities of alpha-bearing radionuclides. In order to produce an ultimate waste package that satisfies the requirements set by safety authorities and the organizations in charge of final waste disposal in the concerned countries, solid waste conditioning takes place in a number of successive steps

Investigation and analysis to the content of natural radionuclides at rate-earth ore and solid waste in China through the first nationwide pollution source survey

International Nuclear Information System (INIS)

Lou Jianjun; Liu Guifang; Sun Qinghong

2011-01-01

China has launched the First Nationwide Pollution Source Survey (FNPSS) during 2006-2009. Ministry Environmental Protection (MEP) sponsored the campaign of measuring the natural radionuclide contents. And the Ministry Environmental Protection (MEP) organized the measurements of natural radionuclide contents of in the factories and mines associated with rare-earth, niobium/tantalum, zircon, tin, lead/zinc, copper, iron, phosphate, coal, aluminum and vanadium. This paper analyzes mainly the data on the contents of U, 232 Th and 226 Ra in the rare-earth ore and solid waste produced by the rare-earth industry in China, as one of a series of papers on naturally occurring radioactive materials (NORM) s investigation. It is concluded that the average of the U, 232 Th and 226 Ra for the monazite sand of rare-earth ore is 16911, 49683, and 20072 Bq/kg, respectively. The average of U, 232 Th and 226 Ra in bastnaesite is 42, 701 and 91 Bq/kg, respectively. The average of U, 232 Th and 226 Ra in the ionic type rare-earth ore is 3918.6, 2315 and 1221 Bq/kg, respectively. (authors)

Simplified analytical model to simulate radionuclide release from radioactive waste trenches

International Nuclear Information System (INIS)

Sa, Bernardete Lemes Vieira de

2001-01-01

In order to evaluate postclosure off-site doses from low-level radioactive waste disposal facilities, a computer code was developed to simulate the radionuclide released from waste form, transport through vadose zone and transport in the saturated zone. This paper describes the methodology used to model these process. The radionuclide released from the waste is calculated using a model based on first order kinetics and the transport through porous media was determined using semi-analytical solution of the mass transport equation, considering the limiting case of unidirectional convective transport with three-dimensional dispersion in an isotropic medium. The results obtained in this work were compared with other codes, showing good agreement. (author)

Evaluation of dry solid waste recycling from municipal solid waste: case of Mashhad city, Iran.

Science.gov (United States)

Farzadkia, Mahdi; Jorfi, Sahand; Akbari, Hamideh; Ghasemi, Mehdi

2012-01-01

The recycling for recovery and reuse of material and energy resources undoubtedly provides a substantial alternative supply of raw materials and reduces the dependence on virgin feedstock. The main objective of this study was to assess the potential of dry municipal solid waste recycling in Mashhad city, Iran. Several questionnaires were prepared and distributed among various branches of the municipality, related organizations and people. The total amount of solid waste generated in Mashhad in 2008 was 594, 800  tons with per capita solid waste generation rate of 0.609  kg  person(-1) day(-1). Environmental educational programmes via mass media and direct education of civilians were implemented to publicize the advantages and necessity of recycling. The amount of recycled dry solid waste was increased from 2.42% of total dry solid waste (2588.36  ton  year(-1)) in 1999 to 7.22% (10, 165  ton  year(-1)) in 2008. The most important fractions of recycled dry solid waste in Mashhad included paper and board (51.33%), stale bread (14.59%), glass (9.73%), ferrous metals (9.73%), plastic (9.73%), polyethylene terephthalate (2.62%) and non-ferrous metals (0.97%). It can be concluded that unfortunately the potential of dry solid waste recycling in Mashhad has not been considered properly and there is a great effort to be made in order to achieve the desired conditions of recycling.

Characterisation of discharge areas of radionuclides originating from nuclear waste repositories

International Nuclear Information System (INIS)

Marklund, L.; Woerman, A.

2008-01-01

In this study, we investigate if there are certain landscape elements that will generally act as discharge areas for radio-nuclides leaking from a subsurface deposit of nuclear waste. We also characterize the typical properties that distinguish these areas from others. Understanding the processes controlling the clustering of discharge to certain areas is an additional topic of study. Landscape topography is the most important driving force for groundwater flow. Because groundwater is the main transporting agent for migrating radio-nuclides, the topography will determine the flow paths of leaking radionuclides. How topography and heterogeneities in the subsurface affect the discharge distribution of the radionuclides is the main scope of this study. An analytical and a numerical model are used. Conclusions are: Our results suggest that the varieties of landscape elements which have potential for receiving significant amounts of radio-nuclides are limited. To save recourses, the surficial radiological assessments should therefore be focused in these areas. Furthermore, the discharge areas of groundwater from repository depth have defining characteristics that distinguish them from discharge areas of shallower groundwater flow cells. Due to the similarities within deep groundwater discharge areas, one can make site-specific analyses of those areas, which have a broad applicability for migration of radio-nuclides originating from a nuclear waste repository (author)(tk)

Risk-informed assessment of radionuclide release from dissolution of spent nuclear fuel and high-level waste glass

Energy Technology Data Exchange (ETDEWEB)

Ahn, Tae M., E-mail: tae.ahn@nrc.gov

2017-06-15

Highlights: • Dissolution of HLW waste form was assessed with long-term risk informed approach. • The radionuclide release rate decreases with time from the initial release rate. • Fast release radionuclides can be dispersed with discrete container failure time. • Fast release radionuclides can be restricted by container opening area. • Dissolved radionuclides may be further sequestered by sorption or others means. - Abstract: This paper aims to detail the different parameters to be considered for use in an assessment of radionuclide release. The dissolution of spent nuclear fuel and high-level nuclear waste glass was considered for risk and performance insights in a generic disposal system for more than 100,000 years. The probabilistic performance assessment includes the waste form, container, geology, and hydrology. Based on the author’s previous extended work and data from the literature, this paper presents more detailed specific cases of (1) the time dependence of radionuclide release, (2) radionuclide release coupled with container failure (rate-limiting process), (3) radionuclide release through the opening area of the container and cladding, and (4) sequestration of radionuclides in the near field after container failure. These cases are better understood for risk and performance insights. The dissolved amount of waste form is not linear with time but is higher at first. The radionuclide release rate from waste form dissolution can be constrained by container failure time. The partial opening area of the container surface may decrease radionuclide release. Radionuclides sequestered by various chemical reactions in the near field of a failed container may become stable with time as the radiation level decreases with time.

Solid Waste Activity Packet for Teachers.

Science.gov (United States)

Illinois Univ., Urbana. Cooperative Extension Service.

This solid waste activity packet introduces students to the solid waste problem in Illinois. Topics explore consumer practices in the market place, packaging, individual and community garbage generation, and disposal practices. The activities provide an integrated approach to incorporating solid waste management issues into subject areas. The…

Solid waste 30-year volume summary

International Nuclear Information System (INIS)

Valero, O.J.; Armacost, L.L.; DeForest, T.J.; Templeton, K.J.; Williams, N.C.

1994-06-01

A 30-year forecast of the solid waste volumes to be generated or received at the US Department of Energy Hanford Site is described in this report. The volumes described are low-level mixed waste (LLMW) and transuranic/transuranic mixed (TRU/TRUM) waste that will require treatment, storage, and disposal at Hanford's Solid Waste Operations Complex (SWOC) during the 30-year period from FY 1994 through FY 2023. The data used to complete this document were collected from onsite and offsite waste generators who currently, or are planning to, ship solid wastes to the Hanford Site. An analysis of the data suggests that over 300,000 m 3 of LLMW and TRU/TRUM waste will be managed at Hanford's SWOC over the next 30 years. An extensive effort was made this year to collect this information. The 1993 solid waste forecast was used as a starting point, which identified approximately 100,000 m 3 of LLMW and TRU/TRUM waste to be sent to the SWOC. After analyzing the forecast waste volume, it was determined that additional waste was expected from the tank waste remediation system (TWRS), onsite decontamination and decommissioning (D ampersand D) activities, and onsite remedial action (RA) activities. Data presented in this report establish a starting point for solid waste management planning. It is recognized that forecast estimates will vary (typically increasing) as facility planning and missions continue to change and become better defined, but the information presented still provides useful insight into Hanford's future solid waste management requirements

Hanford Site Solid Waste Landfill permit application

International Nuclear Information System (INIS)

1991-01-01

Daily activities at the Hanford Site generate sanitary solid waste (nonhazardous and nonradioactive) that is transported to and permanently disposed of at the Hanford Site Solid Waste Landfill. This permit application describes the manner in which the solid Waste Landfill will be operated under Washington State Department of Ecology Minimum Functional Standards for Solid Waste Handling, Washington Administrative Code 173-304. The solid Waste Landfill is owned by the US Department of Energy -- Richland Operations Office and is used for disposal of solid waste generated at the US Department of Energy Hanford Site. The jurisdictional health department's permit application form for the Solid Waste Landfill is provided in Chapter 1.0. Chapter 2.0 provides a description of the Hanford Site and the Solid Waste Landfill and reviews applicable locational, general facility, and landfilling standards. Chapter 3.0 discusses the characteristics and quantity of the waste disposed of in the Solid Waste Landfill. Chapter 4.0 reviews the regional and site geology and hydrology and the groundwater and vadose zone quality beneath the landfill. Chapters 5.0, 6.0, and 7.0 contain the plan of operation, closure plan, and postclosure plan, respectively. The plan of operation describes the routine operation and maintenance of the Solid Waste Landfill, the environmental monitoring program, and the safety and emergency plans. Chapter 5.0 also addresses the operational cover, environmental controls, personnel requirements, inspections, recordkeeping, reporting, and site security. The postclosure plan describes requirements for final cover maintenance and environmental monitoring equipment following final closure. Chapter 8.0 discusses the integration of closure and postclosure activities between the Solid Waste Landfill and adjacent Nonradioactive Dangerous Waste Landfill. 76 refs., 48 figs, 15 tabs

Mobile plant for encapsulating of solid high-level radioactive waste in metal matrix

International Nuclear Information System (INIS)

Sobolev, I.A.; Arustamov, A.Eh.; Shiryaev, V.V.; Ozhovan, M.I.; Semenov, K.N.; Kachalov, M.B.

1993-01-01

Technology for disposal of spent radionuclide sources of ionizing radiation into the standard well-type storage facilities is considered. Universal mobile facility, providing for incorporation of high-level solid wastes into metallic matrices, is proposed. The facility consists of separate moduli, assembled on a transport platform. Electrical meter, wherein the matrix metal (lead and its alloys) is melted and heated up to 600-800 C constitutes the basic modulus in the facility. 4 refs., 4 figs

Solid waste handling

International Nuclear Information System (INIS)

Parazin, R.J.

1995-01-01

This study presents estimates of the solid radioactive waste quantities that will be generated in the Separations, Low-Level Waste Vitrification and High-Level Waste Vitrification facilities, collectively called the Tank Waste Remediation System Treatment Complex, over the life of these facilities. This study then considers previous estimates from other 200 Area generators and compares alternative methods of handling (segregation, packaging, assaying, shipping, etc.)

Groundwater Monitoring Plan for the Solid Waste Landfill

International Nuclear Information System (INIS)

Lindberg, J.W.; Chou, C.J.

2000-01-01

The Solid Waste Landfill (SWL) is regulated by the Washington State Department of Ecology under WAC 173-304. Between 1973 and 1976, the landfill received primarily paper waste and construction debris, but it also received asbestos, sewage, and catch tank liquid waste. Groundwater monitoring results indicate the SWL has contaminated groundwater with volatile organic compounds and possibly metals at levels that exceed regulatory limits. DynCorp, Tri-Cities, Inc. operates the facility under an interim closure plan (final closure plan will be released shortly). Pacific Northwest National Laboratory (PNNL) monitors groundwater at the site. This monitoring plan includes well and constituent lists, and summarizes sampling, analytical, and quality control requirements. Changes from the previous monitoring plan include elimination of two radionuclides from the analyte list and some minor changes in the statistical analysis. Existing wells in the current monitoring network only monitor the uppermost portion of the upper-most aquifer. Therefore, two new downgradient wells and one existing upgradient well are proposed to determine whether groundwater waste constituents have reached the lower portion of the uppermost aquifer. The proposed well network includes three upgradient wells and ten downgradient wells. The wells will be sampled quarterly for 14 analytes required by WAC 173-304-490 plus volatile organic compounds and filtered arsenic as site-specific analytes

Groundwater Monitoring Plan for the Solid Waste Landfill

Energy Technology Data Exchange (ETDEWEB)

JW Lindberg; CJ Chou

2000-12-14

The Solid Waste Landfill (SWL) is regulated by the Washington State Department of Ecology under WAC 173-304. Between 1973 and 1976, the landfill received primarily paper waste and construction debris, but it also received asbestos, sewage, and catch tank liquid waste. Groundwater monitoring results indicate the SWL has contaminated groundwater with volatile organic compounds and possibly metals at levels that exceed regulatory limits. DynCorp, Tri-Cities, Inc. operates the facility under an interim closure plan (final closure plan will be released shortly). Pacific Northwest National Laboratory (PNNL) monitors groundwater at the site. This monitoring plan includes well and constituent lists, and summarizes sampling, analytical, and quality control requirements. Changes from the previous monitoring plan include elimination of two radionuclides from the analyte list and some minor changes in the statistical analysis. Existing wells in the current monitoring network only monitor the uppermost portion of the upper-most aquifer. Therefore, two new downgradient wells and one existing upgradient well are proposed to determine whether groundwater waste constituents have reached the lower portion of the uppermost aquifer. The proposed well network includes three upgradient wells and ten downgradient wells. The wells will be sampled quarterly for 14 analytes required by WAC 173-304-490 plus volatile organic compounds and filtered arsenic as site-specific analytes.

Process for encapsulating radionuclides

International Nuclear Information System (INIS)

Brownell, L.E.; Isaacson, R.E.

1976-01-01

Radionuclides are immobilized in virtually an insoluble form by reacting at a temperature of at least 90 0 C as an aqueous alkaline mixture having a solution pH of at least 10, containing a source of silicon, the radionuclide waste, and a metal cation. The molar ratio of silicon to the metal cation is on the order of unity to produce a gel from which complex metalosilicates crystallize to entrap the radionuclides within the resultant condensed crystal lattice. The product is a silicious stone-like material which is virtually insoluble and nonleachable in alkaline or neutral environment. One embodiment provides for the formation of the complex metalo-silicates, such as synthetic pollucite, by gel formation with subsequent calcination to the solid product; another embodiment utilizes a hydrothermal process, either above ground or deep within basalt caverns, at greater than atmospheric pressures and a temperature between 90 and 500 0 C to form complex metalo-silicates, such as strontium aluminosilicate. Another embodiment provides for the formation of complex metalo-silicates, such as synthetic pollucite, by slurrying an alkaline mixture of bentonite or kaolinite with a source of silicon and the radionuclide waste in salt form. In each of the embodiments a mobile system is achieved whereby the metalo-silicate constituents reorient into a condensed crystal lattice forming a cage structure with the condensed metalo-silicate lattice which completely surrounds the radionuclide and traps the radionuclide therein; thus rendering the radionuclide virtually insoluble

Application od scaling technique for estimation of radionuclide inventory in radioactive waste

International Nuclear Information System (INIS)

Hertelendi, E.; Szuecs, Z.; Gulyas, J.; Svingor, E.; Csongor, J.; Ormai, P.; Fritz, A.; Solymosi, J.; Gresits, I.; Vajda, N.; Molnar, Zs.

1996-01-01

Safety studies related to the disposal of low- and intermediate waste indicate that the long term risk is determined by the presence of long-lived nuclides such as 14 C, 59 Ni, 63 Ni, 99 Tc, 129 I and the transuranium elements. As most of these nuclides are difficult to measure, the correlation between these critical nuclides and some other easily measurable key nuclides such as 60 Co and 137 Cs has been investigated for typical waste streams of Paks Nuclear Power Plant (Hungary) and scaling factors have been proposed. An automated gamma-scanning monitor has been purchased and calibrated to determine the gamma-emitting radionuclides. Radiochemical methods have been developed to determine significant difficult-to-measure radionuclides. The radionuclides of interest have been 3 H, 14 C, 90 Sr, 55 Fe, 59 Ni, 99 Tc, 129 I and TRUs. The measurements taken so far have revealed brand new information and data on radiological composition of waste of WWER-type reactors. The reliability of the radioanalytical methods was checked by an international intercomparison test. For all radionuclides the Hungarian results were in the average range of the total data set. (author)

Method of processing radioactive solid wastes

International Nuclear Information System (INIS)

Ootaka, Hisashi; Aizu, Tadashi.

1980-01-01

Purpose: To improve the volume-reducing effect for the radioactive solids wastes by freezing and then pulverizing them. Method: Miscellaneous radioactive solid wastes produced from a nuclear power plant and packed in vinyl resin bags are filled in a drum can and nitrogen gas at low temperature (lower than 0 0 C) from a cylinder previously prepared by filling liquid nitrogen (at 15kg/cm 2 , -196 0 C) to freeze the radioactive solid wastes. Thereafter, a hydraulic press is inserted into the drum can to compress and pulverize the thus freezed miscellaneous radioactive solid wastes into powder. The powder thus formed does not expand even after removing the hydraulic press from the drum can, whereby the volume reduction of the radioactive solid wastes can be carried out effectively. (Horiuchi, T.)

Determination of radionuclides present in the relation of waste plant storage of El Cabril

International Nuclear Information System (INIS)

Suarez, J.A.; Rodriguez Alcala, M.; Estartero, A.G.; Pina, G.; Gascon, J.L.

1997-03-01

Different waste streams of low and medium level radioactive are generated from the operation of Nuclear Power Plants with light water reactors. The most important waste streams are: spent ion exchange resin, used to purify the water of the reactor coolant and the evaporator concentrates produced in the evaporation of some liquid radioactive waste. In this paper are show the improvement and development of the analytical methods of all these radionuclides, performed in the CIEMAT project about Characterization of Radioactive Wastes and Materials. The alpha, beta and low energy gamma-emitting radionuclides are analyzed after the separation procedure by alpha-spectrometry, liquid scintillation counting and low-energy gamma spectrometry. The high energy gamma-emitting radionuclides (>50 keV) are analyzed by gamma spectrometry without separation. This work has been developed within the framework of the CIEMAT-ENRESA Association Agreement. (Author) 12 refs

1995 Baseline solid waste management system description

International Nuclear Information System (INIS)

Anderson, G.S.; Konynenbelt, H.S.

1995-09-01

This provides a detailed solid waste system description that documents the treatment, storage, and disposal (TSD) strategy for managing Hanford's solid low-level waste, low-level mixed waste, transuranic and transuranic mixed waste, and greater-than-Class III waste. This system description is intended for use by managers of the solid waste program, facility and system planners, as well as system modelers. The system description identifies the TSD facilities that constitute the solid waste system and defines these facilities' interfaces, schedules, and capacities. It also provides the strategy for treating each of the waste streams generated or received by the Hanford Site from generation or receipt through final destination

Technical and economic evaluation of processes being developed for solid waste processing

International Nuclear Information System (INIS)

Tittlova, E.; Hladky, E.

1985-01-01

An analysis was made of the economic benefits of two developed processes for reducing the volume of solid radioactive wastes prior to disposal, namely compacting and incineration. Input data were obtained from the actual production of solid radioactive wastes at the V-1 nuclear power plant, from compacting on site, and the operation of an experimental incineration plant. The two WWER-440 units of the V-1 nuclear power plant generate ca 200 m 3 of wastes per annum (not including air filters and wood) of which 69% is assumed to be incinerable and 27% compactable. The rest is disposed of without prior volume reduction. Disposal costs are assessed at 7,500 Czechoslovak crowns per 1 m 3 of wastes, representing a total of 1.5 million crowns per annum. As compared with the disposal of unprocessed wastes the compacting of 95% of wastes generated, reduces the costs of transport and disposal to 25%. With both compacting and incineration, the costs represent 16 to 25% of the initial sum, depending on the ratio of the two processes. The high capital costs of building the incineration plant will thus be offset by the reduction in costs of the radioactive waste disposal. From the technical point of view the analysis did not make a detailed comparison of the properties of the compacted incinerable wastes and ash with regard to stability and leachability of radionuclides. It did also not take into account operating costs and the technological challenge of the two waste volume redution processes. (Z.M.)

LCA of Solid Waste Management Systems

DEFF Research Database (Denmark)

Bakas, Ioannis; Laurent, Alexis; Clavreul, Julie

2018-01-01

The chapter explores the application of LCA to solid waste management systems through the review of published studies on the subject. The environmental implications of choices involved in the modelling setup of waste management systems are increasingly in the spotlight, due to public health...... concerns and new legislation addressing the impacts from managing our waste. The application of LCA to solid waste management systems, sometimes called “waste LCA”, is distinctive in that system boundaries are rigorously defined to exclude all life cycle stages except from the end-of-life. Moreover...... LCA on solid waste systems....

Solid Waste Management Program Plan

Energy Technology Data Exchange (ETDEWEB)

Duncan, D.R.

1990-08-01

The objective of the Solid Waste Management Program Plan (SWMPP) is to provide a summary level comprehensive approach for the storage, treatment, and disposal of current and future solid waste received at the Hanford Site (from onsite and offsite generators) in a manner compliant with current and evolving regulations and orders (federal, state, and Westinghouse Hanford Company (Westinghouse Hanford)). The Plan also presents activities required for disposal of selected wastes currently in retrievable storage. The SWMPP provides a central focus for the description and control of cost, scope, and schedule of Hanford Site solid waste activities, and provides a vehicle for ready communication of the scope of those activities to onsite and offsite organizations. This Plan represents the most complete description available of Hanford Site Solid Waste Management (SWM) activities and the interfaces between those activities. It will be updated annually to reflect changes in plans due to evolving regulatory requirements and/or the SWM mission. 8 refs., 9 figs., 4 tabs.

Targeted radionuclide therapy for solid tumors: An overview

International Nuclear Information System (INIS)

De Nardo, Sally J.; De Nardo, Gerald L.

2006-01-01

Although radioimmunotherapy (RIT) has been effective in non-Hodgkin's lymphoma (NHL) as a single agent, solid tumors have shown less clinically significant therapeutic response to RIT alone. The clinical impact of RIT or other forms of targeted radionuclide therapy for solid tumors depends on the development of a high therapeutic index (TI) for the tumor vs. normal tissue effect, and the implementation of RIT as part of synergistic combined modality therapy (CMRIT). Preclinical and clinical studies have provided a wealth of information, and new prototypes or paradigms have shed light on future possibilities in many instances. Evidence suggests that combination and sequencing of RIT in CMRIT appropriately can provide effective treatment for many solid tumors. Vascular targets provide RIT enhancement opportunities and nanoparticles may prove to be effective carriers for RIT combined with intracellular drug delivery or alternating magnetic frequency (AMF) induced thermal tumor necrosis. The sequence and timing of combined modality treatments will be of critical importance to achieve synergy for therapy while minimizing toxicity. Fortunately, the radionuclide used for RIT also provides a signal useful for nondestructive quantitation of the influence of sequence and timing of CMRIT on events in animals and patients. This can be readily accomplished clinically using quantitative high-resolution imaging (e.g., positron emission tomography [PET])

FFTF radioactive solid waste handling and transport

International Nuclear Information System (INIS)

Thomson, J.D.

1982-01-01

The equipment necessary for the disposal of radioactive solid waste from the Fast Flux Test Facility (FFTF) is scheduled to be available for operation in late 1982. The plan for disposal of radioactive waste from FFTF will utilize special waste containers, a reusable Solid Waste Cask (SWC) and a Disposable Solid Waste Cask (DSWC). The SWC will be used to transport the waste from the Reactor Containment Building to a concrete and steel DSWC. The DSWC will then be transported to a burial site on the Hanford Reservation near Richland, Washington. Radioactive solid waste generated during the operation of the FFTF consists of activated test assembly hardware, reflectors, in-core shim assemblies and control rods. This radioactive waste must be cleaned (sodium removed) prior to disposal. This paper provides a description of the solid waste disposal process, and the casks and equipment used for handling and transport

Development of scaling factor prediction method for radionuclide composition in low-level radioactive waste

International Nuclear Information System (INIS)

Park, Jin Beak

1995-02-01

Low-level radioactive waste management require the knowledge of the natures and quantities of radionuclides in the immobilized or packaged waste. U. S. NRC rules require programs that measure the concentrations of all relevant nuclides either directly or indirectly by relating difficult-to-measure radionuclides to other easy-to-measure radionuclides with application of scaling factors. Scaling factors previously developed through statistical approach can give only generic ones and have many difficult problem about sampling procedures. Generic scaling factors can not take into account for plant operation history. In this study, a method to predict plant-specific and operational history dependent scaling factors is developed. Realistic and detailed approach are taken to find scaling factors at reactor coolant. This approach begin with fission product release mechanisms and fundamental release properties of fuel-source nuclide such as fission product and transuranic nuclide. Scaling factors at various waste streams are derived from the predicted reactor coolant scaling factors with the aid of radionuclide retention and build up model. This model make use of radioactive material balance within the radioactive waste processing systems. Scaling factors at reactor coolant and waste streams which can include the effects of plant operation history have been developed according to input parameters of plant operation history

Radionuclide Concentration in Soils and Vegetation at Low-Level Radioactive Waste Disposal Area G during 2005

International Nuclear Information System (INIS)

Fresquez, P.R.; McNaughton, M.W.; Winch, M.J.

2005-01-01

Soil samples were collected at 15 locations and unwashed overstory and understory vegetation samples were collected from up to nine locations within and around the perimeter of Area G, the primary disposal facility for low-level radioactive solid waste at Los Alamos National Laboratory (LANL). Soil and plant samples were also collected from the proposed expansion area west of Area G for the purpose of gaining preoperational baseline data. Soil and plant samples were analyzed for radionuclides that have shown a history of detection in past years; these included 3 H, 238 Pu, 239,240 Pu, 241 Am, 234 U, 235 U, and 238 U for soils and 3 H, 238 Pu, and 239,240 Pu for plants. As in previous years, the highest levels of 3 H in soils and vegetation were detected at the south portion of Area G near the 3 H shafts; whereas, the highest concentrations of the Pu isotopes were detected in the northern and northeastern portions near the pads for transuranic waste. All concentrations of radionuclides in soils and vegetation, however, were still very low (pCi range) and far below LANL screening levels and regulatory standards

National Low-Level Waste Management Program radionuclide report series. Volume 2, Niobium-94

International Nuclear Information System (INIS)

Adams, J.P.; Carboneau, M.L.

1995-04-01

The Purpose of the National Low-Level Waste Management Program Radionuclide Report Series is to provide information to, state representatives and developers of low-level radioactive waste disposal facilities about the radiological chemical, and physical characteristics of selected radionuclides and their behavior in the low-level radioactive waste disposal facility environment. Extensive surveys of available literature provided information used to produce this series of reports and an introductory report. This report is Volume 11 of the series. It outlines the basic radiological, chemical, and physical characteristics of niobium-94, waste types and forms that contain it, and its behavior in environmental media such as soils, plants, groundwater, air, animals and the human body

Evaluation of Waste-to-Energy Potential of Domestic Solid Wastes in ...

African Journals Online (AJOL)

ADOWIE PERE

waste in the metropolis ends up on illegal waste dumpsites. The aim of this paper was to investigate the waste-to-energy potentials of domestic solid wastes in Benin metropolis, Nigeria using a three-phase study plan - study of current waste management activities, characterization of domestic solid waste and determination ...

An approach for sampling solid heterogeneous waste at the Hanford Site waste receiving and processing and solid waste projects

International Nuclear Information System (INIS)

Sexton, R.A.

1993-03-01

This paper addresses the problem of obtaining meaningful data from samples of solid heterogeneous waste while maintaining sample rates as low as practical. The Waste Receiving and Processing Facility, Module 1, at the Hanford Site in south-central Washington State will process mostly heterogeneous solid wastes. The presence of hazardous materials is documented for some packages and unknown for others. Waste characterization is needed to segregate the waste, meet waste acceptance and shipping requirements, and meet facility permitting requirements. Sampling and analysis are expensive, and no amount of sampling will produce absolute certainty of waste contents. A sampling strategy is proposed that provides acceptable confidence with achievable sampling rates

Analysis of the low-level waste radionuclide inventory for the Radioactive Waste Management Complex performance assessment

Energy Technology Data Exchange (ETDEWEB)

Plansky, L.E.; Hoiland, S.A.

1992-02-01

This report summarizes the results of a study to improve the estimates of the radionuclides in the low-level radioactive waste (LLW) inventory which is buried in the Idaho National Engineering Laboratory (INEL) Radioactive Waste Management Complex (RWMC) Subsurface Disposal Area (SDA). The work is done to support the RWMC draft performance assessment (PA). Improved radionuclide inventory estimates are provided for the INEL LLW generators. Engineering, environmental assessment or other research areas may find use for the information in this report. It may also serve as a LLW inventory baseline for data quality assurance. The individual INEL LLW generators, their history and their activities are also described in detail.

Analysis of the low-level waste radionuclide inventory for the Radioactive Waste Management Complex performance assessment

International Nuclear Information System (INIS)

Plansky, L.E.; Hoiland, S.A.

1992-02-01

This report summarizes the results of a study to improve the estimates of the radionuclides in the low-level radioactive waste (LLW) inventory which is buried in the Idaho National Engineering Laboratory (INEL) Radioactive Waste Management Complex (RWMC) Subsurface Disposal Area (SDA). The work is done to support the RWMC draft performance assessment (PA). Improved radionuclide inventory estimates are provided for the INEL LLW generators. Engineering, environmental assessment or other research areas may find use for the information in this report. It may also serve as a LLW inventory baseline for data quality assurance. The individual INEL LLW generators, their history and their activities are also described in detail

A Survey of Municipal Solid Waste Generation in 22 Regions of Tehran With Solid Waste Reduction Approach

Directory of Open Access Journals (Sweden)

MA Abduli

2015-07-01

Methods: The study was a descriptive cross-sectional one conducted from 2010 to 2014. Relevant officials of the waste recovery in 22 regions of Tehran were approached in order to collect data about municipal solid waste generation through interviewing, filling out questionnaires, conducting field visits from Aradkooh Disposal and Processing Complex and collecting information on disposal and destiny of wastes. Then the data were compiled and analyzed. Results: Total solid waste generation in Tehran from 2010 to 2014 amounted to respectively 3389662, 3399344, 3449338 and 3245157 Metric Tons, categorized into three groups of municipal, companies and townships and hospital wastes. Most of the generated waste produced in Tehran was that of households and commercial (known as municipal waste from 22 Regions of Tehran. Based on the surveys conducted, per capita solid waste generation of 11 regions of Tehran ranged from 550 to 1000 grams and in other 11 ones from 1000 to 1521 grams per capita per day. The lowest and highest waste generation rate belonged respectively to region 13 with 556 grams and region 12 with 1521 grams per capita per day in 2011. Conclusion: Comparing per capita generation of municipal solid waste in different municipal regions in Tehran with maximum acceptable capacity of waste generation indicates the deviation of waste generation of all Tehran regions from the standard acceptable amount. Therefore, not only is it necessary to plan and take strategic measures to reduce Tehran waste generation but also these programs and measures should be specific to each region considering its specifications and solid waste quality and quantity.

Environmental pollution from solid wastes

International Nuclear Information System (INIS)

Jervis, R.E.; Krishnan, S.S.; Accetone, P.; Arifin, N.; Ko, M.M.C.; Nhan, C.; Nguyen, L.; Vela, L.; Yee, T.

1992-01-01

Research completed under the CRP during the past two years has encompassed several related aspects of environmental problems associated with solid wastes: assessment of major sources of toxic elements in a variety of solid waste forms, their leachability by simulated groundwater or rain/acid rain and the determination of the contribution of hospital incinerator to atmospheric releases. The summary of the findings of these investigations are given in this report. Unexpected high levels of cadmium have been found in many solid wastes. Leaching tests indicate that, in some cases, over 70% of this can be leached out into the nearby waterways. Combustibility tests indicated that 35 to 45% of it is emitted to the atmosphere during burning. This explains the increased levels of cadmium in air particulates sampled downwind from waste incinerators. Plastic items in municipal and hospital wastes were particularly elevated in Cd, Cl, Cr, Ba and Zn. Up to 1300 μg/g of Cd was found in some domestic items. By inference, Pb also is found in some common plastics but the current studies did not permit Pb determination in solid wastes, but only in aerosols. (author). 8 tabs

The diffusion and deposition of the gaseous and solid alpha radionuclides/aerosols in air

International Nuclear Information System (INIS)

Danis, A.; Ciubotariu, M.; Oncescu, M.; Mocsy, I.

1999-01-01

The diffusion and deposition of gaseous and solids alpha radionuclides and aerosols in air are processes which implicate low element amounts and therefore their studies require the using of very accurate and sensitive analysis methods. The alpha track method meets these requirements. The used alpha radionuclides were: Rn-222, as gaseous radionuclide and its solid descendants genetically related as solid radionuclides and the descendants attached to different particles from air as alpha aerosols. All these radionuclides were obtained from a calibrated Ra-226 source. The source was included into an air tight device with a well known volume and used after 40 days when the Ra-226 and its alpha descendants were under radioactive equilibrium. The relative amount and activity of each decay product, at any duration, for any initial mass of Ra-226 parent radionuclide, were calculated using a programme for computation of the U-238 radioactive series gamma accumulation, UURASE, adapted for alpha accumulation as ALFAURASE programme. The radon, Rn-222, as well as the solid alpha radionuclides and aerosols were measured using a new alpha monitoring device with or without paper filter for solid radionuclides and aerosols stopping. The track detectors of CR-39 type were incorporated with these monitoring devices. In order to calibrate the CR-39 detectors, a radon intercomparison programme was established with the participation of the SSNTD group from the Institute of Nuclear Research ATOMKI, Debrecen, Hungary, Institute of Public Health, Cluj-Napoca and SSNTD research group from IFIN-HH. We have used for radon calibration a special experimental device and a Ra-226 source. Using an air tight diffusion and deposition device, coupled with the source device, the concentration of radon and solid alpha radionuclides and aerosols were determined using the alpha track method. The alpha monitoring devices were fixed vertically at different distances from the place of radon penetration into

Development of solid radionuclide waste forms in the United States

International Nuclear Information System (INIS)

Crandall, J.L.

1979-01-01

New ways of reworking the wastes require a new classification in terms of the final waste forms. This paper surveys the candidate forms: encapsulation binders, in-place solidification waste forms, glass and ceramic waste forms, mineral waste forms, matrix waste forms, gaseous waste forms (fixation), and canisters and engineered barriers. Participants in the US-high-level waste form development program are listed. Requirements and selection of waste forms are also discussed. 26 references

Integrated solid waste management in Germany

Energy Technology Data Exchange (ETDEWEB)

NONE

1995-07-01

This report covers Germany`s experience with integrated solid waste management programs. The municipal solid waste practices of four cities include practices and procedures that waste facility managers with local or state governments may consider for managing their own day-to-day operations.

Leachability of radionuclides from cement solidified waste forms produced at operating nuclear power plants

International Nuclear Information System (INIS)

Croney, S.T.

1985-03-01

This study determined the leachability indexes of radionuclides contained in solidified liquid wastes from operating nuclear power plants. Different sizes of samples of cement-solidified liquid wastes were collected from two nuclear power plants - a pressurized water reactor and a boiling water reactor - to correlate radionuclide leaching from small- and full-sized (55-gallon) waste forms. Diffusion-based model analysis (ANS 16.1) of measured radionuclide leach data from both small- and full-sized samples was performed and indicate that leach data from small samples can be used to determine leachability indexes for full-sizes waste forms. The leachability indexes for cesium, strontium, and cobalt isotopes were determined for waste samples from both plants according to the models used for ANS 16.1. The leachability indexes for the pressurized water reactor samples were 6.4 for cesium, 7.1 for strontium, and 10.4 for cobalt. Leachability indexes for the boiling water reactor samples were 6.5 for cesium, 8.6 for strontium, and 11.1 for cobalt

On the use of the spectroscopic techniques to model the interactions between radionuclides and solid minerals

Energy Technology Data Exchange (ETDEWEB)

Simoni, E. [IPN, Paris XI University, 91406 Orsay (France)]. e-mail: simoni@ipno.in2p3.fr

2004-07-01

In order to determine the radionuclides sorption constants on solid natural minerals, both thermodynamic and structural investigations, using spectroscopic techniques, are presented. The natural clays, that could be used as engineering barrier in the nuclear waste geological repository, are rather complex minerals. Therefore, in order to understand how these natural materials retain the radionuclides, it is necessary first to perform these studies on simple substrates such as phosphates, oxides and silicates (as powder and single crystal as well) and then extrapolate the obtained results on the natural minerals. As examples, the main results on the sorption processes of the hexavalent uranium onto zircon (ZrSiO{sub 4}) and lanthanum phosphate (LaPO{sub 4}) are presented. The corresponding sorption curves are simulated using the results obtained with the following spectroscopic techniques: laser induced spectro fluorimetry, X-ray photoelectron spectroscopy (XP S), X-ray absorption spectroscopy (Exafs). Finally, the thermodynamic sorption constants are calculated. (Author)

Electrodialytic remediation of solid waste

DEFF Research Database (Denmark)

Hansen, Henrik K.; Ottosen, Lisbeth M.; Karlsmose, Bodil

1996-01-01

Electrodialytic remediation of heavy metal polluted solid waste is a method that combines the technique of electrodialysis with the electromigration of ions in the solid waste. Results of laboratory scale remediation experiments of soil are presented and considerations are given on how to secure...

Cadmium complexation by solid waste leachates

DEFF Research Database (Denmark)

Xu Ze Lun; Christensen, Thomas H.

1989-01-01

A previously reported method for determination of Cd species in solid waste leachates has been applied to ten leachate samples representing five different types of solid waste: refuse compost, flyash from coal combustion, sewage sludge, refuse incineration residues and landfilled municipal waste......, slowly labile complexes and stable complexes. Leachates originating from the same type of solid waste showed different fractions of Cd, in particular with respect to free divalent Cd and stable Cd complexes. Only coal flyash showed almost identical fractions of Cd in the two leachates. The latter is due...

Municipal solid waste composition determination supporting the integrated solid waste management system in the island of Crete

International Nuclear Information System (INIS)

Gidarakos, E.; Havas, G.; Ntzamilis, P.

2006-01-01

A one-year survey was conducted in the greater region of Crete (located at the lower region of the Aegean Sea) for the purpose of identifying waste composition (including chemical and physical characterization), as well as any seasonal variation. The investigation was carried out repeatedly at seven landfills and one transfer station in Crete, in four phases. Each sampling phase corresponded to a season (autumn, winter, spring, summer). ASTM D5231-92(2003) standard method and RCRA Waste Sampling Draft Technical Guidance were used. Hand sorting was used for classifying the collected wastes into the following categories: plastics, paper, metals, aluminium, leather-wood-textiles-rubbers, organic wastes, non-combustibles and miscellaneous. Further analysis included proximate and ultimate analysis of combustible materials. Metals such as lead, cadmium and mercury were also investigated. The results show that there has been a significant decrease of organic wastes during the last decade due to the increase of packaging materials, as a result of a change in consumption patterns. Three main waste categories were determined: organic wastes, paper and plastics, which combined represent 76% of the total waste in Crete. Furthermore, a high fraction of glass and a seasonal variation of aluminium indicate a strong correlation of waste composition with certain human activities, such as tourism. There is also a variation between the municipal solid waste (MSW) composition in the region of Crete (2003-2004) and MSW composition suggested in the National Solid Waste Planning (2000) [National Solid Waste Planning, 2000. Completion and particularization of Common Ministerial Act 113944//1944/1997: National Solid Waste Planning, June 2000]. The results of this survey are to be utilized by the regional solid waste authorities in order to establish an integrated waste treatment site, capable of fulfilling the regional waste management demands

Municipal solid waste composition determination supporting the integrated solid waste management system in the island of Crete.

Science.gov (United States)

Gidarakos, E; Havas, G; Ntzamilis, P

2006-01-01

A one-year survey was conducted in the greater region of Crete (located at the lower region of the Aegean Sea) for the purpose of identifying waste composition (including chemical and physical characterization), as well as any seasonal variation. The investigation was carried out repeatedly at seven landfills and one transfer station in Crete, in four phases. Each sampling phase corresponded to a season (autumn, winter, spring, summer). ASTM D5231-92(2003) standard method and RCRA Waste Sampling Draft Technical Guidance were used. Hand sorting was used for classifying the collected wastes into the following categories: plastics, paper, metals, aluminium, leather-wood-textiles-rubbers, organic wastes, non-combustibles and miscellaneous. Further analysis included proximate and ultimate analysis of combustible materials. Metals such as lead, cadmium and mercury were also investigated. The results show that there has been a significant decrease of organic wastes during the last decade due to the increase of packaging materials, as a result of a change in consumption patterns. Three main waste categories were determined: organic wastes, paper and plastics, which combined represent 76% of the total waste in Crete. Furthermore, a high fraction of glass and a seasonal variation of aluminium indicate a strong correlation of waste composition with certain human activities, such as tourism. There is also a variation between the municipal solid waste (MSW) composition in the region of Crete (2003-2004) and MSW composition suggested in the National Solid Waste Planning (2000) [National Solid Waste Planning, 2000. Completion and particularization of Common Ministerial Act 113944//1944/1997: National Solid Waste Planning, June 2000]. The results of this survey are to be utilized by the regional solid waste authorities in order to establish an integrated waste treatment site, capable of fulfilling the regional waste management demands.

Possible global environmental impacts of solid waste practices

Energy Technology Data Exchange (ETDEWEB)

Davis, M.M.; Holter, G.M.; DeForest, T.J.; Stapp, D.C. [Pacific Northwest Lab., Richland, WA (United States); Dibari, J.C. [Heritage College, Toppenish, WA (United States)

1994-09-01

Pollutants resulting from the management of solid waste have been shown to affect the air, land, oceans, and waterways. In addition, solid wastes have other, more indirect impacts such as reduction in feedstocks of natural resources, because useful materials are disposed of rather than recycled. The objective of this study is to evaluate solid waste management practices that have negative implications on the global environment and develop recommendations for reducing such impacts. Recommendations identifying needed changes are identified that will reduce global impacts of solid waste practices in the future. The scope of this study includes the range of non-hazardous solid wastes produced within our society, including municipal solid waste (MSW) and industrial solid waste (ISW), as well as industry-specific wastes from activities such as construction, demolition, and landclearing. Most solid waste management decisions continue to be made and implemented at very local levels, predominantly with a short-term focus to respond to relatively immediate pressures of landfill shortages, funding problems, political considerations, and the like. In this rush to address immediate local problems, little consideration is being given to potential impacts, either short- or long-term, at the national or global level resulting from solid waste management practices. More and more, the cumulative impacts from local decisions concerning solid waste management are beginning to manifest themselves in broader, longer-term impacts than are being addressed by the decision-makers or, at the very least, are presenting a greater and greater potential for such impacts.

Radionuclide transport modelling for a buried near surface low level radioactive waste

International Nuclear Information System (INIS)

Terzi, R.

2004-01-01

The disposal of radioactive waste, which is the last step of any radioactive waste management policy, has not yet been developed in Turkey. The existing legislation states only the discharge limits for the radioactive wastes to be discharged to the environment. The objective of this modelling study is to assist in safety assessment and selecting disposal site for gradually increasing non-nuclear radioactive wastes. This mathematical model has been developed for the environmental radiological assessment of near surface disposal sites for the low and intermediate level radioactive wastes. The model comprised of three main components: source term, geosphere transport and radiological assessment. Radiation dose for the babies (1 years age) and adults (≥17 years age) have been computed for the radionuclides Cesium 137 (Cs-137) and Strontium 90 (Sr-90), having the activity of 1.10 12 Becquerel(Bq), in radioactive waste through transport of radionuclide in liquid phase with the various pathways. The model consisted of first order ordinary differential equations was coded as a TCODE file in MATLAB program. The radiation dose to man for the realist case and low probability case have been calculated by using Runge-Kutta solution method in MATLAB programme for radionuclide transport from repository to soil layer and then to the ground water(saturated zone) through drinking water directly and consuming agricultural and animal products pathways in one year period. Also, the fatal cancer risk assessment has been made by taking into account the annual dose received by people. Various dose values for both radionuclides have been found which depended on distribution coefficient, retardation factor and dose conversion factors. The most important critical parameters on radiological safety assessment are the distribution coefficient in soil layer, seepage velocity in unsaturated zone and thickness of the unsaturated zone (soil zone). The highest radiation dose and average dose to

Assessment of LANL solid low-level waste management documentation

International Nuclear Information System (INIS)

Klein, R.B.; Jennrich, E.A.; Lund, D.M.; Danna, J.G.; Davis, K.D.; Rutz, A.C.

1991-04-01

DOE Order 5820.2A requires that a system performance assessment be conducted to assure efficient and compliant management of all radioactive waste. The objective of this report is to determine the present status of the Radioactive Waste Operations Section's capabilities regarding preparation and maintenance of appropriate criteria, plans and procedures and identify particular areas where these documents are not presently in existence or being fully implemented. DOE Order 5820.2A, Radioactive Waste Management, Chapter III sets forth the requirements and guidelines for preparation and implementation of criteria, plans and procedures to be utilized in the management of solid low-level waste. The documents being assessed in this report are: Solid Low-Level Waste Acceptance Criteria, Solid Low-Level Waste Characterization Plan, Solid Low-Level Waste Certification Plan, Solid Low-Level Waste Acceptance Procedures, Solid Low-Level Waste Characterization Procedures, Solid Low-Level Waste Certification Procedures, Solid Low-Level Waste Training Procedures, and Solid Low-Level Waste Recordkeeping Procedures. Suggested outlines for these documents are presented as Appendix A

Solid waste treatment processes for space station

Science.gov (United States)

Marrero, T. R.

1983-01-01

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

The main rules regarding the management of solid waste and liquid effluent contaminated during use at nuclear medicine departments; Les principales regles de gestion des dechets solides et des effluents liquides contamines dans les services de medecine nucleaire

Energy Technology Data Exchange (ETDEWEB)

Boudouin, E. [Autorite de Surete Nucleaire, Direction des rayonnements ionisants et de la sante, 75 - Paris (France)

2011-02-15

This article describes the key requirements applicable to the management of contaminated medical waste and effluent from hospitals and health care centres, and more especially from nuclear medicine departments that use radionuclides for the purposes of diagnosis (in vivo or in vitro) or in patient treatment. It also presents the key management regulations, making a distinction between contaminated solid waste and contaminated liquid waste from such nuclear medicine departments. (author)

Solid-Waste Management

Science.gov (United States)

Science Teacher, 1973

1973-01-01

Consists of excerpts from a forthcoming publication of the United States Environmental Protection Agency, Student's Guide to Solid-Waste Management.'' Discusses the sources of wastes from farms, mines, factories, and communities, the job of governments, ways to collect trash, methods of disposal, processing, and suggests possible student action.…

Radionuclide Retention Mechanisms in Secondary Waste-Form Testing: Phase II

Energy Technology Data Exchange (ETDEWEB)

Um, Wooyong; Valenta, Michelle M.; Chung, Chul-Woo; Yang, Jungseok; Engelhard, Mark H.; Serne, R. Jeffrey; Parker, Kent E.; Wang, Guohui; Cantrell, Kirk J.; Westsik, Joseph H.

2011-09-26

This report describes the results from laboratory tests performed at Pacific Northwest National Laboratory (PNNL) for Washington River Protection Solutions (WRPS) to evaluate candidate stabilization technologies that have the potential to successfully treat liquid secondary waste stream effluents produced by the Hanford Tank Waste Treatment and Immobilization Plant (WTP). WRPS is considering the design and construction of a Solidification Treatment Unit (STU) for the Effluent Treatment Facility (ETF) at Hanford. The ETF, a multi-waste, treatment-and-storage unit that has been permitted under the Resource Conservation and Recovery Act (RCRA), can accept dangerous, low-level, and mixed wastewaters for treatment. The STU needs to be operational by 2018 to receive secondary liquid waste generated during operation of the WTP. The STU will provide the additional capacity needed for ETF to process the increased volume of secondary waste expected to be produced by WTP. This report on radionuclide retention mechanisms describes the testing and characterization results that improve understanding of radionuclide retention mechanisms, especially for pertechnetate, {sup 99}TcO{sub 4}{sup -} in four different waste forms: Cast Stone, DuraLith alkali aluminosilicate geopolymer, encapsulated fluidized bed steam reforming (FBSR) product, and Ceramicrete phosphate bonded ceramic. These data and results will be used to fill existing data gaps on the candidate technologies to support a decision-making process that will identify a subset of the candidate waste forms that are most promising and should undergo further performance testing.

Solid, low-level radioactive waste certification program

International Nuclear Information System (INIS)

Grams, W.H.

1991-11-01

The Hanford Site solid waste treatment, storage, and disposal facilities accept solid, low-level radioactive waste from onsite and offsite generators. This manual defines the certification program that is used to provide assurance that the waste meets the Hanford Site waste acceptance criteria. Specifically, this program defines the participation and responsibilities of Westinghouse Hanford Company Solid Waste Engineering Support, Westinghouse Hanford Company Quality Assurance, and both onsite and offsite waste generators. It is intended that waste generators use this document to develop certification plans and quality assurance program plans. This document is also intended for use by Westinghouse Hanford Company solid waste technical staff involved in providing assurance that generators have implemented a waste certification program. This assurance involves review and approval of generator certification plans, and review of generator's quality assurance program plans to ensure that they address all applicable requirements. The document also details the Westinghouse Hanford Company Waste Management Audit and Surveillance Program. 5 refs

A waste characterization monitor for low-level radioactive waste management

International Nuclear Information System (INIS)

Davey, E.C.; Csullog, G.W.; Kupca, S.; Hippola, K.B.

1985-06-01

The exploitation of nuclear processes and technology for the benefit of Canadians results in the routine generation of approximately 12 000 m 3 of solid low-level radioactive waste annually. To protect the public and the environment, this waste must be isolated for the duration of its potential hazard. In Canada, current planning foresees the development and use of a range of storage and disposal facilities exhibiting differing containment capabilities. To demonstrate adequate isolation safety and to minimize overall costs, the radionuclide content of waste items must be quantified so that the radiological hazards of each waste item can be matched to the isolation capabilities of specific containment facilities. This paper describes a non-invasive, waste characterization monitor that is capable of quantifying the radionuclide content of low-level waste packages to the 9 Bq/g (250 pCi/g) level. The assay technique is based on passive gamma-ray spectroscopy where the concentration of gamma-ray emitting radionuclides in a waste item can be estimated from the analysis of the gamma-ray spectra of the item and calibrated standards

Social Technology Apply to National Policy on Solid Waste: Solid Waste Management Integrated in the Countryside

Directory of Open Access Journals (Sweden)

Greice Kelly Lourenco Porfirio de Oliveira

2016-06-01

Full Text Available This article aims to study the environmentally friendly social technologies through appropriate techniques to the treatment of solid waste disposed of improperly. After exposure of concepts, a reflection on the use of social technologies as a mechanism for realization of integrated management objectives of waste set by the National Solid Waste Policy will be made – 12.305/10 . Finally, data from the Social Technologies Bank of Brazil Foundation will be displayed showing the results of the use of technology to promote the integrated management of solid waste in rural communities Crateús/CE , through a provision aimed at PNRS, selective collection

Interactions of low-level, liquid radioactive wastes with soils. 1. Behavior of radionuclides in soil-waste systems

International Nuclear Information System (INIS)

Fowler, E.B.; Essington, E.H.; Polzer, W.L.

1981-01-01

The characteristics of radioactive wastes and soils vary over a wide range. Liquid radioactive waste entering the environment will eventually contact the soil or geological matrix; interactions will be determined by the chemical and physical nature of the liquid, as well as the soil matrix. We report here the results from an investigation of certain of those characteristics as they relate to retention of radionuclides by soils. Three fractions were demonstrated in the waste as filterable, soluble-sorbable, and soluble-nonsorbable; the physical nature of each fraction was demonstrated using autoradiographic techniques. Isotopes of plutonium and uranium and americium-241 in the soluble fraction of the waste were shown to have a negative charge as determined by ion exchange techniques. In the soil-waste systems, the net charge for those radionuclides was shown to change from predominantly negative to predominantly positive. Nevertheless, cesium-137 was shown to be predominantly positited by TVA and approved by NRC (formerly AEC) since June 1973. This report is based upon the revisions, approved through the end of this reporting period

Solid waste dumping site suitability analysis using geographic ...

African Journals Online (AJOL)

Solid waste dumping is a serious problem in the urban areas because most solid wastes are not dumped in the suitable areas. Bahir Dar Town has the problem of solid waste dumping site identification. The main objective of this study was to select potential areas for suitable solid waste dumping sites for Bahir Dar Town, ...

Sellafield waste radionuclides in Irish sea intertidal and salt marsh sediments.

Science.gov (United States)

Mackenzie, A B; Scott, R D

1993-09-01

Low level liquid radioactive waste discharges from the Sellafield nuclear fuel reprocessing plant in north west England had generated environmental inventories of about 3 × 10(16) Bq of(137)Cs, 6.8 × 10(14) Bq of(239,240)Pu and 8.9 × 10(14) Bq of(241)Am by 1990. Most of the(239,240)Pu and(241)Am and about 10% of the(137)Cs has been retained in a deposit of fine marine sediment close to the discharge point. The quantities of radionuclides discharged annually from Sellafield decreased by two orders of magnitude from the mid-1970s to 1990 but estimated critical group internal and external exposure decreased by less than one order of magnitude over this period. This indicates that during the period of reduced discharges, radionuclides already in the environment from previous releases continued to contribute to the critical group exposure and highlights the need to understand processes controlling the environmental distribution of the radionuclides.Redistribution of the contaminated marine sediment is potentially of major significance in this context, in particular if it results in transport of radionuclides to intertidal areas, where contact with the human population is relatively likely.A review is presented of published work relating to Sellafield waste radionuclides in Irish Sea sediments. Data on temporal and spatial trends in radionuclide concentrations and activity ratios are collated from a number of sources to show that the dominant mechanism of radionuclide supply to intertidal areas is by redistribution of the contaminated marine sediment. The implications of this mechanism of supply for trends in critical group radiation exposure are considered.

SOLID WASTE INTEGRATED FORECAST TECHNICAL (SWIFT) REPORT FY2003 THRU FY2046 VERSION 2003.1 VOLUME 1 [SECTION 1 and 2

International Nuclear Information System (INIS)

BARCOT, R.A.

2003-01-01

The SWIFT Report provides up-to-date life cycle information about the radioactive solid waste expected to be managed by Hanford's Waste Management (WM) Project from onsite and offsite generators. This SWIFT report is a mid-year update to the SWIFT 2003.0 report that was published in January 2003. The SWIFT Report is published in two volumes. SWIFT Volume II provides detailed analyses of the data, graphical representation, comparison to previous years, and waste generator specific information. The data contained in this report are the official data for solid waste forecasting. In this revision, the volume numbers have been switched to reflect the timing of their release. This particular volume provides the following data reports: Summary volume data by DOE Office, company, and location; Annual volume data by waste generator; Annual waste specification record and physical waste form volume; Radionuclide activities and dose-equivalent curies; and Annual container type data by volume and count

Evaluation of interim and final waste forms for the newly generated liquid low-level waste flowsheet

International Nuclear Information System (INIS)

Abotsi, G.M.K.; Bostick, D.T.; Beck, D.E.

1996-05-01

The purpose of this review is to evaluate the final forms that have been proposed for radioactive-containing solid wastes and to determine their application to the solid wastes that will result from the treatment of newly generated liquid low-level waste (NGLLLW) and Melton Valley Storage Tank (MVST) supernate at the Oak Ridge National Laboratory (ORNL). Since cesium and strontium are the predominant radionuclides in NGLLLW and MVST supernate, this review is focused on the stabilization and solidification of solid wastes containing these radionuclides in cement, glass, and polymeric materials-the principal waste forms that have been tested with these types of wastes. Several studies have shown that both cesium and strontium are leached by distilled water from solidified cement, although the leachabilities of cesium are generally higher than those of strontium under similar conditions. The situation is exacerbated by the presence of sulfates in the solution, as manifested by cracking of the grout. Additives such as bentonite, blast-furnace slag, fly ash, montmorillonite, pottery clay, silica, and zeolites generally decrease the cesium and strontium release rates. Longer cement curing times (>28 d) and high ionic strengths of the leachates, such as those that occur in seawater, also decrease the leach rates of these radionuclides. Lower cesium leach rates are observed from vitrified wastes than from grout waste forms. However, significant quantities of cesium are volatilized due to the elevated temperatures required to vitrify the waste. Hence, vitrification will generally require the use of cleanup systems for the off-gases to prevent their release into the atmosphere

Instructive for radioactive solid waste management

International Nuclear Information System (INIS)

Mora Rodriguez, Patricia

2014-01-01

An instructive is established for the management system of radioactive solid residues waste of the Universidad de Costa Rica, ensuring the collection, segregation, storage and disposal of waste. The radioactive solid waste have been segregated and transferred according to features and provisions of the Universidad de Costa Rica and CICANUM [es

Development of a new generation of waste form for entrapment and immobilization of highly volatile and soluble radionuclides.

Energy Technology Data Exchange (ETDEWEB)

Rodriguez, Mark Andrew; Bencoe, Denise Nora; Brinker, C. Jeffrey; Murphy, Andrew Wilson; Holt, Kathleen Caroline; Turnham, Rigney; Kruichak, Jessica Nicole; Tellez, Hernesto; Miller, Andy; Xiong, Yongliang; Pohl, Phillip Isabio; Ockwig, Nathan W.; Wang, Yifeng; Gao, Huizhen

2010-09-01

The United States is now re-assessing its nuclear waste disposal policy and re-evaluating the option of moving away from the current once-through open fuel cycle to a closed fuel cycle. In a closed fuel cycle, used fuels will be reprocessed and useful components such as uranium or transuranics will be recovered for reuse. During this process, a variety of waste streams will be generated. Immobilizing these waste streams into appropriate waste forms for either interim storage or long-term disposal is technically challenging. Highly volatile or soluble radionuclides such as iodine ({sup 129}I) and technetium ({sup 99}Tc) are particularly problematic, because both have long half-lives and can exist as gaseous or anionic species that are highly soluble and poorly sorbed by natural materials. Under the support of Sandia National Laboratories (SNL) Laboratory-Directed Research & Development (LDRD), we have developed a suite of inorganic nanocomposite materials (SNL-NCP) that can effectively entrap various radionuclides, especially for {sup 129}I and {sup 99}Tc. In particular, these materials have high sorption capabilities for iodine gas. After the sorption of radionuclides, these materials can be directly converted into nanostructured waste forms. This new generation of waste forms incorporates radionuclides as nano-scale inclusions in a host matrix and thus effectively relaxes the constraint of crystal structure on waste loadings. Therefore, the new waste forms have an unprecedented flexibility to accommodate a wide range of radionuclides with high waste loadings and low leaching rates. Specifically, we have developed a general route for synthesizing nanoporous metal oxides from inexpensive inorganic precursors. More than 300 materials have been synthesized and characterized with x-ray diffraction (XRD), BET surface area measurements, and transmission electron microscope (TEM). The sorption capabilities of the synthesized materials have been quantified by using stable

Development of a new generation of waste form for entrapment and immobilization of highly volatile and soluble radionuclides

International Nuclear Information System (INIS)

Rodriguez, Mark Andrew; Bencoe, Denise Nora; Brinker, C. Jeffrey; Murphy, Andrew Wilson; Holt, Kathleen Caroline; Turnham, Rigney; Kruichak, Jessica Nicole; Tellez, Hernesto; Miller, Andy; Xiong, Yongliang; Pohl, Phillip Isabio; Ockwig, Nathan W.; Wang, Yifeng; Gao, Huizhen

2010-01-01

The United States is now re-assessing its nuclear waste disposal policy and re-evaluating the option of moving away from the current once-through open fuel cycle to a closed fuel cycle. In a closed fuel cycle, used fuels will be reprocessed and useful components such as uranium or transuranics will be recovered for reuse. During this process, a variety of waste streams will be generated. Immobilizing these waste streams into appropriate waste forms for either interim storage or long-term disposal is technically challenging. Highly volatile or soluble radionuclides such as iodine ( 129 I) and technetium ( 99 Tc) are particularly problematic, because both have long half-lives and can exist as gaseous or anionic species that are highly soluble and poorly sorbed by natural materials. Under the support of Sandia National Laboratories (SNL) Laboratory-Directed Research and Development (LDRD), we have developed a suite of inorganic nanocomposite materials (SNL-NCP) that can effectively entrap various radionuclides, especially for 129 I and 99 Tc. In particular, these materials have high sorption capabilities for iodine gas. After the sorption of radionuclides, these materials can be directly converted into nanostructured waste forms. This new generation of waste forms incorporates radionuclides as nano-scale inclusions in a host matrix and thus effectively relaxes the constraint of crystal structure on waste loadings. Therefore, the new waste forms have an unprecedented flexibility to accommodate a wide range of radionuclides with high waste loadings and low leaching rates. Specifically, we have developed a general route for synthesizing nanoporous metal oxides from inexpensive inorganic precursors. More than 300 materials have been synthesized and characterized with x-ray diffraction (XRD), BET surface area measurements, and transmission electron microscope (TEM). The sorption capabilities of the synthesized materials have been quantified by using stable isotopes I and

General procedure to characterize hazardous waste contaminated with radionuclides

International Nuclear Information System (INIS)

Vokal, A.; Svoboda, K.; Necasova, M.

2002-04-01

The report is structured as follows: Overview of current status of characterization of hazardous wastes contaminated with radionuclides (HWCTR) in the Czech Republic (Legislative aspects; Categorization of HWCwR; Overview of HWCwR emerging from workplaces handling ionizing radiation sources; Mixed waste management in the Czech Republic); General procedure to characterized wastes of the HWCwR type (Information needed from the waste producer; Waste analysis plan - description of waste treatment facilities, verification of wastes, selection of waste parameters followed, selection of sampling method, selection of test methods, selection of frequency of analyses; Radiation protection plan; Non-destructive methods of verification of waste - radiography/tomography, dosimetric inspection, measuring instrumentation, methods usable for the determination of volume and surface activities of materials; Non-destructive invasive methods - internal pressure measurement and gas analysis, endoscopic examination, visual inspection; Destructive methods - sampling, current equipment at Nuclear Research Institute Rez; Identification of hazardous components in waste - chemical screening of mixed wastes; Assessment of immobilization waste matrices; Assessment of packaging; Safety analyses; QA and QC). (P.A.)

Solid waste burial grounds interim safety analysis

International Nuclear Information System (INIS)

Saito, G.H.

1994-01-01

This Interim Safety Analysis document supports the authorization basis for the interim operation and restrictions on interim operations for the near-surface land disposal of solid waste in the Solid Waste Burial Grounds. The Solid Waste Burial Grounds Interim Safety Basis supports the upgrade progress for the safety analysis report and the technical safety requirements for the operations in the Solid Waste Burial Grounds. Accident safety analysis scenarios have been analyzed based on the significant events identified in the preliminary hazards analysis. The interim safety analysis provides an evaluation of the operations in the Solid Waste Burial Grounds to determine if the radiological and hazardous material exposures will be acceptable from an overall health and safety standpoint to the worker, the onsite personnel, the public, and the environment

Solid waste burial grounds interim safety analysis

Energy Technology Data Exchange (ETDEWEB)

Saito, G.H.

1994-10-01

This Interim Safety Analysis document supports the authorization basis for the interim operation and restrictions on interim operations for the near-surface land disposal of solid waste in the Solid Waste Burial Grounds. The Solid Waste Burial Grounds Interim Safety Basis supports the upgrade progress for the safety analysis report and the technical safety requirements for the operations in the Solid Waste Burial Grounds. Accident safety analysis scenarios have been analyzed based on the significant events identified in the preliminary hazards analysis. The interim safety analysis provides an evaluation of the operations in the Solid Waste Burial Grounds to determine if the radiological and hazardous material exposures will be acceptable from an overall health and safety standpoint to the worker, the onsite personnel, the public, and the environment.

Method and device of decontaminating radioactive solid wastes

International Nuclear Information System (INIS)

Hasegawa, Hiroshi; Tamada, Masami.

1983-01-01

Purpose: To surely enable grinding for the inner surface of hollow radioactive solid wastes such as pipeways or valves, as well as enable to decontaminate these solid wastes to such a level as being capable of processing in the same manner for the ordinary wastes. Method: A grinding piece abutting resiliently against the inner surface of a hollow radioactive solid wastes to be contaminated is attached at the top end of a flexible shaft, and the inner surface of the radioactive solid wastes is ground while rotating and slightly reciprocating, as well as axially moving the flexible shaft. Consequently, since the grinding piece is always abutted against the inner surface of the radioactive solid wastes just following after the profile of the inner surface, and the flexible shaft is resiliently flexed corresponding to the profile of the inner surface of the radioactive solid wastes, even an inner surface of radioactive solid wastes with a complicated configuration can surely be ground entirely. This surely enables to remove radioactive claddings and contaminated layers deposited on the surface. (Yoshihara, H.)

Solid Waste Management in Jordan

OpenAIRE

Aljaradin, Mohammad; Persson, Kenneth M

2014-01-01

Solid waste became one of the major environmental problems in Jordan, which has been aggravated over the past 15 years by the sharp increase in the volume of waste generated as well as qualitative changes in its composition. The challenges face solid waste management (SWM) in Jordan are numerous. Financial constraints, shortage of proper equipment and limited availability of trained and skilled manpower together with massive and sudden population increases due to several waves of forced mi...

Solid Waste Management in Jordan

OpenAIRE

Mohammad Aljaradin

2014-01-01

Solid waste became one of the major environmental problems in Jordan, which has been aggravated over the past 15 years by the sharp increase in the volume of waste generated as well as qualitative changes in its composition. The challenges face solid waste management (SWM) in Jordan are numerous. Financial constraints, shortage of proper equipment and limited availability of trained and skilled manpower together with massive and sudden population increases due to several waves of forced migra...

Summary: special waste form lysimeters - arid program

International Nuclear Information System (INIS)

Skaggs, R.L.; Walter, M.B.

1987-01-01

The purpose of the Special Waste Form Lysimeters - Arid Program is to determine the performance of solidified commercial low-level waste forms using a field-scale lysimeter facility constructed for measuring the release and migration of radionuclides from the waste forms. The performance of these waste forms, as measured by radionuclide concentrations in lysimeter effluent, will be compared to that predicted by laboratory characterization of the waste forms. Waste forms being tested include nuclear power reactor waste streams that have been solidified in cement, Dow polymer, and bitumen. To conduct the field leaching experiments a lysimeter facility was built to measure leachate under actual environmental conditions. Field-scale samples of waste were buried in lysimeters equipped to measure water balance components, effluent radionuclide concentrations, and to a limited extent, radionuclide concentrations in lysimeter soil samples. The waste forms are being characterized by standard laboratory leach tests to obtain estimates of radionuclide release. These estimates will be compared to leach rates observed in the field. Adsorption studies are being conducted to determine the amount of contaminant available for transport after the release. Theoretical solubility calculations will also be performed to investigate whether common solid phases could be controlling radionuclide release. 4 references, 8 figures, 1 table

Radioactive solid waste management at Trombay

International Nuclear Information System (INIS)

Jayaraman, A.P.; Balu, K.

1977-01-01

The Radioactive solid waste management programme at BARC, India during 1965-1975 is described in detail. The operational experience, which includes the handling treatment and disposal of these solid wastes is reported alongwith the special problems faced in the case of large volume low hazard potential wastes from the nuclear fuel cycle. (K.B.)

Treatment of radioactive wastes from DOE underground storage tanks

International Nuclear Information System (INIS)

Collins, J.L.; Egan, B.Z.; Spencer, B.B.; Chase, C.W.; Anderson, K.K.; Bell, J.T.

1994-01-01

Bench-scale batch tests have been conducted with sludge and supernate tank waste from the Melton Valley Storage Tank (MVST) Facility at Oak Ridge National Laboratory (ORNL) to evaluate separation technology process for use in a comprehensive sludge processing flow sheet as a means of concentrating the radionuclides and reducing the volumes of storage tank waste at national sites for final disposal. This paper discusses the separation of the sludge solids and supernate, the basic washing of the sludge solids, the acidic dissolution of the sludge solids, and the removal of the radionuclides from the supernate

40 CFR 261.2 - Definition of solid waste.

Science.gov (United States)

2010-07-01

... 40 Protection of Environment 25 2010-07-01 2010-07-01 false Definition of solid waste. 261.2 Section 261.2 Protection of Environment ENVIRONMENTAL PROTECTION AGENCY (CONTINUED) SOLID WASTES (CONTINUED) IDENTIFICATION AND LISTING OF HAZARDOUS WASTE General § 261.2 Definition of solid waste. (a)(1) A...

Radionuclide Concentration in Soils and Vegetation at Low-Level Radioactive Waste Disposal Area G during 2005

Energy Technology Data Exchange (ETDEWEB)

P.R. Fresquez; M.W. McNaughton; M.J. Winch

2005-10-01

Soil samples were collected at 15 locations and unwashed overstory and understory vegetation samples were collected from up to nine locations within and around the perimeter of Area G, the primary disposal facility for low-level radioactive solid waste at Los Alamos National Laboratory (LANL). Soil and plant samples were also collected from the proposed expansion area west of Area G for the purpose of gaining preoperational baseline data. Soil and plant samples were analyzed for radionuclides that have shown a history of detection in past years; these included {sup 3}H, {sup 238}Pu, {sup 239,240}Pu, {sup 241}Am, {sup 234}U, {sup 235}U, and {sup 238}U for soils and {sup 3}H, {sup 238}Pu, and {sup 239,240}Pu for plants. As in previous years, the highest levels of {sup 3}H in soils and vegetation were detected at the south portion of Area G near the {sup 3}H shafts; whereas, the highest concentrations of the Pu isotopes were detected in the northern and northeastern portions near the pads for transuranic waste. All concentrations of radionuclides in soils and vegetation, however, were still very low (pCi range) and far below LANL screening levels and regulatory standards.

Estimation of restaurant solid waste generation rates

International Nuclear Information System (INIS)

Heck, H.H.; Major, I.

2002-01-01

Most solid waste utilities try to create a billing schedule that is proportional to solid waste generation rates. This research was trying to determine if the current billing rate structure was appropriate or if a different rate structure should be implemented. A multiple regression model with forward stepwise addition was developed which accurately predicts weekly solid waste generation rates for restaurants. The model was based on a study of daily solid waste generation at twenty-one different businesses. The weight and volume of solid waste generated was measure daily for two weeks during the winter and two weeks during the summer. Researchers followed the collection truck and measured the volume and weight of the container contents. Data was collected on the following independent variables describing each establishment; weight of waste per collection, volume per collection, container utilization factor, building area, contract haulers bill, yearly property tax, yearly solid waste tax, average number of collections per week, type of restaurant, modal number of collections per week, storage container size, waste density, number of employees, number of hours open per week, and weekly collection capacity (collections per week times storage container size). Independent variables were added to the regression equation based on their partial correlation coefficient and confidence level. The regression equations developed had correlation coefficients of 0.87 to 1.00, which was much better than the correlation coefficient (0.84) of an existing model DeGeare and Ongerth (1971) and a correlation coefficient of 0.54 based on the current solid waste disposal tax. (author)

Solid and Liquid Waste Drying Bag

Science.gov (United States)

Litwiller, Eric (Inventor); Hogan, John A. (Inventor); Fisher, John W. (Inventor)

2009-01-01

Method and system for processing waste from human activities, including solids, liquids and vapors. A fluid-impermeable bag, lined with a liquid-impermeable but vapor-permeable membrane, defining an inner bag, is provided. A vacuum force is provided to extract vapors so that the waste is moved toward a selected region in the inner bag, extracted vapors, including the waste vapors and vaporized portions of the waste liquids are transported across the membrane, and most or all of the solids remain within the liner. Extracted vapors are filtered, and sanitized components thereof are isolated and optionally stored. The solids remaining within the liner are optionally dried and isolated for ultimate disposal.

Groundwater-stream-simulation experiments for the evaluation of the safety of proposed nuclear waste repositories

International Nuclear Information System (INIS)

Seitz, M.G.

1981-01-01

A bench-scale experimental design which integrates repository components to simulate a groundwater stream infiltrating a breached repository is described in this paper. An experiment performed with a nuclear waste solid and one rock core is briefly summarized. The nuclear waste solid consists of borosilicate glass containing formulated nuclear waste and is the source of the leached radionuclides. The rock core used is of granite and serves as the adsorption medium for the leached radionuclides

The role of organic complexants and microparticulates in the facilitated transport of radionuclides

International Nuclear Information System (INIS)

Schilk, A.J.; Robertson, D.E.; Abel, K.H.; Thomas, C.W.

1996-12-01

This progress report describes the results of ongoing radiological and geochemical investigations of the mechanisms of radionuclide transport in groundwater at two low-level waste (LLW) disposal sites within the waste management area of the Chalk River Laboratories (CRL), Ontario, Canada. These sites, the Chemical Pit liquid disposal facility and the Waste Management Area C solid LLW disposal site, have provided valuable 30- to 40-year-old field locations for characterizing the migration of radionuclides and evaluating a number of recent site performance objectives for LLW disposal facilities. This information will aid the NRC and other federal, state, and local regulators, as well as LLW disposal site developers and waste generators, in maximizing the effectiveness of existing or projected LLW disposal facilities for isolating radionuclides from the general public and thereby improving the health and safety aspects of LLW disposal

Determination of radionuclide migration parameters through immobilised radioactive waste; Odredjivanje migracionih parametara radionuklida kroz imobilisani radioaktivni otpad

Energy Technology Data Exchange (ETDEWEB)

Plecas, I; Drljaca, J; Peric, A; Kostadinovic, A [Institut za Nuklearne Nauke Boris Kidric, Belgrade (Yugoslavia)

1988-07-01

In this paper are presented results obtained from leakage rate determination of specific radionuclides (Co-60, Cs-137, Mn-54, Sr-85) in PWR NPP waste. Measurements were carried out using original IBK-Vinca method. This method permits simulation of radionuclide leakage through multiple safety barriers in engineered tranches system for radioactive waste disposal. These results will be used for future Yugoslav radioactive waste storing center. (author)

Solid waste management in Macao: Practices and challenges

International Nuclear Information System (INIS)

Jin Jianjun; Wang Zhishi; Ran Shenghong

2006-01-01

The rapid economic development and population growth in Macao have resulted in a large increase in refuse generated over the past decade. In 2003, the quantity of solid waste generated reached 249,255 tons, corresponding to 1.52 kg/day per capita. This figure has been gradually increasing. Domestic solid waste is the primary source of solid waste generation. The data showed that a considerable amount of the solid waste generated can be recycled and reutilized. Due to Macao's small geographic area and high cost of land, landfilling has the lowest priority for waste disposal. Solid waste incineration has been given a top priority over other waste disposal methods although it is much more expensive. In the last decade, more than 80% of the total waste in Macao was incinerated. However, the incineration capacity of the Macao Incineration Plant is going to reach its saturation earlier than expected. Waste minimization, the establishment of an effective waste collection and disposal fee system, and alternate ways dealing with the limited capacity of waste treatment facilities are regarded to be major challenges in the future

From Solid Waste to Energy.

Science.gov (United States)

Wisely, F. E.; And Others

A project designed to convert solid waste to energy is explained in this paper. In April, 1972, an investor-owned utility began to burn municipal solid waste as fuel for the direct production of electric power. This unique venture was a cooperative effort between the City of St. Louis, Missouri, and the Union Electric Company, with financial…

Life-cycle assessment of municipal solid wastes: Development of the WASTED model

International Nuclear Information System (INIS)

Diaz, R.; Warith, M.

2006-01-01

This paper describes the development of the Waste Analysis Software Tool for Environmental Decisions (WASTED) model. This model provides a comprehensive view of the environmental impacts of municipal solid waste management systems. The model consists of a number of separate submodels that describe a typical waste management process: waste collection, material recovery, composting, energy recovery from waste and landfilling. These submodels are combined to represent a complete waste management system. WASTED uses compensatory systems to account for the avoided environmental impacts derived from energy recovery and material recycling. The model is designed to provide solid waste decision-makers and environmental researchers with a tool to evaluate waste management plans and to improve the environmental performance of solid waste management strategies. The model is user-friendly and compares favourably with other earlier models

Recovering method for solid waste and facility therefor

International Nuclear Information System (INIS)

Omura, Yutaka

1998-01-01

When recovering solid wastes in a dry-type storage vessel, a crusher is hoisted down from a cask, and the crusher is operated to crush the solid wastes while holding them. The crushed wastes are temporarily stored at the upper portion of the crusher, and recovered as crushed wastes. In this case, the crusher is turned down, and a shielding vessel is laid the recover downwardly to temporary store the crushed wastes in the shielding vessel. Then, the crusher and the shielding vessel are turned 180deg to contain the crushed wastes into the shielding vessel. With such procedures, the stored solid wastes can be recovered reliably, the stored solid wastes can be reduced in the size, and efficiency of recovering operation can be improved. (T.M.)

Characteristics and Classification of Solid Radioactive Waste From the Front-End of the Uranium Fuel Cycle.

Science.gov (United States)

Liu, Xinhua; Wei, Fangxin; Xu, Chunyan; Liao, Yunxuan; Jiang, Jing

2015-09-01

The proper classification of radioactive waste is the basis upon which to define its disposal method. In view of differences between waste containing artificial radionuclides and waste with naturally occurring radionuclides, the scientific definition of the properties of waste arising from the front end of the uranium fuel cycle (UF Waste) is the key to dispose of such waste. This paper is intended to introduce briefly the policy and practice to dispose of such waste in China and some foreign countries, explore how to solve the dilemma facing such waste, analyze in detail the compositions and properties of such waste, and finally put forward a new concept of classifying such waste as waste with naturally occurring radionuclides.

Project Plan for the evaluation of REDC waste for TRU-waste radionuclides

International Nuclear Information System (INIS)

Nguyen, L.; Yong, L.; Chapman, J.

1996-09-01

This project plan describes the plan to determine whether the solid radioactive wastes generated by the Radiochemical Engineering Development Center (REDC) meet the Department of Energy's definition of transuranic wastes. Existing waste characterization methods will be evaluated, as well as historical data, and recommendations will be made as necessary

Solid waste management. Principles and practice

Energy Technology Data Exchange (ETDEWEB)

Chandrappa, Ramesha [Karnataka State Pollution Control Board, Biomedical Waste, Bangalore (India); Bhusan Das, Diganta [Loughborough Univ. of Technology (United Kingdom). Dept. of Chemical Engineering

2012-11-01

Solid waste was already a problem long before water and air pollution issues attracted public attention. Historically the problem associated with solid waste can be dated back to prehistoric days. Due to the invention of new products, technologies and services the quantity and quality of the waste have changed over the years. Waste characteristics not only depend on income, culture and geography but also on a society's economy and, situations like disasters that affect that economy. There was tremendous industrial activity in Europe during the industrial revolution. The twentieth century is recognized as the American Century and the twenty-first century is recognized as the Asian Century in which everyone wants to earn 'as much as possible'. After Asia the currently developing Africa could next take the center stage. With transitions in their economies many countries have also witnessed an explosion of waste quantities. Solid waste problems and approaches to tackling them vary from country to country. For example, while efforts are made to collect and dispose hospital waste through separate mechanisms in India it is burnt together with municipal solid waste in Sweden. While trans-boundary movement of waste has been addressed in numerous international agreements, it still reaches developing countries in many forms. While thousands of people depend on waste for their lively hood throughout the world, many others face problems due to poor waste management. In this context solid waste has not remained an issue to be tackled by the local urban bodies alone. It has become a subject of importance for engineers as well as doctors, psychologist, economists, and climate scientists and any others. There are huge changes in waste management in different parts of the world at different times in history. To address these issues, an effort has been made by the authors to combine their experience and bring together a new text book on the theory and practice of the

A Survey of Municipal Solid Waste Generation in 22 Regions of Tehran With Solid Waste Reduction Approach

OpenAIRE

MA Abduli; M Akbarpour Shirazi; B Omidvar; R Samieifard

2015-01-01

Introduction: Solid waste reduction is a key and fundamental factor in creating a sustainable society. Tehran Municipality has embarked on a series of positive measures in recent years in different areas of waste management such as source separation, mechanized waste collection, and constructing compost factories. However these measures have not only brought about any reduction in solid waste reduction but have also resulted in their increase. In this article, first we will describe the curre...

Prediction of radionuclide invention for low-and intermediate-level radioactive waste by considering concentration limit of waste package

Energy Technology Data Exchange (ETDEWEB)

Jung, Kang Il; Kim, Min Seong; Jeong, Noh Gyeon; Park, Jin Beak [Korea Radioactive Waste Agency(KORAD), Daejeon (Korea, Republic of)

2017-03-15

The result of a preliminary safety assessment that was completed by applying the radionuclide inventory calculated on the basis of available data from radioactive waste generation agencies suggested that many difficulties are to be expected with regard to disposal safety and operation. Based on the results of the preliminary safety assessment of the entire disposal system, in this paper, a unit package exceeding the safety goal is selected that occupies a large proportion of radionuclides in intermediate-level radioactive waste. We introduce restrictions on the amount of radioactivity in a way that excludes the high surface dose rate of the package. The radioactivity limit for disposal will be used as the baseline data for establishing the acceptance criteria and the disposal criteria for each disposal facility to meet the safety standards. It is necessary to draw up a comprehensive safety development plan for the Gyeongju waste disposal facility that will contribute to the construction of a Safety Case for the safety optimization of radioactive waste disposal facilities.

Conversion of Waste into Wealth: A Study in Solid Waste Management

OpenAIRE

Janakiram, T.; Sridevi, K.

2010-01-01

Disposal of solid waste has been the talk of the day. An attempt has been made to dispose of the solid waste Jatropha (Kattamanakku). Aerobic composting method was employed. Properly treated solid wastes of different composition were mixed with slurries of cowdung and physicochemical parameters were measured after 30 and 60 days of composting. It was observed that percentages of nitrogen, phosphorous, potassium, sodium, calcium and magnesium increased as time elapsed. Water holding capacity, ...

Municipal Solid Waste Resources

Energy Technology Data Exchange (ETDEWEB)

None

2016-06-01

Municipal solid waste (MSW) is a source of biomass material that can be utilized for bioenergy production with minimal additional inputs. MSW resources include mixed commercial and residential garbage such as yard trimmings, paper and paperboard, plastics, rubber, leather, textiles, and food wastes. Waste resources such as landfill gas, mill residues, and waste grease are already being utilized for cost-effective renewable energy generation. MSW for bioenergy also represents an opportunity to divert greater volumes of residential and commercial waste from landfills.

Radionuclide transport behavior in a generic geological radioactive waste repository.

Science.gov (United States)

Bianchi, Marco; Liu, Hui-Hai; Birkholzer, Jens T

2015-01-01

We performed numerical simulations of groundwater flow and radionuclide transport to study the influence of several factors, including the ambient hydraulic gradient, groundwater pressure anomalies, and the properties of the excavation damaged zone (EDZ), on the prevailing transport mechanism (i.e., advection or molecular diffusion) in a generic nuclear waste repository within a clay-rich geological formation. By comparing simulation results, we show that the EDZ plays a major role as a preferential flowpath for radionuclide transport. When the EDZ is not taken into account, transport is dominated by molecular diffusion in almost the totality of the simulated domain, and transport velocity is about 40% slower. Modeling results also show that a reduction in hydraulic gradient leads to a greater predominance of diffusive transport, slowing down radionuclide transport by about 30% with respect to a scenario assuming a unit gradient. In addition, inward flow caused by negative pressure anomalies in the clay-rich formation further reduces transport velocity, enhancing the ability of the geological barrier to contain the radioactive waste. On the other hand, local high gradients associated with positive pressure anomalies can speed up radionuclide transport with respect to steady-state flow systems having the same regional hydraulic gradients. Transport behavior was also found to be sensitive to both geometrical and hydrogeological parameters of the EDZ. Results from this work can provide useful knowledge toward correctly assessing the post-closure safety of a geological disposal system. © 2014, National Ground Water Association.

Cleaner production for solid waste management in leather industry ...

African Journals Online (AJOL)

Cleaner production for solid waste management in leather industry. ... From the processes, wastes are generated which include wastewater effluents, solid wastes, and hazardous wastes. In developing countries including Ethiopia, many ... The solid waste inventory of the factory has been carried out. The major problems ...

Radionuclide Incorporation and Long Term Performance of Apatite Waste Forms

Energy Technology Data Exchange (ETDEWEB)

Wang, Jianwei [Louisiana State Univ., Baton Rouge, LA (United States); Lian, Jie [Rensselaer Polytechnic Inst., Troy, NY (United States); Gao, Fei [Univ. of Michigan, Ann Arbor, MI (United States)

2016-01-04

This project aims to combines state-of-the-art experimental and characterization techniques with atomistic simulations based on density functional theory (DFT) and molecular dynamics (MD) simulations. With an initial focus on long-lived I-129 and other radionuclides such as Cs, Sr in apatite structure, specific research objectives include the atomic scale understanding of: (1) incorporation behavior of the radionuclides and their effects on the crystal chemistry and phase stability; (2) stability and microstructure evolution of designed waste forms under coupled temperature and radiation environments; (3) incorporation and migration energetics of radionuclides and release behaviors as probed by DFT and molecular dynamics (MD) simulations; and (4) chemical durability as measured in dissolution experiments for long term performance evaluation and model validation.

Managing America`s solid waste

Energy Technology Data Exchange (ETDEWEB)

1998-03-02

This report presents an historical overview of the federal role in municipal solid waste management from 1965 to approximately 1995. Attention is focuses on the federal role in safeguarding public health, protecting the environment, and wisely using material and energy resources. It is hoped that this report will provide important background for future municipal solid waste research and development initiatives.

Predicted radionuclide release from reactor-related unenclosed solid objects dumped in the Sea of Japan and the Pacific Ocean, east coast of Kamchatka

International Nuclear Information System (INIS)

Mount, M.E.; Lynn, N.M.; Warden, J.M.

1996-06-01

Between 1978 and 1991 reactor-related solid radioactive waste was dumped by the former Soviet Union as unenclosed objects in the Pacific Ocean, east coast of Kamchatka, and the Sea of Japan. This paper presented estimates for the current (1994) inventory of activation and corrosion products contained in the reactor-related unenclosed solid objects. In addition, simple models derived for prediction of radionuclide release from marine reactors dumped in the Kara Sea are applied to certain of the dumped objects to provide estimates of radionuclide release to the Pacific Ocean, east coast of Kamchatka, and Sea of Japan environments. For the Pacific Ocean, east coast of Kamchatka, total release rates start below 0.01 GBq yr -1 and over 1,000 years, fall to 100 Bq yr -1 . In the Sea of Japan, the total release rate starts just above 1 GBq yr - 1 , dropping off to a level less than 0.1 GBq yr -1 , extending past the year 4,000

Diffusion and Leaching Behavior of Radionuclides in Category 3 Waste Encasement Concrete and Soil Fill Material – Summary Report

Energy Technology Data Exchange (ETDEWEB)

Mattigod, Shas V.; Wellman, Dawn M.; Bovaird, Chase C.; Parker, Kent E.; Clayton, Libby N.; Powers, Laura; Recknagle, Kurtis P.; Wood, Marcus I.

2011-08-31

One of the methods being considered for safely disposing of Category 3 low-level radioactive wastes is to encase the waste in concrete. Such concrete encasement would contain and isolate the waste packages from the hydrologic environment and would act as an intrusion barrier. The current plan for waste isolation consists of stacking low-level waste packages on a trench floor, surrounding the stacks with reinforced steel, and encasing these packages in concrete. These concrete-encased waste stacks are expected to vary in size with maximum dimensions of 6.4 m long, 2.7 m wide, and 4 m high. The waste stacks are expected to have a surrounding minimum thickness of 15 cm of concrete encasement. These concrete-encased waste packages are expected to withstand environmental exposure (solar radiation, temperature variations, and precipitation) until an interim soil cover or permanent closure cover is installed, and to remain largely intact thereafter. Any failure of concrete encasement may result in water intrusion and consequent mobilization of radionuclides from the waste packages. The mobilized radionuclides may escape from the encased concrete by mass flow and/or diffusion and move into the surrounding subsurface environment. Therefore, it is necessary to assess the performance of the concrete encasement structure and the ability of the surrounding soil to retard radionuclide migration. The retardation factors for radionuclides contained in the waste packages can be determined from measurements of diffusion coefficients for these contaminants through concrete and fill material. Some of the mobilization scenarios include (1) potential leaching of waste form before permanent closure cover is installed; (2) after the cover installation, long-term diffusion of radionuclides from concrete waste form into surrounding fill material; (3) diffusion of radionuclides from contaminated soils into adjoining concrete encasement and clean fill material. Additionally, the rate of

Testing waste forms containing high radionuclide loadings

International Nuclear Information System (INIS)

McConnell, J.W. Jr.; Neilson, R.M. Jr.; Rogers, R.D.

1986-01-01

The Low-Level Waste Data Base Development - EPICOR-II Resin/Liner Investigation Program funded by the US Nuclear Regulatory Commission (NRC) is obtaining information on radioactive waste during NRC-prescribed tests and in a disposal environment. This paper describes the resin solidification task of that program, including the present status and results to date. An unusual aspect of this investigation is the use of commercial grade, ion exchange resins that have been loaded with over five times the radioactivity normally seen in a commercial application. That dramatically increases the total radiation dose to the resins. The objective of the resin solidification task is to determine the adequacy of test procedures specified by NRC for ion exchange resins having high radionuclide loadings

Solid waste management - Pakistan's perspective

International Nuclear Information System (INIS)

Hussain, M.

2003-01-01

The discipline of 'Solid Waste Management' is as old as human civilization itself. The problem had been felt when the human beings commenced living together in the form of communities. The situation got worsened with ever-increasing population and growing industrialization. The developed nations have endeavored to tackle the issue of the industrial and municipal wastes according to the principles of engineering and environment. Most of the developing countries have not dealt with the 'Third Pollution' in the eco-friendly manner. Ironically Pakistan is facing this serious menace because of ever-expanding population (2.2% per annum) and ill management of the wastes and effluents being generated from multifarious activities. These pollutants are degrading the land, air and water resources at alarming rates. In Pakistan about 7,250 tonnes of solid waste is generated per day. Of this quantity only 60-70% is collected and the remaining quantity is allowed to burn indiscriminately or decay in situ. Unfortunately the industrial waste, animal dung and hospital waste are allowed to mix with the municipal waste, which adds to inefficiency of the existing 'Solid Waste Management System'. Scores of faecal, fly, rodent and mosquito born diseases are caused due to open dumping of the waste besides aesthetic impairment of the surroundings. None of the scientifically recognized methods of disposal is practiced. It is not based on administrative, financial, environmental and technical consideration. There is dire necessity of educating the masses to adopt clean habits and resort to generation of minimum waste. Further, nothing is waste as the so-called 'waste material' is the raw material after reuse and recycling for another process. (author)

Solid waste management in Asian countries: a review of solid waste minimisation (3'r) towards low carbon

Science.gov (United States)

Ali, N. E.; Sion, H. C.

2014-02-01

The amount of solid-waste generated in Asian countries has increased tremendously, mainly due to the improvement in living standards, rapid developments in technology, growth in economy and population in the cities. Solid waste management is a global issue and major challenge facing Asian countries and neglecting its management may have negative consequences on the environment. Waste composition data proves the developed countries to have generated more recyclable materials while developing countries produce more organic and less recyclable waste such as paper, plastic and aluminium. In this regard, increase in number of landfills and disposal sites, will have an impact on GHG (greenhouse gas) emissions and pollutants to air and water. Alternative methods should therefore be taken to reduce the volume of waste. Most Asian countries have adopted the 3R (reduce, reuse, recycle) concept in order to reduce solid waste and their governments have implemented laws and regulations in order to support this. Implementation of 3R is the major contributor to the solid waste minimization and it can improve the quality of environmental sustainability and reduction of carbon dioxide emission in to the atmosphere. Based on our review, most of the countries practicing the 3R concept in tandem with laws and regulations perform better than those that just practice the 3R concept without any laws and regulations. The paper suggests that every country must focus on the laws and regulations relating to solid waste minimization so that it could be easily implemented as outlined.

77 FR 69769 - Solid Waste Rail Transfer Facilities

Science.gov (United States)

2012-11-21

...] Solid Waste Rail Transfer Facilities AGENCY: Surface Transportation Board, DOT. ACTION: Final rules. SUMMARY: These final rules govern land-use-exemption permits for solid waste rail transfer facilities. The... Transportation Board over solid waste rail transfer facilities. The Act also added three new statutory provisions...

Importance of biota in radionuclide transport at the SL-1 radioactive waste disposal area

International Nuclear Information System (INIS)

Arthur, W.J.; Grant, J.C.; Markham, O.D.

1983-01-01

During summer 1981 and 1982, radioecological research was conducted at the Stationary Low Power Reactor-1 radioactive waste disposal area to: (1) identify vegetation, wildlife, and invertebrate species occurring at or using the area; (2) determine radionuclide concentrations in these various ecosystem components; and (3) to evaluate their respective roles in radionuclide uptake and transport through the surrounding environment. Cesium-137 concentrations detected in surface soils, small mammal excavated soils and small mammal tissues collected at the waste disposal site were significantly (P less than or equal to 0.05) greater than control area samples. Strontium-90 and 235 U analyses of SL-1 and control area samples and projections of total mass of ecosystem components in SL-1 area will be completed in summer of 1983 at which time estimates will be made on the total quantity of fission and activation radionuclides occurring in ecological media at the SL-1 waste disposal area

Fate of major radionuclides in the liquid wastes released to coastal waters

International Nuclear Information System (INIS)

Bhat, I.S.; Verma, P.C.; Iyer, R.S.; Chandramouli, S.

1980-01-01

131 I, 134 Cs, 137 Cs and 60 Co have been reported as the major radionuclides in the low level liquid wastes released to coastal waters from atomic power stations. Silt absorption and desorption of the radionuclides were investigated. The exchangeability of the silt absorbed radionuclides and its dependence on particle size were also studied. More than 80% instantaneous absorpt;.on of 60 Co by suspended silt and less than 5% exchangeability of absorbed 60 Co were observed. Biological uptake of the radionuclides by the marine organisms present in sea waters was studied to evaluate radiation exposure pathways. A few benthic and crustacean organisms wnich are consumed by coastal population as fresh sea food, were observed to concentrate the radionuclides to a greater extent than other organisms. (H.K.)

Modeling of release of radionuclides from an engineered disposal facility for shallow-land disposal of low-level radioactive wastes

International Nuclear Information System (INIS)

Matsuzuru, H.; Suzuki, A.

1989-01-01

The computer code, ENBAR-1, for the simulation of radionuclide releases from an engineered disposal facility has been developed to evaluate the source term for subsequent migration of radionuclides in and through a natural barrier. The system considered here is that a waste package (waste form and container) is placed, together with backfill materials, into a concrete pit as a disposal unit for shallow-land disposal of low-level radioactive wastes. The code developed includes the following modules: water penetration into a concrete pit, corrosion of a drum as a container, leaching of radionuclides from a waste form, migration of radionuclides in backfill materials, release of radionuclides from the pit. The code has the advantage of its simplicity of operation and presentation while still allowing comprehensive evaluation of each element of an engineered disposal facility to be treated. The performance and source term of the facility might be readily estimated with a few key parameters to define the problem

Management of Port Solid Waste Framework

OpenAIRE

Pereira, Sergio Luiz; Fontana, , Carla Marísia Maccagnan; Fontana, Caio Fernando; Sakurai, Claedson Akio

2014-01-01

One of contemporary environmental issues refers to progressive and diverse generation of solid waste in urban areas or specific, and requires solutions because the traditional methods of treatment and disposal are becoming unviable over the years and, consequently, a significant contingent of these wastes presents final destination inappropriate. The diversity of solid waste generated as a result of human activities must have the appropriate allocation to specific ...

Dynamic effects of tank waste aging on radionuclide-complexant interactions. 1998 annual progress report

International Nuclear Information System (INIS)

Arterburn, J.B.; Chamberlin, R.

1998-01-01

'The overall objective of this project is to provide a scientific basis for safely processing complexant-containing high-level tank wastes for disposal. The key goals are to identify a means to prepare realistic complexant-containing tank waste simulants, and to use those simulants to determine the relative importance of organic complexants and their breakdown products on the partitioning of important radionuclides. These goals will be accomplished by artificially aging complexant-containing tank waste simulants using microwave, ultrasound, and photolysis techniques. The simulants will be compared to samples of actual Hanford tank wastes to determine the most realistic aging method, on the basis of the organic fragmentation and the partitioning behavior of the important radionuclides 90 Sr, 99 Tc, and 239 Pu. Also, the authors will use their simulant aging process to investigate the relative effects of chelator degradation products on the partitioning of important radionuclides from the waste. Using NMR-active labels in the chelators, they will use a combinatorial approach of generating multiple chelator fragments in a single experiment and then determining which fragments have a negative effect on the separations chemistry. The successful completion of this goal will specifically identify the most problematic organic fragments in complexant-containing waste and provide the basis for developing successful treatment strategies for these wastes. This report summarizes work carried out at Los Alamos during the first 8 months of a 3-year project.'

Leaching behavior of various low-level waste solids

International Nuclear Information System (INIS)

Ito, Akihiko; Ouchi, Yasuyoshi; Matsuzuru, Hideo; Wadachi, Yoshiki

1985-01-01

This report deals with the leaching of radioactive nuclides from low-level wastes solidified with cement, bitumen or plastics. Considerations are made on the effects of type of solidification matrix and waste; type, amount and exchange frequency of leachate; type and conditions of embedding soil; temperature and pressure; and secular deterioration. It is assumed that a waste composite is entirely immersed in leachate and that the amount of the leachate is large compared to the surface area of the waste. Cement solid is characterized by its high alkalinity and porosity while plastic and bitumen solids are dense and neutral. The content of waste in a composite is low for cement and high for plastics. It is generally high in bitumen solid though it should be reduced if the solid is likely to bulge. The leaching of 137 Cs from cement solid is slightly dependent on the waste-cement ratio while it increases with increasing waste content in the case of plastic or bitumen solid. For 60 Co, the leaching from cement solid depends on the alkalinity of the cement material used though it is not affected by the waste-cement ratio. In the case of plastics and bitumen, on the other hand, the pH value of the waste have some effects on the leaching of 60 Co; the leaching decreases with increasing pH. (Nogami, K.)

Safety of systems for the retention of wastes containing radionuclides

International Nuclear Information System (INIS)

1980-11-01

Information and minimal requirements demanded by CNEN for the emission of the Approval Certificate of the Safety Analysis Report related to system for the retention of wastes containing radionuclide, are established, aiming to assure low radioactivity levels to the environment. (E.G.) [pt

Fire propagation through arrays of solid-waste storage drums

International Nuclear Information System (INIS)

Smith, S.T.; Hinkle, A.W.

1995-01-01

The extent of propagation of a fire through drums of solid waste has been an unresolved issue that affects all solid-waste projects and existing solid-waste storage and handling facilities at the Hanford site. The issue involves the question of how many drums of solid waste within a given fire area will be consumed in a design-basis fire for given parameters such as drum loading, storage arrays, initiating events, and facility design. If the assumption that all drums of waste within a given fire area are consumed proves valid, then the construction costs of solid waste facilities may be significantly increased

New strategic solid waste management in Sicily

International Nuclear Information System (INIS)

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

2005-01-01

The solid waste management is, today, a very critical issue. In spite of all the attempts in order to recovery and to recycle waste, the dump still remains the more followed solution, while only a small part of solid waste is going to be burnt down. But the rubbish dump isn't, actually, an environmentally sustainable solution. In the last years the waste incineration systems with energy recovery are spreading more over the territory, and if on one hand they allow to recover energy, on the other they also generate waste. So the emergency remains and it has to be faced. Today, the waste incineration system with energy recovery seems to be the best solution for this problem. the following article examinates the main strategic aspects of the solid waste management in Sicily after the General Plan of Waste Management application [it

40 CFR 266.202 - Definition of solid waste.

Science.gov (United States)

2010-07-01

... 40 Protection of Environment 26 2010-07-01 2010-07-01 false Definition of solid waste. 266.202 Section 266.202 Protection of Environment ENVIRONMENTAL PROTECTION AGENCY (CONTINUED) SOLID WASTES... MANAGEMENT FACILITIES Military Munitions § 266.202 Definition of solid waste. (a) A military munition is not...

Potential application of biodrying to treat solid waste

Science.gov (United States)

Zaman, Badrus; Oktiawan, Wiharyanto; Hadiwidodo, Mochtar; Sutrisno, Endro; Purwono; Wardana, Irawan Wisnu

2018-02-01

The generation of solid waste around the world creates problems if not properly managed. The method of processing solid waste by burning or landfill is currently not optimal. The availability of land where the final processing (TPA) is critical, looking for a new TPA alternative will be difficult and expensive, especially in big cities. The processing of solid waste using bio drying technology has the potential to produce renewable energy and prevention of climate change. Solid waste processing products can serve as Refuse Derived Fuel (RDF), reduce water content of solid waste, meningkatkan kualitas lindi and increase the amount of recycled solid waste that is not completely separated from home. Biodrying technology is capable of enhancing the partial disintegration and hydrolysis of macromolecule organic compounds (such as C-Organic, cellulose, hemicellulose, lignin, total nitrogen). The application of biodrying has the potential to reduce greenhouse gas emissions such as carbon dioxide (CO2), methane (CH4), and dinitrooksida (N2O). These gases cause global warming.

Description of Allied-General Nuclear Services on-site solid waste storage concepts

International Nuclear Information System (INIS)

Sumner, W.B.; Thomas, L.L.

1979-01-01

AGNS will divide the majority of the contaminated solid waste generated during reprocessing of commercial spent nuclear reactor fuels into three categories: spent fuel cladding hulls, high-level general process trash (HLGPT) and low-level general process trash (LLGPT). The LLGPT will be stored in cargo containers identical to those used for road, rail, and sea transport. As these cargo containers are filled, they will be covered with earth for protection from natural phenomenon. The cargo containers will be sufficiently monitored to allow detection and recovery of any radionuclides before they reach the environment. The hulls and HLGPT will be stored in caissons within separate engineered soil berms. The caissons will be lined and capped to provide sufficient protection from natural phenomenon. The berms will include impervious clay layers at the bottom to prevent the downward movement of radionuclides and will be provided with sufficient monitoring to allow detection and recovery of radioactivity before it reaches the environment

Anaerobic digestion of municipal solid waste: Technical developments

Energy Technology Data Exchange (ETDEWEB)

Rivard, C.J. [National Renewable Energy Lab., Golden, CO (United States)

1996-01-01

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

Overview of hydrothermal testing of waste-package barrier materials at the Basalt Waste Isolation Project

International Nuclear Information System (INIS)

1982-01-01

The current Waste Package Department (WPD) hydrothermal testing program for the Basalt Waste Isolation Project (BWIP) has followed a systematic approach for the testing of waste-barrier-basalt interactions based on sequential penetration of barriers by intruding groundwaters. Present test activities in the WPD program have focused on determining radionuclide solubility limits (or steady-state conditions) of simulated waste forms and the long-term stability of waste package barriers under site-specific hydrothermal conditions. The resulting data on solution compositions and solid alteration products have been used to evaluate waste form degradation under conditions specific to a nuclear waste repository located in basalt (NWRB). Isothermal, time-invariant compositional data on sampled solutions have been coupled with realistic hydrologic flow data for near-field and far-field modeling for the calculation of meaningful radionuclide release rates. Radionuclides that are not strongly sorbed or precipitated from solution and that, therefore, may require special attention to ensure their isolation within the waste package have been identified. Taken together, these hydrothermal test data have been used to establish design requirements for waste packages located in basalt

Radionuclide concentrations in vegetation at radioactive-waste disposal Area G during the 1994 growing season

International Nuclear Information System (INIS)

Fresquez, P.R.; Biggs, J.B.; Bennett, K.D.

1995-01-01

Overstory (pinon pine) and understory (grass and forb) vegetation samples were collected within and around selected points at Area G-a low-level radioactive solid-waste disposal facility at Los Alamos National Laboratory-for the analysis of tritium ( 3 H), strontium ( 90 Sr), plutonium ( 238 Pu and 239 Pu), cesium ( 137 Cs), americium ( 241 Am), and total uranium. In general, most vegetation samples collected within and around Area G contained radionuclide levels in higher concentrations than vegetation collected from background areas. Tritium, in particular, was detected as high as 5,800 pCi/mL in overstory vegetation collected outside the fence just west of the tritium shafts; this suggests that tritium is migrating from this waste repository through subsurface pathways. Also, understory vegetation collected north of the transuranic (TRU) pads (outside the fence of Area G) contained the highest values of 90 Sr, 238 Pu, 239 Pu, 137 Cs, and 241 Am, and may be a result of surface holding, storage, or disposal activities

40 CFR 260.30 - Non-waste determinations and variances from classification as a solid waste.

Science.gov (United States)

2010-07-01

... from classification as a solid waste. 260.30 Section 260.30 Protection of Environment ENVIRONMENTAL PROTECTION AGENCY (CONTINUED) SOLID WASTES (CONTINUED) HAZARDOUS WASTE MANAGEMENT SYSTEM: GENERAL Rulemaking Petitions § 260.30 Non-waste determinations and variances from classification as a solid waste. In...

Factors influencing household participation in solid waste management (Case study: Waste Bank Malang)

Science.gov (United States)

Maryati, S.; Arifiani, N. F.; Humaira, A. N. S.; Putri, H. T.

2018-03-01

Solid waste management is very important measure in order to reduce the amount of waste. One of solid waste management form in Indonesia is waste banks. This kind of solid waste management required high level of participation of the community. The objective of this study is to explore factors influencing household participation in waste banks. Waste bank in Malang City (WBM) was selected as case study. Questionnaires distribution and investigation in WBM were conducted to identify problems of participation. Quantitative analysis was used to analyze the data. The research reveals that education, income, and knowledge about WBM have relationship with participation in WBM.

Municipal solid waste generation in Kathmandu, Nepal.

Science.gov (United States)

Dangi, Mohan B; Pretz, Christopher R; Urynowicz, Michael A; Gerow, Kenneth G; Reddy, J M

2011-01-01

Waste stream characteristics must be understood to tackle waste management problems in Kathmandu Metropolitan City (KMC), Nepal. Three-stage stratified cluster sampling was used to evaluate solid waste data collected from 336 households in KMC. This information was combined with data collected regarding waste from restaurants, hotels, schools and streets. The study found that 497.3 g capita(-1) day(-1) of solid waste was generated from households and 48.5, 113.3 and 26.1 kg facility(-1) day(-1) of waste was generated from restaurants, hotels and schools, respectively. Street litter measured 69.3 metric tons day(-1). The average municipal solid waste generation rate was 523.8 metric tons day(-1) or 0.66 kg capita(-1) day(-1) as compared to the 320 metric tons day(-1) reported by the city. The coefficient of correlation between the number of people and the amount of waste produced was 0.94. Key household waste constituents included 71% organic wastes, 12% plastics, 7.5% paper and paper products, 5% dirt and construction debris and 1% hazardous wastes. Although the waste composition varied depending on the source, the composition analysis of waste from restaurants, hotels, schools and streets showed a high percentage of organic wastes. These numbers suggest a greater potential for recovery of organic wastes via composting and there is an opportunity for recycling. Because there is no previous inquiry of this scale in reporting comprehensive municipal solid waste generation in Nepal, this study can be treated as a baseline for other Nepalese municipalities. Copyright © 2010 Elsevier Ltd. All rights reserved.

Greater-than-Class C low-level radioactive waste characterization: Estimated volumes, radionuclide activities, and other characteristics

International Nuclear Information System (INIS)

Hulse, R.A.

1991-08-01

Planning for storage or disposal of greater-than-Class C low-level radioactive waste (GTCC LLW) requires characterization of that waste to estimate volumes, radionuclide activities, and waste forms. Data from existing literature, disposal records, and original research were used to estimate the characteristics and project volumes and radionuclide activities to the year 2035. GTCC LLW is categorized as: nuclear utilities waste, sealed sources waste, DOE-held potential GTCC LLW; and, other generator waste. It has been determined that the largest volume of those wastes, approximately 57%, is generated by nuclear power plants. The Other Generator waste category contributes approximately 10% of the total GTCC LLW volume projected to the year 2035. Waste held by the Department of Energy, which is potential GTCC LLW, accounts for nearly 33% of all waste projected to the year 2035; however, no disposal determination has been made for that waste. Sealed sources are less than 0.2% of the total projected volume of GTCC LLW

Municipal Solid Waste Management in Phuntsholing City, Bhutan

Directory of Open Access Journals (Sweden)

Norbu

2010-01-01

Full Text Available Municipal solid waste problem is a major concern in major cities in Bhutan. Despite the lack of reliable data on both waste composition and quantity, no studies have been conducted to identify problems and alternatives to improve the current system. The study objectives are: 1 to determine solid waste composition and generation rate; and 2 to investigate current solid waste management system. Six waste samples were selected in Phuntsholing city from three designated collection spots and from three collection vehicles and analyzed for their composition. Waste generation rate was computed from waste collected by collection vehicles. The investigation was carried out through interviews with municipal authorities, existing document reviews, and field observations. The organic fraction of solid waste composition comprised about 71 percent. The waste generation rate was estimated to 0.40 kg/capita.day. The current management system is inefficient, and recommendations are given to improve the current situation.

Solid Wastes and Water Quality.

Science.gov (United States)

DeWalle, F. B.; Chian, E. S. K.

1978-01-01

Presents a literature review of solid wastes and water quality, covering publications of 1976-77. This review covers areas such as: (1) environmental impacts and health aspects for waste disposal, and (2) processed and hazardous wastes. A list of 80 references is also presented. (HM)

Hazardous gas production by alpha particles in solid organic transuranic waste matrices. 1998 annual progress report

International Nuclear Information System (INIS)

LaVerne, J.A.

1998-01-01

'This project uses fundamental radiation chemical techniques to elucidate the basic processes occurring in the heavy-ion radiolysis of solid hydrocarbon matrices such as polymers and organic resins that are associated with many of the transuranic waste deposits or the transportation of these radionuclides. The environmental management of mixed waste containing transuranic radionuclides is difficult because these nuclides are alpha particle emitters and the energy deposited by the alpha particles causes chemical transformations in the matrices accompanying the waste. Most radiolysis programs focus on conventional radiation such as gamma rays, but the chemical changes induced by alpha particles and other heavy ions are typically very different and product yields can vary by more than an order of magnitude. The objective of this research is to measure the production of gases, especially molecular hydrogen, produced in the proton, helium ion, and carbon ion radiolysis of selected solid organic matrices in order to obtain fundamental mechanistic information on the radiolytic decomposition of these materials. This knowledge can also be used to directly give reasonable estimates of explosive or flammability hazards in the storage or transport of transuranic wastes in order to enhance the safety of DOE sites. This report summarizes the work after eight months of a three-year project on determining the production of hazardous gases in transuranic waste. The first stage of the project was to design and build an assembly to irradiate solid organic matrices using accelerated ion beams. It is necessary to measure absolute radiolytic yields, and simulate some of the conditions found in the field. A window assembly was constructed allowing the beam to pass consecutively through a collimator, a vacuum exit window and into the solid sample. The beam is stopped in the sample and the entire end of the assembly is a Faraday cup. Integration of the collected current, in conjunction

National Low-Level Waste Management Program Radionuclide Report Series, Volume 17: Plutonium-239

International Nuclear Information System (INIS)

Adams, J.P.; Carboneau, M.L.

1999-01-01

This report, Volume 17 of the National Low-Level Waste Management Program Radionuclide Report Series, discusses the radiological and chemical characteristics of plutonium-239 (Pu-239). This report also discusses waste types and forms in which Pu-239 can be found, waste and disposal information on Pu-239, and Pu-239 behavior in the environment and in the human body

National Low-Level Waste Management Program Radionuclide Report Series, Volume 17: Plutonium-239

Energy Technology Data Exchange (ETDEWEB)

J. P. Adams; M. L. Carboneau

1999-03-01

This report, Volume 17 of the National Low-Level Waste Management Program Radionuclide Report Series, discusses the radiological and chemical characteristics of plutonium-239 (Pu-239). This report also discusses waste types and forms in which Pu-239 can be found, waste and disposal information on Pu-239, and Pu-239 behavior in the environment and in the human body.

The Construction Solid Waste Minimization Practices among Malaysian Contractors

Directory of Open Access Journals (Sweden)

Che Ahmad A.

2014-01-01

Full Text Available The function of minimization of construction solid waste is to reduce or eliminates the adverse impacts on the environment and to human health. Due to the increase of population that leads to rapid development, there are possibilities of construction solid waste to be increased shortly from the construction works, demolition or renovation works. Materials such as wood, concrete, paint, brick, roofing, tiles, plastic and any other materials would contribute problem involving construction solid waste. Therefore, the proper waste minimization is needed to control the quantity of construction solid waste produced. This paper identifies the type of construction solid waste produced and discusses the waste minimization practice by the contractors at construction sites in Selangor, Kuala Lumpur and Putrajaya, Malaysia.

Determination of natural radionuclide level in industrial waste slags and evaluation of comprehensive utilization

International Nuclear Information System (INIS)

Li Ruixiang; Liu Xinhua; Gan Lin

1994-09-01

Natural radionuclide contents were measured in various industrial waste slags in China by a low background HPGe γ spectrometer and the radiological impact was estimated for some comprehensive utilization of these slags. Most waste slags can be used for building materials except for tailing and waste rock form nuclear industry

Assessment of LANL solid low-level mixed waste documentation

International Nuclear Information System (INIS)

Jennrich, E.A.; Lund, D.M.; Davis, K.D.; Hoevemeyer, S.S.

1991-04-01

DOE Order 5820.2A requires that a system performance assessment be conducted to assure efficient and compliant management of all radioactive waste. The objective of this report is to determine the present status of the Radioactive Waste Operations Section and the Chemical Waste Operations Section capabilities regarding preparation and maintenance of appropriate criteria, plans, and procedures. Additionally, a comparison is made which identifies areas where these documents are not presently in existence or being fully implemented. The documents being assessed in this report are: Solid Low-Level Mixed Waste Acceptance Criteria, Solid Low-Level Mixed Waste Characterization Plan, Solid Low-Level Mixed waste Certification Plan, Solid Low-Level Mixed Waste Acceptance Procedures, Solid Low-Level Mixed Waste characterization Procedures, Solid Low-Level Mixed Waste Certification Procedures, Solid Low-Level Mixed Waste Training Procedures, and Solid Low-Level Mixed Waste Recordkeeping Requirements. This report compares the current status of preparation and implementation, by the Radioactive Waste Operations Section and the Chemical Waste Operations Section, of these documents to the requirements of DOE 5820.2A,. 40 CFR 260 to 270, and to recommended practice. Chapters 2 through 9 of the report presents the results of the comparison in tabular form for each of the documents being assessed, followed by narrative discussion of all areas which are perceived to be unsatisfactory or out of compliance with respect to the availability and content of the documents. The final subpart of each of the following chapters provides recommendations where documentation practices may be improved to achieve compliance or to follow the recommended practice

Suspended solids in liquid effluents

International Nuclear Information System (INIS)

McGrath, J.J.

1988-06-01

An international literature review and telephone mail survey was conducted with respect to technical and regulatory aspects of suspended solids in radioactive liquid wastes from nuclear power stations. Results of the survey are summarized and show that suspended solids are an important component of some waste streams. The data available, while limited, show these solids to be associated largely with corrosion products. The solids are highly variable in quantity, size and composition. Filtration is commonly applied for their removal from liquid effluents and is effective. Complex interactions with receiving waters can result in physical/chemical changes of released radionuclides and these phenomena have been seen as reason for not applying regulatory controls based on suspended solids content. 340 refs

SOLID WASTE MANAGEMENT IN TABRIZ PETROCHEMICAL COMPLEX

Directory of Open Access Journals (Sweden)

M. A. Abduli, M. Abbasi, T. Nasrabadi, H. Hoveidi, N. Razmkhah

2006-07-01

Full Text Available Tabriz petrochemical complex is located in the northwest of Iran. Major products of this industry include raw plastics like, polyethylene, polystyrene, acrylonitrile, butadiene, styrene, etc. Sources of waste generation include service units, health and cure units, water, power, steam and industrial processes units. In this study, different types of solid waste including hazardous and non hazardous solid wastes were investigated separately. The aim of the study was to focus on the management of the industrial wastes in order to minimize the adverse environmental impacts. In the first stage, locating map and dispersion limits were prepared. Then, the types and amounts of industrial waste generated in were evaluated by an inventory and inspection. Wastes were classified according to Environmental Protection Agency and Basel Standards and subsequently hazards of different types were investigated. The waste management of TPC is quite complex because of the different types of waste and their pollution. In some cases recycling/reuse of waste is the best option, but treatment and disposal are also necessary tools. In this study, using different sources and references, generally petrochemical sources, various solid waste management practices were investigated and the best options were selected. Some wastes should be treated before land filling and some of them should be reused or recycled. In the case of solid waste optimization, source reduction ways were recommended as well as prior incineration system was modified.

Judgment on the presence of radionuclides in sample analysis: A case study

International Nuclear Information System (INIS)

Muhamat Omar; Zalina Laili; Mohd Suhaimi Hamzah

2012-01-01

Qualitative and quantitative analysis of samples require good judgment from the analysts. These two aspects in gamma spectrometric analysis of Proficiency Test and solid radioactive waste samples for the determination of radionuclides are discussed. It is vital to judge and decide what energy peaks belong to which radionuclides prior to the creation of customized radionuclide library for the analysis of specific samples. Corrections due to radionuclide decay and growth, and the half-life assigned to a particular radionuclide in the uranium and thorium series are also discussed. Discussion on judgment to confirm the presence of thorium in food samples based on gamma spectrometry and neutron activation analysis is also provided. (author)

Solid Waste Management in Recreational Forest Areas.

Science.gov (United States)

Spooner, Charles S.

The Forest Service, U. S. Department of Agriculture, requested the Bureau of Solid Waste Management to conduct a study of National Forest recreation areas to establish waste generation rates for major recreation activities and to determine the cost of solid waste handling for selected Forest Service Districts. This report describes the 1968 solid…

Composition of municipal solid waste in Denmark

DEFF Research Database (Denmark)

Edjabou, Vincent Maklawe Essonanawe; Petersen, Claus; Scheutz, Charlotte

2014-01-01

Data for the composition of municipal solid waste is a critical basis for any assessment of waste technologies and waste management systems. The detailed quantification of waste fractions is absolutely needed for a better technological development of waste treatment. The current waste composition...... comparability to characterize municipal solid waste. This methodology was applied to residual waste collected from 1,442 households in three municipalities in Denmark. The main fractions contributing to the residual household waste were food waste and miscellaneous waste. Statistical analysis suggested...... of standardised and commonly accepted waste characterization methodologies, various approaches have been reported in literature. This limits both comparability and applicability of the results. The purpose of this study was to introduce a consistent methodology that reduces uncertainties and ensures data...

Possibilities of municipal solid waste incinerator fly ash utilisation.

Science.gov (United States)

Hartmann, Silvie; Koval, Lukáš; Škrobánková, Hana; Matýsek, Dalibor; Winter, Franz; Purgar, Amon

2015-08-01

Properties of the waste treatment residual fly ash generated from municipal solid waste incinerator fly ash were investigated in this study. Six different mortar blends with the addition of the municipal solid waste incinerator fly ash were evaluated. The Portland cement replacement levels of the municipal solid waste incinerator fly ash used were 25%, 30% and 50%. Both, raw and washed municipal solid waste incinerator fly ash samples were examined. According to the mineralogical composition measurements, a 22.6% increase in the pozzolanic/hydraulic properties was observed for the washed municipal solid waste incinerator fly ash sample. The maximum replacement level of 25% for the washed municipal solid waste incinerator fly ash in mortar blends was established in order to preserve the compressive strength properties. Moreover, the leaching characteristics of the crushed mortar blend was analysed in order to examine the immobilisation of its hazardous contents. © The Author(s) 2015.

Initial Radionuclide Inventories

Energy Technology Data Exchange (ETDEWEB)

H. Miller

2004-09-19

The purpose of this analysis is to provide an initial radionuclide inventory (in grams per waste package) and associated uncertainty distributions for use in the Total System Performance Assessment for the License Application (TSPA-LA) in support of the license application for the repository at Yucca Mountain, Nevada. This document is intended for use in postclosure analysis only. Bounding waste stream information and data were collected that capture probable limits. For commercially generated waste, this analysis considers alternative waste stream projections to bound the characteristics of wastes likely to be encountered using arrival scenarios that potentially impact the commercial spent nuclear fuel (CSNF) waste stream. For TSPA-LA, this radionuclide inventory analysis considers U.S. Department of Energy (DOE) high-level radioactive waste (DHLW) glass and two types of spent nuclear fuel (SNF): CSNF and DOE-owned (DSNF). These wastes are placed in two groups of waste packages: the CSNF waste package and the codisposal waste package (CDSP), which are designated to contain DHLW glass and DSNF, or DHLW glass only. The radionuclide inventory for naval SNF is provided separately in the classified ''Naval Nuclear Propulsion Program Technical Support Document'' for the License Application. As noted previously, the radionuclide inventory data presented here is intended only for TSPA-LA postclosure calculations. It is not applicable to preclosure safety calculations. Safe storage, transportation, and ultimate disposal of these wastes require safety analyses to support the design and licensing of repository equipment and facilities. These analyses will require radionuclide inventories to represent the radioactive source term that must be accommodated during handling, storage and disposition of these wastes. This analysis uses the best available information to identify the radionuclide inventory that is expected at the last year of last emplacement

An integrated approach of composting methodologies for solid waste management

Directory of Open Access Journals (Sweden)

K. Kumaresan

2016-03-01

Full Text Available Organic fraction of solid waste, which upon degradation produces foul smell and generates pathogens, if not properly managed. Composting is not a method of waste disposal but it is a method of waste recycling and used for agricultural purposes. An integrated approach of composting methodology was tested for municipal solid waste management. Solid waste first was composted and after 22 days, was further processed by vermicomposting. Samples were routinely taken for analysis of carbon, nitrogen, moisture content, pH and temperature to determine the quality of composting. Decrease in moisture content to 32.1 %, relative decrease in carbon and nitrogen content were also observed. Among the different types of treatment, municipal solid waste + activated sludge integration showed promising results, followed by vermicomposting municipal solid waste + activated sludge combination, compared to the combinations of dried activated sludge, municipal solid waste + activated sludge semisolid and municipal solid waste + sewage water. Thus, windrow composting followed by vermicomposting gave a better result than other methods. Thus this method would serve as a potential alternative for solid waste management.

An integrated approach of composting methodologies for solid waste management

International Nuclear Information System (INIS)

Kumaresan, K.; Balan, R.; Sridhar, A.; Aravind, J.; Kanmani, P.

2016-01-01

Organic fraction of solid waste, which upon degradation produces foul smell and generates pathogens, if not properly managed. Composting is not a method of waste disposal but it is a method of waste recycling and used for agricultural purposes. An integrated approach of composting methodology was tested for municipal solid waste management. Solid waste first was composted and after 22 days, was further processed by vermicomposting. Samples were routinely taken for analysis of carbon, nitrogen, moisture content, p H and temperature to determine the quality of composting. Decrease in moisture content to 32.1 %, relative decrease in carbon and nitrogen content were also observed. Among the different types of treatment, municipal solid waste + activated sludge integration showed promising results, followed by vermicomposting municipal solid waste + activated sludge combination, compared to the combinations of dried activated sludge, municipal solid waste + activated sludge semisolid and municipal solid waste + sewage water. Thus, windrow composting followed by vermicomposting gave a better result than other methods. Thus this method would serve as a potential alternative for solid waste management.

Solid waste management in Asian countries: a review of solid waste minimisation (3'r) towards low carbon

International Nuclear Information System (INIS)

Ali, N E; Sion, H C

2014-01-01

The amount of solid-waste generated in Asian countries has increased tremendously, mainly due to the improvement in living standards, rapid developments in technology, growth in economy and population in the cities. Solid waste management is a global issue and major challenge facing Asian countries and neglecting its management may have negative consequences on the environment. Waste composition data proves the developed countries to have generated more recyclable materials while developing countries produce more organic and less recyclable waste such as paper, plastic and aluminium. In this regard, increase in number of landfills and disposal sites, will have an impact on GHG (greenhouse gas) emissions and pollutants to air and water. Alternative methods should therefore be taken to reduce the volume of waste. Most Asian countries have adopted the 3R (reduce, reuse, recycle) concept in order to reduce solid waste and their governments have implemented laws and regulations in order to support this. Implementation of 3R is the major contributor to the solid waste minimization and it can improve the quality of environmental sustainability and reduction of carbon dioxide emission in to the atmosphere. Based on our review, most of the countries practicing the 3R concept in tandem with laws and regulations perform better than those that just practice the 3R concept without any laws and regulations. The paper suggests that every country must focus on the laws and regulations relating to solid waste minimization so that it could be easily implemented as outlined

Origin, quantities produced and ways of conditioning of special wastes in regional collection points

International Nuclear Information System (INIS)

Neider, R.

1983-01-01

Radioactive substances to be collected at regional collecting points are mostly related to the radionuclides H-3, Ra-226 and Th-232. These special wastes form a particular group of wastes including such solid wastes which do not contain volatile radionuclides yet cannot, for other reasons, be conditioned in accordance with the old Asse qualifications. (orig./DG) [de

Radiation treatment of solid wastes

International Nuclear Information System (INIS)

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

1977-01-01

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

Dynamic Effects of Tank Waste Aging on Radionuclide-Complexant Interactions - Final Report - 10/01/1997 - 10/01/2000

Energy Technology Data Exchange (ETDEWEB)

Chamberlin, Rebecca M.; Arterburn, Jeffrey B. rmchamberlin@lanl.gov; jarterbu@nmsu.edu

2000-10-01

The long-range objective of this project is to provide a scientific basis for safely processing high-level nuclear tanks wastes for disposal. Our goals are to identify a means to prepare realistic simulant formulations for complexant-containing Hanford tank wastes, and then use those simulants to determine the relative importance of various organic complexants and their breakdown products on the partitioning of important radionuclides. The harsh chemical and radiolytic environment in high-level waste tanks alters both the organic complexants and the metal species, producing radionuclide-chelator complexes that resist standard separation methods. A detailed understanding of the complexation reactions of the key radionuclides in tank wastes would allow for reliable, science-based solutions for high-level waste processing, but a key problem is that tank waste samples are exceedingly difficult to obtain, transport and handle in the laboratory. In contrast, freshly-prepared simulated wastes are safe and readily obtained, but they do not reproduce the partitioning behavior of actual tank waste samples. For this project, we will first artificially age complexant-containing tank waste simulants using microwave, ultrasound, and photolysis techniques that can be applied in any standard laboratory. The aged samples will be compared to samples of actual Hanford tank wastes to determine the most realistic aging method, on the basis of the organic fragments present, and the oxidation states and partitioning behavior of important radionuclides such as 90Sr, 99Tc, and 239Pu. Our successful completion of this goal will make it possible for scientists in academic and industrial laboratories to address tank waste remediation problems without the enormous costs and hazards associated with handling actual tank waste samples. Later, we will use our simulant aging process to investigate the relative effects of chelator degradation products on the partitioning of important radionuclides

Dynamic Effects of Tank Waste Aging on Radionuclide-Complexant Interactions - Final Report - 10/01/1997 - 10/01/2000

International Nuclear Information System (INIS)

Chamberlin, Rebecca M.; Arterburn, Jeffrey B.

2000-01-01

The long-range objective of this project is to provide a scientific basis for safely processing high-level nuclear tanks wastes for disposal. Our goals are to identify a means to prepare realistic simulant formulations for complexant-containing Hanford tank wastes, and then use those simulants to determine the relative importance of various organic complexants and their breakdown products on the partitioning of important radionuclides. The harsh chemical and radiolytic environment in high-level waste tanks alters both the organic complexants and the metal species, producing radionuclide-chelator complexes that resist standard separation methods. A detailed understanding of the complexation reactions of the key radionuclides in tank wastes would allow for reliable, science-based solutions for high-level waste processing, but a key problem is that tank waste samples are exceedingly difficult to obtain, transport and handle in the laboratory. In contrast, freshly-prepared simulated wastes are safe and readily obtained, but they do not reproduce the partitioning behavior of actual tank waste samples. For this project, we will first artificially age complexant-containing tank waste simulants using microwave, ultrasound, and photolysis techniques that can be applied in any standard laboratory. The aged samples will be compared to samples of actual Hanford tank wastes to determine the most realistic aging method, on the basis of the organic fragments present, and the oxidation states and partitioning behavior of important radionuclides such as 90Sr, 99Tc, and 239Pu. Our successful completion of this goal will make it possible for scientists in academic and industrial laboratories to address tank waste remediation problems without the enormous costs and hazards associated with handling actual tank waste samples. Later, we will use our simulant aging process to investigate the relative effects of chelator degradation products on the partitioning of important radionuclides

Hanford Site Solid Waste Acceptance Criteria

Energy Technology Data Exchange (ETDEWEB)

1993-11-17

This manual defines the Hanford Site radioactive, hazardous, and sanitary solid waste acceptance criteria. Criteria in the manual represent a guide for meeting state and federal regulations; DOE Orders; Hanford Site requirements; and other rules, regulations, guidelines, and standards as they apply to acceptance of radioactive and hazardous solid waste at the Hanford Site. It is not the intent of this manual to be all inclusive of the regulations; rather, it is intended that the manual provide the waste generator with only the requirements that waste must meet in order to be accepted at Hanford Site TSD facilities.

Hanford Site Solid Waste Acceptance Criteria

International Nuclear Information System (INIS)

1993-01-01

This manual defines the Hanford Site radioactive, hazardous, and sanitary solid waste acceptance criteria. Criteria in the manual represent a guide for meeting state and federal regulations; DOE Orders; Hanford Site requirements; and other rules, regulations, guidelines, and standards as they apply to acceptance of radioactive and hazardous solid waste at the Hanford Site. It is not the intent of this manual to be all inclusive of the regulations; rather, it is intended that the manual provide the waste generator with only the requirements that waste must meet in order to be accepted at Hanford Site TSD facilities

Natural analogue approach for estimating the health risks from release and migration of radionuclides from radioactive waste

International Nuclear Information System (INIS)

Gilbert, T.L.

1983-01-01

The health risks from radioactive waste may be expressed as a sum of products of transfer factors that characterize the causal chain of events between disposal of radionuclides in a waste field and the consequent health effects. Model estimates for the transfer factors are commonly obtained by modeling transport and other mechanisms in the subsystems that form the links in the causal chain. Natural estimates of some conversion factors for naturally occurring radionuclides can be obtained from data on the concentrations of naturally occurring radionuclides in soil, food, and the human body. These model and natural estimates can be used with scaling procedures to estimate the uncertainties and to obtain better estimates of the values. The scaling procedures take into account the differences in the source characteristics for radionuclides in a waste field of limited size and for radionuclides generally distributed in the natural environment. The ratios of the natural estimates to the model estimates for several transfer factors and several radionuclides belonging to the U-238 decay series have been determined. These ratios range from 1/8 to 4/1 for food-concentration/source-concentration transfer factors for the food pathways and from 1 to 77 for dose-rate/source-concentration transfer factors for the internal radiation dose pathways to various organs. 14 references

Solid medical waste

DEFF Research Database (Denmark)

Udofia, Emilia Asuquo; Gulis, Gabriel; Fobil, Julius

2017-01-01

BACKGROUND: Solid medical waste (SMW) in households is perceived to pose minimal risks to the public compared to SMW generated from healthcare facilities. While waste from healthcare facilities is subject to recommended safety measures to minimize risks to human health and the environment, similar...... waste in households is often untreated and co-mingled with household waste which ends up in landfills and open dumps in many African countries. In Ghana, the management of this potentially hazardous waste stream at household and community level has not been widely reported. The objective of this study...... likely to report harm in the household (OR 2.75, 95%CI 1.15-6.54). CONCLUSION: The belief that one can be harmed by diseases associated with SMW influenced reporting rates in the study area. Disposal practices suggest the presence of unwanted medicines and sharps in the household waste stream conferring...

Global capacity, potentials and trends of solid waste research and management.

Science.gov (United States)

Nwachukwu, Michael A; Ronald, Mersky; Feng, Huan

2017-09-01

In this study, United States, China, India, United Kingdom, Nigeria, Egypt, Brazil, Italy, Germany, Taiwan, Australia, Canada and Mexico were selected to represent the global community. This enabled an overview of solid waste management worldwide and between developed and developing countries. These are countries that feature most in the International Conference on Solid Waste Technology and Management (ICSW) over the past 20 years. A total of 1452 articles directly on solid waste management and technology were reviewed and credited to their original country of research. Results show significant solid waste research potentials globally, with the United States leading by 373 articles, followed by India with 230 articles. The rest of the countries are ranked in the order of: UK > Taiwan > Brazil > Nigeria > Italy > Japan > China > Canada > Germany >Mexico > Egypt > Australia. Global capacity in solid waste management options is in the order of: Waste characterisation-management > waste biotech/composting > waste to landfill > waste recovery/reduction > waste in construction > waste recycling > waste treatment-reuse-storage > waste to energy > waste dumping > waste education/public participation/policy. It is observed that the solid waste research potential is not a measure of solid waste management capacity. The results show more significant research impacts on solid waste management in developed countries than in developing countries where economy, technology and society factors are not strong. This article is targeted to motivate similar study in each country, using solid waste research articles from other streamed databases to measure research impacts on solid waste management.

Infiltration control for low-level radioactive solid waste disposal areas: an assessment

International Nuclear Information System (INIS)

Arora, H.S.

1980-11-01

The primary mode of radionuclide transport from shallow land-disposal sites for low-level wastes can be traced to infiltration of precipitation. This report examines the factors that affect surface water entry and movement in the ground and assesses available infiltration-control technology for solid-waste-disposal sites in the humid eastern portion of the United States. A survey of the literature suggests that a variety of flexible and rigid liner systems are available as barriers for the stored waste and would be effective in preventing water infiltration. Installation of near-surface seals of bentonite clay admixed with dispersive chemicals seem to offer the required durability and low permeability at a reasonable cost. The infiltration rate in a bentonite-sealed area may be further retarded by the application of dispersive chemicals that can be easily admixed with the surface soil. Because the effectiveness of a dispersive chemical for infiltration reduction is influenced by the physico-chemical properties of the soil, appropriate laboratory tests should be conducted prior to field application

On the Durability of Nuclear Waste Forms from the Perspective of Long-Term Geologic Repository Performance

Directory of Open Access Journals (Sweden)

Yifeng Wang

2013-12-01

Full Text Available High solid/water ratios and slow water percolation cause the water in a repository to quickly (on a repository time scale reach radionuclide solubility controlled by the equilibrium with alteration products; the total release of radionuclides then becomes insensitive to the dissolution rates of primary waste forms. It is therefore suggested that future waste form development be focused on conditioning waste forms or repository environments to minimize radionuclide solubility, rather than on marginally improving the durability of primary waste forms.

Method of melting solid waste

International Nuclear Information System (INIS)

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

1982-01-01

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

Solid waste electron beam treatment

International Nuclear Information System (INIS)

Chmielewski, A.G.

1998-01-01

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

Solid waste electron beam treatment

Energy Technology Data Exchange (ETDEWEB)

Chmielewski, A G

1998-07-01

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

Development of a master plan for industrial solid waste management

International Nuclear Information System (INIS)

Karamouz, M.; Zahraie, B.; Kerachian, R.; Mahjouri, N.; Moridi, A.

2006-01-01

Rapid industrial growth in the province of Khuzestan in the south west of Iran has resulted in disposal of about 1750 tons of solid waste per day. Most of these industrial solid wastes including hazardous wastes are disposed without considering environmental issues. This has contributed considerably to the pollution of the environment. This paper introduces a framework in which to develop a master plan for industrial solid waste management. There are usually different criteria for evaluating the existing solid waste pollution loads and how effective the management schemes are. A multiple criteria decision making technique, namely Analytical Hierarchy Process, is used for ranking the industrial units based on their share in solid waste related environmental pollution and determining the share of each unit in total solid waste pollution load. In this framework, a comprehensive set of direct, indirect, and supporting projects are proposed for solid waste pollution control. The proposed framework is applied for industrial solid waste management in the province of Khuzestan in Iran and a databank including GIS based maps of the study area is also developed. The results have shown that the industries located near the capital city of the province, Ahwaz, produce more than 32 percent of the total solid waste pollution load of the province. Application of the methodology also has shown that it can be effectively used for development of the master plan and management of industrial solid wastes

Conversion of Waste into Wealth: A Study in Solid Waste Management

Directory of Open Access Journals (Sweden)

T. Janakiram

2010-01-01

Full Text Available Disposal of solid waste has been the talk of the day. An attempt has been made to dispose of the solid waste Jatropha (Kattamanakku. Aerobic composting method was employed. Properly treated solid wastes of different composition were mixed with slurries of cowdung and physicochemical parameters were measured after 30 and 60 days of composting. It was observed that percentages of nitrogen, phosphorous, potassium, sodium, calcium and magnesium increased as time elapsed. Water holding capacity, electrical conductivity and moisture content were found to increase, while pH and C/N ratio have been observed to decrease.

Integrated waste management - Looking beyond the solid waste horizon

International Nuclear Information System (INIS)

Seadon, J.K.

2006-01-01

Waste as a management issue has been evident for over four millennia. Disposal of waste to the biosphere has given way to thinking about, and trying to implement, an integrated waste management approach. In 1996 the United Nations Environmental Programme (UNEP) defined 'integrated waste management' as 'a framework of reference for designing and implementing new waste management systems and for analysing and optimising existing systems'. In this paper the concept of integrated waste management as defined by UNEP is considered, along with the parameters that constitute integrated waste management. The examples used are put into four categories: (1) integration within a single medium (solid, aqueous or atmospheric wastes) by considering alternative waste management options (2) multi-media integration (solid, aqueous, atmospheric and energy wastes) by considering waste management options that can be applied to more than one medium (3) tools (regulatory, economic, voluntary and informational) and (4) agents (governmental bodies (local and national), businesses and the community). This evaluation allows guidelines for enhancing success: (1) as experience increases, it is possible to deal with a greater complexity; and (2) integrated waste management requires a holistic approach, which encompasses a life cycle understanding of products and services. This in turn requires different specialisms to be involved in the instigation and analysis of an integrated waste management system. Taken together these advance the path to sustainability

Processing method for miscellaneous radioactive solid waste

International Nuclear Information System (INIS)

Matsuda, Masami; Komori, Itaru; Nishi, Takashi.

1995-01-01

Miscellaneous solid wastes are subjected to heat treatment at a temperature not lower than a carbonizing temperature of organic materials in the wastes and not higher than the melting temperature of inorganic materials in the wastes, for example, not lower than 200degC but not higher than 660degC, and then resultant miscellaneous solid wastes are solidified using a water hardening solidification material. With such procedures, the organic materials in the miscellaneous solids are decomposed into gases. Therefore, solid materials excellent in long term stability can be formed. In addition, since the heat treatment is conducted at a relatively low temperature such as not higher than 660degC, the generation amount of off gases is reduced to simplify an off gas processing system, and since molten materials are not formed, handing is facilitated. (T.M.)

Evaluation of municipal solid waste management in egyptian rural areas.

Science.gov (United States)

El-Messery, Mamdouh A; Ismail, Gaber A; Arafa, Anwaar K

2009-01-01

A two years study was conducted to evaluate the solid waste management system in 143 villages representing the Egyptian rural areas. The study covers the legal responsibilities, service availability, environmental impacts, service providers, financial resources, private sector participation and the quality of collection services. According to UN reports more than 55% of Egyptian population lives in rural areas. A drastic change in the consumption pattern altered the quantity and quality of the generated solid wastes from these areas. Poor solid waste management systems are stigmata in most of the Egyptian rural areas. This causes several environmental and health problems. It has been found that solid waste collection services cover only 27% of the surveyed villages, while, the statistics show that 75% of the surveyed villages are formally covered. The service providers are local villager units, private contractors and civil community associations with a percentage share 71%, 24% and 5% respectively. The operated services among these sectors were 25%, 71% and 100% respectively. The share of private sector in solid waste management in rural areas is still very limited as a result of the poverty of these communities and the lack of recyclable materials in their solid waste. It has been found that direct throwing of solid waste on the banks of drains and canals as well as open dumping and uncontrolled burning of solid waste are the common practice in most of the Egyptian rural areas. The available land for landfill is not enough, pitiable designed, defectively constructed and unreliably operated. Although solid waste generated in rural areas has high organic contents, no composting plant was installed. Shortage in financial resources allocated for valorization of solid waste management in the Egyptian rural areas and lower collection fees are the main points of weakness which resulted in poor solid waste management systems. On the other hand, the farmer's participation

Race, wealth, and solid waste facilities in North Carolina.

Science.gov (United States)

Norton, Jennifer M; Wing, Steve; Lipscomb, Hester J; Kaufman, Jay S; Marshall, Stephen W; Cravey, Altha J

2007-09-01

Concern has been expressed in North Carolina that solid waste facilities may be disproportionately located in poor communities and in communities of color, that this represents an environmental injustice, and that solid waste facilities negatively impact the health of host communities. Our goal in this study was to conduct a statewide analysis of the location of solid waste facilities in relation to community race and wealth. We used census block groups to obtain racial and economic characteristics, and information on solid waste facilities was abstracted from solid waste facility permit records. We used logistic regression to compute prevalence odds ratios for 2003, and Cox regression to compute hazard ratios of facilities issued permits between 1990 and 2003. The adjusted prevalence odds of a solid waste facility was 2.8 times greater in block groups with > or = 50% people of color compared with block groups with or = 100,000 dollars. Among block groups that did not have a previously permitted solid waste facility, the adjusted hazard of a new permitted facility was 2.7 times higher in block groups with > or = 50% people of color compared with block groups with waste facilities present numerous public health concerns. In North Carolina solid waste facilities are disproportionately located in communities of color and low wealth. In the absence of action to promote environmental justice, the continued need for new facilities could exacerbate this environmental injustice.

Electricity production from municipal solid waste in Brazil.

Science.gov (United States)

Nordi, Guilherme Henrique; Palacios-Bereche, Reynaldo; Gallego, Antonio Garrido; Nebra, Silvia Azucena

2017-07-01

Brazil has an increasing production of municipal solid waste that, allied to the current waste management system, makes the search for alternatives of energy recovery essential. Thus, this work aims to study the incineration of municipal solid waste and the electricity production through steam cycles evaluating the influence of municipal solid waste composition. Several scenarios were studied, in which it was assumed that some fractions of municipal solid waste were removed previously. The municipal solid waste generated in Santo André city, São Paulo State, Brazil, was adopted for this study. Simulation results showed that the removal of organic matter and inert components impacts advantageously on the cycle performance, improving their parameters in some cases; in addition, there is the possibility of reusing the separated fractions. The separation of some recyclables, as plastic material, showed disadvantages by the reduction in the electricity generation potential owing to the high calorific value of plastics. Despite the high energy content of them, there are other possible considerations on this subject, because some plastics have a better recovery potential by recycling.

Treatment of organic solid waste for reuse: a step towards zero waste

International Nuclear Information System (INIS)

Ali, M.; Khan, Z.M.; Raja, I.A.

2013-01-01

Large amounts of organic solid wastes are being generated from municipal, industrial and agricultural activities. After necessary processing, the organic solid waste can be reused for agriculture not only as a nutrient supplement for plant growth, but also as a conditioner for seedbed soil. Processed organic wastes may improve soil structure and enhance water and nutrient-holding capacity of the soil, as well as increase the microbial activity within the soil, thereby increasing soil fertility. In this study, problems like undesirably high moisture contents and large volumes per unit weight of the processed organic solid wastes have been addressed through pelletization. Physical properties like durability, percent of fines content, and bulk and particle density of the processed and pelletized organic waste have been investigated, and the optimum values for storage, handling and transportation of the pelletized organic waste have been determined. Three different sizes of extruding sieve (4.35, 6.35 and 7.9 mm) and three different waste-mixing ratios (1:1:2, 1:2:2 and 1:3:3) of farmyard waste, wastewater sludge and sugar industry press mud were used respectively for the production of bio-solid pellets. The physical properties of the palletes show that durability increases by increasing the amount of sewage sludge while fines content, bulk density and unit density decrease. The large sieve size has more durability and less fine content. The results showed that the pelletization technique can be efficiently used by the farmers and appears to be a good option for sustainable management and re-use of organic solid wastes. (author)

Methods and machinery for pulverising solid wastes

CSIR Research Space (South Africa)

Simpkins, MJ

1976-11-01

Full Text Available This report is published on behalf of the South African Committee for Solid Wastes which in turn advises the National Committee for Environmental Sciences on problems concerned with Solid Wastes in South Africa. It is particularly concerned...

Solid waste disposal into salt mines

International Nuclear Information System (INIS)

Repke, W.

1981-01-01

The subject is discussed as follows: general introduction to disposal of radioactive waste; handling of solid nuclear waste; technology of final disposal, with specific reference to salt domes; conditioning of radioactive waste; safety barriers for radioactive waste; practice of final disposal in other countries. (U.K.)

Energy aspects of solid waste management: Proceedings

Energy Technology Data Exchange (ETDEWEB)

1990-12-31

The Eighteenth Annual Illinois Energy Conference entitled ``Energy Aspects of Solid Waste Management`` was held in Chicago, Illinois on October 29--30, 1990. The conference program was developed by a planning committee that drew upon Illinois energy and environmental specialists from the major sectors including energy industries, environmental organizations, research universities, utility companies, federal, state and local government agencies, and public interest groups. Within this framework, the committee identified a number of key topic areas surrounding solid waste management in Illinois which were the focus of the conference. These issues included: review of the main components of the solid waste cycle in the Midwest and what the relative impact of waste reduction, recycling, incineration and land disposal might be on Illinois` and the Midwest`s solid waste management program. Investigation of special programs in the Midwest dealing with sewage sludge, combustion residuals and medical/infectious wastes. Review of the status of existing landfills in Illinois and the Midwest and an examination of the current plans for siting of new land disposal systems. Review of the status of incinerators and waste-to-energy systems in Illinois and the Midwest, as well as an update on activities to maximize methane production from landfills in the Midwest.

Energy aspects of solid waste management: Proceedings

Energy Technology Data Exchange (ETDEWEB)

1990-01-01

The Eighteenth Annual Illinois Energy Conference entitled Energy Aspects of Solid Waste Management'' was held in Chicago, Illinois on October 29--30, 1990. The conference program was developed by a planning committee that drew upon Illinois energy and environmental specialists from the major sectors including energy industries, environmental organizations, research universities, utility companies, federal, state and local government agencies, and public interest groups. Within this framework, the committee identified a number of key topic areas surrounding solid waste management in Illinois which were the focus of the conference. These issues included: review of the main components of the solid waste cycle in the Midwest and what the relative impact of waste reduction, recycling, incineration and land disposal might be on Illinois' and the Midwest's solid waste management program. Investigation of special programs in the Midwest dealing with sewage sludge, combustion residuals and medical/infectious wastes. Review of the status of existing landfills in Illinois and the Midwest and an examination of the current plans for siting of new land disposal systems. Review of the status of incinerators and waste-to-energy systems in Illinois and the Midwest, as well as an update on activities to maximize methane production from landfills in the Midwest.

Uncertainties in geologic disposal of high-level wastes - groundwater transport of radionuclides and radiological consequences

International Nuclear Information System (INIS)

Kocher, D.C.; Sjoreen, A.L.; Bard, C.S.

1983-01-01

The analysis for radionuclide transport in groundwater considers models and methods for characterizing (1) the present geologic environment and its future evolution due to natural geologic processes and to repository development and waste emplacement, (2) groundwater hydrology, (3) radionuclide geochemistry, and (4) the interactions among these phenomena. The discussion of groundwater transport focuses on the nature of the sources of uncertainty rather than on quantitative estimates of their magnitude, because of the lack of evidence that current models can provide realistic quantitative predictions of radionuclide transport in groundwater for expected repository environments. The analysis for the long-term health risk to man following releases of long-lived radionuclides to the biosphere is more quantitative and involves estimates of uncertainties in (1) radionuclide concentrations in man's exposure environment, (2) radionuclide intake by exposed individuals per unit concentration in the environment, (3) the dose per unit intake, (4) the number of exposed individuals, and (5) the health risk per unit dose. For the important long-lived radionuclides in high-level waste, uncertainties in most of the different components of a calculation of individual and collective dose per unit release appear to be no more than two or three orders of magnitude; these uncertainties are certainly much less than uncertainties in predicting groundwater transport of radionuclides between a repository and the biosphere. Several limitations in current models for predicting the health risk to man per unit release to the biosphere are discussed

Solid Waste Management in Nigeria: Problems and Issues.

Science.gov (United States)

AGUNWAMBA

1998-11-01

/ This paper is a presentation of the problems of solid waste management in Nigeria and certain important issues that must be addressed in order to achieve success. At the core of the problems of solid waste management are the absence of adequate policies, enabling legislation, and an environmentally stimulated and enlightened public. Government policies on the environment are piecemeal where they exist and are poorly implemented. Public enlightenment programs lacked the needed coverage, intensity, and continuity to correct the apathetic public attitude towards the environment. Up to now the activities of the state environmental agencies have been hampered by poor funding, inadequate facilities and human resources, inappropriate technology, and an inequitable taxation system. Successful solid waste management in Nigeria will require a holistic program that will integrate all the technical, economic, social, cultural, and psychological factors that are often ignored in solid waste programs.KEY WORDS: Solid waste; Management; Problems; Solutions; Nigeria

Waste management and enzymatic treatment of Municipal Solid Waste

DEFF Research Database (Denmark)

Jensen, Jacob Wagner

generation for subsequent biogas production. Municipal solid waste (MSW) is produced in large amounts every year in the developed part of the world. The household waste composition varies between geographical areas and between seasons. However the overall content of organic and degradable material is rather......The work carried out during the Ph.D. project is part of the Danish Energy Authority funded research project called PSO REnescience and is focussed on studying the enzymatic hydrolysis and liquefaction of waste biomass. The purpose of studying the liquefaction of waste biomass is uniform slurry...... constant between 50 - 60 % wet weight and therefore holds a potential for bioenergy production. The degradable fraction has positive effects for anaerobic digestion when evaluated to desired parameters of anaerobic digestion plants. Wanted parameters are: 1) high organic content (high volatile solid...

Managing America's solid waste

Energy Technology Data Exchange (ETDEWEB)

Phillips, J. A.

1998-09-15

This report presents an historical overview of the federal role in municipal solid waste management from 1965 to approximately 1995. Attention is focuses on the federal role in safeguarding public health, protecting the environment, and wisely using material and energy resources. It is hoped that this report will provide important background for future municipal solid waste research and development initiatives.

Solid Waste Management Holistic Decision Modeling

OpenAIRE

World Bank

2008-01-01

This study provides support to the Bank's ability to conduct client dialogue on solid waste management technology selection, and will contribute to client decision-making. The goal of the study was to fully explore the use of the United States Environmental Protection Agency and the Research Triangle Institute (EPA/RTI) holistic decision model to study alternative solid waste systems in a ...

Land Use Management for Solid Waste Programs

Science.gov (United States)

Brown, Sanford M., Jr.

1974-01-01

The author discusses the problems of solid waste disposal and examines various land use management techniques. These include the land use plan, zoning, regionalization, land utilities, and interim use. Information concerning solid waste processing site zoning and analysis is given. Bibliography included. (MA)

Management of Radioactive Wastes

International Nuclear Information System (INIS)

Tchokosa, P.

2010-01-01

Management of Radioactive Wastes is to protect workers and the public from the radiological risk associated with radioactive waste for the present and future. It application of the principles to the management of waste generated in a radioisotope uses in the industry. Any material that contains or is contaminated with radionuclides at concentrations or radioactivity levels greater than ‘exempt quantities’ established by the competent regulatory authorities and for which no further use is foreseen or intended. Origin of the Radioactive Waste includes Uranium and Thorium mining and milling, nuclear fuel cycle operations, Operation of Nuclear power station, Decontamination and decommissioning of nuclear facilities and Institutional uses of isotopes. There are types of radioactive waste: Low-level Waste (LLW) and High-level Waste. The Management Options for Radioactive Waste Depends on Form, Activity, Concentration and half-lives of the radioactive waste, Storage and disposal methods will vary according to the following; the radionuclides present, and their concentration, and radio toxicity. The contamination results basically from: Contact between radioactive materials and any surface especially during handling. And it may occur in the solid, liquid or gas state. Decontamination is any process that will either reduce or completely remove the amount of radionuclides from a contaminated surface

Life cycle assessments of energy from solid waste

Energy Technology Data Exchange (ETDEWEB)

Finnveden, Goeran; Johansson, Jessica; Lind, Per; Moberg, Aasa [Stockholm Univ. (Sweden). Dept. of Systems Ecology/Natural Resoruces Management Inst.]|[Defence Research Establishment, Stockholm (Sweden). Div. of Defence Analysis

2000-09-01

The overall aim of the present study is to evaluate different strategies for treatment of solid waste based on a life-cycle perspective. Important goals are to identify advantages and disadvantages of different methods for treatment of solid waste, and to identify critical factors in the systems, including the background systems, which may significantly influence the results. Included in the study are landfilling, incineration, recycling, digestion and composting. The waste fractions considered are the combustible and recyclable or compostable fractions of municipal solid waste. The methodology used is Life Cycle Assessment. The results can be used for policy decisions as well as strategic decisions on waste management systems.

National low-level waste management program radionuclide report series, Volume 14: Americium-241

International Nuclear Information System (INIS)

Winberg, M.R.; Garcia, R.S.

1995-09-01

This report, Volume 14 of the National Low-Level Waste Management Program Radionuclide Report Series, discusses the radiological and chemical characteristics of americium-241 ( 241 Am). This report also includes discussions about waste types and forms in which 241 Am can be found and 241 Am behavior in the environment and in the human body

National Low-Level Waste Management Program radionuclide report series. Volume 13, Curium-242

International Nuclear Information System (INIS)

Adams, J.P.

1995-08-01

This report, Volume 13 of the National Low-Level Waste Management Program Radionuclide Report Series, discusses the radiological and chemical characteristics of curium-242 ( 242 Cm). This report also includes discussions about waste types and forms in which 242 Cm can be found and 242 Cm behavior in the environment and in the human body

Modeling for speciation of radionuclides in waste packages with high-level radioactive wastes

International Nuclear Information System (INIS)

Weyand, Torben; Bracke, Guido; Seher, Holger

2016-10-01

Based on a literature search on radioactive waste inventories adequate thermodynamic data for model inventories were derived for geochemical model calculations using PHREEQC in order to determine the solid phase composition of high-level radioactive wastes in different containers. The calculations were performed for different model inventories (PWR-MOX, PWR-UO2, BWR-MOX, BMR-UO2) assuming intact containers under reduction conditions. The effect of a defect in the container on the solid phase composition was considered in variation calculations assuming air contact induced oxidation.

Tribal Decisions-Makers Guide to Solid Waste Management: Chapter 2 - Developing Solid Waste Management Plans

Science.gov (United States)

Solid waste management plans offer a host of benefits for tribes and Alaskan Native villages. Through the preparation of these plans, you can assess your cur-rent and future waste management needs, set priorities, and allocate resources accordingly.

Exploring the sustainability of composting as a solid waste ...

African Journals Online (AJOL)

Solid waste composting has emerged as an innovative approach to managing solid waste in various regions of the world. However, the sustainability of this approach to solid waste management has been sparsely investigated in the study area. This paper reviews composting case studies in Nigeria with the aim of providing ...

Facility for low-level solid waste treatment

International Nuclear Information System (INIS)

Vicente, R.; Miyamoto, H.

1987-01-01

A facility for low-level solid waste compaction, encapsulation and storage is described. Solid wastes are compacted in 200 l drums and stored over concrete platforms covered with canvas, for decay or for interim storage before transport to the final disposal site. (Author) [pt

Development of thermodynamic databases and geochemical/transport models for prediction of long-term radionuclide migration (Germany)

International Nuclear Information System (INIS)

Kienzler, B.

2000-01-01

The isolation capacity of a repository system for radionuclides is described by geochemical modeling. The models for interpretation of experimental findings and for long-term extrapolation of experimental results are based on thermodynamic approaches. The geochemical models include dissolution reactions of waste forms, the evolution of the geochemical milieu, interactions of radionuclides with constituents of the groundwater (brines) and the precipitation of new solid phases. Reliable thermodynamic data, understanding of radionuclide complexation in aqueous multi-electrolyte solutions at the relevant ionic strength and knowledge on the formation of pure and mixed solids and on sorption processes are urgently needed for such model calculations. (author)

Genotoxicity and mutagenicity of solid waste leachates: A review

African Journals Online (AJOL)

user

2013-07-03

Jul 3, 2013 ... There is need for a shift from waste disposal to sustainable waste management. Awareness on possible health ... Key words: Solid waste leachate, genotoxicity, mutagenicity, environmental pollution. INTRODUCTION. Solid wastes .... landfills and incineration residues from Japan include persistent organic ...

Characterization of urban solid waste in Chihuahua, Mexico

International Nuclear Information System (INIS)

Gomez, Guadalupe; Meneses, Montserrat; Ballinas, Lourdes; Castells, Francesc

2008-01-01

The characterization of urban solid waste generation is fundamental for adequate decision making in the management strategy of urban solid waste in a city. The objective of this study is to characterize the waste generated in the households of Chihuahua city, and to compare the results obtained in areas of the city with three different socioeconomic levels. In order to identify the different socioeconomic trends in waste generation and characterization, 560 samples of solid waste were collected during 1 week from 80 households in Chihuahua and were hand sorted and classified into 15 weighted fractions. The average waste generation in Chihuahua calculated in this study was 0.676 kg per capita per day in April 2006. The main fractions were: organic (48%), paper (16%) and plastic (12%). Results show an increased waste generation associated with the socioeconomic level. The characterization in amount and composition of urban waste is the first step needed for the successful implementation of an integral waste management system

Characterization of urban solid waste in Chihuahua, Mexico.

Science.gov (United States)

Gomez, Guadalupe; Meneses, Montserrat; Ballinas, Lourdes; Castells, Francesc

2008-12-01

The characterization of urban solid waste generation is fundamental for adequate decision making in the management strategy of urban solid waste in a city. The objective of this study is to characterize the waste generated in the households of Chihuahua city, and to compare the results obtained in areas of the city with three different socioeconomic levels. In order to identify the different socioeconomic trends in waste generation and characterization, 560 samples of solid waste were collected during 1 week from 80 households in Chihuahua and were hand sorted and classified into 15 weighted fractions. The average waste generation in Chihuahua calculated in this study was 0.676 kg per capita per day in April 2006. The main fractions were: organic (48%), paper (16%) and plastic (12%). Results show an increased waste generation associated with the socioeconomic level. The characterization in amount and composition of urban waste is the first step needed for the successful implementation of an integral waste management system.

National Low-Level Waste Management Program radionuclide report series. Volume 13, Curium-242

Energy Technology Data Exchange (ETDEWEB)

Adams, J.P.

1995-08-01

This report, Volume 13 of the National Low-Level Waste Management Program Radionuclide Report Series, discusses the radiological and chemical characteristics of curium-242 ({sup 242}Cm). This report also includes discussions about waste types and forms in which {sup 242}Cm can be found and {sup 242}Cm behavior in the environment and in the human body.

Solid Waste Projection Model: Model user's guide

International Nuclear Information System (INIS)

Stiles, D.L.; Crow, V.L.

1990-08-01

The Solid Waste Projection Model (SWPM) system is an analytical tool developed by Pacific Northwest Laboratory (PNL) for Westinghouse Hanford company (WHC) specifically to address solid waste management issues at the Hanford Central Waste Complex (HCWC). This document, one of six documents supporting the SWPM system, contains a description of the system and instructions for preparing to use SWPM and operating Version 1 of the model. 4 figs., 1 tab

Municipal solid waste management in Malaysia: Practices and challenges

International Nuclear Information System (INIS)

Manaf, Latifah Abd; Samah, Mohd Armi Abu; Zukki, Nur Ilyana Mohd

2009-01-01

Rapid economic development and population growth, inadequate infrastructure and expertise, and land scarcity make the management of municipal solid waste become one of Malaysia's most critical environmental issues. The study is aimed at evaluating the generation, characteristics, and management of solid waste in Malaysia based on published information. In general, the per capita generation rate is about 0.5-0.8 kg/person/day in which domestic waste is the primary source. Currently, solid waste is managed by the Ministry of Housing and Local Government, with the participation of the private sector. A new institutional and legislation framework has been structured with the objectives to establish a holistic, integrated, and cost-effective solid waste management system, with an emphasis on environmental protection and public health. Therefore, the hierarchy of solid waste management has given the highest priority to source reduction through 3R, intermediate treatment and final disposal.

Stock flow diagram analysis on solid waste management in Malaysia

Science.gov (United States)

Zulkipli, Faridah; Nopiah, Zulkifli Mohd; Basri, Noor Ezlin Ahmad; Kie, Cheng Jack

2016-10-01

The effectiveness on solid waste management is a major importance to societies. Numerous generation of solid waste from our daily activities has risked for our communities. These due to rapid population grow and advance in economic development. Moreover, the complexity of solid waste management is inherently involved large scale, diverse and element of uncertainties that must assist stakeholders with deviating objectives. In this paper, we proposed a system dynamics simulation by developing a stock flow diagram to illustrate the solid waste generation process and waste recycle process. The analysis highlights the impact on increasing the number of population toward the amount of solid waste generated and the amount of recycled waste. The results show an increment in the number of population as well as the amount of recycled waste will decrease the amount of waste generated. It is positively represent the achievement of government aim to minimize the amount of waste to be disposed by year 2020.

Activity measurement algorithm in solid radioactive waste clearance procedure

International Nuclear Information System (INIS)

Hinca, R.; Skala, L.

2014-01-01

Most of European metrology experts prefer in radiation wastes characterization process to use scaling factor method in combination with high definition gamma spectrometry rather than radionuclide vector method in combination with gross gamma activity measurement. The second method is actually used in Slovakian nuclear facilities. The international (IAEA) and Slovak national authorities (UVZ) recognize both approach but there is a fact, that high definition gamma spectrometry radionuclides more properly. (authors)

Lyophilization for Water Recovery From Solid Waste

Science.gov (United States)

Flynn, Michael; Litwiller, Eric; Reinhard, Martin

2003-01-01

This abstract describes the development of a solid waste treatment system designed for a near term human exploration mission. The technology being developed is an energy- efficient lyophilization technique that recovers water from spacecraft solid waste. In the lyophilization process water in an aqueous waste is frozen and then sublimed, resulting in the separation of the waste into a dried solid material and liquid water. This technology is ideally suited to applications where water recovery rates approaching 100% are desirable but production of CO, is not. Water contained within solid wastes accounts for approximately 3% of the total water balance. If 100% closure of the water loop is desired the water contained within this waste would need to be recovered. To facilitate operation in microgravity thermoelectric heat pumps have be used in place of traditional fluid cycle heat pumps. A mathematical model of a thermoelectric lyophilizer has been developed and used to generate energy use and processing rate parameters. The results of laboratory investigations and discussions with ALS program management have been used to iteratively arrive at a prototype design. This design address operational limitations which were identified in the laboratory studies and handling and health concerns raised by ALS program management. The current prototype design is capable of integration into the ISS Waste Collection System.

Radionanalysis in solid waste research and management

International Nuclear Information System (INIS)

Das, H.A.

1994-01-01

Risk assessment of dumping or recycling of solid waste makes part of environmental geochemistry. Radioanalysis provides efficient procedures for the characterization of solid wastes, both granular and as recycled products. Radiotracers are applied to measure the situ values of transport parameters. Activation analysis is used in the determination of trace constituents in solids and leachates. This text summarizes some important applications of radioanalysis in this part of environmental monitoring

Initial site characterization and evaluation of radionuclide contaminated soil waste burial grounds

International Nuclear Information System (INIS)

Phillips, S.J.; Reisenauer, A.E.; Rickard, W.H.; Sandness, G.A.

1977-02-01

A survey of historical records and literature containing information on the contents of 300 Area and North Burial Grounds was completed. Existing records of radioactive waste location, type, and quantity within each burial ground facility were obtained and distributed to cooperating investigators. A study was then initiated to evaluate geophysical exploration techniques for mapping buried waste materials, waste containers, and trench boundaries. Results indicate that a combination of ground penetrating radar, magnetometer, metal detector, and acoustic measurements will be effective but will require further study, hardware development, and field testing. Drilling techniques for recovering radionuclide-contaminated materials and sediment cores were developed and tested. Laboratory sediment characterization and fluid transport and monitoring analyses were begun by installation of in situ transducers at the 300 North Burial Ground site. Biological transport mechanisms that control radionuclide movement at contaminated sites were also studied. Flora and fauna presently inhabiting specific burial ground areas were identified and analyzed. Future monitoring of specific mammal populations will permit determination of dose rate and pathways of contaminated materials contained in and adjacent to burial ground sites

Obtaining fuel briquets from the solid municipal waste

International Nuclear Information System (INIS)

Armenski, Slave; Kachurkov, Gjorgji; Vasilevski, Goce

1998-01-01

Recycling systems for solid waste materials are designed to reduce the amount of solid waste materials going to land fields. Through the Trash Separation Systems, clean municipal waste are reused in production of fuel pellets. Other waste streams such as coal fines, sawdust, wood chips, coke breeze and agricultural waste can be blended with these pellets along with a high thermal value binder and/or used motor oil to form a quality clean burning alternative fuel. (Author)

Experimental methodology to study radionuclide sorption and migration in geological formations and engineered barriers of waste repositories

International Nuclear Information System (INIS)

Rojo Sanz, H.

2010-01-01

In Spain, the waste management options include either the possibility of a final storage in a deep geological repository (DGR) or the centralized temporal surface disposal (CTS). DGRs are based in a multi-barrier concept with the geological barrier and including the vitrified waste, the metal containers and engineered barriers such as compacted bentonite and cement-based materials. On the other hand, CTS mainly considers concrete and cement to confine the metal canisters containing the waste. Radionuclide migration will mainly take place by the existence of chemical concentration gradients being thus diffusion the main transport mechanism or by the existence of hydraulic gradients due to the existence of water-conductive fractures. Radionuclide sorption/retention on the materials composing the natural and engineered barriers is the fundamental process controlling contaminant migration. The evaluation of sorption parameters and the understanding of the different mechanisms leading to radionuclide retention are very important issues. The study of diffusion processes is very relevant as well. This paper describes the main experimental methodologies applied to analyse radionuclide transport in the different barriers of radioactive repositories. Particularly we focused on obtaining of retention parameters as distribution coefficients, kd, or retardation factors, Rf, and diffusion coefficients of radionuclides. (Author) 6 refs.

Disposal and environmental assessment of solid waste and radioactive waste

International Nuclear Information System (INIS)

Tan Chenglong

2000-01-01

Along with the development of economic construction, the industrial and agricultural production, military and scientific activities of human being, large amounts of solid and radioactive wastes have been produced, causing serious pollution of ecologic environments and living space of human being itself. To assess and administer the solid and radioactive wastes in geologic-ecologic environments are duty-bound responsibilities of modern geologists and the focus of recent geo-ecologic work

Natural sorbents as barriers against migration of radionuclides from radioactive waste repositories

International Nuclear Information System (INIS)

Stefanova, I.; Gradev, G.D.

1993-01-01

The sorption properties of Bulgarian inorganic sorbents - clinoptilolite, vermiculite, bentonite, glauconite, celadonite and loess, which can be used as buffer, backfill and sealing materials in radwaste repository are studied. Experimental data about sorption and desorption capacities, radiation and thermal stability of sorbents from different Bulgarian deposits are reported and compared. Clinoptilolite from Beli Plast and its sodium variety from Kostino and Moryantsi is recommended as a barrier against radionuclide migration from radwaste repository due to their high sorption capacity of 137 Ce, 90 Sr and 60 Co. The high selectivity of vermiculite for polyvalent ions ( 144 Ce, 59 Fe and 90 Sr) gives grounds to include the sorption on vermiculite as a second step in the ion exchange technology for low level laundry waste decontamination. Bentonite is studied as a proposed buffer, backfill and sealing material. Its selectivity for cesium is lower compared to those of clinoptilolite. Thus a tailored-made mixture of bentonite and clinoptilolite will act as a barrier against radionuclides in different oxidation state. Glauconite can be successfully used as a barrier against migration of 144 Ce, 90 Sr, 54 Mn and 65 Zn. Loess is also included in the study, as the Kozloduy NPP is sited on loess formation and it is a natural potential site for low and intermediate level waste burial. It is concludes that zeolites and clays of Bulgarian deposits can be used effectively against radionuclide migration from radioactive waste repositories. 59 refs., 5 tabs. (author)

Solid Waste Management with Emphasis on Environmental Aspect

Science.gov (United States)

Sinha, Navin Kr.; Choudhary, Binod Kumar; Shree, Shalini

2011-12-01

In this paper focus on Solid waste management. Its comprises of purposeful and systematic control of generation, storage, collection, transport, separations, processing, recycling, recovery and disposal of solid waste. Awareness of Four R's management & EMS support also for management Solid waste. Basel convention on the Control of transboundary movements of hazardous wastes and their Disposal usually known simply as the Basel Convention, is an international treaty that was designed to reduce the movements of hazardous waste between nations, and specifically to prevent transfer of hazardous waste from developed to less developed countries (LDCs). it came into force 5 May 1992. According to this "Substances or objects which are disposed of or are intended to be disposed of or are required to be disposed of by the provisions of national law"(UNEP).

1993 baseline solid waste management system description

International Nuclear Information System (INIS)

Armacost, L.L.; Fowler, R.A.; Konynenbelt, H.S.

1994-02-01

Pacific Northwest Laboratory has prepared this report under the direction of Westinghouse Hanford Company. The report provides an integrated description of the system planned for managing Hanford's solid low-level waste, low-level mixed waste, transuranic waste, and transuranic mixed waste. The primary purpose of this document is to illustrate a collective view of the key functions planned at the Hanford Site to handle existing waste inventories, as well as solid wastes that will be generated in the future. By viewing this system as a whole rather than as individual projects, key facility interactions and requirements are identified and a better understanding of the overall system may be gained. The system is described so as to form a basis for modeling the system at various levels of detail. Model results provide insight into issues such as facility capacity requirements, alternative system operating strategies, and impacts of system changes (ie., startup dates). This description of the planned Hanford solid waste processing system: defines a baseline system configuration; identifies the entering waste streams to be managed within the system; identifies basic system functions and waste flows; and highlights system constraints. This system description will evolve and be revised as issues are resolved, planning decisions are made, additional data are collected, and assumptions are tested and changed. Out of necessity, this document will also be revised and updated so that a documented system description, which reflects current system planning, is always available for use by engineers and managers. It does not provide any results generated from the many alternatives that will be modeled in the course of analyzing solid waste disposal options; such results will be provided in separate documents

Natural and Synthetic Barriers to Immobilize Radionuclides

International Nuclear Information System (INIS)

Um, W.

2011-01-01

The experiments of weathering of glass waste form and the reacted sediments with simulated glass leachates show that radionuclide sequestration can be significantly enhanced by promoting the formation of secondary precipitates. In addition, synthetic phosphate-bearing nanoporous material exhibits high stability at temperature and has a very high K d value for U(VI) removal. Both natural and synthetic barrier materials can be used as additional efficient adsorbents for retarding transport of radionuclides for various contaminated waste streams and waste forms present at U. S. Department of Energy clean-up sites and the proposed geologic radioactive waste disposal facility. In the radioactive waste repository facility, natural or synthetic materials are planned to be used as a barrier material to immobilize and retard radionuclide release. The getter material can be used to selectively scavenge the radionuclide of interest from a liquid waste stream and subsequently incorporate the loaded getters in a cementitious or various monolithic waste forms. Also, the getter material is to reduce the release of radionuclides from monolithic waste forms. Also, the getter material is to reduce the release of radionuclides from monolithic waste forms. Also, the getter material is to reduce the release of radionuclides form monolithic waste forms by being emplaced as a backfill barrier material around the wastes or waste form to minimize the potential around the wastes or waste form to minimize the potential hazard of leached radioactive wastes. The barrier material should be highly efficient to sequester radionuclides and possess physical and chemical stability for long-term exposure to severe weathering conditions. Because potential leaching of radionuclides depends on various environmental and weathering conditions of the near-field repository, the barrier materials must be durable and not disintegrate under a range of moisture, temperature, pressure, radiation, Eh, ph. and

Microorganisms and their influence on radionuclide migration in igneous rock environments

International Nuclear Information System (INIS)

Pedersen, Karsten

2005-01-01

Microorganisms interact with their surroundings and in some cases they greatly modify the characteristics of their environment. Several such interactions may have a significant influence on the behaviour of radionuclides possibly escaping from underground radioactive waste repositories. Microbes can mobilise trace elements. Unattached microbes may act as large colloids, transporting radionuclides on their cell surfaces with the groundwater flow. Many microbes produce ligands that can mobilise trace elements from solid phases and that can inhibit trace element sorption to solid phases. Bacterial species from the deep subsurface have demonstrated a significant effect on the mobilization of 59 Fe(III), 147 Pm(III), 234 Th(IV) and 241 Am(III) under varying redox conditions. The extent of bacterial immobilisation of radionuclides has been investigated under in situ conditions. Experiments have demonstrated this effect with 60 Co, 147 Pm, 234 Th, 237 Np, and 232 U. A large group of microbes catalyse the formation of iron oxides from dissolved ferrous iron in groundwater that reaches an oxidising environment. Such biological iron oxide systems (BIOS) will have a retardation effect on many radionuclides. Microorganisms execute an important influence on the chemical situation in groundwater. Especially, they may catalyse reactions that stabilise the redox potential in groundwater at a low and, therefore, beneficial level for a radioactive waste repository. (author)

characterization and composition analysis of municipal solid waste

African Journals Online (AJOL)

userpc

ABSTRACT. Municipal Solid Waste (MSW) is produced through human activities and in the last two ... Solid waste samples were collected and analysed from the four major dumpsites in ..... Technology, Ueberlandstrasse 133,. Switzerland.

SOLID WASTE MANAGEMENT IN TABRIZ PETROCHEMICAL COMPLEX

OpenAIRE

M. A. Abduli, M. Abbasi, T. Nasrabadi, H. Hoveidi, N. Razmkhah

2006-01-01

Tabriz petrochemical complex is located in the northwest of Iran. Major products of this industry include raw plastics like, polyethylene, polystyrene, acrylonitrile, butadiene, styrene, etc. Sources of waste generation include service units, health and cure units, water, power, steam and industrial processes units. In this study, different types of solid waste including hazardous and non hazardous solid wastes were investigated separately. The aim of the study was to focus on the management ...

Households willingness to pay for improved solid waste management

Directory of Open Access Journals (Sweden)

S. Akhtar

2017-04-01

Full Text Available Waste is a byproduct of human life. Nowadays, municipal solid waste is being produced in excessive amounts and in this way, both developing and developed countries are facing challenges regarding generation of waste. Economic development, urbanization and improved living standards in cities have contributed to increase in the amount and complexity of solid waste produced. The present study was conducted in the residential area of main Boulevard Gulberg, Lahore to determine the present methods and efficiency of current solid waste management facility and to estimate the willingness of the selected households to pay for the improvement of solid waste management through questionnaire survey. It was found that current Solid waste management system in the area is fair but needs more improvement in terms of improved collection efficiency and rates, recycling bins, and segregation of waste at storage. According to the questionnaire survey, majority of the respondents despite belonging to middle class incomes are willing to pay an amount less than USD 4.8 for the improvement of waste management facility in the area. The area lacks frequent collection of waste containers. Therefore, there is a need for upgradation of storage and collection facilities in terms of increase in collection efficiency and rates, introduction of recycling facility and segregation of waste at source. Waste storage and collection sites of the area should be monitored periodically and waste should be disposed of in a scientific manner in sanitary landfills.

Effect of organic complexants on the mobility of low-level-waste radionuclides in soils

International Nuclear Information System (INIS)

Swanson, J.L.

1982-02-01

The effect of certain organic complexants on the distribution of some radionuclides between solution and soil has been measured. The complexants and radionuclides examined are some of those most likely to be present in low-level waste disposal sites; Cs, Sr, Ni, Co, and Eu radionuclides, and EDTA, DTPA, oxalate, and citrate complexants. The effect of complexants was found to vary widely; in some systems there was no effect and in other systems there were large effects. In some cases slow rates of reaction have not allowed equilibrium measurements to be made

Solid wastes management in Lebanon

International Nuclear Information System (INIS)

Daniel, Simon E.

1999-01-01

The paper describes the problem of wastes in Lebanon and their management according to international (European and French) descriptions. It presents the situation in Lebanon including the policies taken by the ministry of environment towards the treatment of different types of wastes especially solid wastes. It is estimated that the production of wastes in Lebanon is 5854 tones per day and it is distributed as follows: Domestic wastes 3200 t/d; industrial wastes 1300 t/d; commercial wastes 1000 t/d; slaughter-houses 150 t/d; waste oils 100 t/d; hospital wastes 64 t/d; vehicle wheels 40 t/d. The annual production within regions is also presented in tables. Collection, transportation, recycling, composting and incineration of wastes are included

MUNICIPAL SOLID WASTE AND RECOVERY POTENTIAL: BANGLADESH PERSPECTIVE

Directory of Open Access Journals (Sweden)

M. Alamgir, A. Ahsan

2007-04-01

Full Text Available A total of 7690 tons of municipal solid waste generated daily at the six major cities of Bangladesh, namely, Dhaka, Chittagong, Khulna, Rajshahi, Barisal and Sylhet, as estimated in 2005. Sampling was done at different waste generation sources such as residential, commercial, institutional and open areas, in different seasons. The composition of the entire waste stream was about 74.4% organic matter, 9.1% paper, 3.5% plastic, 1.9% textile and wood, 0.8% leather and rubber, 1.5% metal, 0.8% glass and 8% other waste. The per capita generation of municipal solid waste was ranged from 0.325 to 0.485 kg/cap/day while the average rate was 0.387 kg/cap/day as measured in the six major cities. The potential for waste recovery and reduction based on the waste characteristics are evaluated and it is predicted that 21.64 million US$/yr can be earned from recycling and composting of municipal solid waste.

Waterproofing improvement of radioactive waste asphalt solid

International Nuclear Information System (INIS)

Adachi, Katsuhiko; Yamaguchi, Takashi; Ikeoka, Akira.

1981-01-01

Purpose: To improve the waterproofing of asphalt solid by adding an alkaline earth metal salt and, further, paraffin, into radioactive liquid waste when processing asphalt solidification of the radioactive liquid waste. Method: Before processing molten asphalt solidification of radioactive liquid waste, soluble salts of alkaline earth metal such as calcium chloride, magnesium chloride, or the like is added to the radioactive liquid waste. Paraffin having a melting point of higher than 60 0 C, for example, is added to the asphalt, and waterproofing can be remarkably improved. The waste asphalt solid thus fabricated can prevent the swelling thereof, and can improve its waterproofing. (Yoshihara, H.)

Conditions inside Water Pooled in a Failed Nuclear Waste Container and its Effect on Radionuclide Release

Science.gov (United States)

Hamdan, L. K.; Walton, J. C.; Woocay, A.

2009-12-01

Nuclear power use is expected to expand in the future, as part of the global clean energy initiative, to meet the world’s surging energy demand, and attenuate greenhouse gas emissions, which are mainly caused by fossil fuels. As a result, it is estimated that hundreds of thousands of metric tons of spent nuclear fuel (SNF) will accumulate. SNF disposal has major environmental (radiation exposure) and security (nuclear proliferation) concerns. Storage in unsaturated zone geological repositories is a reasonable solution for dealing with SNF. One of the key factors that determine the performance of the geological repository is the release of radionuclides from the engineered barrier system. Over time, the nuclear waste containers are expected to fail gradually due to general and localized corrosions and eventually infiltrating water will have access to the nuclear waste. Once radionuclides are released, they will be transported by water, and make their way to the accessible environment. Physical and chemical disturbances in the environment over the container will lead to different corrosion rates, causing different times and locations of penetration. One possible scenario for waste packages failure is the bathtub model, where penetrations occur on the top of the waste package and water pools inside it. In this paper the bathtub-type failed waste container is considered. We shed some light on chemical and physical processes that take place in the pooled water inside a partially failed waste container (bathtub category), and the effects of these processes on radionuclide release. Our study considers two possibilities: temperature stratification of the pooled water versus mixing process. Our calculations show that temperature stratification of the pooled water is expected when the waste package is half (or less) filled with water. On the other hand, when the waste package is fully filled (or above half) there will be mixing in the upper part of water. The effect of

Integrated models for solid waste management in tourism regions: Langkawi Island, Malaysia.

Science.gov (United States)

Shamshiry, Elmira; Nadi, Behzad; Mokhtar, Mazlin Bin; Komoo, Ibrahim; Hashim, Halimaton Saadiah; Yahaya, Nadzri

2011-01-01

The population growth, changing consumption patterns, and rapid urbanization contribute significantly to the growing volumes of solid waste that are generated in urban settings. As the rate of urbanization increases, demand on the services of solid waste management increases. The rapid urban growth in Langkawi Island, Malaysia, combined with the increasing rates of solid waste production has provided evidence that the traditional solid waste management practices, particularly the methods of waste collection and disposal, are inefficient and quite nonsustainable. Accordingly, municipal managers and planners in Langkawi need to look for and adopt a model for solid waste management that emphasizes an efficient and sustainable management of solid wastes in Langkawi Island. This study presents the current practices of solid waste management in Langkawi Island, describes the composition of the solid waste generated in that area, and presents views of local residents and tourist on issues related to solid waste management like the aesthetic value of the island environment. The most important issue of this paper is that it is the first time that integrated solid waste management is investigated in the Langkawi Island.

Solid Waste Management Districts

Data.gov (United States)

Vermont Center for Geographic Information — The Solid waste management districts layer is part of a dataset that contains administrative boundaries for Vermont's Agency of Natural Resources. This dataset...

Environmental assessment of solid waste systems and technologies: EASEWASTE