Superfund Sites

Data.gov (United States)

National Oceanic and Atmospheric Administration, Department of Commerce — This layer represents active Superfund Sites published by the Environmental Protection Agency (EPA). These data were extracted from the Superfund Enterprise...

Reclamation of waste rock material at the Summitville Mine Superfund site using organic matter and topsoil treatments

Energy Technology Data Exchange (ETDEWEB)

Winter, M.E.; Redente, E.F.

1999-07-01

The Summitville Mine was a high elevation (3,500 m) open-pit gold mine located in southwestern Colorado. The mine was abandoned in 1992 leaving approximately 200 ha of disturbed area comprised partially of two large waste rock piles. Reclamation of waste rock material is challenging due to extreme climatic conditions in conjunction with a high acid-production potential and low organic matter concentration of the material. In addition, stockpiled topsoil at the site is acidic and may be biologically inactive due to long-term storage, and therefore sufficient plant growth medium may be limited. The purpose of this study was to determine the effect of organic amendments (mushroom compost vs. biosolids) and topsoil (stockpiled vs. nonstockpiled) on aboveground biomass, herbaceous cover, and trace element uptake. An on-site field study was established in 1995 to identify the most effective combination of treatments for successful reclamation of waste rock material. Incorporation of organic matter increased total aboveground production and cover, with mushroom compost being more effective than biosolids, but did not show significant trends relative to trace element uptake. The use of topsoil did not show a significant response relative to aboveground production, cover, and trace element uptake. This study shows that waste rock materials can be directly revegetated if properly neutralized, fertilized, and amended with organic matter. Additionally, stockpiled topsoil was equivalent in plant growth to non-stockpiled topsoil when neutralized with lime.

TREATABILITY STUDY REPORT OF GREEN MOUNTAIN LABORATORIES, INC.'S BIOREMEDIATION PROCESS, TREATMENT OF PCB CONTAMINATED SOILS, AT BEEDE WASTE OIL/CASH ENERGY SUPERFUND SITE, PLAISTOW, NEW HAMPSHIRE

Science.gov (United States)

In 1998, Green Mountain Laboratories, Inc. (GML) and the USEPA agreed to carry out a Superfund Innovative Technology Evaluation (SITE) project to evaluate the effectiveness of GML's Bioremediation Process for the treatment of PCB contaminated soils at the Beede Waste Oil/Cash Ene...

Estimating risk at a Superfund site contaminated with radiological and chemical wastes

International Nuclear Information System (INIS)

Temeshy, A.; Liedle, J.M.; Sims, L.M.; Efird, C.R.

1992-01-01

This paper describes the method and results for estimating carcinogenic and noncarcinogenic effects at a Superfund site that is radiologically and chemically contaminated. Risk to receptors from disposal of waste in soil and resulting contamination of groundwater, air, surface water, and sediment is quantified. Specific risk assessment components which are addressed are the exposure assessment, toxicity assessment, and the resulting risk characterization. In the exposure assessment, potential exposure pathways are identified using waste disposal inventory information for soil and modeled information for other media. Models are used to calculate future radionuclide concentrations in groundwater, soil, surface water and air. Chemical exposure concentrations are quantified using site characterization data. Models are used to determine concentrations of chemicals in surface water and in air. Toxicity parameters used to quantify the dose-response relationship associated with the carcinogenic contaminants are slope factors and with noncarcinogenic contaminants are reference doses. In the risk characterization step, results from the exposure assessment and toxicity assessment are summarized and integrated into quantitative risk estimates for carcinogens and hazard induces for noncarcinogens. Calculated risks for carcinogenic contaminants are compared with EPA's target risk range. At WAG 6, the risk from radionuclides and chemicals for an on-WAG homesteader exceeds EPA's target risk range. Hazard indices are compared to unity for noncarcinogenic contaminants. At WAG 6, the total pathway hazard index for the on-WAG homesteader exceeds unity

U.S. EPA Superfund Program's Policy for Community Involvement at Radioactively Contaminated Sites

International Nuclear Information System (INIS)

Carey, Pat; Walker, Stuart

2008-01-01

This paper describes the Superfund program's statutory requirements for community involvement. It also discusses the efforts the Superfund program has made that go beyond these statutory requirements to involve communities. The Environmental Protection Agency (EPA) implements the Superfund program under the authority of the Comprehensive Environmental Response, Compensation, and Liability Act of 1980 (CERCLA), as amended by the Superfund Amendments and Reauthorization Act of 1986 (SARA). From the beginning of the Superfund program, Congress envisioned a role for communities. This role has evolved and expanded during the implementation of the Superfund program. Initially, the CERCLA statute had community involvement requirements designed to inform surrounding communities of the work being done at a site. CERCLA's provisions required 1) development of a community relations plan for each site, 2) establishment of information repositories near each site where all publicly available materials related to the site would be accessible for public inspection, 3) opportunities for the public to comment on the proposed remedy for each site and 4) development of a responsiveness summary responding to all significant comments received on the proposed remedy. In recognition of the need for people living near Superfund sites to be well-informed and involved with decisions concerning sites in their communities, SARA expanded Superfund's community involvement activities in 1986. SARA provided the authority to award Technical Assistance Grants (TAGs) to local communities enabling them to hire independent technical advisors to assist them in understanding technical issues and data about the site. The Superfund Community Involvement Program has sought to effectively implement the statutory community involvement requirements, and to go beyond those requirements to find meaningful ways to involve citizens in the cleanup of sites in their communities. We've structured our program around

E-Alerts: Environmental pollution and control (solid waste pollution and control). E-mail newsletter

Energy Technology Data Exchange (ETDEWEB)

NONE

1999-04-01

The paper discusses pollution by solid wastes including garbage, scrap, junked automobiles, spoil, sludge, containers; Disposal methods such as composts or land application, injection wells, incineration, sanitary landfills; Mining wastes; Processing for separation and materials recovery; Solid waste utilization; Recycling; Biological and ecological effects; Superfund (Records of Decision, etc.); SITE technology; Laws, legislation, and regulations; Public administration; Economics; Land use. The discussion includes disposal of concentrated or pure liquids such as brines, oils, chemicals, and hazardous materials.

Superfund fact sheet: The remedial program. Fact sheet

International Nuclear Information System (INIS)

1992-09-01

The fact sheet describes what various actions the EPA can take to clean up hazardous wastes sites. Explanations of how the criteria for environmental and public health risk assessment are determined and the role of state and local governments in site remediation are given. The fact sheet is one in a series providing reference information about Superfund issues and is intended for readers with no formal scientific training

Hazardous waste management: Reducing the risk

International Nuclear Information System (INIS)

Goldman, B.A.; Hulme, J.A.; Johnson, C.

1986-01-01

Congress has strengthened the laws under which active hazardous waste facilities are regulated. Nevertheless, after visiting a number of active treatment, storage, and disposal facilities, the Council on Economic Priorities (CEP) found that not only do generators not know which facilities are the best, but that the EPA has not always selected the best facilities to receive wastes removed from Superfund sites. Other facilities were better managed, better located, and better at using more advanced technologies than the facilities the EPA selected. In fact, of the ten facilities CEP evaluated in detail the EPA chose the one that performed worst - CECOS International, Inc. in Williamsburg, Ohio - to receive Superfund wastes in more instances than any of the other nine facilities. Data from a house subcommittee survey indicate that almost half of the operating hazardous waste facilities the EPA chose to receive wastes removed from Superfund sites may have contaminated groundwater. Some of the chosen facilities may even be partially responsible for a share of the wastes they are being paid to clean up. Hazardous waste management strategies and technology, how to evaluate facilities, and case studies of various corporations and hazardous waste management facilities are discussed

Regulatory and management requirements for investigation-derived waste generated during environmental investigations and cleanups

International Nuclear Information System (INIS)

Clary, M.B.

1994-01-01

Environmental cleanup efforts often result in the generation of waste materials, such as soil samples, drill cuttings, decontamination water, drilling muds, personal protective equipment, and disposable sampling equipment. The management of associated with site characterization and remediation issues is a complicated issue at many CERCLA/RCRA facilities throughout the country, primarily because of the federal hazardous waste regulations. The hazardous waste regulations were intended to apply to the active generation of hazardous waste at industrial facilities and do not often make sense when applied to sites con by poor disposal practices of the past. In order to manage investigation derived waste in a more rational, logical manner, EPA issued guidance on the management of investigation-derived waste (IDW) at Superfund sites in January, 1992. The basic intent of the EPA guidance is to provide Superfund Site Managers with options for handling, managing, and disposing of IDW. The second part of this paper provides a detailed analysis of current IDW practices at various Department of Energy (DOE) facilities and Superfund sites across the nation. Some sites, particularly the DOE facilities, with more complicated on-going cleanup efforts have developed site-specific written procedures for managing IDW, often incorporating risk assessment. In come cases, these site-specific policies are going farther than the current EPA and Colorado policies in terms of conservatively managing IDW

Towards identifying the next generation of superfund and hazardous waste site contaminants

Science.gov (United States)

Ela, Wendell P.; Sedlak, David L.; Barlaz, Morton A.; Henry, Heather F.; Muir, Derek C.G.; Swackhamer, Deborah L.; Weber, Eric J.; Arnold, Robert G.; Ferguson, P. Lee; Field, Jennifer A.; Furlong, Edward T.; Giesy, John P.; Halden, Rolf U.; Henry, Tala; Hites, Ronald A.; Hornbuckle, Keri C.; Howard, Philip H.; Luthy, Richard G.; Meyer, Anita K.; Saez, A. Eduardo; vom Saal, Frederick S.; Vulpe, Chris D.; Wiesner, Mark R.

2011-01-01

Background This commentary evolved from a workshop sponsored by the National Institute of Environmental Health Sciences titled "Superfund Contaminants: The Next Generation" held in Tucson, Arizona, in August 2009. All the authors were workshop participants.

FUSRAP adapts to the amendments of Superfund

International Nuclear Information System (INIS)

Atkin, R.G.; Liedle, S.D.; Clemens, B.W.

1988-01-01

With the promulgation of the Superfund Amendments and Reauthorization Act (SARA) federal facilities were required to comply with the Comprehensive Environmental Response Compensation and Liability Act (CERCLA) in the same manner as any non-government entity. This situation presented challenges for the Department of Energy (DOE) and other federal agencies involved in remedial action work because of the requirements under SARA that overlap other laws requiring DOE compliance, e.g., the National Environmental Policy Act (NEPA). This paper outlines options developed to comply with CERCLA and NEPA as part of an active, multi-site remedial action program. The program, the Formerly Utilized Sites Remedial Action Program (FUSRAP), was developed to identify, clean up, or control sites containing residual radioactive contamination resulting from the nation's early development of nuclear power. During the Manhattan Project, uranium was extracted from domestic and foreign ores and resulted in mill concentrates, purified metals, and waste products that were transported for use or disposal at other locations. Figure 1 shows the steps for producing uranium metal during the Manhattan Project. As a result of these activities materials equipment, buildings, and land became contaminated, primarily with naturally occurring radionuclides. Currently, FUSRAP includes 29 sites; three are on the Environmental Protection Agency's (EPA's) National Priorities List (NPL) of hazardous waste sites

TECHNICAL GUIDANCE DOCUMENT: CONSTRUCTION QUALITY MANAGEMENT FOR REMEDIAL ACTION AND REMEDIAL DESIGN WASTE CONTAINMENT SYSTEMS

Science.gov (United States)

This Technical Guidance Document is intended to augment the numerous construction quality control and construction quality assurance (CQC and CQA) documents that are available far materials associated with waste containment systems developed for Superfund site remediation. In ge...

Geochemical Characterization of Mine Waste, Mine Drainage, and Stream Sediments at the Pike Hill Copper Mine Superfund Site, Orange County, Vermont

Science.gov (United States)

Piatak, Nadine M.; Seal, Robert R.; Hammarstrom, Jane M.; Kiah, Richard G.; Deacon, Jeffrey R.; Adams, Monique; Anthony, Michael W.; Briggs, Paul H.; Jackson, John C.

2006-01-01

The Pike Hill Copper Mine Superfund Site in the Vermont copper belt consists of the abandoned Smith, Eureka, and Union mines, all of which exploited Besshi-type massive sulfide deposits. The site was listed on the U.S. Environmental Protection Agency (USEPA) National Priorities List in 2004 due to aquatic ecosystem impacts. This study was intended to be a precursor to a formal remedial investigation by the USEPA, and it focused on the characterization of mine waste, mine drainage, and stream sediments. A related study investigated the effects of the mine drainage on downstream surface waters. The potential for mine waste and drainage to have an adverse impact on aquatic ecosystems, on drinking- water supplies, and to human health was assessed on the basis of mineralogy, chemical concentrations, acid generation, and potential for metals to be leached from mine waste and soils. The results were compared to those from analyses of other Vermont copper belt Superfund sites, the Elizabeth Mine and Ely Copper Mine, to evaluate if the waste material at the Pike Hill Copper Mine was sufficiently similar to that of the other mine sites that USEPA can streamline the evaluation of remediation technologies. Mine-waste samples consisted of oxidized and unoxidized sulfidic ore and waste rock, and flotation-mill tailings. These samples contained as much as 16 weight percent sulfides that included chalcopyrite, pyrite, pyrrhotite, and sphalerite. During oxidation, sulfides weather and may release potentially toxic trace elements and may produce acid. In addition, soluble efflorescent sulfate salts were identified at the mines; during rain events, the dissolution of these salts contributes acid and metals to receiving waters. Mine waste contained concentrations of cadmium, copper, and iron that exceeded USEPA Preliminary Remediation Goals. The concentrations of selenium in mine waste were higher than the average composition of eastern United States soils. Most mine waste was

U.S. EPA Superfund Program's Policy for Community Involvement at Radioactively Contaminated Sites

International Nuclear Information System (INIS)

Martin, K.; Walker, St.

2009-01-01

This paper describes the EPA Superfund program's statutory requirements for community involvement. It also discusses the efforts the Superfund program has made that go beyond these statutory requirements to involve communities, and what lessons have been learned by EPA when trying to conduct meaningful community involvement at sites. In addition, it discusses tools that EPA has designed to specifically enhance community involvement at radioactively contaminated Superfund sites. In summary, the Superfund program devotes substantial resources to involving the local community in the site cleanup decision making process. We believe community involvement provides us with highly valuable information that must be available to carefully consider remedial alternatives at a site. We also find our employees enjoy their jobs more. Rather than fighting with an angry public they can work collaboratively to solve the problems created by the hazardous waste sites. We have learned the time and resources we devote at the beginning of a project to developing relationships with the local community, and learning about their issues and concerns is time and resources well spent. We believe the evidence shows this up-front investment helps us make better cleanup decisions, and avoids last minute efforts to work with a hostile community who feels left out of the decision-making process. (authors)

Superfund tio videos: Set A. Overview of superfund, response activities and responsibilities, site discovery, notification, and evaluation. Part 1. Audio-Visual

International Nuclear Information System (INIS)

1990-01-01

The videotape is divided into three sections. Section 1 discusses the development and framework of CERCLA and the Superfund Program and outlines the implementing rules that guide Superfund site cleanups. The Superfund response actions - remedial, removal, and enforcement - are reviewed. Section 2 outlines On-Scene Coordinator's (OSC) and Remedial Project Manager's (RPM) roles and responsibilities in Superfund removal, remedial, and enforcement activities. The other players involved in Superfund response activities also are identified. Section 3 describes how EPA learns of potential Superfund sites and lists the authorities that determine the requirements for site discovery. The procedures used to prioritize the sites and to identify and select sites for remediation are discussed

Waste Material Management: Energy and materials for industry

Energy Technology Data Exchange (ETDEWEB)

1993-05-01

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

Superfund Query

Data.gov (United States)

U.S. Environmental Protection Agency — The Superfund Query allows users to retrieve data from the Comprehensive Environmental Response, Compensation, and Liability Information System (CERCLIS) database.

Key Principles of Superfund Remedy Selection

Science.gov (United States)

Guidance on the primary considerations of remedy selection which are universally applicable at Superfund sites. Key guidance here include: Rules of Thumb for Superfund Remedy Selection and Role of the Baseline Risk Assessment.

Stigma: The Psychology and Economics of Superfund (2004)

Science.gov (United States)

Study documents the long-term impacts of Superfund cleanup on property values in communities neighboring prominent Superfund sites, examining the sale prices of nearly 35,000 homes for up to a thirty-year period near six very large Superfund sites.

An evaluation of remote sensing technologies for the detection of fugitive contamination at selected Superfund hazardous waste sites in Pennsylvania

Science.gov (United States)

Slonecker, E. Terrence; Fisher, Gary B.

2014-01-01

This evaluation was conducted to assess the potential for using both traditional remote sensing, such as aerial imagery, and emerging remote sensing technology, such as hyperspectral imaging, as tools for postclosure monitoring of selected hazardous waste sites. Sixteen deleted Superfund (SF) National Priorities List (NPL) sites in Pennsylvania were imaged with a Civil Air Patrol (CAP) Airborne Real-Time Cueing Hyperspectral Enhanced Reconnaissance (ARCHER) sensor between 2009 and 2012. Deleted sites are those sites that have been remediated and removed from the NPL. The imagery was processed to radiance and atmospherically corrected to relative reflectance with standard software routines using the Environment for Visualizing Imagery (ENVI, ITT–VIS, Boulder, Colorado) software. Standard routines for anomaly detection, endmember collection, vegetation stress, and spectral analysis were applied.

1992 update of US EPA's Superfund Innovative Technology Evaluation (SITE) Emerging Technology Program

International Nuclear Information System (INIS)

Lewis, N.M.; Barkley, N.P.; Williams, T.

1992-01-01

The Superfund Innovative Technology Evaluation (SITE) Emerging Technology Program (ETP) has financially supported further development of bench- and pilot-scale testing and evaluation of innovative technologies for use at hazardous waste sites for five years. The ETP was established under the Superfund Amendments and Reauthorization Act (SARA) of 1986. The ETP complies with the goal of the SITE Program to promote, accelerate and make commercially available the development of alternative/innovative treatment technologies for use at Superfund sites. Technologies are submitted to the ETP through yearly solicitations for Preproposals. Applicants are asked to submit a detailed project proposal and a cooperative agreement application that requires Developer/EPA cost sharing. EPA co-funds selected Developers for one to two years. Second-year funding requires documentation of significant progress during the first year. Facilities, equipment, data collection, performance and development are monitored throughout the project. The US Department of Energy (DOE) and the US Air Force (USAF) are participants in the ETP. DOE has co-funded ETP projects since 1990 and the USAF since 1991. A goal of the ETP is to move developed technologies to the field-demonstration stage. A developer may be considered for participation in the SITE Demonstration Program if performance in the ETP indicates the technology is field-ready for evaluation. Six technology categories: biological, chemical, materials handling, physical, solidification/stabilization and thermal, are presently in the ETP. Technologies of primary interest to EPA are those that can treat complex mixtures of hazardous organic and inorganic contaminants and provide improved solids handling and/or pretreatment. An account of the background and progress of the ETP's first five years is presented in this paper. Technologies currently in the ETP are noted, and developers and EPA Project Managers, are listed. 4 refs., 11 figs., 6 tabs

Remediation of the Wells G & H Superfund Site, Woburn, Massachusetts.

Science.gov (United States)

Bair, E Scott; Metheny, Maura A

2002-01-01

Remediation of ground water and soil contamination at the Wells G & H Superfund Site, Woburn, Massachusetts, uses technologies that reflect differences in hydrogeologic settings, concentrations of volatile organic compounds (VOCs), and costs of treatment. The poorly permeable glacial materials that overlie fractured bedrock at the W.R. Grace property necessitate use of closely spaced recovery wells. Contaminated ground water is treated with hydrogen peroxide and ultraviolet (UV) oxidation. At UniFirst, a deep well completed in fractured bedrock removes contaminated ground water, which is treated by hydrogen peroxide, UV oxidation, and granular activated carbon (GAC). The remediation system at Wildwood integrates air sparging, soil-vapor extraction, and ground water pumping. Air stripping and GAC are used to treat contaminated water; GAC is used to treat contaminated air. New England Plastics (NEP) uses air sparging and soil-vapor extraction to remove VOCs from the unsaturated zone and shallow ground water. Contaminated air and water are treated using separate GAC systems. After nine years of operation at W.R. Grace and UniFirst, 30 and 786 kg, respectively, of VOCs have been removed. In three years of operation, 866 kg of VOCs have been removed at Wildwood. In 15 months of operation, 36 kg of VOCs were removed at NEP. Characterization work continues at the Olympia Nominee Trust, Whitney Barrel, Murphy Waste Oil, and Aberjona Auto Parts properties. Risk assessments are being finalized that address heavy metals in the floodplain sediments along the Aberjona River that are mobilized from the Industri-Plex Superfund Site located a few miles upstream.

Fifteen years of Superfund at South Valley: Reengineering required

International Nuclear Information System (INIS)

Cormier, J.; Horak, F.

1995-01-01

It is no surprise to many of Superfund's practitioners that the law and its application are flawed. The South Valley Superfund Site in Albuquerque, New Mexico has not escaped Superfund's problems. The problems and issues arising out of the South Valley Superfund site have spurred the desire to seek a better way to administer and manage cleanup. This new method applies organizational and role changes that bring Superfund closer to an efficient business-like entity. This ''Reengineered'' Superfund strives for reorganization, contractor reduction, improved communication, reporting reduction, and teaming. In addition, modifications are made to the roles of regulators, potentially responsible parties (PRPs), and the public. Today the site encompasses roughly one square mile in area, includes six identified contaminant sources, and deals with solvent and petroleum by-product contamination

In-situ stabilization of the Geiger (C and M Oil) Superfund Site

International Nuclear Information System (INIS)

Andromalos, K.B.; Ameel, M.E.

1994-01-01

The Geiger (C and M Oil) Superfund Site is the first US Army Corps of Engineers managed soil remediation project which utilized the in-situ stabilization/solidification technique to remediate the soil. This project involved the remediation of approximately 23,000 cubic yards of contaminated soil. Contaminants of concern included chromium, lead, PCB'S, toluene, benzene, and other organic compounds. Clean-up criteria for the stabilized material was equal to the National Primary Drinking Water Regulations, when tested using the TCLP leachate extraction method. Chromium, lead, and toluene were the main contaminants of concern, with TCLP clean-up goals of 150, 15 and 1,000 parts per billion (ppb), respectively. This National Priorities List (NPL) site is located near Charleston, SC and was an abandoned old waste oil facility that utilized unlined shallow trenches for the storage of waste oil. This paper summarizes the initial testing programs and the final production work at the site. Extensive testing was performed throughout all phases of the project. This testing was performed for the purpose of mix optimization, quality assurance, and verification testing. Specific parameters tested included: TCLP testing of organics, metals and PCBs, permeability testing, and unconfirmed compression strength

Radioactive waste material melter apparatus

Science.gov (United States)

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

1990-04-24

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

Radioactive waste material melter apparatus

International Nuclear Information System (INIS)

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

1990-01-01

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

Defense radioactive waste management

International Nuclear Information System (INIS)

Hindman, T.B. Jr.

1988-01-01

The Office of Defense Programs (DP), U.S. Department of Energy, is responsible for the production of nuclear weapons and materials for national defense. Pursuant to this mission, DP operates a large industrial complex that employs over 60,000 people at various installations across the country. As a byproduct of their activities, these installations generate radioactive, hazardous, or mixed wastes that must be managed in a safe and cost-effective manner in compliance with all applicable Federal and STate environmental requirements. At the Federal level such requirements derive primarily from the Atomic Energy Act, the Resource Conservation and Recovery Act (RCRA), the comprehensive Environmental Response, Compensation, and Liability Act (CERCLA) and the Superfund Amendments and Reauthorization Act (SARA). Responsibility for DP activities in connection with the disposal of defense wastes is consolidated within the Office of Defense Waste and Transportation Management (DWTM). This paper discusses these activities which consist of five principal elements: the environmental restoration of inactive DP facilities and sites, the processing storage and disposal of wastes associated with ongoing operations at active DP facilities, research and development directed toward the long-term disposal of radioactive, hazardous, mixed wastes, technology development directly supporting regulatory compliance, and the development of policies, procedures, and technologies for assuring the safe transportation of radioactive and hazardous materials

Superfund Site Information

Data.gov (United States)

U.S. Environmental Protection Agency — This asset includes a number of individual data sets related to site-specific information for Superfund, which is governed under the Comprehensive Environmental...

Delineation of areas having elevated electrical conductivity, orientation and characterization of bedrock fractures, and occurrence of groundwater discharge to surface water at the U.S. Environmental Protection Agency Barite Hill/Nevada Goldfields Superfund site near McCormick, South Carolina

Science.gov (United States)

Chapman, Melinda J.; Huffman, Brad A.; McSwain, Kristen Bukowski

2015-07-16

During October 2012 through March 2013, the U.S. Geological Survey (USGS), in cooperation with the U.S. Environmental Protection Agency (EPA) Region 4, Superfund Section, conducted borehole geophysical logging, surface geophysical surveys, and water-quality profiling in selected wells and areas to characterize or delineate the extent of elevated subsurface electrical conductivity at the EPA Barite Hill/Nevada Goldfields Superfund site near McCormick, South Carolina. Elevated electrical conductivity measured at the site may be related to native rock materials, waste rock disposal areas used in past operations, and (or) groundwater having elevated dissolved solids (primarily metals and major ions) related to waste migration. Five shallow screened wells and four open-borehole bedrock wells were logged by using a suite of borehole tools, and downhole water-quality profiles were recorded in two additional wells. Well depths ranged from about 26 to 300 feet below land surface. Surface geophysical surveys based on frequency-domain electromagnetic and distributed temperature sensing (DTS) techniques were used to identify areas of elevated electrical conductivity (Earth materials and groundwater) and potential high dissolved solids in groundwater and surface water on land and in areas along the northern unnamed tributary at the site.

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

Science.gov (United States)

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

Chromosomal aberrations in Sigmodon hispidus from a Superfund site

International Nuclear Information System (INIS)

Bowers, B.; McBee, K.; Lochmiller, R.; Burks, S.; Qualls, C.

1995-01-01

Cotton rats (Sigmodon hispidus) were collected from an EPA Superfund site located on an abandoned oil refinery. Three trapping grids were located on the refinery and three similar grids were located at uncontaminated localities which served as reference sites. Bone marrow metaphase chromosome preparations were examined for chromosomal damage. For each individual, 50 cells were scored for six classes of chromosomal lesions. For the fall 1991 trapping period, mean number of aberrant cells per individual was 2.33, 0.85, and 1.50 for the three Superfund grids., Mean number of aberrant cells per individual was 2.55, 2.55, and 2.12 from the reference grids. Mean number of lesions per cell was 2.77, 0.86, and 1.9 from the Superfund grids, and 3.55, 2.77, and 2.50 from the reference grids. For the spring 1992 trapping period, more damage was observed in animals from both Superfund and reference sites; however, animals from Superfund grids had more damage than animals from reference grids. Mean number of aberrant cells per individual was 3.50, 3.25, and 3.70 from the Superfund grids, and 2.40, 2.11, and 1.40 from the reference grids. Mean number of lesions per cell was 4.80, 4.25, and 5.50 from the Superfund grids, and 2.60, 2.33, and 1.50 from the reference grids. These data suggest animals may be more susceptible to chromosomal damage during winter months, and animals from the Superfund grids appear to be more severely affected than animals from reference grids

ZeroWaste BYG: Redesigning construction materials towards zero waste society

DEFF Research Database (Denmark)

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

2014-01-01

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

Recovery of fissile materials from nuclear wastes

Science.gov (United States)

Forsberg, Charles W.

1999-01-01

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

Waste package materials selection process

International Nuclear Information System (INIS)

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

1994-01-01

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

Managing liabilities which arise out of radioactive waste

International Nuclear Information System (INIS)

Hall, R.M. Jr.

1986-01-01

The Atomic Energy Act has established a comprehensive regulatory program which governs the management of most radioactive wastes. There are substantial civil and criminal penalties for violations. In addition, environmental statutes such as the Resource Conservation and Recovery Act and the Superfund law impose liabilities on managers of ''non-nuclear'' hazardous wastes. The availability of common law remedies by private parties subjects companies and their officers and employees, and in some cases the government, to liability for personal injuries or property damage. An environmental manager at any facility where radioactive materials are being handled must be aware of these potential liabilities and should engage in a regular program of environmental auditing to ensure compliance

TRADE instructional materials for SARA/OSHA training. Volume 2, Managers and supervisors training

Energy Technology Data Exchange (ETDEWEB)

1989-03-01

This document provides instructional materials for an eight-hour training course for managers and supervisors of hazardous waste sites. It is one of three volumes of course materials TRADE is preparing to help DOE contractor training staff comply with 29 CFR 1910.120, the Occupational Health and Safety Administration (OSHA) rule that implements Title I of the Superfund Amendments and Reauthorization Act (SARA) of 1986. OSHA`s final rule for hazardous waste operators was published in the Federal Register of March 6, 1989 (54 FR 9294). Combined with the materials in Volumes I and III and with appropriate site-specific information, these materials will help DOE contractors to meet the requirements of 1910.120 (e) that ``on-site management and supervisors directly responsible for, or who supervise employees engaged in, hazardous waste operations`` receive the same initial training as that of the employees they supervise and at least eight additional hours of specialized training in managing hazardous waste operations.

Alternating current electrocoagulation for Superfund site remediation

International Nuclear Information System (INIS)

Farrell, C.W.

1991-01-01

A study is being conducted by Electro-Pure Systems, Inc. (EPS) under the Emerging Technology portion of the U.S. Environmental Protection Agency's (EPA's) Superfund Innovative Technology Evaluation (SITE) Program to study alternating current electrocoagulation for Superfund site remediation. Alternating current electrocoagulation has proven to be effective in agglomerating and removing colloidal solids, metals and certain organic contaminants from surrogate soils prepared from the US EPA's Synthetic Soil Matrix. Treatments under a wide range of operating conditions have enabled the optimum parameter settings to be established for multiple phase separation. Electrocoagulation enables appreciably enhanced filtration and dewatering rates to be realized for metals- and diesel fuel-spiked surrogate soil slurries; such enhancements are prompted by growth in the mean particle size of the clays and particulates from typically < 10 microns to as much as 150 microns depending on the degree of electrocoagulation. Reduction in the total suspended solids content of clays in all slurries in excess of 90% can routinely be achieved. Bench-scale experiments of the metals-spiked surrogate soils indicate that electrocoagulation preferentially concentrates soluble metals into the sludge phase; excellent metals separation (Pb, Cr, Cu, Cd) can be realized. Experiments on surrogate wastes spiked with volatile organics suggest that this technology is not capable of effecting good volatile extractions from the aqueous phase. Reductions in excess of 80% in the total organic carbon (TOC) content of the diesel fuel-spiked surrogates can, however, be achieved

Estimating remediation costs for the Montclair radium superfund sites

International Nuclear Information System (INIS)

Turner, M.J.

1995-01-01

The Montclair/West Orange and Glen Ridge Superfund Sites, located in Essex County, NJ, are contaminated to varying degrees with radioactive materials. The waste originated from radium processing facilities prevalent in the area during the early 1900s. The design for remediation of these sites is managed by Bechtel National, Inc. on behalf of the United States Army Corps of Engineers, Kansas City District, which administers the project through an interagency agreement with the US Environmental Protection Agency (EPA). Design efforts for the project began in 1990. A portion of the scope, which is the topic of this article, was preparing the remediation costs estimates. These estimates were to be prepared from the detailed design packages; the Corps of Engineers required that the estimates were prepared using the Micro Computer-Aided Cost Estimating System (MCACES). This article discusses the design methods used, provides an overview of MCACES, and discusses the structure and preparation of the cost estimate and its uses. However, the main focus of the article is the methods used to generate the required project-specific cost estimate format for this project. 6 figs

CONSTRUCTION MATERIALS FROM WASTE PRODUCTS

Directory of Open Access Journals (Sweden)

Тахира Далиевна Сидикова

2016-02-01

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

Superfund at work: Hazardous waste cleanup efforts nationwide, fall 1992. (CIBA-GEIGY Corporation, McIntosh, Alabama)

International Nuclear Information System (INIS)

1992-01-01

On March 31, 1992, the U.S. Environmental Protection Agency (EPA) reached an agreement with Ciba-Geigy Corporation in McIntosh, Alabama to clean up soil and ground water contaminated by DDT, herbicides, and chemicals. The agreement is one of the largest private party settlements in Superfund history, valued at approximately $120 million. EPA activities at the site included: conducting preliminary contamination investigations jointly with the Alabama Environmental Health Administration, beginning in 1979; designing a multi-phased cleanup that is responsive to the complex nature of the contamination and reduces potential risk to the local population and environment; and awarding a grant to a community group to help them participate in cleanup decisions. Ciba-Geigy, like EPA, has made consistent efforts to build and maintain good relations with the community. These efforts demonstrate the increasing trend toward cooperation between industries, local communities, and EPA at Superfund sites

Sustainable Materials Management (SMM) WasteWise Data

Science.gov (United States)

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

Radiation Effects in Nuclear Waste Materials

International Nuclear Information System (INIS)

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

2003-01-01

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

Radiation Effects in Nuclear Waste Materials

International Nuclear Information System (INIS)

Weber, William J.

2005-01-01

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

Superfund Technical Assistance Grants

Data.gov (United States)

U.S. Environmental Protection Agency — This asset includes data related to the Superfund Technical Assistance Grant program, including grant number, award amounts, award dates, period of performance,...

TECHNOLOGY EVALUATION REPORT, SITE PROGRAM DEMONSTRATION TEST: SHIRCO PILOT-SCALE INFRARED INCINERATION SYSTEM ROSE TOWNSHIP DEMODE ROAD SUPERFUND SITE - VOLUME II

Science.gov (United States)

The performance of the Shirco pilot-scale infrared thermal destruction system has been evaluated at the Rose Township, Demode Road Superfund Site and is presented in the report. The waste tested consisted of solvents, organics and heavy metals in an illegal dump site. Volume I gi...

Special Report: Hazardous Wastes in Academic Labs.

Science.gov (United States)

Sanders, Howard J.

1986-01-01

Topics and issues related to toxic wastes in academic laboratories are addressed, pointing out that colleges/universities are making efforts to dispose of hazardous wastes safely to comply with tougher federal regulations. University sites on the Environmental Protection Agency Superfund National Priorities List, costs, and use of lab packs are…

Challenge of superfund community relations

International Nuclear Information System (INIS)

Goldman, N.J.

1991-01-01

Conducting a community relations effort in a community which is home to a Superfund site is a formidable challenge. Any education press, however appropriate, quickly falls victim to doubt, mistrust of fears of the very public intended to be served by the effort. While each site is uniquely different, the issues raised by affected communities in one part of the country are strikingly similar to those raised in other parts. Those most involved must join those most affected in seeking meaningful solutions and in building the trust that is so vital in moving forward with Superfund

Absorption properties of waste matrix materials

Energy Technology Data Exchange (ETDEWEB)

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

1997-06-01

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

Aquatic assessment of the Ely Copper Mine Superfund site, Vershire, Vermont

Science.gov (United States)

Seal, Robert R.; Kiah, Richard G.; Piatak, Nadine M.; Besser, John M.; Coles, James F.; Hammarstrom, Jane M.; Argue, Denise M.; Levitan, Denise M.; Deacon, Jeffrey R.; Ingersoll, Christopher G.

2010-01-01

The Ely Mine, which operated from 1821 to 1905, and its area of downstream impact constitute the Ely Copper Mine Superfund site. The site was placed on the National Priorities List in 2001. The mine comprises underground workings, foundations from historical structures, several waste-rock piles, roast beds associated with the smelting operation, and slag piles resulting from the smelting. The mine site is drained by Ely Brook, which includes several tributaries, one of which drains a series of six ponds. Ely Brook empties into Schoolhouse Brook, which flows 3.3 kilometers and joins the Ompompanoosuc River.

Waste management, energy generation, material recycling

Energy Technology Data Exchange (ETDEWEB)

1982-01-01

The concept of process pyrolysis according to the system of low-temperature pyrolysis (up to 450 Cel) for the purpose of waste processing is described. This system not only uses the material value (raw materials) but also the processing value (energetic utilization of organic components). Three product groups are mentioned where process pyrolysis can be applied: 1. rubber-metall connecting, coated and non-coated components, 2. Compound materials like pc boards, used electronic devices, films, used cables and batteries, 3. organic waste and residues like foils, insulating material, lubricating, oil and grease, flooring. Importance of waste management is emphasized, economic aspects are illustrated.

USA - Paper provided by the US delegation to the RWMC. Site Decontamination and Clean-up Under the U.S. EPA 'Superfund'

International Nuclear Information System (INIS)

2003-01-01

capability, permanence, and cost may be considered to select between or modify alternatives. The ultimate disposal destination and disposal method for decontamination waste may be specified as part of the clean-up agreement. Release from Liability: Once clean-up goals have been met, a site may undergo 'close-out' and be removed from the National Priorities List. Due to the nature of liability under the Superfund law, however, a potentially responsible party remains potentially liable indefinitely. New information revealing additional hazards can provide grounds for re-opening a site. Current Issues: Some nuclear facilities have the potential to be regulated by both the Nuclear Regulatory Commission (NRC) and the EPA upon decommissioning. To avoid uncertainty and duplication of effort in these situations, EPA and NRC signed a Memorandum of Understanding in 2002. The agreement clarifies how EPA and NRC will cooperate regarding sites that operate and are decommissioned under an NRC license. In accordance with the Nuclear Waste Policy Act of 1982 (NWPA), the costs for disposal of commercial spent nuclear fuel (SNF) in a potential repository are to be funded by $0.001 per kWh fee levied on electricity generated and sold. For SNF generated prior to enactment of the NWPA, utilities were required to pay a one-time fee equivalent to an average charge of $0.001 per kWh. These fees are deposited in a Nuclear Waste Fund (NWF) held by the U.S treasury and managed by DOE The NWF is to be used for development and implementation of a radioactive waste management system in accordance with the NWPA, including a potential geologic repository. DOE is required to pay its fair share of cost for disposal of defence-related materials. DOE is currently in the process of developing a license application to be submitted to the NRC in December 2004 for the construction of a geologic repository at the Yucca Mountain site (Nevada). It is planned that, after waste emplacement and performance confirmation

Low-level waste forum meeting reports

International Nuclear Information System (INIS)

1992-01-01

This paper provides highlights from the spring meeting of the Low Level Radioactive Waste Forum. Topics of discussion included: state and compact reports; New York's challenge to the constitutionality of the Low-Level Radioactive Waste Amendments Act of 1985; DOE technical assistance for 1993; interregional import/export agreements; Department of Transportation requirements; superfund liability; nonfuel bearing components; NRC residual radioactivity criteria

Hazardous-materials waste disposal: Land, January 1988-July 1991 (Citations from the NTIS Data Base). Rept. for Jan 88-Jul 91

International Nuclear Information System (INIS)

1991-06-01

The bibliography contains citations concerning the disposal of hazardous industrial and municipal wastes, chemical agents, and a variety of other dangerous substances into and from the land. Topics include restoration operations, contamination abatement studies, appropriate regulation and legislation, and remedial response strategies. Considerable attention is given to waste disposal sites at military installations and to incineration operations. Citations pertaining specifically to radioactive waste disposal, state by state toxic release inventories, Best Demonstrated Available Technology as defined by Environmental Protection Agency, Health Assessments for individual companies sponsored by the Toxic Substances and Disease Registry, Atlanta, GA., and the Superfund Record of Decisions are excluded. (The bibliography contains 153 citations with a subject index.)

Hazardous materials waste disposal: Water, January 1988-July 1991 (Citations from the NTIS Data Base). Rept. for Jan 88-Jul 91

International Nuclear Information System (INIS)

1991-06-01

The bibliography contains citations concerning the disposal of hazardous industrial and municipal wastes, chemical agents, and a variety of other dangerous substances into and from the water. Topics include restoration operations, contamination abatement studies, appropriate regulation and legislation, and remedial response strategies. Considerable attention is given to waste disposal sites at military installations and to incineration operations. Citations pertaining specifically to radioactive waste disposal, state by state toxic release inventories, Best Demonstrated Available Technology as defined by Environmental Protection Agency, Health Assessments for individual companies sponsored by the Toxic Substances and Disease Registry, Atlanta, GA., and the Superfund Record of Decisions are excluded. (The bibliography contains 153 citations with a subject index.)

Environmental restoration waste materials co-disposal

International Nuclear Information System (INIS)

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

1993-09-01

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

Risk management at hazardous waste sites

International Nuclear Information System (INIS)

Travis, C.C.; Doty, C.B.

1990-01-01

The Superfund Amendments and Reauthorization Act of 1986 (SARA) provided the Environmental Protection Agency (EPA) with additional resources and direction for the identification, evaluation, and remediation of hazardous waste sites in the United States. SARA established more stringent requirements for the Superfund program, both in terms of the pace of the program and the types of remedial alternatives selected. The central requirement is that remedial alternatives be ''protective of public health and the environment'' and ''significantly and permanently'' reduce the toxicity, mobility, or volume of contaminants. The mandate also requires that potential risk be considered in the decision-making process. This document discusses risk management at hazardous waste sites. Topics include selection of sites for placement on the National Priority List, risk assessment and the decision process, risk reduction and remedial alternative selection, and aquifer restoration. 10 refs., 2 figs

SITE COMPREHENSIVE LISTING (CERCLIS) (Superfund)

Data.gov (United States)

U.S. Environmental Protection Agency — The Comprehensive Environmental Response, Compensation and Liability Information System (CERCLIS) (Superfund) Public Access Database contains a selected set of...

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

International Nuclear Information System (INIS)

1988-01-01

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

Region 9 NPL Sites (Superfund Sites 2013)

Science.gov (United States)

NPL site POINT locations for the US EPA Region 9. NPL (National Priorities List) sites are hazardous waste sites that are eligible for extensive long-term cleanup under the Superfund program. Eligibility is determined by a scoring method called Hazard Ranking System. Sites with high scores are listed on the NPL. The majority of the locations are derived from polygon centroids of digitized site boundaries. The remaining locations were generated from address geocoding and digitizing. Area covered by this data set include Arizona, California, Nevada, Hawaii, Guam, American Samoa, Northern Marianas and Trust Territories. Attributes include NPL status codes, NPL industry type codes and environmental indicators. Related table, NPL_Contaminants contains information about contaminated media types and chemicals. This is a one-to-many relate and can be related to the feature class using the relationship classes under the Feature Data Set ENVIRO_CONTAMINANT.

Radiochemical Analyses of the Filter Cake, Granular Activated Carbon, and Treated Ground Water from the DTSC Stringfellow Superfund Site Pretreatment Plant

International Nuclear Information System (INIS)

Esser, B K; McConachie, W; Fischer, R; Sutton, M; Szechenyi, S

2005-01-01

The Department of Toxic Substance Control (DTSC) requested that Lawrence Livermore National Laboratory (LLNL) evaluate the treatment process currently employed at the Department's Stringfellow Superfund Site Pretreatment Plant (PTP) site to determine if wastes originating from the site were properly managed with regards to their radioactivity. In order to evaluate the current management strategy, LLNL suggested that DTSC characterize the effluents from the waste treatment system for radionuclide content. A sampling plan was developed; samples were collected and analyzed for radioactive constituents. Following is brief summary of those results and what implications for waste characterization may be made. (1) The sampling and analysis provides strong evidence that the radionuclides present are Naturally Occurring Radioactive Material (NORM). (2) The greatest source of radioactivity in the samples was naturally occurring uranium. The sample results indicate that the uranium concentration in the filter cake is higher than the Granular Activated Carbon (GAC) samples. (11 -14 and 2-6 ppm respectively). (3) No radiologic background for geologic materials has been established for the Stringfellow site, and comprehensive testing of the process stream has not been conducted. Without site-specific testing of geologic materials and waste process streams, it is not possible to conclude if filter cake and spent GAC samples contain radioactivity concentrated above natural background levels, or if radionuclides are being concentrated by the waste treatment process. Recommendation: The regulation of Technologically Enhanced, Naturally Occurring Radioactive Materials (T-NORM) is complex. Since the results of this study do not conclusively demonstrate that natural radioactive materials have not been concentrated by the treatment process it is recommended that the DTSC consult with the Department of Health Services (DHS) Radiological Health Branch to determine if any further action is

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

International Nuclear Information System (INIS)

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

1991-07-01

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

Test plan for buried waste containment system materials

International Nuclear Information System (INIS)

Weidner, J.; Shaw, P.

1997-03-01

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

Cement-Based Materials for Nuclear Waste Storage

CERN Document Server

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

2013-01-01

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

Aqueous Corrosion Rates for Waste Package Materials

Energy Technology Data Exchange (ETDEWEB)

S. Arthur

2004-10-08

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

Aqueous Corrosion Rates for Waste Package Materials

International Nuclear Information System (INIS)

Arthur, S.

2004-01-01

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

RADIATION EFFECTS IN NUCLEAR WASTE MATERIALS

International Nuclear Information System (INIS)

Weber, William J.

2000-01-01

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

75 FR 49414 - Cooperative Agreements and Superfund State Contracts for Superfund Response Actions

Science.gov (United States)

2010-08-13

...-0276. FOR FURTHER INFORMATION CONTACT: Angelo Carasea, Assessment and Remediation Division, Office of Superfund Remediation and Technology Innovation, (5204P), Environmental Protection Agency, 1200 Pennsylvania... funds to a State, political subdivision, or Indian Tribe that assumes responsibility as the lead or...

Superfund TIO videos: Set B. Financial management and SCAP. Part 8. Audio-Visual

International Nuclear Information System (INIS)

1990-01-01

The videotape covers various aspects of financial management for the Superfund Program. The importance of effective financial management and execution is discussed. The objectives and definitions of the Superfund Comprehensive Accomplishment Plan (SCAP) and the roles and responsibilities of Superfund personnel in the SCAP process are covered

Feasibility study for the United Heckathorn Superfund Site, Richmond, California

Energy Technology Data Exchange (ETDEWEB)

Lincoff, A.H. [US Environmental Protection Agency, San Francisco, CA (United States). Region IX; Costan, G.P.; Montgomery, M.S.; White, P.J. [Pacific Northwest Lab., Richland, WA (United States)

1994-07-01

The United Heckathom Superfund Site in Richmond, California, was used to formulate pesticides from approximately 1947 to 1966. Soils at the site and sediments in the harbor were contaminated with various chlorinated pesticides, primarily DDT, as a result of these activities. The US Environmental Protection Agency listed the site on the Superfund National Priorities List in 1990. This document is part of the Remedial Investigation and Feasibility Study phase of the Superfund response, which will provide the basis for selection of a final remedy that will protect human health and the environment and achieve compliance with federal and state envirorunental laws.

Feasibility study for the United Heckathorn Superfund Site, Richmond, California

International Nuclear Information System (INIS)

Lincoff, A.H.

1994-07-01

The United Heckathom Superfund Site in Richmond, California, was used to formulate pesticides from approximately 1947 to 1966. Soils at the site and sediments in the harbor were contaminated with various chlorinated pesticides, primarily DDT, as a result of these activities. The US Environmental Protection Agency listed the site on the Superfund National Priorities List in 1990. This document is part of the Remedial Investigation and Feasibility Study phase of the Superfund response, which will provide the basis for selection of a final remedy that will protect human health and the environment and achieve compliance with federal and state envirorunental laws

Materials aspects of nuclear waste isolation

International Nuclear Information System (INIS)

Bennett, J.W.

1984-01-01

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

SUPERFUND TREATABILITY CLEARINGHOUSE: BDAT FOR SOLIDIFICATION/STABILIZATION TECHNOLOGY FOR SUPERFUND SOILS (DRAFT FINAL REPORT)

Science.gov (United States)

This report evaluates the performance of solidification as a method for treating solids from Superfund sites. Tests were conducted on four different artificially contaminated soils which are representative of soils found at the sites. Contaminated soils were solidified us...

Gas from waste materials

Energy Technology Data Exchange (ETDEWEB)

Leroux, H

1943-01-01

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

Nuclear-waste-package materials degradation modes and accelerated testing

International Nuclear Information System (INIS)

1981-09-01

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

Disposal of radioactive waste material to sea

International Nuclear Information System (INIS)

Burton, W.R.

1985-01-01

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

Superfund Site Information - Site Sampling Data

Data.gov (United States)

U.S. Environmental Protection Agency — This asset includes Superfund site-specific sampling information including location of samples, types of samples, and analytical chemistry characteristics of...

Material selection for Multi-Function Waste Tank Facility tanks

International Nuclear Information System (INIS)

Carlos, W.C.

1994-01-01

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

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

International Nuclear Information System (INIS)

Rubin, L.S.

1986-01-01

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

78 FR 14543 - Ward Transformer Superfund Site; Raleigh, Wake County, NC; Notice of Settlement

Science.gov (United States)

2013-03-06

... ENVIRONMENTAL PROTECTION AGENCY [FRL 9788-2; CERCLA-04-2013-3754] Ward Transformer Superfund Site... Ward Transformer Superfund Site located in Raleigh, Wake County, North Carolina. Under the terms of the.... Submit your comments by Site name Ward Transformer Superfund Site by one of the following methods: [[Page...

EVALUATION OF CAUSES OF CONSTRUCTION MATERIAL WASTE

African Journals Online (AJOL)

Osondu

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

Use of risk to resolve conflicts in assessing hazards at mixed-waste sites

International Nuclear Information System (INIS)

Rechard, R.P.; Chu, M.S.Y.

1991-01-01

Two main issues contribute to the assessment of health hazard from mixed waste: the scientific methods to assess these materials and the legislative and regulatory control of these materials. This paper is primarily concerned with the scientific method of assessing hazards from mixed waste (i.e., carcinogenic chemicals, noncarcinogenic chemicals, and radioactive material). This paper discusses SRS, a Site Ranking System, and its use of risk concepts to avoid introducing new inconsistencies when ranking mixed-waste sites. SRS ranks each site by scoring factors that influence the human health risk. The factors are (1) the potentially exposed population, (2) the average amount of exposure to the waste, and (3) the toxicity of the waste. The relative risk of a release is measured as the product of these three factors. The third factor, toxicity, is indexed with a single score, but because methods of measuring toxicity differ for carcinogenic chemicals, noncarcinogenic chemicals, and radionuclides, comparison can be difficult; hence, this paper also summarizes the logic and assumptions used to make toxicity comparisons in SRS. As may be expected, results from a ranking scheme based on risk are different from results generated by the original Hazard Ranking System (HRS), used by the Environmental Protection Agency. This paper briefly discusses these differences for five Superfund sites (no mixed waste). The legislative and regulatory control of these materials to protect human health is also discussed. 37 refs., 1 tab

Glass-crystalline materials for active waste incorporation

International Nuclear Information System (INIS)

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

1979-01-01

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

A COMPARISON: ORGANIC EMISSIONS FROM HAZARDOUS WASTE INCINERATORS VERSUS THE 1990 TOXICS RELEASE INVENTORY AIR RELEASES.

Science.gov (United States)

Incineration is often the preferred technology for disposing of hazardous waste, and remediating Superfund sites. The effective implementation of this technology is frequently impeded by strong public opposition `to hazardous waste' incineration HWI). One of the reasons cited for...

Use of selected waste materials in concrete mixes

International Nuclear Information System (INIS)

Batayneh, Malek; Marie, Iqbal; Asi, Ibrahim

2007-01-01

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

Use of selected waste materials in concrete mixes.

Science.gov (United States)

Batayneh, Malek; Marie, Iqbal; Asi, Ibrahim

2007-01-01

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

Recommendations concerning Tennessee's hazardous waste management policies by a task force representing generators, environmentalists, and other key constituencies

International Nuclear Information System (INIS)

Colglazier, E.W.; English, M.R.

1987-01-01

Four recommendations are proposed. 1) A Governor's Roundtable on Hazardous and Solid Wastes should be established to ensure that Tennessee have sound policies and plans for waste management, adequate waste treatment and disposal capacity, and the means to meet the October, 1989 deadline for certification of hazardous waste capacity. 2) Opportunities for early public information and participation in Tennessee's RCRA permitting process should be improved. 3) A Superfund Public Involvement Task Force should be appointed by the Commissioner of Health and Environment to find ways to ensure that a community affected by a Tennessee Superfund site has early and adequate opportunities for information and involvement. 4) Communications about hazardous waste issues should be improved by the appointment of a hazardous waste information officer, the establishment of a Speakers Bureau, the funding of the UT Center for Industrial Services' Hazardous Waste Extension Program, establishment of a crisis situation network of consultants for communities, and exploration of the possibility of Amnesty Days for household hazardous waste and for small-quantity generators waste

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

International Nuclear Information System (INIS)

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

2014-01-01

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

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

African Journals Online (AJOL)

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

Radiation damage in nuclear waste materials

International Nuclear Information System (INIS)

Jencic, I.

2000-01-01

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

Nuclear Materials: Reconsidering Wastes and Assets - 13193

International Nuclear Information System (INIS)

Michalske, T.A.

2013-01-01

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

Bacterial leaching of waste uranium materials.

Science.gov (United States)

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

1976-01-01

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

Bacterial leaching of waste uranium materials

International Nuclear Information System (INIS)

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

1976-01-01

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

78 FR 23563 - LWD, Inc. Superfund Site; Calvert City, Marshall County, Kentucky; Notice of Settlement

Science.gov (United States)

2013-04-19

... ENVIRONMENTAL PROTECTION AGENCY [FRL-9805-2; CERCLA-04-2013-3751] LWD, Inc. Superfund Site... costs concerning the LWD, Inc., Superfund Site located in Calvert City, Marshall County, Kentucky. The... V. Painter. Submit your comments by Site name LWD, Inc., Superfund Site by one of the following...

In situ vitrification of mixed wastes: Progress and regulatory status

International Nuclear Information System (INIS)

Kindle, C.H.; Barich, J.J. III

1991-08-01

In situ vitrification (ISV) technology targets mixed wastes in in situ near-surface environments. Federal laws governing toxic substances (TSCA), hazardous waste (RCRA), and abandoned sites (Superfund) create the need for remediation technology and define the required performance characteristics. The need for ISV depends, in part, on the extent of regulation and how well ISV's demonstrated performance characteristics match up with regulatory criteria. The regulatory requirements are easier to identify and meet in short-duration site- and situation-specific applications of the technology than they are simpler in long-term, generalized applications. ISV's ability to treat both inorganics and organics in a single process supports applications for mixed, hazardous, and radioactive sites of moderate depth (20 ft). The durability of the ISV waste form is a major advantage of the technology when demonstrating permanence of a waste management strategy. Achieving depth and vapor containment assurance are issues being addressed as the ISV process is refined for new applications having different processing concerns. Refinements include moveable electrodes and sheet steel as the material for the containment structure. 16 refs., 4 figs., 6 tabs

Radioactive waste solidification material

International Nuclear Information System (INIS)

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

1992-01-01

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

Co-disposal of mixed waste materials

International Nuclear Information System (INIS)

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

1993-08-01

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

The waste of assistance material perceived by nursing students

Directory of Open Access Journals (Sweden)

Magaly Cecília Franchini Reichert

2017-11-01

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

SITE COMPREHENSIVE LISTING (CERCLIS) (Superfund) - NPL Sites

Data.gov (United States)

U.S. Environmental Protection Agency — National Priorities List (NPL) Sites - The Comprehensive Environmental Response, Compensation and Liability Information System (CERCLIS) (Superfund) Public Access...

A Comparison of Organic Emissions from Hazardous Waste Incinerators Versus the 1990 Toxics Release Inventory Air Releases

Science.gov (United States)

Incineration is often the preferred technology for disposing of hazardous waste and remediating Superfund sites. The effective implementation of this technology is frequently impeded by strong public opposition to hazardous waste incineration (HWI). One of the reasons cited for t...

Method of treating radioactive waste material

International Nuclear Information System (INIS)

Allison, W.

1980-01-01

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

Superfund Sites as Anti-landscapes

DEFF Research Database (Denmark)

Nye, David

2017-01-01

Americans have used a range of narratives to make sense of their settlement and use of natural resources. This article focuses on narratives of environmental degradation after the United States passed legislation mandating the cleanup of toxic sites and provided a Superfund for that purpose. Thre...

CERCLIS (Superfund) ASCII Text Format - CPAD Database

Data.gov (United States)

U.S. Environmental Protection Agency — The Comprehensive Environmental Response, Compensation and Liability Information System (CERCLIS) (Superfund) Public Access Database (CPAD) contains a selected set...

Solid waste and materials systems alternatives study summary

International Nuclear Information System (INIS)

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

1996-01-01

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

Material control and accountability procedures for a waste isolation repository

International Nuclear Information System (INIS)

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

1978-05-01

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

Laboratory Testing of Waste Isolation Pilot Plant Surrogate Waste Materials

Science.gov (United States)

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

2011-12-01

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

Superfund Record of Decision (EPA Rregion 4): Oak Ridge Reservation (USDOE), (Operable Unit 3), Anderson County, Oak Ridge, TN. (Second remedial action), September 1991

International Nuclear Information System (INIS)

1991-01-01

The Oak Ridge Reservation (ORR) (USDOE) (Operable Unit 3) site is an active nuclear weapons component manufacturing facility located in Oak Ridge, Anderson County, Tennessee. The Y-12 plant, which is addressed as Operable Unit 3, is one of several hundred waste disposal sites or areas of contamination at the ORR site requiring Superfund remedial action. The site occupies the upper reaches of East Fork Poplar Creek (EFPC) in Bear Creek Valley. From 1940 to the present, the Y-12 plant has been used to produce nuclear weapons components. From 1955 to 1963, mercury was used in a column-exchange process to separate lithium isotopes. Testing of the three concrete tanks showed that the tank sediment contained mercury, and that contaminated waste is still being discharged into two of the three tanks. The Record of Decision (ROD) focuses on the contaminated sediment in the sedimentation tanks as an interim action. The primary contaminants of concern affecting the sediment are mercury, a metal and radioactive materials. The selected interim remedial action for the site is included

Materials Science of High-Level Nuclear Waste Immobilization

International Nuclear Information System (INIS)

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

2009-01-01

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

Charging generators for waste management costs

International Nuclear Information System (INIS)

Berry, J.B.; Homan, F.J.

1988-01-01

The Department of Energy (DOE) has recognized the need for waste management that incorporates improved waste-handling techniques and more stringent regulatory requirements to prevent future liabilities such as Superfund sites. DOE-Oak Ridge Operations (DOE-ORO) has recognized that an effective waste management program focuses on control at the source and that the burden for responsible waste management can be placed on generators by charging for waste management costs. The principle of including the waste management costs in the total cost of the product, even when the product is research and development, is being implemented at Oak Ridge National Laboratory (ORNL). This paper summarizes a plan to charge waste generators, the administrative structure of the plan, a comparison between the rate structure and changes in waste disposal operations, and issues that have surfaced as the plan is implemented

Cleanups In My Community (CIMC) - Superfund National Priority List (NPL) Sites, National Layer

Data.gov (United States)

U.S. Environmental Protection Agency — This data layer provides access to Superfund National Priority List Sites as part of the CIMC web service. Superfund is a program administered by the EPA to locate,...

Buried waste containment system materials. Final Report

International Nuclear Information System (INIS)

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

1997-10-01

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

Nuclear Materials: Reconsidering Wastes and Assets - 13193

Energy Technology Data Exchange (ETDEWEB)

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

2013-07-01

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

Activities in department of energy hazardous and mixed waste defense waste management

International Nuclear Information System (INIS)

Eyman, L.D.

1988-01-01

In January 1986, the U.S. Department of Energy (DOE) Office of Assistant Secretary for Defense Programs (DP) created the Hazardous Waste and Remedial Actions Division within the Office of Defense Waste and Transportation Management. The Oak Ridge Operations Office (ORO) was assigned the responsibility for supporting DOE Headquarters (HQ) in planning nationally integrated activities for Resource Conservation and Recovery Act/Comprehensive Environmental Response, Compensation, and Liability Act/Superfund Amendments and Reauthorization Act (RCRA/CERCLA/SARA) compliance. In turn, ORO created the Hazardous Waste Remedial Actions Program Support Contractor Office (HAZWRAPSCO) to assist with the expanded lead assignment. The HAZWRAPSCO activities are currently supported by three distinct DOE-HQ funding elements: the Environmental Restoration Program, the Hazardous Waste Compliance Technology Program, and the Hazardous Waste Research and Development R and D Program. The Environmental Restoration Program is discussed in the paper, entitled The DOE Defense Program for Environmental Restoration

Remediation System Evaluation, McCormick and Baxter Superfund SiteRemediation System Evaluation, McCormick and Baxter Superfund Site

Science.gov (United States)

The McCormick and Baxter Creosoting Company, Portland Plant, Superfund Site is located adjacent tothe Willamette River in Portland, Oregon and addresses contamination of soil, groundwater, and riversediments stemming from creosoting operations...

Rock-welding materials for deep borehole nuclear waste disposal.

Energy Technology Data Exchange (ETDEWEB)

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

2015-11-01

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

Coastal structures, waste materials and fishery enhancement

Energy Technology Data Exchange (ETDEWEB)

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

1994-09-01

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

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

International Nuclear Information System (INIS)

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

1981-06-01

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

Youth Solid Waste Educational Materials List, November 1991.

Science.gov (United States)

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

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

Incentivizing secondary raw material markets for sustainable waste management.

Science.gov (United States)

Schreck, Maximilian; Wagner, Jeffrey

2017-09-01

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

Characterization of materials for waste-canister compatibility studies

International Nuclear Information System (INIS)

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

1981-10-01

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

Effect of Waste Materials on Performance of Self Compacting Concrete

OpenAIRE

DEMİREL, Sevgi; ÖZ, Hatice Öznur

2017-01-01

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

Material chemistry challenges in vitrification of high level radioactive waste

International Nuclear Information System (INIS)

Kaushik, C.P.

2008-01-01

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

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

Directory of Open Access Journals (Sweden)

Pi-Cheng Chen

2017-05-01

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

Physico-chemical characterisation of material fractions in household waste

DEFF Research Database (Denmark)

Götze, Ramona; Boldrin, Alessio; Scheutz, Charlotte

2016-01-01

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

Superfund National Priority List (NPL) Site Boundaries

Data.gov (United States)

U.S. Environmental Protection Agency — A set of site boundaries for each site in EPA Region 1 (Connecticut, Maine, Massachusetts, New Hampshire, Rhode Island, and Vermont) on EPA's Superfund National...

Cementitions materials in nuclear waste management

International Nuclear Information System (INIS)

Roy, D.M.

1990-01-01

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

Materials considerations relative to multibarrier waste isolation

International Nuclear Information System (INIS)

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

1981-07-01

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

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

Science.gov (United States)

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

2018-01-01

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

Buying time: Franchising hazardous and nuclear waste cleanup

Energy Technology Data Exchange (ETDEWEB)

Hale, D.R. [Dept. of Energy, Washington, DC (United States)

1997-05-01

This paper describes a private franchise approach to long-term custodial care, monitoring and eventual cleanup of hazardous and nuclear waste sites. The franchise concept could be applied to Superfund sites, decommissioning commercial reactors and safeguarding their wastes and to Department of Energy sites. Privatization would reduce costs by enforcing efficient operations and capital investments during the containment period, by providing incentives for successful innovation and by sustaining containment until the cleanup`s net benefits exceed its costs. The franchise system would also permit local governments and citizens to demand and pay for more risk reduction than provided by the federal government. In principle, they would have the option of taking over site management. The major political drawback of the idea is that it requires society to be explicit about what it is willing to pay for now to protect current and future generations. Hazardous waste sites are enduring legacies of energy development. Abandoned mines, closed refineries, underground storage tanks and nuclear facilities have often become threats to human health and water quality. The policy of the United States government is that such sites should quickly be made nonpolluting and safe for unrestricted use. That is, the policy of the United States is prompt cleanup. Orphaned commercial hazardous waste sites are addressed by the US Environmental Protection Agency`s Superfund program. 17 refs., 2 tabs.

Materials and Waste Management Research

Science.gov (United States)

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

Compacting biomass waste materials for use as fuel

Science.gov (United States)

Zhang, Ou

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

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

International Nuclear Information System (INIS)

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

1995-12-01

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

Engineering materials for high level radioactive waste repository

International Nuclear Information System (INIS)

Wen Zhijian

2009-01-01

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

SITE COMPREHENSIVE LISTING (CERCLIS) (Superfund) - Non-NPL Sites

Data.gov (United States)

U.S. Environmental Protection Agency — Non-NPL Sites - The Comprehensive Environmental Response, Compensation and Liability Information System (CERCLIS) (Superfund) Public Access Database contains a...

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

International Nuclear Information System (INIS)

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

1988-02-01

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

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

International Nuclear Information System (INIS)

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

1988-01-01

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

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

International Nuclear Information System (INIS)

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

1978-11-01

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

Survey of matrix materials for solidified radioactive high-level waste

Energy Technology Data Exchange (ETDEWEB)

Gurwell, W.E.

1981-09-01

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

Survey of matrix materials for solidified radioactive high-level waste

International Nuclear Information System (INIS)

Gurwell, W.E.

1981-09-01

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

Superfund reauthorization. Hearings before the Subcommittee on Commerce, Transportation, and Tourism of the Committee on Energy and Commerce, House of Representatives, Ninety-Eighth Congress, Second Session on H. R. 4813 and H. R. 4915, February 28, March 1, 8, and 15, 1984

Energy Technology Data Exchange (ETDEWEB)

1984-01-01

Four days of hearings on two bills (H.R. 4813 and H.R. 4915) designed to provide cleanup funds for hazardous waste sites cover the testimony of 42 witnesses, including that of Environmental Protection Agency Director Ruckelshaus and representatives of the US Chamber of Commerce, government agencies, environmental and other interest groups, the medical profession, the chemical and mining industries, and waste treatment agencies and organizations. The three-year-old Superfund has only cleaned up a few sites, and EPA predicts that the $1.6 billion fund can handle only 170 of the 546 priority sites. The reauthorizing bills increase funding, set cleanup standards, increase enforcement provisions, and encourage a state and federal partnership in the cleanup process. Material submitted for the record follows the text of the two bills and the testimony.

Materials design considerations and selection for a large rad waste incinerator

International Nuclear Information System (INIS)

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

1997-01-01

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

The waste minimization program at the Feed Materials Production Center

International Nuclear Information System (INIS)

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

1987-01-01

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

Waste in Education: The Potential of Materiality and Practice

Science.gov (United States)

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

2018-01-01

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

Removal of radioactive and other hazardous material from fluid waste

Science.gov (United States)

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

2006-10-03

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

Microwave reactor for utilizing waste materials

Directory of Open Access Journals (Sweden)

M. Pigiel

2010-01-01

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

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

International Nuclear Information System (INIS)

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

1987-03-01

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

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

African Journals Online (AJOL)

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

In-Depth Case Studies of Superfund Reuse

Science.gov (United States)

SRI’s in-depth case studies explore Superfund reuse stories from start to finish. Their purpose is to see what redevelopment strategies worked, acknowledge reuse barriers and understand how communities overcame the barriers to create new reuse outcomes.

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

International Nuclear Information System (INIS)

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

1981-04-01

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

Materials for high-level waste containment

International Nuclear Information System (INIS)

Marsh, G.P.

1982-01-01

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

Remote automated material handling of radioactive waste containers

International Nuclear Information System (INIS)

Greager, T.M.

1994-09-01

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

Human Health Toxicity Values in Superfund Risk Assessments

Science.gov (United States)

This memorandum revises the hierarchy of human health toxicity values generally recommended for use inr isk assessments, originally presented in Risk Assessment Guidance for Superfund Volume I, Part A.

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

International Nuclear Information System (INIS)

Doering, Thomas; Pasupathi, V.

2002-01-01

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

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

OpenAIRE

Cuizhen Xue; Aiqin Shen; Yinchuan Guo; Tianqin He

2016-01-01

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

SHIRCO PILOT-SCALE INFRARED INCINERATION SYSTEM AT THE ROSE TOWNSHIP DEMODE ROAD SUPERFUND SITE

Science.gov (United States)

Under the Superfund Innovative Technology Evaluation or SITE Program, an evaluation was made of the Shirco Pilot-Scale Infrared Incineration System during 17 separate test runs under varying operating conditions. The tests were conducted at the Demode Road Superfund site in Ros...

78 FR 729 - Ellman Battery Superfund Site; Orlando, Orange County, FL; Notice of Settlement

Science.gov (United States)

2013-01-04

... ENVIRONMENTAL PROTECTION AGENCY [FRL-9767-6; CERCLA-04-2012-3780] Ellman Battery Superfund Site; Orlando, Orange County, FL; Notice of Settlement AGENCY: Environmental Protection Agency (EPA). ACTION... Action at the Ellman Battery Superfund Site located in Orlando, Orange County, Florida. DATES: The Agency...

Feed Materials Production Center Waste Management Plan

International Nuclear Information System (INIS)

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

1986-01-01

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

Processing method for liquid waste containing various kinds of radioactive material

International Nuclear Information System (INIS)

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

1996-01-01

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

Corrosion assessment of refractory materials for high temperature waste vitrification

International Nuclear Information System (INIS)

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

1995-01-01

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

Risks associated with nuclear material recovery and waste preparation

Energy Technology Data Exchange (ETDEWEB)

Fullwood, R R; Erdmann, R C

1983-01-01

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

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

International Nuclear Information System (INIS)

1988-12-01

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

Peer Review of the Waste Package Material Performance Interim Report

International Nuclear Information System (INIS)

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

2001-01-01

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

PURIFIED WASTE FCC CATALYST AS A CEMENT REPLACEMENT MATERIAL

Directory of Open Access Journals (Sweden)

Danute Vaiciukyniene

2015-06-01

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

Calcium phosphate nuclear materials: apatitic ceramics for separated wastes

International Nuclear Information System (INIS)

Carpena, J.; Lacout, J.L.

2005-01-01

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

SITE COMPREHENSIVE LISTING (CERCLIS) - Contaminants at CERCLIS (Superfund) Sites

Data.gov (United States)

U.S. Environmental Protection Agency — Contaminants at Comprehensive Environmental Response, Compensation and Liability Information System (CERCLIS) (Superfund) Sites - The CERCLIS Public Access Database...

The Control of Hazardous Wastes and the Role of Environmental Educators.

Science.gov (United States)

Pfortner, Ray

1984-01-01

Discusses legislation aimed at hazardous waste issues which are implemented by the Environmental Protection Agency and state governments. Particular attention is given to Comprehensive Environmental Response, Compensation, and Liability Act of 1980 (CERCLA). A case study of an abandoned acres superfund site is included with two related student…

Release of powdered material from waste packages

International Nuclear Information System (INIS)

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

1990-01-01

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

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

International Nuclear Information System (INIS)

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

2000-01-01

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

Northwest Hazardous Waste Research, Development, and Demonstration Center: Program Plan

International Nuclear Information System (INIS)

1988-02-01

The Northwest Hazardous Waste Research, Development, and Demonstration Center was created as part of an ongoing federal effort to provide technologies and methods that protect human health and welfare and environment from hazardous wastes. The Center was established by the Superfund Amendments and Reauthorization Act (SARA) to develop and adapt innovative technologies and methods for assessing the impacts of and remediating inactive hazardous and radioactive mixed-waste sites. The Superfund legislation authorized $10 million for Pacific Northwest Laboratory to establish and operate the Center over a 5-year period. Under this legislation, Congress authorized $10 million each to support research, development, and demonstration (RD and D) on hazardous and radioactive mixed-waste problems in Idaho, Montana, Oregon, and Washington, including the Hanford Site. In 1987, the Center initiated its RD and D activities and prepared this Program Plan that presents the framework within which the Center will carry out its mission. Section 1.0 describes the Center, its mission, objectives, organization, and relationship to other programs. Section 2.0 describes the Center's RD and D strategy and contains the RD and D objectives, priorities, and process to be used to select specific projects. Section 3.0 contains the Center's FY 1988 operating plan and describes the specific RD and D projects to be carried out and their budgets and schedules. 9 refs., 18 figs., 5 tabs

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

International Nuclear Information System (INIS)

Drace, Zoran; Ojovan, Michael I.

2012-01-01

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

Materials and wastes from power generation of nuclear origin

International Nuclear Information System (INIS)

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

2014-01-01

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

Report: Remedial Project Manager Turnover at Superfund Sites

Science.gov (United States)

Report #2001-M-000015, June 15, 2001. We determined that EPA Region III did not have formal procedures in place to mitigate continuity problems caused by turnover of EPA personnel in the Superfund program.

Product Control of Waste Products with New Coating Materials

International Nuclear Information System (INIS)

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

2009-01-01

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

Feasibility of Target Material Recycling as Waste Management Alternative

International Nuclear Information System (INIS)

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

2004-01-01

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

Charging for waste motivates generators to optimize waste control at the source

International Nuclear Information System (INIS)

Berry, J.B.; Homan, F.J.

1988-01-01

The Department of Energy (DOE) has recognized the need for waste management that incorporates improved waste-handling techniques and more stringent regulatory requirements to prevent future liabilities such as Superfund sites. DOE-Oak Ridge Operations (DOE-ORO) has recognized that an effective waste management program focuses on control at the source and that the burden for responsible waste management can be placed on generators by charging for waste management costs. The principle of including the waste management costs in the total cost of the product, even when the product is research and development, is being implemented at Oak Ridge National Laboratory (ORNL). Charging waste management costs to generators creates an incentive to optimize processes so that less waste is produced, and it provides a basis for determining the cost effectiveness of capital improvements so that the mature phase of waste management can be attained. Improving waste management practices requires a long-range commitment and consistent administration. Making this commitment and providing adequate funding for proper waste disposal are most cost-effective measures than the alternative of paying for remedial actions after improper disposal. This paper summarizes a plan to charge waste generators, the administrative structure of the plan, a comparison between the rate structure and changes in waste disposal operations, and issues that have surfaced as the plan is implemented

Producing glass-ceramics from waste materials

Energy Technology Data Exchange (ETDEWEB)

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

2002-10-01

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

77 FR 16548 - Florida Petroleum Reprocessors Superfund Site; Davie, Broward County, FL; Notice of Settlements

Science.gov (United States)

2012-03-21

...-2012- 3766; CERCLA-04-2012-3765] Florida Petroleum Reprocessors Superfund Site; Davie, Broward County... costs concerning the Florida Petroleum Reprocessors Superfund Site located in Davie, Broward County.... Painter. Submit your comments by Site name Florida Petroleum Reprocessors by one of the following methods...

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

International Nuclear Information System (INIS)

Moak, D.P.

1986-09-01

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

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

Directory of Open Access Journals (Sweden)

Serdar Özlü

2017-12-01

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

Influence of Handling Practices on Material Recovery from Residential Solid Waste

Directory of Open Access Journals (Sweden)

Jairo F. Pereira

2010-07-01

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

Waste glass as eco-friendly replacement material in construction products

Science.gov (United States)

Sharma, Gayatri; Sharma, Anu

2018-05-01

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

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

Science.gov (United States)

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

2017-09-01

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

Degradation modes of nickel-base alternate waste package overpack materials

International Nuclear Information System (INIS)

Pitman, S.G.

1988-07-01

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

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

International Nuclear Information System (INIS)

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

2012-01-01

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

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

CERN Document Server

Cheremisinoff, Nicholas P

1995-01-01

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

77 FR 11533 - Anniston PCB Superfund Site, Anniston, Calhoun County, Alabama; Notice of Amended Settlement

Science.gov (United States)

2012-02-27

... ENVIRONMENTAL PROTECTION AGENCY [CERCLA-04-2012-3763; FRL 9637-7] Anniston PCB Superfund Site... past response costs concerning the Anniston PCB Superfund Site located in Anniston, Calhoun County.... Submit your comments by Site name Anniston PCB by one of the following methods: www.epa.gov/region4...

Smart moves in superfund - revitalization one year later. Volume 1, Number 3, January 1993. Bulletin

International Nuclear Information System (INIS)

1993-01-01

The issue of the Smart Moves in Superfund bulletin series provides an update on the revitalization effort, highlighting National Priorities List (NPL) construction completions, accelerating cleanup, the Superfund Accelerated Cleanup Model, risk assessment/risk management, contracts management, enforcement policy/equity, interagency cooperation, public forms, and state meetings

Initial specifications for nuclear waste package external dimensions and materials

International Nuclear Information System (INIS)

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

1983-09-01

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

Composition of waste materials and recyclables

DEFF Research Database (Denmark)

Götze, Ramona

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

Maxey Flats low-level waste disposal site closure activities

International Nuclear Information System (INIS)

Haight, C.P.; Mills, D.; Razor, J.E.

1987-01-01

The Maxey Flats Radioactive Waste Disposal Facility in Fleming County, Kentucky is in the process of being closed. The facility opened for commercial business in the spring of 1963 and received approximately 4.75 million cubic feet of radioactive waste by the time it was closed in December of 1977. During fourteen years of operation approximately 2.5 million curies of by-product material, 240,000 kilograms of source material, and 430 kilograms of special nuclear material were disposed. The Commonwealth purchased the lease hold estate and rights in May 1978 from the operating company. This action was taken to stabilize the facility and prepare it for closure consisting of passive care and monitoring. To prepare the site for closure, a number of remedial activities had to be performed. The remediation activities implemented have included erosion control, surface drainage modifications, installation of a temporary plastic surface cover, leachate removal, analysis, treatment and evaporation, US DOE funded evaporator concentrates solidification project and their on-site disposal in an improved disposal trench with enhanced cover for use in a humid environment situated in a fractured geology, performance evaluation of a grout injection demonstration, USGS subsurface geologic investigation, development of conceptual closure designs, and finally being added to the US EPA National Priority List for remediation and closure under Superfund. 13 references, 3 figures

Unify a hazardous materials/waste program

International Nuclear Information System (INIS)

Carson, H.T.

1988-01-01

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

Centredale Manor Superfund Site in Rhode Island included on EPA List of Targeted for Immediate Attention

Science.gov (United States)

Today, the U.S. Environmental Protection Agency released the list of Superfund sites that Administrator Pruitt has targeted for immediate and intense attention. The Centredale Manor Restoration Project superfund site is one of the 21 sites on the list.

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

Energy Technology Data Exchange (ETDEWEB)

None

1992-10-01

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

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

Energy Technology Data Exchange (ETDEWEB)

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

1997-12-31

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

Materials selection for process equipment in the Hanford waste vitrification plant

Energy Technology Data Exchange (ETDEWEB)

Elmore, M R; Jensen, G A

1991-07-01

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

2009 National inventory of radioactive material and wastes. Synthesis report

International Nuclear Information System (INIS)

2009-01-01

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

Report on current research into organic materials in radioactive waste

International Nuclear Information System (INIS)

Norris, G.H.

1987-11-01

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

Superfund at work: Hazardous waste cleanup efforts nationwide, fall 1992. (Wide Beach section of Brant, New York)

International Nuclear Information System (INIS)

1992-01-01

Wide-spread contamination of polychlorinated biphenyls (PCBs) threatened the Wide Beach section of Brant, New York, a popular vacation resort. EPA's Superfund program effectively completed a permanent cleanup of Wide Beach in the span of one year. Other highlights included: a new and innovative technology to remove PCB contamination; reduction of PCBs to one-fifth of acceptable levels; temporary relocation of residents who were concerned for their health while cleanup activities took place; newly paved roads and driveways, re-landscaped yards, and a new storm sewer system; and restoration of ecologically sensitive wetlands. EPA's achievements significantly reduced PCB risks at Wide Beach, and left a satisfied community in Brant

Remediation System Evaluation, Douglas Road Landfill Superfund Site

Science.gov (United States)

The Douglas Road Landfill Superfund Site is located in St. Joseph County just north of Mishawaka,Indiana. The site consists of a 16-acre capped landfill located on an approximately 32-acre lot (includingthe land purchased in 1999 for a wetlands...

Mechanism of lead removal by waste materials

International Nuclear Information System (INIS)

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

2007-01-01

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

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

Energy Technology Data Exchange (ETDEWEB)

Esch, R.A.

1997-04-14

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

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

DEFF Research Database (Denmark)

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

2013-01-01

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

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

OpenAIRE

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

2018-01-01

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

SITE COMPREHENSIVE LISTING (CERCLIS) (Superfund) - Responsible Parties at CERCLIS Sites

Data.gov (United States)

U.S. Environmental Protection Agency — Responsible Parties at CERCLIS Sites - The Comprehensive Environmental Response, Compensation and Liability Information System (CERCLIS) (Superfund) Public Access...

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

International Nuclear Information System (INIS)

Halsey, W.G.

1991-01-01

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

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

Science.gov (United States)

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

2013-09-01

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

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

Energy Technology Data Exchange (ETDEWEB)

Lindle, Dennis W.

2011-04-21

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

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

International Nuclear Information System (INIS)

Magoulas, Virginia

2013-01-01

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

The changing Arena: New DOE waste management orders

International Nuclear Information System (INIS)

Albenesius, E.L.; Kluk, A.F.

1988-01-01

There are five orders that address waste management within the Department of Energy (DOE); three of these orders are being revised, which emphasize the rapidly changing arena in which the department is contending in this field. The need to change the Comprehensive Environmental Response, Compensation and Liability Act (CERCLA) Order arose from the Superfund amendments of 1986 (SARA) with its hammer provisions in Section 120 for compliance at Federal facilities. The need to change the Hazardous and Mixed Waste Management Order was accelerated by the promulgation by DOE of the new mixed waste rule on May 1, 1987, (1) and cancellation of the obsolete existing order on October 5, 1987. The new rule requires coregulation of all DOE mixed waste with the Environmental Protection Agency (EPA) and the respective authorized states. 5 refs

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

International Nuclear Information System (INIS)

1993-11-01

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

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

International Nuclear Information System (INIS)

2013-02-01

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

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

Directory of Open Access Journals (Sweden)

B. Oleksiak

2018-01-01

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

2009 National inventory of radioactive material and wastes. In short

International Nuclear Information System (INIS)

2009-01-01

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

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

International Nuclear Information System (INIS)

Ehrlicher, Ulrich; Pauli, Heinz

2009-01-01

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

Developing an institutional strategy for transporting defense transuranic waste materials

International Nuclear Information System (INIS)

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

1986-01-01

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

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

Science.gov (United States)

Ajayi, Saheed O; Oyedele, Lukumon O

2018-05-01

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

40 CFR 35.4040 - How many groups can receive a TAG at one Superfund site?

Science.gov (United States)

2010-07-01

... 40 Protection of Environment 1 2010-07-01 2010-07-01 false How many groups can receive a TAG at one Superfund site? 35.4040 Section 35.4040 Protection of Environment ENVIRONMENTAL PROTECTION AGENCY... Eligible? § 35.4040 How many groups can receive a TAG at one Superfund site? (a) Only one TAG may be...

A strategy for end point criteria for Superfund remediation

International Nuclear Information System (INIS)

Hwang, S.T.

1992-06-01

Since the inception of cleanup for hazardous waste sites, estimating target cleanup levels has been the subject of considerable investigation and debate in the Superfund remediation process. Establishing formal procedures for assessing human health risks associated with hazardous waste sites has provided a conceptual framework for determining remediation goals and target cleanup levels (TCLs) based on human health and ecological risk consideration. This approach was once considered at variance with the concept of the pre-risk assessment period; that is, cleaning up to the background level, or using containment design or best available control technologies. The concept has been gradually adopted by the regulatory agencies and the parties responsible for cleanup. Evaluation of cleanup strategies at the outset of the planning stage will eventually benefit the parties responsible for cleanup and the oversight organizations, including regulatory agencies. Development of the strategies will provide an opportunity to promote an improvement in the pace and quality of many activities to be carried out. The strategies should help address the issues related to (1) improving remediation management activities to arrive at remediation as expeditiously as possible, (2) developing alternate remediation management activities, (3) identifying obstructing issues to management for resolution, (4) adapting the existing framework to correspond to the change in remediation statutes and guidelines, and (5) providing the basis for evaluating options for the record of decision process. This paper will discuss some of the issues and the research efforts that were addressed as part of the strategies requiring future discussion and comment

Standardization of waste acceptance test methods by the Materials Characterization Center

International Nuclear Information System (INIS)

Slate, S.C.

1985-01-01

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

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

International Nuclear Information System (INIS)

Arthur, E.D.

1997-10-01

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

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

DEFF Research Database (Denmark)

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

2014-01-01

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

Method and apparatus for the management of hazardous waste material

Science.gov (United States)

Murray, Jr., Holt

1995-01-01

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

Nuclear waste package materials testing report: basaltic and tuffaceous environments

International Nuclear Information System (INIS)

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

1983-03-01

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

Compression device for feeding a waste material to a reactor

Science.gov (United States)

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

2001-08-21

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

Chemical digestion of low level nuclear solid waste material

International Nuclear Information System (INIS)

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

1976-01-01

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

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

International Nuclear Information System (INIS)

Romano, Stephen; Welling, Steven; Bell, Simon

2003-01-01

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

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

Energy Technology Data Exchange (ETDEWEB)

Horn, J. M., LLNL

1998-01-01

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

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

Science.gov (United States)

Tanigaki, Nobuhiro; Ishida, Yoshihiro; Osada, Morihiro

2015-03-01

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

Design of a deposit of waste materials coming from mining exploitations

International Nuclear Information System (INIS)

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

2005-01-01

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

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

International Nuclear Information System (INIS)

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

2016-01-01

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

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

International Nuclear Information System (INIS)

Kuburovic, M.; Jovovic, A.

2002-01-01

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

Material Recovery and Waste Form Development FY 2014 Accomplishments Report

Energy Technology Data Exchange (ETDEWEB)

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

2014-11-01

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

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

Energy Technology Data Exchange (ETDEWEB)

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

1998-09-01

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

Recycling ceramic industry wastes in sound absorbing materials

Directory of Open Access Journals (Sweden)

C. Arenas

2016-10-01

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

Environmentally benign destruction of waste energetic materials (EMs)

International Nuclear Information System (INIS)

Schneider, R. L.; Donahue, B. A.

1998-01-01

Studies by the U. S. Army Corps of Engineers during 1991-1997 involving various methods for the destruction of waste generated by pyrotechnic, explosive and propellant materials are described. The methods assessed and evaluated include controlled incineration (CI), wet air oxidation (WAO), and hydrothermal oxidation (HTO), using a U.S. Army triple-base propellant as the initial common standard for all destructor comparative testing. All three of these methods has special feed line restrictions requiring mechanical diminution and comminution of the energetic material which, for safety reasons, cannot be used with contaminated heterogeneous production wastes. Supercritical fluid extraction with carbon dioxide, alkaline hydrolysis, electrolysis and fluid cutting with very high pressure water jets and liquid nitrogen are alternate technologies that were evaluated as pre-treatment for production wastes. Wet air oxidation and electrochemical reduction studies were conducted using the U.S. Navy double propellant NOSIH-AA2, which contains a lead-based ballistic modifier. Wet air oxidation and hydrothermal oxidation studies were done using potassium dinitramide phase-stabilized nitrate as an oxidizer. All of these technologies are considered to be suitable for the environmentally benign destruction of pyrotechnic materials, including fireworks. 17 refs., 8 tabs., 4 figs

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

International Nuclear Information System (INIS)

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

1988-01-01

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

PROCESS DEVELOPMENT FOR THE RECOVERY OF CRITICAL MATERIALS FROM ELECTRONIC WASTE

Energy Technology Data Exchange (ETDEWEB)

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

2016-09-01

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

Forming artificial soils from waste materials for mine site rehabilitation

Science.gov (United States)

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

2014-05-01

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

Methodologies for estimating one-time hazardous waste generation for capacity generation for capacity assurance planning

International Nuclear Information System (INIS)

Tonn, B.; Hwang, Ho-Ling; Elliot, S.; Peretz, J.; Bohm, R.; Hendrucko, B.

1994-04-01

This report contains descriptions of methodologies to be used to estimate the one-time generation of hazardous waste associated with five different types of remediation programs: Superfund sites, RCRA Corrective Actions, Federal Facilities, Underground Storage Tanks, and State and Private Programs. Estimates of the amount of hazardous wastes generated from these sources to be shipped off-site to commercial hazardous waste treatment and disposal facilities will be made on a state by state basis for the years 1993, 1999, and 2013. In most cases, estimates will be made for the intervening years, also

Innovative design and construction solutions to remediate radiologically contaminated residential communities in Essex County New Jersey

International Nuclear Information System (INIS)

MacIndoe, M.S.; Johnson, R.T.; Wilkinson, S.G.

1995-01-01

The Montclair/West Orange and Glen Ridge Superfund Sites, located in Essen Country, New Jersey, are contaminated to varying degrees with radioactive materials. Both sites are listed on the Superfund National Priorities List (NPL). The waste materials originated from radium processing facilities prevalent in the area during the early 1900's. The design for remediation of these sites is performed by Bechtel National, Inc. on the behalf of the US Army Corps of Engineers (USACE) Kansas City District, which administers the project through an Interagency Agreement with the US Environmental Protection Agency (EPA) Region 2

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

International Nuclear Information System (INIS)

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

2014-01-01

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

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

Directory of Open Access Journals (Sweden)

Diana BAJARE

2014-09-01

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

Strategy to Ensure Institutional Control Implementation at Superfund Sites

Science.gov (United States)

This document sets forth EPA’s strategy (Strategy) for ensuring that institutional controls (ICs) are successfully implemented at Superfund sites, with an emphasis on evaluating ICs at sites where all construction of all remedies is complete (construction complete sites).

Privacy Impact Assessment for the Enforcement Superfund Tracking System

Science.gov (United States)

This Enforcement Superfund Tracking System (ESTS) collects publicly available information from the California Secretary of State on businesses. Learn how this data is collected, how it will be used, access to the data, and the purpose of data collection.

Melting behaviour of raw materials and recycled stone wool waste

DEFF Research Database (Denmark)

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

2018-01-01

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

78 FR 47317 - Ore Knob Mine Superfund Site; Laurel Springs, Ashe County, North Carolina; Notice of Settlement

Science.gov (United States)

2013-08-05

... ENVIRONMENTAL PROTECTION AGENCY [FRL-9843-3; CERCLA-04-2013-3759] Ore Knob Mine Superfund Site; Laurel Springs, Ashe County, North Carolina; Notice of Settlement AGENCY: Environmental Protection Agency... settlement with Herbert N. Francis concerning the Ore Knob Mine Superfund Site located in Laurel Springs...

Phosphate bonded ceramics as candidate final-waste-form materials

International Nuclear Information System (INIS)

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

1994-04-01

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

National inventory of radioactive wastes and valorizable materials. Synthesis report

International Nuclear Information System (INIS)

2004-01-01

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

Superfund Removal Site Points, Region 9, 2012, US EPA Region 9

Data.gov (United States)

U.S. Environmental Protection Agency — Point geospatial dataset representing locations of CERCLA (Superfund) Removal sites. CERCLA (Comprehensive Environmental Response, Compensation, and Liability Act)...

Mechanical degradation temperature of waste storage materials

International Nuclear Information System (INIS)

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

1993-01-01

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

Advanced Thermoelectric Materials for Efficient Waste Heat Recovery in Process Industries

Energy Technology Data Exchange (ETDEWEB)

Adam Polcyn; Moe Khaleel

2009-01-06

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

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

International Nuclear Information System (INIS)

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

2016-01-01

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

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

International Nuclear Information System (INIS)

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

1981-10-01

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

Radioactive material inventory control at a waste characterization facility

International Nuclear Information System (INIS)

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

1996-01-01

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

Transport packages for nuclear material and waste

International Nuclear Information System (INIS)

1997-01-01

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

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

OpenAIRE

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

2008-01-01

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

Materials And Carbon Flow In A Waste Refinery Process Using Enzymes

DEFF Research Database (Denmark)

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

2011-01-01

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

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

Energy Technology Data Exchange (ETDEWEB)

Casey, C.; Heath, B.A.

1992-11-01

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

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

International Nuclear Information System (INIS)

Berusch, A.; Gause, E.

1987-01-01

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

Physical and mechanical properties of degraded waste surrogate material

International Nuclear Information System (INIS)

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

1998-03-01

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

Use of waste materials in rubber matrix

Directory of Open Access Journals (Sweden)

Pajtášová Mariana

2018-01-01

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

DECISION ANALYSIS OF INCINERATION COSTS IN SUPERFUND SITE REMEDIATION

Science.gov (United States)

This study examines the decision-making process of the remedial design (RD) phase of on-site incineration projects conducted at Superfund sites. Decisions made during RD affect the cost and schedule of remedial action (RA). Decision analysis techniques are used to determine the...

Corrosion of canister materials for radioactive waste disposal

International Nuclear Information System (INIS)

Kienzler, Bernhard

2017-01-01

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

Waste Plastic Converting into Hydrocarbon Fuel Materials

Energy Technology Data Exchange (ETDEWEB)

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

2010-09-15

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

Radioactive waste - a select list of material

International Nuclear Information System (INIS)

Lambert, C.M.

1982-01-01

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

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

Energy Technology Data Exchange (ETDEWEB)

Koppers, H

1916-10-29

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

Measurement of volatile organic compounds during start-up of bioremediation of French limited superfund site in Crosby Texas using wind dependent whole-air sampling

International Nuclear Information System (INIS)

Pleil, J.D.; Fortune, C.R.; Yoong, M.; Oliver, K.D.

1993-01-01

Whole-air sampling was performed before and after the start-up of the bioremediation of an industrial (primarily petrochemical) waste lagoon in Crosby Texas, near Houston. Four 'Sector Samplers' were deployed at the four corners of the French Limited Superfund Site. These samplers collect air into one of two SUMMA polished canisters depending upon wind direction and speed. When the wind blows at the sampler from across the waste lagoon, air is routed to the 'IN' sector canister, otherwise sample is collected in the 'OUT' sector canister. As such, each sampler provides its own background sample, and, upon gas chromatographic analysis, individual compounds can be associated with the waste lagoon. Five sets of 24-hour sector samples were taken; the first set was collected prior to the start of the bioremediation effort and the remaining four sets were taken sequentially for four 24-hour periods after the start-up of the procedure

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

Energy Technology Data Exchange (ETDEWEB)

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

1995-12-01

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

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

International Nuclear Information System (INIS)

Kolasiński, Piotr; Kolasińska, Ewa

2016-01-01

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

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

Energy Technology Data Exchange (ETDEWEB)

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

2015-03-15

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

PRODUCTION OF AN INSULATION MATERIAL FROM CARPET AND BORON WASTES

OpenAIRE

Yasin ERDOĞAN

2016-01-01

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

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

International Nuclear Information System (INIS)

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

1995-01-01

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

Elaboration and characterisation of plutonium waste reference materials

International Nuclear Information System (INIS)

Perolat, J.P.

1990-01-01

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

Utilization of Blended Waste Materials in Bricks

Directory of Open Access Journals (Sweden)

Muhammad Ekhlasur Rahman

2018-01-01

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

Optimization Review: Carson River Mercury Superfund Site, Carson City, Nevada

Science.gov (United States)

The Carson River Mercury Site (CRMS) (Figure 1) is located in northwest Nevada and was designated a Superfund site in 1990 because of elevated mercury concentrations observed in surface water, sediments and biota inhabiting the site.

Material Not Categorized As Waste (MNCAW) data report

International Nuclear Information System (INIS)

Casey, C.; Heath, B.A.

1992-11-01

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

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

Energy Technology Data Exchange (ETDEWEB)

Wender, H

1980-08-01

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

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

International Nuclear Information System (INIS)

Nnorom, Innocent Chidi; Osibanjo, Oladele

2008-01-01

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

Characteristics of and sorption to biochars derived from waste material

Science.gov (United States)

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

2015-04-01

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

Remediation System Evaluation, Savage Municipal Water Supply Superfund Site (PDF)

Science.gov (United States)

The Savage Municipal Water Supply Superfund Site, located on the western edge of Milford, New Hampshire, consists of a source area and an extended plume that is approximately 6,000 feet long and 2,500 feet wide.

Corrosion of canister materials for radioactive waste disposal

Energy Technology Data Exchange (ETDEWEB)

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

2017-08-15

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

ERG review of waste package container materials selection and corrosion

International Nuclear Information System (INIS)

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

1986-07-01

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

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

International Nuclear Information System (INIS)

Lindle, Dennis W.

2011-01-01

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

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

Science.gov (United States)

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

2016-08-01

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

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

International Nuclear Information System (INIS)

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

1994-03-01

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

POLYMER COMPOSITES MODIFIED BY WASTE MATERIALS CONTAINING WOOD FIBRES

Directory of Open Access Journals (Sweden)

Bernardeta Dębska

2016-11-01

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

Laboratory-performance criteria for in situ waste-stabilization materials

International Nuclear Information System (INIS)

Shaw, P.; Weidner, J.

1996-01-01

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

Package materials, waste form

International Nuclear Information System (INIS)

Anon.

1980-01-01

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

Mining-Related Sediment and Soil Contamination in a Large Superfund Site: Characterization, Habitat Implications, and Remediation.

Science.gov (United States)

Juracek, K E; Drake, K D

2016-10-01

Historical mining activity (1850-1970) in the now inactive Tri-State Mining District provided an ongoing source of lead and zinc to the environment including the US Environmental Protection Agency Superfund site located in Cherokee County, southeast Kansas, USA. The resultant contamination adversely affected biota and caused human health problems and risks. Remediation in the Superfund site requires an understanding of the magnitude and extent of contamination. To provide some of the required information, a series of sediment and soil investigations were conducted in and near the Superfund site to characterize lead and zinc contamination in the aquatic and floodplain environments along the main-stem Spring River and its major tributaries. In the Superfund site, the most pronounced lead and zinc contamination, with concentrations that far exceed sediment quality guidelines associated with potential adverse biological effects, was measured for streambed sediments and floodplain soils located within or downstream from the most intensive mining-affected areas. Tributary streambeds and floodplains in affected areas are heavily contaminated with some sites having lead and zinc concentrations that are an order of magnitude (or more) greater than the sediment quality guidelines. For the main-stem Spring River, the streambed is contaminated but the floodplain is mostly uncontaminated. Measured lead and zinc concentrations in streambed sediments, lakebed sediments, and floodplain soils documented a persistence of the post-mining contamination on a decadal timescale. These results provide a basis for the prioritization, development, and implementation of plans to remediate contamination in the affected aquatic and floodplain environments within the Superfund site.

Mining-related sediment and soil contamination in a large Superfund site: Characterization, habitat implications, and remediation

Science.gov (United States)

Juracek, Kyle E.; Drake, K. D.

2016-01-01

Historical mining activity (1850–1970) in the now inactive Tri-State Mining District provided an ongoing source of lead and zinc to the environment including the US Environmental Protection Agency Superfund site located in Cherokee County, southeast Kansas, USA. The resultant contamination adversely affected biota and caused human health problems and risks. Remediation in the Superfund site requires an understanding of the magnitude and extent of contamination. To provide some of the required information, a series of sediment and soil investigations were conducted in and near the Superfund site to characterize lead and zinc contamination in the aquatic and floodplain environments along the main-stem Spring River and its major tributaries. In the Superfund site, the most pronounced lead and zinc contamination, with concentrations that far exceed sediment quality guidelines associated with potential adverse biological effects, was measured for streambed sediments and floodplain soils located within or downstream from the most intensive mining-affected areas. Tributary streambeds and floodplains in affected areas are heavily contaminated with some sites having lead and zinc concentrations that are an order of magnitude (or more) greater than the sediment quality guidelines. For the main-stem Spring River, the streambed is contaminated but the floodplain is mostly uncontaminated. Measured lead and zinc concentrations in streambed sediments, lakebed sediments, and floodplain soils documented a persistence of the post-mining contamination on a decadal timescale. These results provide a basis for the prioritization, development, and implementation of plans to remediate contamination in the affected aquatic and floodplain environments within the Superfund site.

Prevention of spontaneous combustion of backfilled plant waste material.

CSIR Research Space (South Africa)

Adamski, SA

2003-06-01

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

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

Science.gov (United States)

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

2012-04-01

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

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

International Nuclear Information System (INIS)

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

1986-01-01

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

EXPERIMENTAL INVESTIGATION ON PREFABRICATED ROAD PANEL BY USING WASTE MATERIALS

OpenAIRE

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

2018-01-01

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

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

International Nuclear Information System (INIS)

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

1981-01-01

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

Material Balance Assessment for Double-Shell Tank Waste Pipeline Transfer

International Nuclear Information System (INIS)

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

2001-01-01

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

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

International Nuclear Information System (INIS)

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

2007-01-01

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

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

International Nuclear Information System (INIS)

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

1987-01-01

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

Power plant wastes capitalization as geopolymeric building materials

Science.gov (United States)

Ciobanu, Gabriela; Litu, Loredana; Harja, Maria

2017-11-01

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

Superfund Technology Evaluation Report: SITE Program Demonstration Test Shirco Pilot-Scale Infrared Incineration System at the Rose Township Demode Road Superfund Site Volume I

Science.gov (United States)

The Shirco Pilot-Scale Infrared Incineration System was evaluated during a series of seventeen test runs under varied operating conditions at the Demode Road Superfund Site located in Rose Township, Michigan. The tests sought to demonstrate the effectiveness of the unit and the t...

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

Directory of Open Access Journals (Sweden)

Steffen Lehmann

2011-01-01

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

Tests with ceramic waste form materials made by pressureless consolidation

International Nuclear Information System (INIS)

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

2002-01-01

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

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

International Nuclear Information System (INIS)

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

1984-12-01

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

Treatment of contaminated waste plastics material

International Nuclear Information System (INIS)

Sims, J.; Hitchcock, J.W.

1984-01-01

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

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

International Nuclear Information System (INIS)

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

2005-01-01

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

Management of radioactive wastes produced by users of radioactive materials

International Nuclear Information System (INIS)

1985-01-01

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

Diffusive flux of PAHs across sediment-water and water-air interfaces at urban superfund sites.

Science.gov (United States)

Minick, D James; Anderson, Kim A

2017-09-01

Superfund sites may be a source of polycyclic aromatic hydrocarbons (PAHs) to the surrounding environment. These sites can also act as PAH sinks from present-day anthropogenic activities, especially in urban locations. Understanding PAH transport across environmental compartments helps to define the relative contributions of these sources and is therefore important for informing remedial and management decisions. In the present study, paired passive samplers were co-deployed at sediment-water and water-air interfaces within the Portland Harbor Superfund Site and the McCormick and Baxter Superfund Site. These sites, located along the Willamette River (Portland, OR, USA), have PAH contamination from both legacy and modern sources. Diffusive flux calculations indicate that the Willamette River acts predominantly as a sink for low molecular weight PAHs from both the sediment and the air. The sediment was also predominantly a source of 4- and 5-ring PAHs to the river, and the river was a source of these same PAHs to the air, indicating that legacy pollution may be contributing to PAH exposure for residents of the Portland urban center. At the remediated McCormick and Baxter Superfund Site, flux measurements highlight locations within the sand and rock sediment cap where contaminant breakthrough is occurring. Environ Toxicol Chem 2017;36:2281-2289. © 2017 SETAC. © 2017 SETAC.

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

International Nuclear Information System (INIS)

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

1983-01-01

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

Electrochemical peroxidation of PCBs and VOCs in superfund site water and sediments

Energy Technology Data Exchange (ETDEWEB)

Scrudato, R.J.; Chiarenzelli, J.R. [SUNY, Oswego, NY (United States)

1996-12-31

An electrochemical peroxidation (ECP) process has been developed and used to degrade polychlorinated biphenyls (PCB) and volatile organic compounds (VOC)-contaminated water, sludge, and sediments at a New York State Federal and State Superfund Site. The process involves passing an oscillating low-amperage (<10 amps) current through steel electrodes immersed in an acidified water or sediment slurry into which hydrogen peroxide (<1,000 ppm) is added. The generated free radicals attack organic compounds, including organo-metallic complexes and refractory compounds including PCBs. PCB degradation ranged from about 30% to 80% in experiments involving Federal Superfund Site sediments; total PCBs were reduced by {approximately}97% to 68%, respectively, in water and slurry collected from a State Superfund subsurface storage tank. VOC bench-scale experiments involved chloroethane, 1,1-dichloroethane, dichloromethane, 1,1,1-trichloroethane, and acetone and after a 3-min ECP treatment, degradation ranged from >94% to about 99.9%. Results indicate the ECP is a viable process to degrade organic contaminants in water and sediment suspensions. Because the treated water suspensions are acidified, select trace metal sorbed to the particulates is solubilized and therefore can be segregated from the particulates, offering a process that simultaneously degrades organic contaminants and separates trace metals. 19 refs., 1 fig., 4 tabs.

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

International Nuclear Information System (INIS)

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

2015-01-01

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

Materials evaluation programs at the Defense Waste Processing Facility

International Nuclear Information System (INIS)

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

1992-01-01

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

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

Directory of Open Access Journals (Sweden)

Hamza Ali

2017-01-01

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

Heterogeneous redox conditions, arsenic mobility, and groundwater flow in a fractured-rock aquifer near a waste repository site in New Hampshire, USA

Science.gov (United States)

Anthropogenic sources of carbon from landfill or waste leachate can promote reductive dissolution of in situ arsenic (As) and enhance the mobility of As in groundwater. Groundwater from residential-supply wells in a fractured crystalline-rock aquifer adjacent to a Superfund site ...

Environmentally sound management of hazardous waste and hazardous recyclable materials

International Nuclear Information System (INIS)

Smyth, T.

2002-01-01

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

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

International Nuclear Information System (INIS)

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

2012-01-01

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

Radiation effects on ion exchange materials used in waste management

International Nuclear Information System (INIS)

Pillay, K.K.S.

1982-01-01

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

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

International Nuclear Information System (INIS)

2009-01-01

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

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

International Nuclear Information System (INIS)

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

2013-10-01

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

CERCLA and RCRA requirements affecting cleanup of a hazardous waste management unit at a Superfund site: A case study

International Nuclear Information System (INIS)

Walsh, T.J.

1995-03-01

The Fernald Environmental Management Project (FEMP) attempted to address both RCRA and CERCLA requirements at the fire training facility (FTF) by integrating a CERCLA removal action work plan with a RCRA closure plan. While the regulatory agencies involved with the FTF cleanup agreed the integrated document was a good idea, implementation proved complicated, owing to disposition of clean debris from a Superfund site, treatment of contaminated media, duration of cleanup activities, and cleanup certification. While all the complications have not been resolved, solutions to all have been proposed to Ohio EPA and U.S. EPA. Both agencies have worked closely with FEMP to find the most effective fulfillment of RCRA and CERCLA requirements

Qualification test of packages for transporting radioactive materials and wastes

International Nuclear Information System (INIS)

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

1990-01-01

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

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

International Nuclear Information System (INIS)

Otsuka, Yoshiki; Banba, Tsunetaka

2007-09-01

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

Recovering energy and materials from hazardous waste

Energy Technology Data Exchange (ETDEWEB)

Anon.

2003-12-01

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

Permanent disposal of radioactive particulate waste in cartridge containing ferromagnetic material

International Nuclear Information System (INIS)

Troy, M.

1986-01-01

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

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

International Nuclear Information System (INIS)

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

1984-10-01

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

Potential applications of nanostructured materials in nuclear waste management.

Energy Technology Data Exchange (ETDEWEB)

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

2003-09-01

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

Ensuring the adequacy of cost share provisions in superfund state contracts. Directive

International Nuclear Information System (INIS)

1993-01-01

The memorandum requests regional offices to re-examine existing Superfund State Contracts (SSCs) for Fund-financed remedial actions to verify that they adequately reflect incurred and projected remedial action costs

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

International Nuclear Information System (INIS)

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

1997-01-01

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

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

International Nuclear Information System (INIS)

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

1992-01-01

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

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

International Nuclear Information System (INIS)

Plecas, I.

1995-01-01

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

Handbook of solid waste disposal: materials and energy recovery

Energy Technology Data Exchange (ETDEWEB)

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

1975-01-01

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

Apparatus and method for treating waste material

International Nuclear Information System (INIS)

Allison, W.

1981-01-01

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

Radiolytic gas generation in plutonium contaminated waste materials

International Nuclear Information System (INIS)

Kazanjian, A.R.

1976-01-01

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

Technology needs and trends for hazardous waste site remediation

International Nuclear Information System (INIS)

Kovalick, W.W. Jr.

1995-01-01

Over the next few decades, federal, state, and local governments and private industry will commit billions of dollars annually to clean up sites contaminated with hazardous waste and petroleum products. While these needs represent an obligation for society, they also represent an important business opportunity for vendors of remediation services. This presentation assesses the remediation market by characterizing sites that comprise the demand for cleanup services, observing remedy selection trends in the Superfund program, and discussing gaps in the supply of technologies

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

International Nuclear Information System (INIS)

Temus, C.J.

1987-01-01

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

Plant waste materials from restaurants as the adsorbents for dyes

Directory of Open Access Journals (Sweden)

Pavlović Marija D.

2015-01-01

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

Bentonite as a waste isolation pilot plant shaft sealing material

International Nuclear Information System (INIS)

Daemen, J.; Ran, Chongwei

1996-12-01

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

Bentonite as a waste isolation pilot plant shaft sealing material

Energy Technology Data Exchange (ETDEWEB)

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

1996-12-01

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

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

OpenAIRE

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

2017-01-01

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

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

International Nuclear Information System (INIS)

DUTZER, Michel; Rives, Jean Francois

2014-01-01

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

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

International Nuclear Information System (INIS)

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

2013-01-01

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

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

Science.gov (United States)

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

2013-01-01

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

Regulatory barriers to hazardous waste technology innovation

International Nuclear Information System (INIS)

Kuusinen, T.L.; Siegel, M.R.

1991-02-01

The primary federal regulatory programs that influence the development of new technology for hazardous waste are the Resource Conservation and Recovery Act (RCRA) and the Comprehensive Environmental Response, Compensation and Liability Act (CERCLA, also commonly known as Superfund). Two important aspects of RCRA that can create barriers to hazardous waste technology innovation are technology-based waste pre-treatment standards and a cumbersome permitting program. By choosing a technology-based approach to the RCRA land disposal restrictions program, the US Environmental Protection Agency (EPA) has simultaneously created tremendous demand for the technologies specified in its regulations, while at the same time significantly reduced incentives for technology innovation that might have otherwise existed. Also, the RCRA hazardous waste permitting process can take years and cost hundreds of thousands of dollars. The natural tendency of permit writers to be cautious of unproven (i.e., innovative) technology also can create a barrier to deployment of new technologies. EPA has created several permitting innovations, however, to attempt to mitigate this latter barrier. Understanding the constraints of these permitting innovations can be important to the success of hazardous waste technology development programs. 3 refs

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

Science.gov (United States)

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

2018-03-01

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

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

Science.gov (United States)

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

2015-10-01

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

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

Directory of Open Access Journals (Sweden)

Cuizhen Xue

2016-01-01

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

Textural development and hydrogen adsorption of carbon materials from PET waste

International Nuclear Information System (INIS)

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

2004-01-01

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

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

International Nuclear Information System (INIS)

2017-01-01

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

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

International Nuclear Information System (INIS)

2016-12-01

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

Graphite matrix materials for nuclear waste isolation

International Nuclear Information System (INIS)

Morgan, W.C.

1981-06-01

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

Positive utilization of waste materials from mines and quarries

International Nuclear Information System (INIS)

Blunden, J.R.

1980-01-01

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

Method of encapsulating solid radioactive waste material for storage

International Nuclear Information System (INIS)

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

1976-01-01

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

Processing agricultural and industrial waste materials to fodder

Energy Technology Data Exchange (ETDEWEB)

Varga, J; Baintner, F; Schmidt, J

1977-11-28

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

Hydrothermal carbonization of food waste and associated packaging materials for energy source generation.

Science.gov (United States)

Li, Liang; Diederick, Ryan; Flora, Joseph R V; Berge, Nicole D

2013-11-01

Hydrothermal carbonization (HTC) is a thermal conversion technique that converts food wastes and associated packaging materials to a valuable, energy-rich resource. Food waste collected from local restaurants was carbonized over time at different temperatures (225, 250 and 275°C) and solids concentrations to determine how process conditions influence carbonization product properties and composition. Experiments were also conducted to determine the influence of packaging material on food waste carbonization. Results indicate the majority of initial carbon remains integrated within the solid-phase at the solids concentrations and reaction temperatures evaluated. Initial solids concentration influences carbon distribution because of increased compound solubilization, while changes in reaction temperature imparted little change on carbon distribution. The presence of packaging materials significantly influences the energy content of the recovered solids. As the proportion of packaging materials increase, the energy content of recovered solids decreases because of the low energetic retention associated with the packaging materials. HTC results in net positive energy balances at all conditions, except at a 5% (dry wt.) solids concentration. Carbonization of food waste and associated packaging materials also results in net positive balances, but energy needs for solids post-processing are significant. Advantages associated with carbonization are not fully realized when only evaluating process energetics. A more detailed life cycle assessment is needed for a more complete comparison of processes. Copyright © 2013 Elsevier Ltd. All rights reserved.

PRODUCTION OF AN INSULATION MATERIAL FROM CARPET AND BORON WASTES

Directory of Open Access Journals (Sweden)

Yasin ERDOĞAN

2016-12-01

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

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

International Nuclear Information System (INIS)

Wilkins, J.D.

1988-02-01

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

The useful application of sulphur-bound waste materials

NARCIS (Netherlands)

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

1996-01-01

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

Hazardous materials management and compliance training

International Nuclear Information System (INIS)

Dalton, T.F.

1991-01-01

OSHA training for hazardous waste site workers is required by the Superfund Amendments and Reauthorization Act of 1986 (SARA). In December 1986, a series of regulations was promulgated by OSHA on an interim basis calling for the training of workers engaged in hazardous waste operations. Subsequent to these interim regulations, final rules were promulgated and these final rules on hazardous waste operations and emergency response became effective on March 6, 1990. OSHA has conducted hearings on the accreditation of training programs. OSHA would like to follow the accreditation process under the AHERA regulations for asbestos, in which the model plan for accreditation of asbestos abatement training was included in Section 206 of Title 11 of the Toxic Substance Control Act (TSCA). OSHA proposed on January 26, 1990, to perform the accreditation of training programs for hazardous waste operations and that proposal suggested that they follow the model plan similar to the one used for AHERA. They did not propose to accredited training programs for workers engaged in emergency response. These new regulations pose a significant problem to the various contractors and emergency responders who deal with hazardous materials spill response, cleanup and site remediation since these programs have expanded so quickly that many people are not familiar with what particular segment of the training they are required to have and whether or not programs that have yet to be accredited are satisfactory for this type of training. Title III of SARA stipulates a training program for first responders which includes local emergency response organizations such as firemen and policemen. The purpose of this paper is to discuss the needs of workers at hazardous waste site remediation projects and workers who are dealing with hazardous substances, spill response and cleanup

Using thermal power plants waste for building materials

Science.gov (United States)

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

2017-10-01

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

Co-combustion of waste materials using fluidized bed technology

Energy Technology Data Exchange (ETDEWEB)

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

2004-07-01

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

Gas generation by self-radiolysis of tritiated waste materials

International Nuclear Information System (INIS)

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

1980-01-01

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

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

International Nuclear Information System (INIS)

Norazli Othman; Nor Ezlin Ahmad Basri; Lariyah Mohd Sidek

2009-01-01

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

Textural development and hydrogen adsorption of carbon materials from PET waste

Energy Technology Data Exchange (ETDEWEB)

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

2004-10-06

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

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

International Nuclear Information System (INIS)

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

2009-01-01

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

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

CERN Document Server

American Society for Testing and Materials. Philadelphia

2007-01-01

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

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

International Nuclear Information System (INIS)

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

1979-11-01

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

Waste management, waste resource facilities and waste conversion processes

International Nuclear Information System (INIS)

Demirbas, Ayhan

2011-01-01

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

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

International Nuclear Information System (INIS)

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

2010-01-01

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

DOE materials program supporting immobilization of radioactive wastes

International Nuclear Information System (INIS)

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

1979-01-01

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

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

Energy Technology Data Exchange (ETDEWEB)

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

2016-07-01

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

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

International Nuclear Information System (INIS)

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

2016-01-01

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

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

Science.gov (United States)

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

2012-05-01

Pyrolysis may be an alternative for the reclamation of rejected streams of waste from sorting plants where packing and packaging plastic waste is separated and classified. These rejected streams consist of many different materials (e.g., polyethylene (PE), polypropylene (PP), polystyrene (PS), polyvinyl chloride (PVC), polyethylene terephthalate (PET), acrylonitrile butadiene styrene (ABS), aluminum, tetra-brik, and film) for which an attempt at complete separation is not technically possible or economically viable, and they are typically sent to landfills or incinerators. For this study, a simulated plastic mixture and a real waste sample from a sorting plant were pyrolyzed using a non-stirred semi-batch reactor. Red mud, a byproduct of the aluminum industry, was used as a catalyst. Despite the fact that the samples had a similar volume of material, there were noteworthy differences in the pyrolysis yields. The real waste sample resulted, after pyrolysis, in higher gas and solid yields and consequently produced less liquid. There were also significant differences noted in the compositions of the compared pyrolysis products. Copyright © 2011 Elsevier Ltd. All rights reserved.

Hazardous materials transportation. Part 2. Radioactive materials and wastes (citations from the NTIS Data Base). Final report for 1964--March 1978

International Nuclear Information System (INIS)

Reimherr, G.W.

1978-06-01

The bibliography cites studies on the hazards, risks, and uncertainty of transporting radioactive wastes and materials. The design of shipping containers and special labels for identification purposes for transporting fuels and wastes are also cited. Studies are included on legislation dealing with the safety and health of the population and the environmental problems associated with transporting radioactive materials

Estimation of global inventories of radioactive waste and other radioactive materials

International Nuclear Information System (INIS)

2008-06-01

A variety of nuclear activities have been carried out in the second part of the twentieth century for different purposes. Initially the emphasis was on military applications, but with the passage of time the main focus of nuclear activities has shifted to peaceful uses of nuclear energy and to the use of radioactive material in industry, medicine and research. Regardless of the objectives, the nuclear activities generate radioactive waste. It was considered worthwhile to produce a set of worldwide data that could be assessed to evaluate the legacy of the nuclear activities performed up to the transition between the twentieth and the twenty first century. The assessment tries to cover the inventory of all the human produced radioactive material that can be considered to result from both military and civilian applications. This has caused remarkable difficulties since much of the data, particularly relating to military programmes, are not readily available. Consequently the data on the inventory of radioactive material should be considered as order-of-magnitude approximations. This report as a whole should be considered as a first iteration in a continuing process of updating and upgrading. The accumulations of radioactive materials can be considered a burden for human society, both at present and in the future, since they require continuing monitoring and control. Knowing the amounts and types of such radioactive inventories can help in the assessment of the relative burdens. Knowledge of the national or regional radioactive waste inventory is necessary for planning management operations, including the sizing and design of conditioning, storage and disposal facilities. A global inventory, either of radioactive waste or of other environmental accumulations of radioactive material, could be used to provide a perspective on the requirements and burdens associated with their management, by means of comparisons with the burdens caused by other types of waste or other

Assessing Technical and Programmatic Viability of Nuclear Waste and Material Stream Disposition Plans

International Nuclear Information System (INIS)

R. S. Hill; B. Griebenow

1999-01-01

The U.S. Department of Energy (DOE), Office of Environmental Management (EM) has responsibility for cleanup and disposition of nuclear wastes and excess materials that are a legacy of the nuclear arms race. In fulfilling this responsibility, EM applies a systems engineering approach to identify baseline disposition plans for the wastes and materials (storage, stabilization, treatment, and disposal), assess the path viability, and develop integration opportunities to improve the disposition viability or to combine, eliminate, and/or simplify activities, technologies, and facilities across the DOE Complex, evaluate the baseline and alternatives to make informed decisions, and implement and track selected opportunities. This paper focuses on processes used to assess the disposition path viability - the likelihood that current planning for disposition of nuclear waste and materials can be implemented

Private-Sector Cleanup Expenditures and Transaction Costs at 18 Superfund Sites (1993)

Science.gov (United States)

Superfund allows the government either to clean up a site and recover its cost from the potentially responsible parties (PRPs) or to require the PRPs to undertake the cleanup themselves. This study examines private-sector expenditures and transaction-costs

A Strategy for Quantifying Radioactive Material in a Low-Level Waste Incineration Facility

International Nuclear Information System (INIS)

Hochel, R.C.

1997-03-01

One of the methods proposed by the U.S. Department of Energy (DOE) for the volume reduction and stabilization of a variety of low-level radioactive wastes (LLW) is incineration. Many commercial incinerators are in operation treating both non-hazardous and hazardous wastes. These can obtain volume reductions factors of 50 or more for certain wastes, and produce a waste (ash) that can be easily stabilized if necessary by vitrification or cementation. However, there are few incinerators designed to accommodate radioactive wastes. One has been recently built at the Savannah River Site (SRS) near Aiken, SC and is burning non-radioactive hazardous waste and radioactive wastes in successive campaigns. The SRS Consolidated Incineration Facility (CIF) is RCRA permitted as a Low Chemical Hazard, Radiological facility as defined by DOE criteria (Ref. 1). Accordingly, the CIF must operate within specified chemical, radionuclide, and fissile material inventory limits (Ref. 2). The radionuclide and fissile material limits are unique to radiological or nuclear facilities, and require special measurement and removal strategies to assure compliance, and the CIF may be required to shut down periodically in order to clean out the radionuclide inventory which builds up in various parts of the facility

Mass, energy and material balances of SRF production process. Part 2: SRF produced from construction and demolition waste.

Science.gov (United States)

Nasrullah, Muhammad; Vainikka, Pasi; Hannula, Janne; Hurme, Markku; Kärki, Janne

2014-11-01

In this work, the fraction of construction and demolition waste (C&D waste) complicated and economically not feasible to sort out for recycling purposes is used to produce solid recovered fuel (SRF) through mechanical treatment (MT). The paper presents the mass, energy and material balances of this SRF production process. All the process streams (input and output) produced in MT waste sorting plant to produce SRF from C&D waste are sampled and treated according to CEN standard methods for SRF. Proximate and ultimate analysis of these streams is performed and their composition is determined. Based on this analysis and composition of process streams their mass, energy and material balances are established for SRF production process. By mass balance means the overall mass flow of input waste material stream in the various output streams and material balances mean the mass flow of components of input waste material stream (such as paper and cardboard, wood, plastic (soft), plastic (hard), textile and rubber) in the various output streams of SRF production process. The results from mass balance of SRF production process showed that of the total input C&D waste material to MT waste sorting plant, 44% was recovered in the form of SRF, 5% as ferrous metal, 1% as non-ferrous metal, and 28% was sorted out as fine fraction, 18% as reject material and 4% as heavy fraction. The energy balance of this SRF production process showed that of the total input energy content of C&D waste material to MT waste sorting plant, 74% was recovered in the form of SRF, 16% belonged to the reject material and rest 10% belonged to the streams of fine fraction and heavy fraction. From the material balances of this process, mass fractions of plastic (soft), paper and cardboard, wood and plastic (hard) recovered in the SRF stream were 84%, 82%, 72% and 68% respectively of their input masses to MT plant. A high mass fraction of plastic (PVC) and rubber material was found in the reject material

ECONOMIC AND LEGAL ASPECTS OF MANAGEMENT OF WASTES AND SECONDARY MATERIAL RESOURCES (ON THE EXAMPLE OF CONSTRUCTION COMPLEX

Directory of Open Access Journals (Sweden)

Tskhovrebov Eduard Stanislavovich

2018-05-01

Full Text Available Subject: technical and economic processes and aspects of handling wastes and secondary material resources; stages of transition of anthropogenic object of environment to wastes and secondary material resources; technical possibility and economic feasibility of using secondary material resources as a secondary raw material for making products, providing energy, works, services. The problem of economy and rational use of material and power resources is relevant and significant within the limits of maintenance of a strategic course of Russia on innovative sustainable development. In this article, issues of actualization and harmonization of the regulatory and legal base in the field of management of wastes and secondary material resources are considered from the viewpoint of maintenance of minimization of waste formation and maximum use of secondary material resources in an industrial-economic cycle, provision of economic incentives for innovative activity in the given field. The actual multi-plan problem, chosen here as a topic of research, concerns regulations in management of wastes and secondary material resources in construction complex, in which economic, civil-law, ecological, social, industrial and legal relations are closely coordinated and define a subject of the present research. Production and consumption waste is a dangerous anthropogenic object of the environment but at the same time, it is a valuable secondary material resource. The non-use of wastes to be recycled as secondary raw materials for energy generation, production and, as a result, their increasing accumulation in the environment causes irreparable harm to natural objects and human health due to their dangerous properties. Research objectives: scientific and methodological substantiation of legal regulation, economic basis for formation of wastes and secondary material resources management system (on the example of construction complex and building materials industry

Optimization Evaluation: Lee Chemical Superfund Site, City Of Liberty, Clay County, Missouri

Science.gov (United States)

The Lee Chemical Superfund Site (site) is located along Missouri Highway 210 in Liberty, Missouri, approximately 15 miles east of Kansas City, Missouri. Currently, the site is a vacant lot of approximately2.5 acres in a flat alluvial plain.

Reuse of materials from recyclable-waste collection for road building

International Nuclear Information System (INIS)

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

2006-01-01

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

Preparations for Retrieval of Buried Waste at Material Disposal Area B

International Nuclear Information System (INIS)

Chaloupka, A.B.; Criswell, C.W.; Goldberg, M.S.; Gregory, D.R.; Worth, E.P.

2009-01-01

Material Disposal Area B, a hazard category 3 nuclear facility, is scheduled for excavation and the removal of its contents. Wastes and excavated soils will be characterized for disposal at approved off-site waste disposal facilities. Since there were no waste disposal records, understanding the context of the historic operations at MDA B was essential to understanding what wastes were disposed of and what hazards these would pose during retrieval. The operational history of MDA B is tied to the earliest history of the Laboratory, the scope and urgency of World War II, the transition to the Atomic Energy Commission in January 1947, and the start of the cold war. A report was compiled that summarized the development of the process chemistry, metallurgy, and other research and production activities at the Laboratory during the 1944 to 1948 time frame that provided a perspective of the work conducted; the scale of those processes; and the handling of spent chemicals and contaminated items in lieu of waste disposal records. By 1947, all laboratories had established waste disposal procedures that required laboratory and salvage wastes to be boxed and sealed. Large items or equipment were to be wrapped with paper or placed in wooden crates. Most wastes were placed in cardboard boxes and were simply piled into the active trench. Bulldozers were used to cover the material with fill dirt on a weekly basis. No effort was made to separate waste types or loads, or to compact the wastes under the soil cover. Using the historical information and a statistical analysis of the plutonium inventory, LANL prepared a documented safety analysis for the waste retrieval activities at MDA B, in accordance with DOE Standard 1120-2005, Integration of Environment, Safety, and Health into Facility Disposition Activities, and the provisions of 29 CFR 1910.120, Hazardous Waste Operations and Emergency Response. The selected hazard controls for the MDA B project consist of passive design