Advanced technologies for decontamination and conversion of scrap metal

International Nuclear Information System (INIS)

Valerie MacNair; Steve Sarten; Thomas Muth; Brajendra Mishra

1999-01-01

The Department of Energy (DOE) faces the task of decommissioning much of the vast US weapons complex. One challenge of this effort includes the disposition of large amounts of radioactively contaminated scrap metal (RSM) including but not limited to steel, nickel, copper, and aluminum. The decontamination and recycling of RSM has become a key element in the DOE's strategy for cleanup of contaminated sites and facilities. Recycling helps to offset the cost of decommissioning and saves valuable space in the waste disposal facilities. It also reduces the amount of environmental effects associated with mining new metals. Work on this project is geared toward finding decontamination and/or recycling alternatives for the RSM contained in the decommissioned gaseous diffusion plants including approximately 40,000 tons of nickel. The nickel is contaminated with Technetium-99, and is difficult to remove using traditional decontamination technologies. The project, titled ''Advanced Technologies for Decontamination and Conversion of Scrap Metal'' was proposed as a four phase project. Phase 1 and 2 are complete and Phase 3 will complete May 31, 1999. Stainless steel made from contaminated nickel barrier was successfully produced in Phase 1. An economic evaluation was performed and a market study of potential products from the recycled metal was completed. Inducto-slag refining, after extensive testing, was eliminated as an alternative to remove technetium contamination from nickel. Phase 2 included successful lab scale and pilot scale demonstrations of electrorefining to separate technetium from nickel. This effort included a survey of available technologies to detect technetium in volumetrically contaminated metals. A new process to make sanitary drums from RSM was developed and implemented. Phase 3 included a full scale demonstration of electrorefining, an evaluation of electro-refining alternatives including direct dissolution, melting of nickel into anodes, a laser cutting

System for Prevention, Detection and Response to Radioactive Materials in Scrap Metal in Ukraine

Energy Technology Data Exchange (ETDEWEB)

Makarovska, O., E-mail: makarovska@hq.snrc.gov.ua [State Nuclear Regulatory Committee of Ukraine, Kiev (Ukraine)

2011-07-15

The State control system to prevent, detect and respond to cases of radioactive material in scrap metal is functioning in Ukraine. The system includes regulations for the safe and secure management of metal scrap and administrative and technical measures to prevent, detect and respond to cases of radioactive material in scrap metal. The key elements of prevention are the system of licensing and supervision in the sphere of radioactive material use and the State system for inventory, registration and control of radiation sources. Metal scrap management is licensed by the Ministry of Industrial Policy and one of the licence conditions is radiation control of the scrap metal. State supervision of the operations with metal scrap is provided by Ministry of Health and Ministry of Environmental Protection according to the regulation 'State sanitary-ecological standard for metal scrap management'. Specific standards exist for the export of metal scrap. Export consignments are followed by a certificate that proves the radiological safety of the metal. Ukrainian metallurgical plants provide an input radiation control of metal scrap and an output control of the produced metal. Thus, there exists a five barrier system of metal scrap control: border control; exclusion zone perimeter control; metal scrap dealers control; metallurgical plants (input control and output control of produced metal); and export consignments radiological certification. To regain control over orphan sources (including occasional radioactive material in the scrap metal) the 'procedure for interaction of executive authorities and involved legal entities in case of revealing of radiation sources in no legal use' was approved by a Resolution of the Cabinet of Ministers of Ukraine. The investigation of each case with feedback, information of involved bodies, safe and secure storage of restored radioactive material are provided according to this procedure. (author)

Management options for recycling radioactive scrap metals

Energy Technology Data Exchange (ETDEWEB)

Dehmel, J.C.; MacKinney, J.; Bartlett, J.

1997-02-01

The feasibility and advantages of recycling radioactive scrap metals (RSM) have yet to be assessed, given the unique technical, regulatory, safety, and cost-benefit issues that have already been raised by a concerned recycling industry. As is known, this industry has been repeatedly involved with the accidental recycling of radioactive sources and, in some cases, with costly consequences. If recycling were deemed to be a viable option, it might have to be implemented with regulatory monitoring and controls. Its implementation may have to consider various and complex issues and address the requirements and concerns of distinctly different industries. There are three basic options for the recycling of such scraps. They are: (1) recycling through the existing network of metal-scrap dealers and brokers, (2) recycling directly and only with specific steelmills, or (3) recycling through regional processing centers. Under the first option, scrap dealers and brokers would receive material from RSM generators and determine at which steelmills such scraps would be recycled. For the second option, RSM generators would deal directly with selected steelmills under specific agreements. For the third option, generators would ship scraps only to regional centers for processing and shipment to participating steelmills. This paper addresses the potential advantages of each option, identifies the types of arrangements that would need to be secured among all parties, and attempts to assess the receptivity of the recycling industry to each option.

Management of radioactive scrap metal at SCK-CEN

International Nuclear Information System (INIS)

Noynaert, L.; Klein, M.; Cornelissen, R.; Ponnet, M.

2000-01-01

The environmental concern and public perception as well as the steadily increase of the conditioning and disposal costs are pushing the nuclear sector to minimise the amount of radioactive waste. Hence it is a strong incentive to prefer the management option 'recycling and reuse' instead of the option 'disposal and replacement'. The 'recycling and reuse' option requires the availability of decontamination techniques as well as measuring techniques allowing to prove that the release criteria are met. Therefore SCK-CEN has now two decontamination installations for scrap metal on its own site. One installation uses a wet abrasive technique while the other one uses a chemical process based on the Ce 4+ . These two installations, combined with the use of foundries for free release or for radioactive scrap metal recycling are now common practices at SCK-CEN and will allow to reduce the metallic waste to 10% of the metallic scrap production and the costs at least by a factor 2.5. (author)

Advanced technologies for decomtamination and conversion of scrap metal

Energy Technology Data Exchange (ETDEWEB)

Valerie MacNair; Steve Sarten; Thomas Muth; Brajendra Mishra

1999-05-27

The Department of Energy (DOE) faces the task of decommissioning much of the vast US weapons complex. One challenge of this effort includes the disposition of large amounts of radioactively contaminated scrap metal (RSM) including but not limited to steel, nickel, copper, and aluminum. The decontamination and recycling of RSM has become a key element in the DOE's strategy for cleanup of contaminated sites and facilities. Recycling helps to offset the cost of decommissioning and saves valuable space in the waste disposal facilities. It also reduces the amount of environmental effects associated with mining new metals. Work on this project is geared toward finding decontamination and/or recycling alternatives for the RSM contained in the decommissioned gaseous diffusion plants including approximately 40,000 tons of nickel. The nickel is contaminated with Technetium-99, and is difficult to remove using traditional decontamination technologies. The project, titled ``Advanced Technologies for Decontamination and Conversion of Scrap Metal'' was proposed as a four phase project. Phase 1 and 2 are complete and Phase 3 will complete May 31, 1999. Stainless steel made from contaminated nickel barrier was successfully produced in Phase 1. An economic evaluation was performed and a market study of potential products from the recycled metal was completed. Inducto-slag refining, after extensive testing, was eliminated as an alternative to remove technetium contamination from nickel. Phase 2 included successful lab scale and pilot scale demonstrations of electrorefining to separate technetium from nickel. This effort included a survey of available technologies to detect technetium in volumetrically contaminated metals. A new process to make sanitary drums from RSM was developed and implemented. Phase 3 included a full scale demonstration of electrorefining, an evaluation of electro-refining alternatives including direct dissolution, melting of nickel into anodes, a

40 CFR 63.10885 - What are my management practices for metallic scrap and mercury switches?

Science.gov (United States)

2010-07-01

... minimize the presence of mercury in scrap from end-of-life vehicles. (3) Option for specialty metal scrap... metallic scrap and mercury switches? 63.10885 Section 63.10885 Protection of Environment ENVIRONMENTAL... Affected Sources § 63.10885 What are my management practices for metallic scrap and mercury switches? (a...

Radioactive materials in scrap metal, the situation in Switzerland

International Nuclear Information System (INIS)

Jossen, H.

2005-01-01

About 10 years ago, different happenings in the Swiss and international metal scrap recycling scene created a sensibility to unwanted radioactive substances in scrap metal. Italy, one of the main buyers for scrap metals, started at its borders with systematic checks, arranged by authorities. As a consequence, in Switzerland a concept was elaborated under cooperation of the recycling companies, the Italian authorities, the Federal Office of Public Health (BAG), Swiss Federal Nuclear Safety Inspectorate (HSK) and the Swiss National Accident Insurance Fund (Suva) to fulfil the different requirements. Individual radioprotection, protection of environment, protection of work yard and machinery and the quality assurance of the recycled metals and the resulting products requires adapted solutions with the main issues: training, suitable measuring equipment and an intervention-and waste management. Detected radioactive substances are professionally recovered, stored and submitted to the radioactive waste collection. The investigation of the happenings can lead to useful hints on gaps and on chances for improvements in general radioprotection. (orig.)

Radiation protection aspects in importing metallic scraps

International Nuclear Information System (INIS)

Risica, S.; Di Ciaccio, P.

1996-09-01

The meeting deals with radiation protection problems caused by the possibility that radioactive metal scraps or radioactive sources hidden in the scraps, may arrive in a foundry. The importance of this issue and of rational and systematic solutions is showed by several accidents, happened in the past in numerous countries, by many signals in Italy and by some papers published in international scientific journals or reports issued by authorities and institutions in different countries

Feasibility study of a portable smelter for scrap metals

International Nuclear Information System (INIS)

Cavendish, J.H.

1976-06-01

The use of a portable smelter to process uranium-contaminated scrap metals was studied. Objectives were to convert scrap metal located at many diverse sites into a form which would be suitable for unlicensed sale and reduce the problems associated with storing the scrap. The Foundry Design Company study indicated the portable smelter concept was feasible from an equipment and transportation standpoint. Capital costs for a 5-ton/hour (steel) nominal capacity unit were estimated to be $2,349,000. Technical evaluation indicates that all the common metals considered, i.e., iron, nickel, copper, and aluminum, are amenable to uranium decontamination by smelting except aluminum. An economic evaluation of the processing of the 30,000 tons of steel scrap to be generated by the Cascade Improvement Program by a portable smelter was made based upon information supplied by Foundry Design Company, plus the assumption that the product metal could be sold for $120.00 per ton. This evaluation indicated a net return of $2,424,000 to the government could be realized. The Health and Safety study indicated no major problems of this nature would be encountered in operating a portable smelter. The legal review indicated the proposed operation fell within the authority of existing regulations. Consideration of possible conflicts with regard to competition with the private sector was suggested

Recycled scrap metal and soils/debris with low radioactive contents

International Nuclear Information System (INIS)

Carriker, A.W.

1996-01-01

Two types of large volume bulk shipments of materials with low radioactivity have characteristics that complicate compliance with normal transport regulations. Scrap metal for recycling sometimes contains radioactive material that was not known or identified by the shipper prior to it being offered for transport to a scrap recycle processor. If the radioactive material is not detected before the scrap is processed, radiological and economic problems may occur. If detected before processing, the scrap metal will often be returned to the shipper. Uranium mill-tailings and contaminated soils and debris have created potential public health problems that required the movement of large volumes of bulk material to isolated safe locations. Similarly, old radium processing sites have created contamination problems needing remediation. The US Department of Transportation has issued exemptions to shippers and carriers for returning rejected scrap metal to original shippers. Other exemptions simplify transport of mill-tailings and debris from sites being remediated. These exemptions provide relief from detailed radioassay of the radioactive content in each conveyance as well as relief from the normal requirements for packaging, shipping documents, marking, labelling, and placarding which would be required for some of the shipments if the exemptions were not issued. (Author)

Recovering heavy rare earth metals from magnet scrap

Science.gov (United States)

Ott, Ryan T.; McCallum, Ralph W.; Jones, Lawrence L.

2017-08-08

A method of treating rare earth metal-bearing permanent magnet scrap, waste or other material in a manner to recover the heavy rare earth metal content separately from the light rare earth metal content. The heavy rare earth metal content can be recovered either as a heavy rare earth metal-enriched iron based alloy or as a heavy rare earth metal based alloy.

Slovenian System for Protecting Against Radioactive Material in Scrap Metal Shipments

Energy Technology Data Exchange (ETDEWEB)

Stritar, A.; Cesarek, J.; Vokal Nemec, B., E-mail: andrej.stritar@gov.si [Slovenian Nuclear Safety Administration, Ljubljana (Slovenia)

2011-07-15

The Slovenian experience shows that the majority of detected orphan sources are associated with imports of scrap metal to Slovenia and transits of that material through Slovenia. Such orphan sources originate from past industrial activities and weak regulatory control in the countries of origin. In order to minimise the number of sources outside regulatory control several regulatory and law enforcement measures have been implemented. To prevent illicit trafficking across the border the 'First line of defence' - customs and police - are equipped with radiation detection devices. Since 2002, the Slovenian Nuclear Safety Administration (SNSA) has provided a 24-hour on-duty officer, who gives advice in case of the discovery of an orphan source. The majority of scrap metal collectors and re-cyclers are equipped with portal monitors and/or hand-held radiation detection equipment. Generally, good cooperation has been established between different organizations within Slovenia, with neighbouring countries and with some international organizations. To regulate the scrap metal activities, a new Decree on checking the radioactivity of shipments of metal scrap has been in force since 1 January 2008. This decree requires that every importer has to present a certificate of radiation measurement before any shipment of scrap metal is brought into Slovenia. Such measurements can be performed only by certified organizations. These organizations can obtain certification from the SNSA providing that they have the prescribed measuring devices, adequate training and procedures, and that their capabilities have been checked by a technical support organization. The experience after one year of application of the decree is positive. Awareness, including the adequacy of response, has increased. The paper discusses the general scheme for protection against illicit radioactive material in scrap metal shipments and the Slovenian experience in the last decade. (author)

Evaluation of radioactive scrap metal recycling

International Nuclear Information System (INIS)

Nieves, L.A.; Chen, S.Y.; Kohout, E.J.; Nabelssi, B.; Tilbrook, R.W.; Wilson, S.E.

1995-12-01

This report evaluates the human health risks and environmental and socio-political impacts of options for recycling radioactive scrap metal (RSM) or disposing of and replacing it. Argonne National Laboratory (ANL) is assisting the US Department of Energy (DOE), Office of Environmental Restoration and Waste Management, Oak Ridge Programs Division, in assessing the implications of RSM management alternatives. This study is intended to support the DOE contribution to a study of metal recycling being conducted by the Task Group on Recycling and Reuse of the Organization for Economic Cooperation and Development. The focus is on evaluating the justification for the practice of recycling RSM, and the case of iron and steel scrap is used as an example in assessing the impacts. To conduct the evaluation, a considerable set of data was compiled and developed. Much of this information is included in this document to provide a source book of information

Evaluation of radioactive scrap metal recycling

Energy Technology Data Exchange (ETDEWEB)

Nieves, L.A.; Chen, S.Y.; Kohout, E.J.; Nabelssi, B.; Tilbrook, R.W.; Wilson, S.E.

1995-12-01

This report evaluates the human health risks and environmental and socio-political impacts of options for recycling radioactive scrap metal (RSM) or disposing of and replacing it. Argonne National Laboratory (ANL) is assisting the US Department of Energy (DOE), Office of Environmental Restoration and Waste Management, Oak Ridge Programs Division, in assessing the implications of RSM management alternatives. This study is intended to support the DOE contribution to a study of metal recycling being conducted by the Task Group on Recycling and Reuse of the Organization for Economic Cooperation and Development. The focus is on evaluating the justification for the practice of recycling RSM, and the case of iron and steel scrap is used as an example in assessing the impacts. To conduct the evaluation, a considerable set of data was compiled and developed. Much of this information is included in this document to provide a source book of information.

Problems concerned with scrap metal monitoring at borders

International Nuclear Information System (INIS)

Duftschmid, K.E.

1997-01-01

Since the early 1980's numerous incidents have been reported in which radioactive material or empty labelled containers for radioactive sources have been found in scrap metal. Apart from the potential health hazard to employees and the general public resulting costs for decontamination, shutdown of production and waste of products already amounted to multi-million dollar figures. Since the opening of the ''iron border'' in Europe, incidents of illicit trafficking of radioactive sources across borders and contamination of scrap metal imported from the former ''Eastern Countries'' have considerably increased, as a result of the lack of a suitable radiation protection infrastructure in some of these countries. This initiated monitoring of scrap metal transports at the borders of several European countries, such as Austria, Finland, Germany and Italy. Up to now neither universally accepted clearance levels for scrap contamination, nor an agreed standardised procedure for its control exist, although the IAEA as well as the European Commission have proposed some recommendations. As a pragmatic solution for border monitoring it is suggested to apply, as practical clearance level, a dose rate on the outside of the vehicle in the order of 0,1 μSv/h, which is approximately equivalent to double natural environmental background. This dose rate would correspond to an activity concentration for 60 Co in the order of 1 kBq/kg and therefore be in a tolerable range, even in view of products coming in close contact with the public. (author)

Advanced technologies for decontamination and conversion of scrap metal

International Nuclear Information System (INIS)

Muth, T.R.; Shasteen, K.E.; Liby, A.L.

1995-01-01

The Department of Energy (DOE) accumulated large quantities of radioactive scrap metal (RSM) through historic maintenance activities. The Decontamination and Decommissioning (D ampersand D) of major sites formerly engaged in production of nuclear materials and manufacture of nuclear weapons will generate additional quantities of RSM, as much as 3 million tons of such metal according to a recent study. The recycling of RSM is quickly becoming appreciated as a key strategy in DOE's cleanup of contaminated sites and facilities. The work described here has focused on recycle of the concentrated and high-value contaminated scrap metal resource that will arise from cleanup of DOE's gaseous diffusion plants

Advanced technologies for decontamination and conversion of scrap metal

Energy Technology Data Exchange (ETDEWEB)

Muth, T.R.; Shasteen, K.E.; Liby, A.L. [Manufacturing Sciences Corp., Oak Ridge, TN (United States)] [and others

1995-10-01

The Department of Energy (DOE) accumulated large quantities of radioactive scrap metal (RSM) through historic maintenance activities. The Decontamination and Decommissioning (D&D) of major sites formerly engaged in production of nuclear materials and manufacture of nuclear weapons will generate additional quantities of RSM, as much as 3 million tons of such metal according to a recent study. The recycling of RSM is quickly becoming appreciated as a key strategy in DOE`s cleanup of contaminated sites and facilities. The work described here has focused on recycle of the concentrated and high-value contaminated scrap metal resource that will arise from cleanup of DOE`s gaseous diffusion plants.

Control and Management of Radioactive Material Inadvertently Incorporated into Scrap Metal. Proceedings of an International Conference

International Nuclear Information System (INIS)

2011-01-01

Radioactive substances can become associated with scrap metal in various ways and if not discovered they can be incorporated into steel and non-ferrous metals through the melting process. This can cause health hazards as well as environmental concerns and there can be serious commercial implications. Numerous incidents have occurred in recent years involving the discovery of radioactive substances in scrap metal and, in some cases, in metal from the melting process. These incidents have proved to be very costly in relation to the recovery and cleanup operations required but also in terms of the potential loss of confidence of the industry in scrap metal as a resource. This has led the scrap metal industry to seek ways of managing the problem. In most countries, shipments of scrap metal are monitored but at different points in the distribution chain and to different extents and efficiencies. As yet, only limited efforts towards unifying and harmonizing monitoring strategies and methods in the context of scrap metal have been made at the international level. The Conference was organized into five sessions: the global perspective, national policies and strategies, compliance with radiological criteria, management of incidents with contaminated scrap metal, and improving confidence and protecting the interests of stakeholders. The aim of the first session was to present the views and perspectives of the different organizations concerned with radioactive material in scrap metal, scrap metal recycling, steel making, radiation source security and safety and international trade and economics. The second session covered some of the national policies and strategies being used to address the control of radioactive material that has been inadvertently incorporated into scrap metal were presented. In addition to the oral presentations, contributions describing the situation in many countries of the world in the form of posters were displayed. The many posters reporting national

Control and Management of Radioactive Material Inadvertently Incorporated into Scrap Metal. Proceedings of an International Conference

Energy Technology Data Exchange (ETDEWEB)

NONE

2011-07-15

Radioactive substances can become associated with scrap metal in various ways and if not discovered they can be incorporated into steel and non-ferrous metals through the melting process. This can cause health hazards as well as environmental concerns and there can be serious commercial implications. Numerous incidents have occurred in recent years involving the discovery of radioactive substances in scrap metal and, in some cases, in metal from the melting process. These incidents have proved to be very costly in relation to the recovery and cleanup operations required but also in terms of the potential loss of confidence of the industry in scrap metal as a resource. This has led the scrap metal industry to seek ways of managing the problem. In most countries, shipments of scrap metal are monitored but at different points in the distribution chain and to different extents and efficiencies. As yet, only limited efforts towards unifying and harmonizing monitoring strategies and methods in the context of scrap metal have been made at the international level. The Conference was organized into five sessions: the global perspective, national policies and strategies, compliance with radiological criteria, management of incidents with contaminated scrap metal, and improving confidence and protecting the interests of stakeholders. The aim of the first session was to present the views and perspectives of the different organizations concerned with radioactive material in scrap metal, scrap metal recycling, steel making, radiation source security and safety and international trade and economics. The second session covered some of the national policies and strategies being used to address the control of radioactive material that has been inadvertently incorporated into scrap metal were presented. In addition to the oral presentations, contributions describing the situation in many countries of the world in the form of posters were displayed. The many posters reporting national

Health risk and impact evaluation for recycling of radioactive scrap metal

International Nuclear Information System (INIS)

Nieves, L.A.; Chen, S.Y.; Murphie, W.E.; Lilly, M.J. III

1994-01-01

The DoE, Office of Environmental Restoration and Waste Management, is participating with the Organization for Economic Cooperation and Development in providing analytical support for developing international standards for recycling of radioactive scrap metals. For this purpose, Argonne National Laboratory is assessing health, environmental and societal implications of recycling and/or disposal process alternatives. This effort includes development of international inventory estimates for contaminated metals; investigation of international scrap metal markets; assessment of radiological and non-radiological human health risks; impacts on environmental quality and resources; and investigation of social and political factors. The RSM disposal option is being assessed with regard to the environmental and health impacts of replacing the metals if they are withdrawn from use. Impact estimates are developed for steel as an illustrative example because steel comprises a major portion of the scrap metal inventory. Current and potential sources of RSM include nuclear power plants, fuel cycle and weapons production facilities, industrial and medical facilities and equipment, and petroleum and phosphate rock extraction equipment. Millions of metric tons (t) of scrap iron and steel, stainless steel, and copper, as well as lesser quantities of aluminum, nickel, lead, and zirconium, are likely to become available in the future as these facilities are withdrawn from service

Assessment of recycling or disposal alternatives for radioactive scrap metal

International Nuclear Information System (INIS)

Murphie, W.E.; Lilly, M.J. III; Nieves, L.A.; Chen, S.Y.

1993-01-01

The US Department of Energy, Office of Environmental Restoration and Waste Management, Oak Ridge Programs Division, is participating with the Organization for Economic Cooperation and Development in providing analytical support for evaluation of management alternatives for radioactive scrap metals. For this purpose, Argonne National Laboratory is assessing environmental and societal implications of recycling and/or disposal process alternatives. This effort includes development of inventory estimates for contaminated metals; investigation of scrap metal market structure, processes, and trends; assessment of radiological and nonradiological effects of recycling; and investigation of social and political factors that are likely to either facilitate or constrain recycling opportunities. In addition, the option of scrap metal disposal is being assessed, especially with regard to the environmental and health impacts of replacing these metals if they are withdrawn from use. This paper focuses on the radiological risk assessment and dose estimate sensitivity analysis. A open-quotes tieredclose quotes concept for release categories, with and without use restrictions, is being developed. Within the tiers, different release limits may be indicated for specific groupings of radionuclides. Depending on the spectrum of radionuclides that are present and the level of residual activity after decontamination and/or smelting, the scrap may be released for unrestricted public use or for specified public uses, or it may be recycled within the nuclear industry. The conservatism of baseline dose estimates is examined, and both more realistic parameter values and protective measures for workers are suggested

Soil and groundwater contamination with heavy metals at two scrap iron and metal recycling facilities

DEFF Research Database (Denmark)

Jensen, Dorthe Lærke; Holm, P. E.; Christensen, Thomas Højlund

2000-01-01

Field studies were performed at two actual scrap iron and metal recycling facilities in order to evaluate the extent of heavy metal migration into subsoil and groundwater caused by more than 25 years of handling scrap directly on the ground without any measures to prevent leaching. Surface soil...... samples, called `scrap dirt', representing the different activities on the two recycling facilities, all showed very high concentrations of lead (Pb), copper (Cu) and zinc (Zn), high concentrations of cadmium (Cd) , chromium (Cr) and nickel (Ni) and somewhat elevated concentrations of many other metals....... In particular high concentrations were found for Pb at the car-battery salvage locations (13 to 26 g Pb kg±1) and Cu at the cable burning location (22 g Cu kg±1) at one site. The migration of metals below the surface in general (except at the car-battery salvage locations) was very limited even after...

Transboundary Movement of Radioactively Contaminated Scrap Metal - Lessons Learned

Energy Technology Data Exchange (ETDEWEB)

Nizamska, M., E-mail: m.nimzamska@bnra.bg [Emergency Planning and Preparedness Division, Bulgarian Nuclear Regulatory Agency, Sofia (Bulgaria)

2011-07-15

Starting in 1989, Bulgaria has undergone a comprehensive transformation of its economy and social conditions. Part of this process is related to the intensive privatization that started in 2001. This privatization included facilities, as well as sites that use radioactive material for different applications - industry, medicine, agriculture, science, etc. The rapid change of property ownership and, in some cases, the resulting bankruptcy, has caused difficulties in tracing and identifying radioactive sources and materials and a deterioration of the system of safety, physical protection, etc. of radioactive material. In some cases, radioactive sources were stolen because of the value of their protective containers and sold for scrap metal. This led to the occurrence of different types of radiation incidents, mainly related to the discovery of radioactive sources in scrap metal. The consequences of these incidents include the risk of radiation exposure of the workers at scrap metal yards or reprocessing facilities and of members of the public and, in addition, radioactive contamination of the environment. The Bulgarian Nuclear Regulatory Agency (BNRA) has been responding to these incidents and has carried out a series of measures to improve the control over materials (e.g. activated or surface contaminated materials) and radioactive sources and to strengthen the preventive, monitoring, emergency preparedness and mitigating measures at facility, national and transboundary levels. This paper presents an analysis of the lessons learned by the BNRA and of the control of the transboundary movement of radioactively contaminated scrap metal through the territory of Bulgaria. (author)

US Department of Energy`s weapons complex scrap metal inventory. Research report

Energy Technology Data Exchange (ETDEWEB)

Duda, J.R.

1993-07-01

Two tasks comprise the thrust of this contracted effort. Task 1 is the development of a Source List and is based on determining a list of public documents pertaining to contaminated/uncontaminated scrap metals, equipment, and other materials of value, were they not contaminated or could they be decontaminated. Task 2 is to develop an inventory of such materials from the Task 1 list of public documentation. In more detail, the Task 2 Inventory Report is based upon fulfillment of the following requirement to prepare and submit an Inventory Report based on the information obtained in the Source List. The Inventory Report shall define the type, quantity, and location of used equipment, scrap metal, and other materials existing within DOE`s system. The Inventory Report shall list: the site where the equipment, scrap metal, or other material resides; the type and size of equipment; the type and volume and/or weight of scrap metal or other material; its source; the type and level of contamination; its accessibility; the current annual rate of generation; and the projected annual rate of generation of the material.

U.S. Department of Energy National Center of Excellence for Metals Recycle

International Nuclear Information System (INIS)

Adams, V.; Bennett, M.; Bishop, L.

1998-05-01

The US Department of Energy (DOE) National Center of Excellence for Metals Recycle has recently been established. The vision of this new program is to develop a DOE culture that promotes pollution prevention by considering the recycle and reuse of metal as the first and primary disposition option and burial as a last option. The Center of Excellence takes the approach that unrestricted release of metal is the first priority because it is the most cost-effective disposition pathway. Where this is not appropriate, restricted release, beneficial reuse, and stockpile of ingots are considered. Current recycling activities include the sale of 40,000 tons of scrap metal from the East Tennessee Technology Park (formerly K-25 Plant) K-770 scrap yard, K-1064 surplus equipment and machinery, 7,000 PCB-contaminated drums, 12,000 tons of metal from the Y-l2 scrap yard, and 1,000 metal pallets. In addition, the Center of Excellence is developing a toolbox for project teams that will contain a number of specific tools to facilitate metals recycle. This Internet-based toolbox will include primers, computer programs, and case studies designed to help sites to perform life cycle analysis, perform ALARA (As Low As is Reasonably Achievable) analysis for radiation exposures, provide pollution prevention information and documentation, and produce independent government estimates. The use of these tools is described for two current activities: disposition of scrap metal in the Y-12 scrapyard, and disposition of PCB-contaminated drums

Ferrous and common nonferrous metals industries and associated scrap metals: a review

International Nuclear Information System (INIS)

Mautz, E.W.

1975-11-01

Literature on the common metals industries, scrap metal relationships, and transportation aspects has been reviewed as background information in a study to determine the feasibility of a portable melting facility for radioactively contaminated metals. This report draws substantially on government-sponsored studies. Aluminum, copper, iron and steel, and nickel metal industries are discussed from the viewpoints of the general industry characteristics, primary metal production processes, and secondary metal processing aspects. 46 references, 10 tables

U.S. Department of Energy National Center of Excellence for Metals Recycle

International Nuclear Information System (INIS)

Adams, V.; Bennett, M.; Bishop, L.

1998-06-01

The US Department of Energy (DOE) National Center of Excellence for Metals Recycle has recently been established. The vision of this new program is to develop a DOE culture that promotes pollution prevention by considering the recycle and reuse of metal as the first and primary disposition option and burial as a last option. The Center of Excellence takes the approach that unrestricted release of metal is the first priority because it is the most cost-effective disposition pathway. Where this is not appropriate, restricted release, beneficial reuse, and stockpile of ingots are considered. The Center has gotten off to a fast start. Current recycling activities include the sale of 40,000 tons of scrap metal from the East Tennessee Technology Park (formerly K-25 Plant) K-770 scrap yard, K-1064 surplus equipment and machinery, 7,000 PCB-contaminated drums, 12,000 tons of metal from the Y-12 scrap yard, and 1,000 metal pallets. In addition, the Center of Excellence is developing a toolbox for project teams that will contain a number of specific tools to facilitate metals recycle. This Internet-based toolbox will include primers, computer software, and case studies designed to help sites to perform life cycle analysis, perform ALARA (As Low As is Reasonably Achievable) analysis for radiation exposures, produce pollution prevention information and documentation, manage their materials inventory, produce independent government estimates, and implement sale/service contracts. The use of these tools is described for two current activities: disposition of scrap metal in the Y-12 scrap yard, and disposition of PCB-contaminated drums. Members of the Center look forward to working with all DOE sites, regulatory authorities, the private sector, and other stakeholders to achieve the metals recycle goals

Advanced technologies for decontamination and conversion of scrap metals

International Nuclear Information System (INIS)

Muth, T.R.; Moore, J.; Olson, D.; Mishra, B.

1994-01-01

Recycle of radioactive scrap metals (RSM) from decommissioning of DOE uranium enrichment and nuclear weapons manufacturing facilities is mandatory to recapture the value of these metals and avoid the high cost of disposal by burial. The scrap metals conversion project detailed below focuses on the contaminated nickel associated with the gaseous diffusion plants. Stainless steel can be produced in MSC's vacuum induction melting process (VIM) to the S30400 specification using nickel as an alloy constituent. Further the case alloy can be rolled in MSC's rolling mill to the mechanical property specification for S30400 demonstrating the capability to manufacture the contaminated nickel into valuable end products at a facility licensed to handle radioactive materials. Bulk removal of Technetium from scrap nickel is theoretically possible in a reasonable length of time with the high calcium fluoride flux, however the need for the high temperature creates a practical problem due to flux volatility. Bulk decontamination is possible and perhaps more desirable if nickel is alloyed with copper to lower the melting point of the alloy allowing the use of the high calcium fluoride flux. Slag decontamination processes have been suggested which have been proven technically viable at the Colorado School of Mines

Statistical treatment of hazards result from radioactive material in metal scrap

International Nuclear Information System (INIS)

Salem, E.F.; Rashad, S.M.

2013-01-01

Radioactive sources have a wide range of uses in medicine and industry. Radioactive materials entering the public domain in an uncontrolled manner may creating a serious risk of radiation exposure for workers and the public as well as excessive costs for plant decontamination and waste of product to be borne by the metal industry. This paper describes the major accidents that had happened in the last decades due to radioactive material in metal scrap, provides assessment of associated hazards and lessons learned. This will help Regulatory Authority to introduce measures capable to avoid the recurrence of similar events. The study highlights the situation for metal scrap incidents in Egypt.

Fernald scrap metal and recycling and beneficial reuse

International Nuclear Information System (INIS)

Motl, G.P.

1993-01-01

The Fernald plant, formerly known as the Feed Materials Production Facility, is located on a 1050-acre site 17 miles northwest of downtown Cincinnati, Ohio. Site construction was initiated in 1951 to fabricate uranium metal to meet defense production requirements of the U.S. Department of Energy (DOE). In October 1990, the DOE transferred management responsibility for the site from its Defense Programs organization to the Office of Environmental Restoration and Waste Management. In August 1991, the site was renamed the Fernald Environmental Management Project (FEMP) to reflect the site's new cleanup mission. During 40 yr of plant operation, a scrap metal storage area grew to contain 5000 t of scrap metal. Material in the pile, such as structural steel, crushed drums, tanks, and pipes, is contaminated with uranium to levels up to 200,000 disintegrations per minute alpha. In July 1991, cleanup of this pile was designated a CERCLA removal action under the Comprehensive Environmental Response, Compensation, and Liability Act and a consent agreement executed between the DOE and the U.S. Environmental Protection Agency

Recycle and reuse of radioactive scrap metals within the department of energy

International Nuclear Information System (INIS)

Adams, V.; Murphie, W.; Gresalfi, M.

2000-01-01

The United States Department of Energy (DOE) National Center of Excellence for Metals Recycle (NMR) is pursuing recycle and reuse alternatives to burial of radioactive scrap metal. This approach is being implemented in a safe and environmentally sound manner, while significantly lowering dis-positioning cost and accelerating cleanup activities. This paper will define the NMR's success to date in promoting safe and cost effective recycle and reuse strategies for DOE's excess metals, through the use of case studies. The paper will also present actual volumes of metal moved by DOE into restricted and unrestricted uses since 1997. In addition, this paper will discuss the principle underlying the Three Building Decommissioning and Decontamination (D and D) Project in Oak Ridge, Tennessee. In January 2000, the Secretary of Energy placed a moratorium on the unrestricted release of volumetrically contaminated metals from the DOE sites. Pursuant to that moratorium, the Secretary also established a ''Re-Use and Recycling Task Force'' to conduct a review of DOE policies regarding the management and release of all materials for recycle and reuse from DOE facilities. This task force was charged to develop a set of recommendations to ensure the protection of public health and the environment, openness and public trust, and fiscal responsibility. This paper will present an overview of the DOE's present range of recycle and reuse alternatives to disposal, as practiced by the NMR, and discuss the policy and issues associated with the task force mission. (authors)

INEL metal recycle radioactive scrap metal survey report

International Nuclear Information System (INIS)

Funk, D.M.

1994-09-01

DOE requested that inventory and characterization of radioactive scrap metal (RSM) be conducted across the DOE complex. Past studies have estimated the metal available from unsubstantiated sources. In meetings held in FY-1993, with seven DOE sites represented and several DOE-HQ personnel present, INEL personnel discovered that these numbers were not reliable and that large stockpiles did not exist. INEL proposed doing in-field measurements to ascertain the amount of RSM actually available. This information was necessary to determine the economic viability of recycling and to identify feed stock that could be used to produce containers for radioactive waste. This inventory measured the amount of RSM available at the selected DOE sites. Information gathered included radionuclide content and chemical form, general radiation field, alloy type, and mass of metal

Recycling decontaminated scrap metal from the nuclear industry

International Nuclear Information System (INIS)

Bordas, F.

2000-01-01

The Commissariat a l'Energie Atomique (CEA) has set up a pilot program for recycling decontaminated scrap metal. In decommissioning its enriched uranium production facilities at Pierrelatte, the CEA has accumulated some 700 metric tons of scrap metal from dismantled uranium hexafluoride transport containers. The containers were decontaminated by SOCATRI at the Tricastin site, then cut up and recycled by a steelmaker. The project was submitted to the Ionizing Radiation Protection Office, the Nuclear Facilities Safety Division and the Regional Directorate for Industry, Research and Environmental Protection for approval. It was also submitted to the Ministry of Industry's Nuclear Information and Safety Council and to the Permanent Secretariat for Industrial Pollution Problems (an informational group chaired by the Prefect of the Provence Alpes-Cote d Azur region and including representatives of local and regional authorities, associations, elected officials and the media). The permit was granted for this program under the terms of a prefectorial decree stipulating additional requirements for the steelmaker, and contingent on the demonstration of full control over the operations, demonstrated traceability and the absence of any significant harmful effects. The key elements of this demonstration include the choice of operators, identification of the objects, itemization of the operations, discrimination of operators, the contractual framework of the operations, the signature of agreements by the CEA with SOCATRI and with the steelmaker, documentary monitoring of the operations, contradictory inspections and measurements, second-level inspection by the CEA/Valrho, audits of the operators and impact assessments. All the procedures of operations related to the scrap metal are described in quality assurance documents. (author)

Use of Portal Monitors for Detection of Technogenic Radioactive Sources in Scrap Metal

Science.gov (United States)

Solovev, D. B.; Merkusheva, A. E.

2017-11-01

The article considers the features of organization of scrap-metal primary radiation control on the specialized enterprises engaging in its deep processing and storage at using by primary technical equipment - radiation portal monitors. The issue of this direction relevance, validity of radiation control implementation with the use of radiation portal monitors, physical and organizational bases of radiation control are considered in detail. The emphasis is put on the considerable increase in the number of technogenic radioactive sources detected in scrap-metal that results in the entering into exploitation of radioactive metallic structures as different building wares. One of reasons of such increase of the number of technogenic radioactive sources getting for processing with scrap-metal is the absence of any recommendations on the radiation portal monitors exploitation. The practical division of the article offers to recommendation on tuning of the modes of work of radiation portal monitors depending on influence the weather factor thus allowing to considerably increase the percent of technogenic radioactive sources detection.

The radiological monitoring protocol for metallic products and cleared scrap management

International Nuclear Information System (INIS)

Gil Lopez, E.

2003-01-01

Event though the use of nuclear and radiological techniques is subject to strict controls in most countries, the presence of radioactive material in batches of metallic scrap has been detected with relative frequency in the last few years. This circumstance has motivated the implementation of a series of national and international initiatives aimed at detecting and preventing this type of events, whether they be intentional or involuntary. The Spanish iron and steel industry is one of the country's most important industrial sectors, and to a great extent it depends on the importation of a very significant amount of metallic scrap that it uses as raw material. Experience has shown that countries that import large amounts of scrap, apart from supporting the mentioned international initiatives, should complement them with other national initiatives to reduce the risks resulting from the presence of radioactive material in scrap. In this context, the Spanish authorities, together with trade unions and entrepreneurial associations in the metal reclamations and smelting sectors and ENRESA, have signed a voluntary Protocol that defines and implements a national radiological monitoring and control system for scrap materials and their byproducts. The Protocol defines the obligations and rights of the signatories, and it describes the monitoring and control system and its legal bases, the operation of both specific and other general-purpose radiological monitoring equipment that existed prior to this initiative, the development of radiological training and dissemination plans for professionals in the metal reclamation and smelting sectors, the establishment of effective systems for the safe management of any radioactive materials detected, and the general improvement of the national response system in the event of radiological emergencies. Since the Protocol took effect in November 1999, more than 100 enterprises from the metallurgical (steel, copper, lead and aluminum

The prospect for recycle of radioactive scrap metals to products for restricted and unrestricted use

International Nuclear Information System (INIS)

Liby, A.L.

1995-01-01

Large quantities of radioactive scrap metals will arise from decontamination and decommissioning of nuclear power plants and DOE facilities. Much of this metal can be easily decontaminated and released to the existing secondary metals industry for recycling. For metal that can not be readily released, recycle into restricted-use end products is an economically attractive alternative to burial as low level radioactive waste. This paper will examine sources and types of scrap metal, technical approaches, potential products, and economics of metals recycle. Construction, licensing, environmental compliance, and possible reuse of existing nuclear facilities for metals recycling will be discussed. (author)

Radiation protection aspects of the trafficking radionuclides contaminated metal scrap

International Nuclear Information System (INIS)

Prouza, Z.

1999-01-01

This paper covers the legal base of the release in the environment of radionuclides containing materials and the radiation protection aspects of trafficking in radionuclides contaminated materials. Materials, substance and objects containing radionuclides or contaminated by them may be released into the environment, if they do not exceed values authorized by SONS (State Office of Nuclear Safety). Legislative measures should be taken against illicit trafficking of the nuclear material in all the areas. The creation of a sophisticated system for the control and regulation of all important radionuclides released into the environment should be based on the radiation protection limits, constraints, reference and exemption levels which are introduced in the legislative documents; the strong supervision of producers and users of the sealed sources by SONS side, in addition to the requirements of the licensing process of their sources; a complete data-base and information exchange system related to illicit trafficking in contaminated material; in this system all the authorities with jurisdiction should be involved. The responsibilities of the persons involved in metal scrap trafficking should include arrangement of appropriate monitoring, rules for transport of the metal scrap, an adequate measuring system to monitor metal scrap including monitoring to prevent processing or smelting of the radioactive material, control measures, etc. All of the above items of legislation are an important challenge for the Czech Republic. (author)

Assignment of Responsibilities in the Management of Scrap Metal in Brazil

Energy Technology Data Exchange (ETDEWEB)

Costa, E.L., E-mail: evaldo@cnen.gov.br [Comissao Nacional de Energia Nuclear (CNEN), Rio de Janeiro (Brazil)

2011-07-15

This paper gives an overview of the activities of the National Commission of Nuclear Energy (CNEN), as the Brazilian regulatory authority responsible for licensing, inspecting, controlling and regulating all practices involving sources of ionizing radiation. The activities of the main departments of CNEN responsible for taking care of the practices and sources are described, especially those related to orphan sources and radioactive material in scrap metal. Finally, although Brazil does not yet have the necessary infrastructure to take care of the scrap metal issue, through the joint action of the relevant departments of CNEN it is hoped that the appropriate steps can be taken to build a national protocol, following the examples of other countries, especially Spain. (author)

Innovative technologies for recycling contaminated concrete and scrap metal

International Nuclear Information System (INIS)

Bossart, S.J.; Moore, J.

1993-01-01

Decontamination and decommissioning of US DOE's surplus facilities will generate enormous quantities of concrete and scrap metal. A solicitation was issued, seeking innovative technologies for recycling and reusing these materials. Eight proposals were selected for award. If successfully developed, these technologies will enable DOE to clean its facilities by 2019

Advanced technologies for decontamination and conversion of scrap metal

International Nuclear Information System (INIS)

Muth, T.R.; Shasteen, K.E.; Liby, A.L.

1995-01-01

The Department of Energy (DOE) accumulated large quantities of radioactive scrap metal (RSM) through historic maintenance activities. The Decontamination and Decommissioning (D ampersand D) of major sites formerly engaged in production of nuclear materials and manufacture of nuclear weapons will generate additional quantities of RSM, as much as 3 million tons of such metal according to a recent study. The recycling of RSM is quickly becoming appreciated as a key strategy in DOE's cleanup of contaminated sites and facilities

Bioleaching of metals from electronic scrap by moderately thermophilic acidophilic bacteria

NARCIS (Netherlands)

Ilyas, Sadia; Anwar, Munir A.; Niazi, Shahida B.; Ghauri, M. Afzal

The present work was aimed at studying the bioleachability of metals from electronic scrap by the selected moderately thermophilic strains of acidophilic chemolithotrophic and acidophilic heterotrophic bacteria. These included Sulfobacillus thermosulfidooxidans and an unidentified acidophilic

Challenges in the Management of Potentially Contaminated Scrap Metal

Energy Technology Data Exchange (ETDEWEB)

Meehan, R.W., E-mail: meehanrw@em.doe.gov [US Department of Energy, National Nuclear Security Administration, Washington, DC (United States)

2011-07-15

This paper describes the background and current status of the management of potentially contaminated metals and materials at the US Department of Energy (DOE) sites across the USA. The current DOE policy prohibiting the release of metal scrap for recycling from radiation areas is explained. Finally, a potential path forward to competently assess, characterize and clear material from radiological control is proposed that uses a combination of administrative processes and empirical techniques that are valid irrespective of the standard used for clearance. (author)

Metal Exposures at three U.S. electronic scrap recycling facilities.

Science.gov (United States)

Ceballos, Diana; Beaucham, Catherine; Page, Elena

2017-06-01

Many metals found in electronic scrap are known to cause serious health effects, including but not limited to cancer and respiratory, neurologic, renal, and reproductive damage. The National Institute for Occupational Safety and Health, Centers for Disease Control and Prevention performed three health hazard evaluations at electronic scrap recycling facilities in the U.S. to characterize employee exposure to metals and recommend control strategies to reduce these exposures. We performed air, surface, and biological monitoring for metals. We found one overexposure to lead and two overexposures to cadmium. We found metals on non-production surfaces, and the skin and clothing of workers before they left work in all of the facilities. We also found some elevated blood lead levels (above 10 micrograms per deciliter), however no employees at any facility had detectable mercury in their urine or exceeded 34% of the OELs for blood or urine cadmium. This article focuses on sampling results for lead, cadmium, mercury, and indium. We provided recommendations for improving local exhaust ventilation, reducing the recirculation of potentially contaminated air, using respirators until exposures are controlled, and reducing the migration of contaminants from production to non-production areas. We also recommended ways for employees to prevent taking home metal dust by using work uniforms laundered on-site, storing personal and work items in separate lockers, and using washing facilities equipped with lead-removing cleaning products.

Radioactive scrap metal decontamination technology assessment report

International Nuclear Information System (INIS)

Buckentin, J.M.; Damkroger, B.K.; Schlienger, M.E.

1996-04-01

Within the DOE complex there exists a tremendous quantity of radioactive scrap metal. As an example, it is estimated that within the gaseous diffusion plants there exists in excess of 700,000 tons of contaminated stainless steel. At present, valuable material is being disposed of when it could be converted into a high quality product. Liquid metal processing represents a true recycling opportunity for this material. By applying the primary production processes towards the material's decontamination and re-use, the value of the strategic resource is maintained while drastically reducing the volume of material in need of burial. Potential processes for the liquid metal decontamination of radioactively contaminated metal are discussed and contrasted. Opportunities and technology development issues are identified and discussed. The processes compared are: surface decontamination; size reduction, packaging and burial; melting technologies; electric arc melting; plasma arc centrifugal treatment; air induction melting; vacuum induction melting; and vacuum induction melting and electroslag remelting

Assessment of recycling or disposal alternatives for radioactive scrap metal

International Nuclear Information System (INIS)

Murphie, W.E.; Lilly, M.J. III

1993-01-01

The US Department of Energy, Office of Environmental Restoration and Waste Management, is participating with the Organization for Economic Cooperation and Development (OECD) is an evaluation of management alternatives for radioactive scarp metals. For this purpose, Argonne National Laboratory is assessing alternatives for radioactive scrap metals. For this purpose, Argonne National Laboratory is assessing environmental and societal implications of recycling and/or disposal process alternatives (with metal replacement). Findings will be presented in a report from the OECD Task Group. This paper focuses on the radiological risk assessment and dose estimate sensitivity analysis. A ''tiered'' concept for release categories, with and without use restrictions, is being developed. Within the tiers, different release limits may be indicated for specific groupings of radionuclides. Depending on the spectrum of radionuclides that are present and the level of residual activity after decontamination and/or smelting, the scrap may be released for unrestricted public use or for specified public uses, or it may be recycled within the nuclear industry. The conversatism of baseline dose estimates is examined, and both more realistic parameter values and protective measures for workers are suggested

An assessment on the recycling opportunities of wastes emanating from scrap metal processing in Mauritius

Energy Technology Data Exchange (ETDEWEB)

Mauthoor, Sumayya, E-mail: sumayya.mauthoor@umail.uom.ac.mu [Department of Chemical and Environmental Engineering, University of Mauritius, Réduit (Mauritius); Mohee, Romeela [Professor of Chemical and Environmental Engineering, National Research Chair in Solid Waste Management, Mauritius Research Council (Mauritius); Kowlesser, Prakash [Solid Waste/Beach Management Unit, Ministry of Local Government and Outer Islands (Mauritius)

2014-10-15

Highlights: • Scrap metal processing wastes. • Areas of applications for slag, electric arc furnace dust, mill scale and wastewater sludge. • Waste generation factor of 349.3 kg per ton of steel produced. • Waste management model. - Abstract: This paper presents an assessment on the wastes namely slag, dust, mill scale and sludge resulting from scrap metal processing. The aim of this study is to demonstrate that there are various ways via which scrap metal processing wastes can be reused or recycled in other applications instead of simply diverting them to the landfill. These wastes are briefly described and an overview on the different areas of applications is presented. Based on the results obtained, the waste generation factor developed was 349.3 kg per ton of steel produced and it was reported that slag represents 72% of the total wastes emanating from the iron and steel industry in Mauritius. Finally the suitability of the different treatment and valorisation options in the context of Mauritius is examined.

Application of the UNECE Recommendations on Monitoring and Response Procedures for Radioactive Scrap Metal: From Theory to Practice

Energy Technology Data Exchange (ETDEWEB)

Magold, M.; Mansourian-Stephenson, S., E-mail: stephanie.mansourian-stephenson@unece.org [United Nations Economic Council for Europe, Geneva (Switzerland)

2011-07-15

The work of the United Nations Economic Commission for Europe (UNECE) in addressing the issue of radioactive material appearing inadvertently in scrap metal is summarized. After hosting several meetings of national and international representatives of the scrap metal industry and radiation protection experts, the UNECE issued recommendations in 2006 on Monitoring and Response Procedures for Radioactive Scrap Metal. Since then, the UNECE has been exploring, with its Member States, the extent to which the Recommendations have been utilized - by means of a questionnaire. In this paper the results of the questionnaire are presented and, on the basis of the results of the questionnaire, conclusions are drawn and recommendations made for international action in this field for the future. (author)

Scrap metals' role in circular economy in Ghana, using Sunyani as a ...

African Journals Online (AJOL)

EJIRO

quantity and economic value of scrap metals as essential part of resource ... Therefore, proper education, policy and regulatory measures are key recommendations to ... The methodology of this research includes the description of the.

Utilization of metal scrap for the production of waste drums for ultimate disposal

International Nuclear Information System (INIS)

Janberg, K.; Rittscher, D.

1988-01-01

The contribution reviews the history of development of the techniques for treatment of decommissioning scrap from the beginning of the 1980's onwards (decommissioning of the Niederaichbach and Gundremmingen nuclear power stations), together with the radiological measuring methods required for regulatory purposes. The advantages of the recycling of the metal scrap by means of melting, and of materials utilization for production of waste containers for ultimate storage are discussed together with product quality assurance criteria. (RB) [de

Process for removing and detoxifying cadmium from scrap metal including mixed waste

International Nuclear Information System (INIS)

Kronberg, J.W.

1994-01-01

Cadmium-bearing scrap from nuclear applications, such as neutron shielding and reactor control and safety rods, must usually be handled as mixed waste since it is radioactive and the cadmium in it is both leachable and highly toxic. Removing the cadmium from this scrap, and converting it to a nonleachable and minimally radioactive form, would greatly simplify disposal or recycling. A process now under development will do this by shredding the scrap; leaching it with reagents which selectively dissolve out the cadmium; reprecipitating the cadmium as its highly insoluble sulfide; then fusing the sulfide into a glassy matrix to bring its leachability below EPA limits before disposal. Alternatively, the cadmium may be recovered for reuse. A particular advantage of the process is that all reagents (except the glass frit) can easily be recovered and reused in a nearly closed cycle, minimizing the risk of radioactive release. The process does not harm common metals such as aluminum, iron and stainless steel, and is also applicable to non-nuclear cadmium-bearing scrap such as nickel-cadmium batteries

Worker exposures from recycling surface contaminated radioactive scrap metal

International Nuclear Information System (INIS)

Kluk, A.; Phillips, J.W.; Culp, J.

1996-01-01

Current DOE policy permits release from DOE control of real property with residual levels of surficial radioactive contamination if the contamination is below approved guidelines. If the material contains contamination that is evenly distributed throughout its volume (referred to as volumetric contamination), then Departmental approval for release must be obtained in advance. Several DOE sites presently recycle surface contaminated metal, although the quantities are small relative to the quantities of metal processed by typical mini-mills, hence the potential radiation exposures to mill workers from processing DOE metals and the public from the processed metal are at present also a very small fraction of their potential value. The exposures calculated in this analysis are based on 100% of the scrap metal being processed at the maximum contamination levels and are therefore assumed to be maximum values and not likely to occur in actual practice. This paper examines the relationship between the surface contamination limits established under DOE Order 5400.5, open-quotes Radiation Protection of the Public and the Environment,close quotes and radiation exposures to workers involved in the scrap metal recycling process. The analysis is limited to surficial contamination at or below the guideline levels established in DOE Order 5400.5 at the time of release. Workers involved in the melting and subsequent fabrication of products are not considered radiation workers (no requirements for monitoring) and must be considered members of the public. The majority of the exposures calculated in this analysis range from tenths of a millirem per year (mrem/yr) to less than 5 mrem/yr. The incremental risk of cancer associated with these exposures ranges from 10 -8 cancers per year to 10 -6 cancers per year

Activities and Issues in Monitoring Scrap Metal Against Radioactive Sources

Energy Technology Data Exchange (ETDEWEB)

Chen, S.Y., E-mail: sychen@anl.gov [Argonne National Laboratory, Argonne, IL (United States)

2011-07-15

Over the past few decades, the global scrap metal industry has grown increasingly vigilant regarding radioactive contamination. Accidental melts of radioactive sources in some smelting facilities, in particular, have caused considerable damage and required recovery efforts costing tens of millions of dollars. In response, the industry has developed and deployed countermeasures. Increasingly expensive and sophisticated radiation monitoring devices have been implemented at key scrap entry points - ports and scrapyards. Recognition of the importance of such endeavors has led to a series of activities aimed at establishing organized and coordinated efforts among the interested parties. Recent concerns over the potential use of radioactive sources for radiological devices in terrorist acts have substantially heightened the need for national and international authorities to further control, intercept, and secure the sources that have escaped the regulatory domain. Enhanced collaboration by the government and industry could substantially improve the effectiveness of efforts at control; the 'Spanish Protocol' as developed by the Spanish metal industry and government regulators is a good example of such collaboration. (author)

Liquid metal extraction of Nd from NdFeB magnet scrap

Energy Technology Data Exchange (ETDEWEB)

Xu, Yanchen [Iowa State Univ., Ames, IA (United States)

1999-12-10

This research involves using molten magnesium (Mg) to remove neodymium (Nd) from NdFeB magnet scrap by diffusion. The results show that liquid metal extraction of Nd may be a viable and inexpensive method for recovering the expensive rare earth element Nd for use in Mg castings.

32 CFR 644.522 - Clearance of military scrap.

Science.gov (United States)

2010-07-01

... 32 National Defense 4 2010-07-01 2010-07-01 true Clearance of military scrap. 644.522 Section 644... Excess Land and Improvements § 644.522 Clearance of military scrap. Military scrap can contain or be... destruction, by using command, of all military scrap and scrap metal from lands suitable for cultivation or...

Efficient recovery of gold and other noble metals from electronic and other scraps

Energy Technology Data Exchange (ETDEWEB)

Baba, Hidetoshi

1987-01-01

Pure gold is extracted from crude gold by the solvent extraction method in the recovery and refining process for Noble metals recovered from electronic and other scraps. This solvent extraction method is advantageous in that it facilitates rapid processing, thereby reducing the interest burden of gold staying too long in the unit. Therefore, the method is also used in the refining of platinum and palladium. Technological innovation has created more complex and diversified types of scraps, and efforts are being made to accommodate ourselves to such a trend.

Radiometric monitoring of contaminated scrap metals imported in Italy. Technical and regulatory features

International Nuclear Information System (INIS)

Dobici, F.; Piermattei, S.; Susanna, A.

1996-01-01

During these last ten years there have been occasional reports of mishaps from trafficking of contaminated scraps or containing radioactive sources. Recently an increase of events indicated that the problem becomes more important as to generate possible consequences, from a radiation protection standpoint, for workers and general public. Following the detection of contaminated metal scraps in some recycling industries and in some consignments entering the Italian borders, the competent Authorities laid down rules to put the matter under control. In this paper technical and regulatory features are discussed. (author)

A study of liberation and separation process of metals from printed circuit boards (PCBs) scrap

International Nuclear Information System (INIS)

Noorliyana, H.A.; Zaheruddin, K.; Mohd Fazlul Bari; M. Sri Asliza; Nurhidayah, A.Z.; Kamarudin, H.

2009-01-01

Since the metallic elements are covered with or encapsulated by various plastic or ceramic materials on printed circuit boards, a mechanical pre-treatment process allowing their liberation and separation is first needed in order to facilitate their efficient extraction with hydrometallurgy route. Even though many studies have been performed on the mechanical pre-treatment processing for the liberation and separation of the metallic components of printed circuit boards scrap, further studies are required to pave the way for efficient recycling of waste printed circuit boards through a combination of mechanical pre-treatment and hydrometallurgical technology. In this work, a fundamental study has been carried out on the mechanical pre-treatment that is necessary to recover metallic concentrates from printed circuit boards scraps. The most important problem is to separate or release particles from the associated gangue minerals at the possible liberation particle size. The distribution of metallic elements has been also investigated in relation to the particle size of the milled printed circuit boards. The samples of printed circuit boards were separated into the magnetic and non-magnetic fractions by Rare-earth Roll Magnetic separator. Thereafter, the magnetic and non-magnetic fractions were separated to heavy fraction (metallic elements) and light fraction (plastic) by Mozley Laboratory Table Separator. The recovery ratios and the evaluation of the metallic concentrates recovered by each separation process were also investigated. This study is expected to provide useful data for the efficient mechanical separation of metallic components from printed circuit boards scraps. (author)

Considerations in recycling contaminated scrap metal and rubble

International Nuclear Information System (INIS)

Kluk, A.F.; Hocking, E.K.

1992-01-01

Management options for the Department of Energy's increasing amounts of contaminated scrap metal and rubble include reuse as is, disposal, and recycling. Recycling, with its promise of resource recovery, virgin materials conservation, and land disposal minimization, emerges as a preferred management technique. Implementing a cost effective recycling program requires resolution of several issues including: establishing release limits for contaminants, controlling use of recycled materials creating effective public communication programs; developing economical, reliable assay technologies; managing secondary waste streams, expanding availability of unrestricted markets; and solving conflicting legal considerations

Demonstration test on manufacturing 200 l drum inner shielding material for recycling of reactor operating metal scrap

International Nuclear Information System (INIS)

Umemura, A.; Kimura, K.; Ueno, H.

1993-01-01

Low-level reactor wastes should be safely recycled considering those resource values, the reduction of waste disposal volume and environmental effects. The reasonable recycling system of reactor operating metal scrap has been studied and it was concluded that the 200 liter drum inner shielding material is a very promising product for recycling within the nuclear industry. The drum inner shielding material does not require high quality and so it is expected to be easily manufactured by melting and casting from roughly sorted scrap metals. This means that the economical scrap metal recycling system can be achieved by introducing it. Furthermore its use will ensure safety because of being contained in a drum. In order to realize this recycling system with the drum inner shielding material, the demonstration test program is being conducted. The construction of the test facility, which consists of a melting and refining furnace, a casting apparatus, a machining apparatus etc., was finishing in September, 1992

Current status of scrap metal recycling and reuse in USA and European countries

International Nuclear Information System (INIS)

Matsumoto, Akira

1997-01-01

Recycling and reuse of natural resources has become a global issue to be pursued, but less effective without voluntary efforts from the every industries and of the individuals. In Japan, recycling and reuse of the scrap metal from dismantling of the nuclear facilities are currently noticed as a promising option and the responsible government organizations just started activities to develope the system for enabling and encouraging the nuclear facility owners to recycle their waste. Coincidently, there have been many reports published recently, which inform successful results of the method and the activities of the international organizations for the same intention. Taking this opportunity, current trends of scrap metal recycling and reuse in the experienced countries are reviewed and the proposals from IAEA, EC and OECD/NEA on the relating issues are summarized and compared in this paper. (author)

Evaluation of the costs and benefits of recycling radioactively contaminated scrap metal

International Nuclear Information System (INIS)

Durman, E.C.; Tsirigotis, P.; MacKinney, J.A.

1995-01-01

The U.S. Environmental Protection Agency (EPA) is evaluating the economic and technical issues associated with the potential recycling of radioactive scrap metals (RSM). These metals, usually only slightly contaminated, originate primarily from the decommissioning and decontamination (D and D) of federal facilities, licensees of the Nuclear Regulatory Commission, and certain unlicensed industries. EPA conducted a study entitled Analysis of the Potential Recycling of Department of Energy Radioactive Scrap Metal, September 6, 1994, for the U.S. Department of Energy (DOE) to provide information and tools to DOE for assessing DOE's problem with RSM from the D and D of their sites. EPA is now initiating an evaluation of RSM recycling to support a recycling regulation. Although the study prepared for DOE will provide a useful start for the regulatory analysis, additional information must be gathered to analyze the impacts of a recycling regulation that will apply to all potential generators of RSM. This paper summarizes cost-benefit issues related to an RSM recycling regulatory analysis, including: the quantity of potentially recyclable contaminated metals; costs of disposal at federal and private waste repositories; all potential environmental, health, and safety, and market impacts; and the potential for adverse effects on radio-sensitive industries. (author)

Gained experiences concerning the treatment of radioactive metal scrap from German NPP'S in Studsvik - Gained experience concerning the treatment of radioactive metal scrap from German nuclear power plants

International Nuclear Information System (INIS)

Westerwinter, Boris; Buckanie, Niemma

2014-01-01

The company Gesellschaft fuer Nuklear-Service mbH, Essen/Germany (GNS), operates on behalf of the utilities E.ON, RWE, EnBW and VENE since the nineteen-nineties - amongst its other duties - on the waste management of metal scrap which originates from German nuclear power plants. The main objective within this responsibility is to maximize the value of recyclable fractions for re-use while minimizing the resulting radioactive waste. To achieve the aforementioned objective, melting of metallic scrap proved to be an outstanding choice. The use of this technique combined with all accompanying processes and regulations is accepted by the competent authorities and independent experts as a qualified treatment method over the entire time period. The motivation of this paper is to reflect on the experiences gained concerning the planning, implementation and results, acquired by GNS by using the Studsvik service. The focus will be on characteristics within processing of such campaigns. (authors)

Design of the network for the radiological control in the recycling of metal scrap in Cuba

International Nuclear Information System (INIS)

Dominguez Ley, Orlando; Caveda Ramos, Celia; Ramos Viltre, Enma O.; Capote Ferrera, Eduardo; Alonso Abad, Dolores; Zerquera, Juan Tomas

2008-01-01

Full text: During the last six years, the Centre of Protection and Hygiene of the Radiations (CPHR) has given answer to the problem about the presence of radioactive materials in the scrap which is exported in Cuba. The service of radioactivity measurement in scraps has reduced the risks of the occurrence of this type of events in the main import and export enterprises in Cuba. This has been carried out using few resources, a properly qualified staff and a laboratory credited by the norm ISO 17025:00. There is not the same control in the enterprises that manipulate and process metallic scrap inside the country. With the objective of extending the radiological control of the metallic scrap to the whole country, a monitoring network was designed. The design was based on the experience accumulated during the years of service to the import and export enterprises. First, It was defined the most vulnerable points in the whole recycle chain for each province, prioritizing the scrap melting plants and the longest scrap yards. All possible scenarios were identified, a quality system was also designed and implemented and a course of Radiological Protection oriented to the metallurgist technicians who are linked with the performance of this practice was elaborated. The monitoring has two phases. First, the measurements are carried out in the measurement points in each province and the transmissions of the data related to the monitored scrap loads are sent to the CPHR. The second phase is the confection of the Declaration of Conformity at the CPHR. This declaration certifies that this scrap may be processed. For the operation of this network, two software were developed and are currently used. One of them allows the control of the information in monitoring point and sends the necessary data to CPHR for the confection of the Declaration of Conformity. The other controls all the information received from the monitoring points and generates the Declaration of Conformity

Beneficial reuse of US DOE Radioactive scrap metal

Energy Technology Data Exchange (ETDEWEB)

Motl, G.P.

1995-01-19

The US Department of Energy (DOE) has more than 2.5 million tons of radioactive scrap metal (RSM) that is either in inventory or expected to be generated over the next 25 years as major facilities within the weapons complex are decommissioned. Since much of this metal cannot be decontaminated easily, past practice has been to either retain this material in inventory or ship it to DOE disposal sites for burial. In an attempt to conserve natural resources and to avoid burial of this material at DOE disposal sites, options are now being explored to ``beneficially reuse`` this material. Under the beneficial reuse concept, RSM that cannot be decontaminated and free released is used in applications where the inherent contamination is not a detriment to its end use. This paper describes initiatives currently in progress in the United States that support the DOE beneficial reuse concept.

Beneficial reuse of US DOE Radioactive scrap metal

International Nuclear Information System (INIS)

Motl, G.P.

1995-01-01

The US Department of Energy (DOE) has more than 2.5 million tons of radioactive scrap metal (RSM) that is either in inventory or expected to be generated over the next 25 years as major facilities within the weapons complex are decommissioned. Since much of this metal cannot be decontaminated easily, past practice has been to either retain this material in inventory or ship it to DOE disposal sites for burial. In an attempt to conserve natural resources and to avoid burial of this material at DOE disposal sites, options are now being explored to ''beneficially reuse'' this material. Under the beneficial reuse concept, RSM that cannot be decontaminated and free released is used in applications where the inherent contamination is not a detriment to its end use. This paper describes initiatives currently in progress in the United States that support the DOE beneficial reuse concept

Submerged Glow-Discharge Plasma: An Economical Approach to Convert Construction Scrap Metal into Nanomaterials

Science.gov (United States)

Yek, Peter Nai Yuh; Rafiq Mirza Julaihi, Muhammad; Shahril Osman, Mohammad; Tiong, Tung Chuan; Lee, Wak Ha; Leing Lee, Chern

2018-03-01

Submerged glow-discharge plasma (SGDP) is relatively new among the various methods available for nanomaterials synthesis (NMs) techniques. This method allows great control over the production cost of nanomaterials synthesis. A lab-scale batch type SDGP technology has been constructed to produce nanomaterials and investigate the inter-relationship between plasma excitation voltages, electrodes submerged areas and electrolyte concentration. Metal oxide nanospheres has been synthesised from different electrolyte concentrations (1M-0.001M) and characterized by Scanning Electron Microscopy (SEM) and Energy Dispersive Spectroscopy (EDS). As the major results showed that the nanospheres are uniformly spherical with diameter size distribution are between 100 nm - 2μm. EDS analysis shown the nano-Iron Oxide have been formed. Scrap metal initially showed around 6.45% and 93.55% of Carbon and Iron composition respectively. After SGDP process to the scrap metal, Carbon content has increased to 34-35% and Iron content has reduced to around 15-40%. EDS results also shown the higher percentage of Iron amount has remained with lower electrolyte concentration and Current is proportionally related to submersion area of cathode.

Radiation protection aspects in importing metallic scraps; Problemi di radioprotezione connessi con l`importazione di rottami metallici

Energy Technology Data Exchange (ETDEWEB)

Risica, S.; Di Ciacco, P. [Istituto Superiore di Sanita`, Rome (Italy). Laboratorio di Fisica

1996-09-01

The meeting deals with radiation protection problems caused by the possibility that radioactive metal scraps or radioactive sources hidden in the scraps, may arrive in a foundry. The importance of this issue and of rational and systematic solutions is showed by several accidents, happened in the past in numerous countries, by many signals in Italy and by some papers published in international scientific journals or reports issued by authorities and institutions in different countries.

Effect of Acid Dissolution Conditions on Recovery of Valuable Metals from Used Plasma Display Panel Scrap

Directory of Open Access Journals (Sweden)

Kim Chan-Mi

2017-06-01

Full Text Available The objective of this particular study was to recover valuable metals from waste plasma display panels using high energy ball milling with subsequent acid dissolution. Dissolution of milled (PDP powder was studied in HCl, HNO3, and H2SO4 acidic solutions. The effects of dissolution acid, temperature, time, and PDP scrap powder to acid ratio on the leaching process were investigated and the most favorable conditions were found: (1 valuable metals (In, Ag, Mg were recovered from PDP powder in a mixture of concentrated hydrochloric acid (HCl:H2O = 50:50; (2 the optimal dissolution temperature and time for the valuable metals were found to be 60°C and 30 min, respectively; (3 the ideal PDP scrap powder to acid solution ratio was found to be 1:10. The proposed method was applied to the recovery of magnesium, silver, and indium with satisfactory results.

Reuse of waste water from high pressure water jet decontamination for reactor decommissioning scrap metal

International Nuclear Information System (INIS)

Deng Junxian; Li Xin; Hou Huijuan

2011-01-01

For recycle and reuse of reactor decommissioning scrap metal by high pressure water jet decontamination, large quantity of radioactive waste water will be generated. To save the cost of radioactive waste water treatment and to reduce the cost of the scrap decontamination, this part of radioactive waste water should be reused. Most of the radioactivities in the decontamination waste water come from the solid particle in the water. Thus to reuse the waste water, the solid particle in the waster should be removed. Different possible treatment technologies have been investigated. By cost benefit analysis the centrifugal separation technology is selected. (authors)

Submerged Glow-Discharge Plasma: An Economical Approach to Convert Construction Scrap Metal into Nanomaterials

Directory of Open Access Journals (Sweden)

Yek Peter Nai Yuh

2018-01-01

Full Text Available Submerged glow-discharge plasma (SGDP is relatively new among the various methods available for nanomaterials synthesis (NMs techniques. This method allows great control over the production cost of nanomaterials synthesis. A lab-scale batch type SDGP technology has been constructed to produce nanomaterials and investigate the inter-relationship between plasma excitation voltages, electrodes submerged areas and electrolyte concentration. Metal oxide nanospheres has been synthesised from different electrolyte concentrations (1M-0.001M and characterized by Scanning Electron Microscopy (SEM and Energy Dispersive Spectroscopy (EDS. As the major results showed that the nanospheres are uniformly spherical with diameter size distribution are between 100 nm - 2μm. EDS analysis shown the nano-Iron Oxide have been formed. Scrap metal initially showed around 6.45% and 93.55% of Carbon and Iron composition respectively. After SGDP process to the scrap metal, Carbon content has increased to 34-35% and Iron content has reduced to around 15-40%. EDS results also shown the higher percentage of Iron amount has remained with lower electrolyte concentration and Current is proportionally related to submersion area of cathode.

Catalytic extraction processing of contaminated scrap metal

Energy Technology Data Exchange (ETDEWEB)

Griffin, T.P.; Johnston, J.E.; Payea, B.M. [Molten Metal Technology, Inc., Waltham, MA (United States)] [and others

1995-10-01

The U.S. Department of Energy issued a Planned Research and Development Announcement (PRDA) in 1993, with the objective of identifying unique technologies which could be applied to the most hazardous waste streams at DOE sites. The combination of radioactive contamination with additional contamination by hazardous constituents such as those identified by the Resource Conservation and Recovery Act (RCRA) pose an especially challenging problem. Traditional remediation technologies are increasingly becoming less acceptable to stakeholders and regulators because of the risks they pose to public health and safety. Desirable recycling technologies were described by the DOE as: (1) easily installed, operated, and maintained; (2) exhibiting superior environmental performance; (3) protective of worker and public health and safety; (4) readily acceptable to a wide spectrum of evaluators; and (5) economically feasible. Molten Metal Technology, Inc. (MMT) was awarded a contract as a result of the PRDA initiative to demonstrate the applicability of Catalytic Extraction Processing (CEP), MMT`s proprietary elemental recycling technology, to DOE`s inventory of low level mixed waste. This includes DOE`s inventory of radioactively- and RCRA-contaminated scrap metal and other waste forms expected to be generated by the decontamination and decommissioning (D&D) of DOE sites.

Catalytic extraction processing of contaminated scrap metal

International Nuclear Information System (INIS)

Griffin, T.P.; Johnston, J.E.; Payea, B.M.

1995-01-01

The U.S. Department of Energy issued a Planned Research and Development Announcement (PRDA) in 1993, with the objective of identifying unique technologies which could be applied to the most hazardous waste streams at DOE sites. The combination of radioactive contamination with additional contamination by hazardous constituents such as those identified by the Resource Conservation and Recovery Act (RCRA) pose an especially challenging problem. Traditional remediation technologies are increasingly becoming less acceptable to stakeholders and regulators because of the risks they pose to public health and safety. Desirable recycling technologies were described by the DOE as: (1) easily installed, operated, and maintained; (2) exhibiting superior environmental performance; (3) protective of worker and public health and safety; (4) readily acceptable to a wide spectrum of evaluators; and (5) economically feasible. Molten Metal Technology, Inc. (MMT) was awarded a contract as a result of the PRDA initiative to demonstrate the applicability of Catalytic Extraction Processing (CEP), MMT's proprietary elemental recycling technology, to DOE's inventory of low level mixed waste. This includes DOE's inventory of radioactively- and RCRA-contaminated scrap metal and other waste forms expected to be generated by the decontamination and decommissioning (D ampersand D) of DOE sites

Distribution, enrichment and accumulation of heavy metals in coastal sediments of Alang-Sosiya ship scrapping yard, India.

Science.gov (United States)

Reddy, M Srinivasa; Basha, Shaik; Sravan Kumar, V G; Joshi, H V; Ramachandraiah, G

2004-06-01

Since its inception in 1982, the Alang-Sosiya yard has become the largest ship scrapping works in the world. Several hundreds of ships arrive every year. The degree of heavy metal contamination has been studied in bulk and fine sediments from the intertidal zone of this ship scrapping yard, two stations, one on either side at 5 km distance and one reference station 60 km distance near Mahuva, towards the south. The samples have been subjected to a total digestion technique and analysed for elements: Cd, Co, Cu, Cr, Fe, Mn, Ni, Pb, Zn and Al, and %TOC. The absolute metal concentrations reflected variations in BF and FF sediment samples with organic matter content. Enrichment factors (EF) and geoaccumulation indices (Igeo) have been calculated and the relative contamination levels are assessed at these sites. At Alang-Sosiya, the enrichment of heavy metals has been observed to be relatively high.

Control of Transboundary Movement of Radioactive Material Inadvertently Incorporated into Scrap Metal and Semi-finished Products of the Metal Recycling Industries. Results of the Meetings Conducted to Develop a Draft Code of Conduct

International Nuclear Information System (INIS)

2014-02-01

In 2010, the IAEA initiated the development of a code of conduct on the transboundary movement of radioactive material inadvertently incorporated into scrap metal and semi- finished products of the metal recycling industries (Metal Recycling Code of Conduct). The Metal Recycling Code of Conduct was intended to harmonize the approaches of Member States in relation to the discovery of radioactive material that may inadvertently be present in scrap metals and semi-finished products subject to transboundary movement, and their safe handling and management to facilitate regulatory control. The Metal Recycling Code of Conduct was envisaged as being complementary to the Safety Guide on Control of Orphan Sources and Other Radioactive Material in the Metal Recycling and Production Industries (IAEA Safety Standards Series No. SSG-17), which provides recommendations, principally within a national context, on the protection of workers, members of the public and the environment in relation to the control of radioactive material inadvertently incorporated in scrap metal. In February 2013, the third open-ended meeting of technical and legal experts to develop the Metal Recycling Code of Conduct was organized. The objective of this meeting was to address the comments received from Member States and to finalize the text of the draft Metal Recycling Code of Conduct. Representatives from 55 Member States, one non-Member State and the EU, together with seven observers from the metal recycling industry, reviewed the comments and revised the draft accordingly. In September 2013, in Resolution GC(57)/RES/9, the IAEA General Conference recorded that it 'Appreciates the intensive efforts undertaken by the Secretariat to develop a code of conduct on the transboundary movement of scrap metal, or materials produced from scrap metal, that may inadvertently contain radioactive material, and encourages the Secretariat to make the results of the discussion conducted on this issue available to

Heavy metal partitioning from electronic scrap during thermal End-of-Life treatment

International Nuclear Information System (INIS)

Scharnhorst, Wolfram; Ludwig, Christian; Wochele, Joerg; Jolliet, Olivier

2007-01-01

Samples of identical Printed Wiring Board Assemblies (PWBA) have been thermally treated in a Quartz Tube Reactor (QTR) in order to detect the volatility of selected heavy metals contained in electronic scrap being of environmental concern. In preparation, evaporation experiments were performed using a Thermo Gravimeter (TG) in connection with an Inductively Coupled Plasma-Optical Emissions Spectrometer (ICP-OES). The QTR experiments were performed under reducing and under oxidising conditions at 550 and at 880 deg. C. The volatilisation has been determined for As, Cd, Ni, Ga, Pb, and Sb using ICP-OES analysis of the ash residues. The results were evaluated by thermodynamic equilibrium calculations, the TG-ICP measurements and in comparison with similar studies. In coincidence with the preparative TG-ICP measurements as well as with thermodynamic equilibrium calculations neither As nor Cd could be detected in the residuals of the thermally treated PWBA samples, suggesting a high volatility of these metals. Ga does not show a distinct volatilisation mechanism and seems to be incorporated in the siliceous fraction. Ni remains as stable compound in the bottom ash. Sb shows a high volatility nearly independent of temperature and oxygen supply. The results imply that, if electronic scrap is thermally processed, attention has to be paid in particular to Sb, As, and Ga. These metals are increasingly used in new electronic equipment such as mobile phone network equipment of the third generation

Radioactive sources and contaminated materials in scrap: monitoring, detection and remedial actions

International Nuclear Information System (INIS)

Gallini, R.; Berna, V.; Bonora, A.; Santini, M.

1999-01-01

The scrap recycling in steel and other metal mills represents one of the most relevant activities in the Province of Brescia (Lombardy, Italy). In our Province more than 20 million tonnes of metal scrap are recycled every year by a melting process. Since 1990, many accidents which took place were caused by the unwanted melting of radioactive sources, that were probably hidden in metal scrap. In 1993, the Italian Government stated directives to monitor metal scrap imported from non-EC countries because of the suspicion of the illegal traffic of radioactive materials. In 1996, a law imposed the control of all metal scrap, regardless of their origins. Since 1993, our staff have controlled thousands of railway wagons and trucks. Approximately a hundred steel mills and foundries of aluminium, cooper, brass, etc. have also been controlled and many samples have been collected (flue dust, slag, finished products). During these controls, contaminated areas have been brought to light in two warehouses (Cs 137), in 6 companies (Cs 137 and Am 241), in two landfills of industrial waste (Cs 137) and in a quarry (Cs 137). Up to now the contaminated areas have been cleaned, except for the last one. About 150 radioactive sources on contaminated materials have been found in metal scrap. We found radioactive sources of Co 60, Ra 226, Ir 192, Kr 85, Am 241, while the contamination of metals was mainly due to Ra 226. The situation described above justifies an accurate control of the amount of scrap to reduce the risk of contamination of the workers in the working areas, in the environment and in the general public. (author)

Contaminated nickel scrap processing

International Nuclear Information System (INIS)

Compere, A.L.; Griffith, W.L.; Hayden, H.W.; Johnson, J.S. Jr.; Wilson, D.F.

1994-12-01

The DOE will soon choose between treating contaminated nickel scrap as a legacy waste and developing high-volume nickel decontamination processes. In addition to reducing the volume of legacy wastes, a decontamination process could make 200,000 tons of this strategic metal available for domestic use. Contaminants in DOE nickel scrap include 234 Th, 234 Pa, 137 Cs, 239 Pu (trace), 60 Co, U, 99 Tc, and 237 Np (trace). This report reviews several industrial-scale processes -- electrorefining, electrowinning, vapormetallurgy, and leaching -- used for the purification of nickel. Conventional nickel electrolysis processes are particularly attractive because they use side-stream purification of process solutions to improve the purity of nickel metal. Additionally, nickel purification by electrolysis is effective in a variety of electrolyte systems, including sulfate, chloride, and nitrate. Conventional electrorefining processes typically use a mixed electrolyte which includes sulfate, chloride, and borate. The use of an electrorefining or electrowinning system for scrap nickel recovery could be combined effectively with a variety of processes, including cementation, solvent extraction, ion exchange, complex-formation, and surface sorption, developed for uranium and transuranic purification. Selected processes were reviewed and evaluated for use in nickel side-stream purification. 80 refs

Development of a recovery process of scraps resulting from the manufacture of metallic uranium fuels

International Nuclear Information System (INIS)

Camilo, Ruth L.; Kuada, Terezinha A.; Forbicini, Christina A.L.G.O.; Cohen, Victor H.; Araujo, Bertha F.; Lobao, Afonso S.T.

1996-01-01

The study of the dissolution of natural metallic uranium fuel samples with aluminium cladding is presented, in order to obtain optimized conditions for the system. The aluminium cladding was dissolved in an alkaline solution of Na OH/Na NO 3 and the metallic uranium with HNO 3 . A fumeless dissolution with total recovery of nitrous gases was achieved. The main purpose of this project was the recovery of uranium from scraps resulting from the manufacture of the metallic uranium fuel or other non specified fuels. (author)

Evaluation of the electrorefining technique for the processing of radioactive scrap metals

Energy Technology Data Exchange (ETDEWEB)

Kessinger, G.F.

1993-10-01

This report presents the results of a literature study performed to identify applications of the electrorefining technique to the decontamination of radioactively-contaminated scrap metal (RSM). Upon the completion of the literature search and the review of numerous references, it was concluded that there were applications of this technique that were appropriate for the decontamination of some types of RSM, especially when the desired product is a pure elemental metal of high purity. It was also concluded that this technique was not well-suited for the decontamination of RSM stainless steels and other alloys, when it was desired that the metallurgical characteristics of the alloy be present in the decontaminated product.

Evaluation of the electrorefining technique for the processing of radioactive scrap metals

International Nuclear Information System (INIS)

Kessinger, G.F.

1993-10-01

This report presents the results of a literature study performed to identify applications of the electrorefining technique to the decontamination of radioactively-contaminated scrap metal (RSM). Upon the completion of the literature search and the review of numerous references, it was concluded that there were applications of this technique that were appropriate for the decontamination of some types of RSM, especially when the desired product is a pure elemental metal of high purity. It was also concluded that this technique was not well-suited for the decontamination of RSM stainless steels and other alloys, when it was desired that the metallurgical characteristics of the alloy be present in the decontaminated product

Recycle of contaminated scrap metal, Volume 1. Semi-annual report, September 1993--January 1996

International Nuclear Information System (INIS)

1996-07-01

Catalytic Extraction Processing (CEP) has been demonstrated to be a robust, one-step process that is relatively insensitive to wide variations in waste composition and is applicable to a broad spectrum of DOE wastes. Catalytic Processing Unit (CPU) design models have been validated through experimentation to provide a high degree of confidence in our ability to design a bulk solids CPU for processing DOE wastes. Two commercial CEP facilities have been placed in commission and are currently processing mixed low level wastes. These facilities provide a compelling indication of the maturity, regulatory acceptance, and commercial viability of CEP. In concert with the DOE, Nolten Metal Technology designed a program which would challenge preconceptions of the limitations of waste processing technologies: demonstrate the recycling of ferrous and non-ferrous metals--to establish that radioactively contaminated scrap metal could be converted to high-grade, ferrous and non-ferrous alloys which can be reused by DOE or reintroduced into commerce; immobilize radionuclides--that CEP would concentrate the radionuclides in a durable vitreous phase, minimize secondary waste generation and stabilize and reduce waste volume; destroy hazardous organics--that CEP would convert hazardous organics to valuable industrial gases, which could be used as an energy source; recover volatile heavy metals--that CEP's off-gas treatment system would capture volatile heavy metals, such as mercury and lead; establish that CEP is economical for processing contaminated scrap metal in the DOE inventory. The execution of this program resulted in all objectives being met. Volume I covers: executive summary; task 1.1 design CEP system; Task 1.2 experimental test plan; Task 1.3 experimental testing

Recycle of contaminated scrap metal, Volume 1. Semi-annual report, September 1993--January 1996

Energy Technology Data Exchange (ETDEWEB)

NONE

1996-07-01

Catalytic Extraction Processing (CEP) has been demonstrated to be a robust, one-step process that is relatively insensitive to wide variations in waste composition and is applicable to a broad spectrum of DOE wastes. Catalytic Processing Unit (CPU) design models have been validated through experimentation to provide a high degree of confidence in our ability to design a bulk solids CPU for processing DOE wastes. Two commercial CEP facilities have been placed in commission and are currently processing mixed low level wastes. These facilities provide a compelling indication of the maturity, regulatory acceptance, and commercial viability of CEP. In concert with the DOE, Nolten Metal Technology designed a program which would challenge preconceptions of the limitations of waste processing technologies: demonstrate the recycling of ferrous and non-ferrous metals--to establish that radioactively contaminated scrap metal could be converted to high-grade, ferrous and non-ferrous alloys which can be reused by DOE or reintroduced into commerce; immobilize radionuclides--that CEP would concentrate the radionuclides in a durable vitreous phase, minimize secondary waste generation and stabilize and reduce waste volume; destroy hazardous organics--that CEP would convert hazardous organics to valuable industrial gases, which could be used as an energy source; recover volatile heavy metals--that CEP`s off-gas treatment system would capture volatile heavy metals, such as mercury and lead; establish that CEP is economical for processing contaminated scrap metal in the DOE inventory. The execution of this program resulted in all objectives being met. Volume I covers: executive summary; task 1.1 design CEP system; Task 1.2 experimental test plan; Task 1.3 experimental testing.

High Purity Tungsten Spherical Particle Preparation From WC-Co Spent Hard Scrap

Directory of Open Access Journals (Sweden)

Han Chulwoong

2015-06-01

Full Text Available Tungsten carbide-cobalt hard metal scrap was recycled to obtain high purity spherical tungsten powder by a combined hydrometallurgy and physical metallurgy pathway. Selective leaching of tungsten element from hard metal scrap occurs at solid / liquid interface and therefore enlargement of effective surface area is advantageous. Linear oxidation behavior of Tungsten carbide-cobalt and the oxidized scrap is friable to be pulverized by milling process. In this regard, isothermally oxidized Tungsten carbide-cobalt hard metal scrap was mechanically broken into particles and then tungsten trioxide particle was recovered by hydrometallurgical method. Recovered tungsten trioxide was reduced to tungsten particle in a hydrogen environment. After that, tungsten particle was melted and solidified to make a spherical one by RF (Ratio Frequency thermal plasma process. Well spherical tungsten micro-particle was successfully obtained from spent scrap. In addition to the morphological change, thermal plasma process showed an advantage for the purification of feedstock particle.

Contaminated nickel scrap processing

Energy Technology Data Exchange (ETDEWEB)

Compere, A.L.; Griffith, W.L.; Hayden, H.W.; Johnson, J.S. Jr.; Wilson, D.F.

1994-12-01

The DOE will soon choose between treating contaminated nickel scrap as a legacy waste and developing high-volume nickel decontamination processes. In addition to reducing the volume of legacy wastes, a decontamination process could make 200,000 tons of this strategic metal available for domestic use. Contaminants in DOE nickel scrap include {sup 234}Th, {sup 234}Pa, {sup 137}Cs, {sup 239}Pu (trace), {sup 60}Co, U, {sup 99}Tc, and {sup 237}Np (trace). This report reviews several industrial-scale processes -- electrorefining, electrowinning, vapormetallurgy, and leaching -- used for the purification of nickel. Conventional nickel electrolysis processes are particularly attractive because they use side-stream purification of process solutions to improve the purity of nickel metal. Additionally, nickel purification by electrolysis is effective in a variety of electrolyte systems, including sulfate, chloride, and nitrate. Conventional electrorefining processes typically use a mixed electrolyte which includes sulfate, chloride, and borate. The use of an electrorefining or electrowinning system for scrap nickel recovery could be combined effectively with a variety of processes, including cementation, solvent extraction, ion exchange, complex-formation, and surface sorption, developed for uranium and transuranic purification. Selected processes were reviewed and evaluated for use in nickel side-stream purification. 80 refs.

Recycle of contaminated scrap metal, Volume 2. Semi-annual report, September 1993--January 1996

Energy Technology Data Exchange (ETDEWEB)

NONE

1996-07-01

Catalytic Extraction Processing (CEP) has been demonstrated to be a robust, one-step process that is relatively insensitive to wide variations in waste composition and is applicable to a broad spectrum of DOE wastes. Catalytic Processing Unit (CPU) design models have been validated through experimentation to provide a high degree of confidence in our ability to design a bulk solids CPU for processing DOE wastes. Two commercial CEP facilities have been placed in commission and are currently processing mixed low level wastes. These facilities provide a compelling indication of the maturity, regulatory acceptance, and commercial viability of CEP. In concert with the DOE, Nolten Metal Technology designed a program which would challenge preconceptions of the limitations of waste processing technologies: demonstrate the recycling of ferrous and non-ferrous metals--to establish that radioactively contaminated scrap metal could be converted to high-grade, ferrous and non-ferrous alloys which can be reused by DOE or reintroduced into commerce; immobilize radionuclides--that CEP would concentrate the radionuclides in a durable vitreous phase, minimize secondary waste generation and stabilize and reduce waste volume; destroy hazardous organics--that CEP would convert hazardous organics to valuable industrial gases, which could be used as an energy source; recover volatile heavy metals--that CEP`s off-gas treatment system would capture volatile heavy metals, such as mercury and lead; and establish that CEP is economical for processing contaminated scrap metal in the DOE inventory. The execution of this program resulted in all objectives being met. Volume II contains: Task 1.4, optimization of the vitreous phase for stabilization of radioactive species; Task 1.5, experimental testing of Resource Conservation and Recovery Act (RCRA) wastes; and Task 1.6, conceptual design of a CEP facility.

Recycle of contaminated scrap metal, Volume 2. Semi-annual report, September 1993--January 1996

International Nuclear Information System (INIS)

1996-07-01

Catalytic Extraction Processing (CEP) has been demonstrated to be a robust, one-step process that is relatively insensitive to wide variations in waste composition and is applicable to a broad spectrum of DOE wastes. Catalytic Processing Unit (CPU) design models have been validated through experimentation to provide a high degree of confidence in our ability to design a bulk solids CPU for processing DOE wastes. Two commercial CEP facilities have been placed in commission and are currently processing mixed low level wastes. These facilities provide a compelling indication of the maturity, regulatory acceptance, and commercial viability of CEP. In concert with the DOE, Nolten Metal Technology designed a program which would challenge preconceptions of the limitations of waste processing technologies: demonstrate the recycling of ferrous and non-ferrous metals--to establish that radioactively contaminated scrap metal could be converted to high-grade, ferrous and non-ferrous alloys which can be reused by DOE or reintroduced into commerce; immobilize radionuclides--that CEP would concentrate the radionuclides in a durable vitreous phase, minimize secondary waste generation and stabilize and reduce waste volume; destroy hazardous organics--that CEP would convert hazardous organics to valuable industrial gases, which could be used as an energy source; recover volatile heavy metals--that CEP's off-gas treatment system would capture volatile heavy metals, such as mercury and lead; and establish that CEP is economical for processing contaminated scrap metal in the DOE inventory. The execution of this program resulted in all objectives being met. Volume II contains: Task 1.4, optimization of the vitreous phase for stabilization of radioactive species; Task 1.5, experimental testing of Resource Conservation and Recovery Act (RCRA) wastes; and Task 1.6, conceptual design of a CEP facility

Radioactive Scrap Metal (RSM) recycling: A doe white paper

International Nuclear Information System (INIS)

Chatterjee, S.; Moore, H.H.; Ghoshal, A.

1992-01-01

An effective White Paper on recycling radioactive scrap metals has been drafted at the request of the U.S. Department of Energy (DOE) recently. The paper has received the praise and commendation of the DOE's Director of Environmental Management. However, obstructionist posturing by the petty bureaucrats in DOE continues to plague the meaningful implementation of RSM recycling. The key findings of the White Paper study and its major recommendations have discussed in this paper. The study indicates that several technologies, such as melt refining and electro refining, are currently available for surface and volume decontamination of metals. The unit cost of decontamination was found to vary from $700 to $400/ton; recycling of most low-contaminated metals can therefore be cost-effective vis-a vis the average cost of low-level radioactive wastes disposal of %400 to $2800/ton. Major recycling demonstration projects with emphasis on restricted RSM reuse options have been recommended. Volume contamination standard for unrestricted release should be established only after adequate studies of health effects and scientific/industrial effects of RSM reuse has been conducted by the Environmental Protection Agency (EPA) and the Nuclear Regulatory Commission (NRC). Some of the significant technical data developed during this study have also been briefly discussed in this paper. (author)

Options for the disposition of current inventory of Rocky Flats Plant residues

International Nuclear Information System (INIS)

Chang, Lychin.

1994-01-01

With the end of the Cold War, much concern has been directed towards the accumulation of special nuclear material resulting from the dismantlement of a large number of nuclear weapons. This concern has opened up a debate over the final disposition of the large inventory of weapons-capable plutonium. Technologies for the conversion of plutonium into acceptable forms will need to be assessed and evaluated. Candidate strategies for interim and final disposition include a variety of immobilization techniques (vitrification in glass, ceramic, or metal), conversion to reactor fuel, or direct discard as waste. The selected disposition strategy will be chosen based upon a range of decision metric such as expected conversion costs, equipment requirements, and waste generation. To this end, a systems analysis approach is necessary for the evaluation and comparison of the different disposition strategies. Current data on inventory of plutonium, such as that at the Rocky Flats Plant (RFP), may be useful for the evaluation and selection of candidate disposition technologies. A preliminary analysis of the residues of scrap at Rocky Flats was performed to establish a foundation for comparison of candidate strategies. About 3 metric tons of plutonium and 270 metric tons of other wastes remain in the inventory at Rocky Flats. Estimates on the equipment, facility, manpower, and cost requirements to process this inventory over a proposed 10-year cleanup campaign will provide a benchmark for comparison and assessment of proposed disposition technologies

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

Energy Technology Data Exchange (ETDEWEB)

Gruetzmacher, K. M. (Kathleen M.); MacArthur, D. W. (Duncan W.)

2002-01-01

At Los Alamos National Laboratory (LANL), a recent effort in waste minimization has focused on scrap metal from radiological controlled areas (RCAs). In particular, scrap metal from RCAs needs to be dispositioned in a reasonable and cost effective manner. Recycling of DOE scrap metals from RCAs is currently under a self-imposed moratorium. Since recycling is not available and reuse is difficult, often metal waste from RCAs, which could otherwise be recycled, is disposed of as low-level waste. Estimates at LANL put the cost of low-level waste disposal at $550 to $4000 per cubic meter, depending on the type of waste and the disposal site. If the waste is mixed, the cost for treatment and disposal can be as high as $50,000 per cubic meter. Disposal of scrap metal as low-level waste uses up valuable space in the low-level waste disposal areas and requires transportation to the disposal site under Department of Transportation (DOT) regulations for low-level waste. In contrast, disposal as non-radioactive waste costs as little as $2 per cubic meter. While recycling is unavailable, disposing of the metal at an industrial waste site could be the best solution for this waste stream. A Green Is Clean (GIC) type verification program needs to be in place to provide the greatest assurance that the waste does not contain DOE added radioactivity. This paper is a review of available and emerging radiation monitoring and assay systems that could be used for scrap metal as part of the LANL GIC program.

Management of radiation protection aspects in the recycling of metallurgical scrap: the report of UNECE team of specialists on radioactive contaminated scrap

International Nuclear Information System (INIS)

Deckers, B.

2001-01-01

Complete text of publication follows: In 1999, the United Nations Economic Commission for Europe (UNECE) has created a Team of Specialists on Radioactive Contaminated Metal Scrap: technically qualified representatives of the steel industry, government representatives and competent international organizations representatives have studied the problem of radioactively contaminated scrap and steel, and have proposed solutions in this context acceptable at the international level in order to harmonize the legislation, the systems of measurement of radioactivity, the levels of detection. This team has established a document which will be published by the United Nations, and where good practices on managing radioactive metal scrap are presented, and which also contains numerous recommendations in order to harmonize legislations. The paper presents the content of the document and the main recommendations of the team. (author)

Controlling the Outcome of Melting Radioactive Sources in Scrap Metal: from Exclusion, Exemption and Clearance towards a 'Codex Metallarius'

Energy Technology Data Exchange (ETDEWEB)

Gonzalez, A.J., E-mail: agonzale@sede.arn.gov.ar [Autoridad Regulatoria Nuclear, Buenos Aires (Argentina)

2011-07-15

Orphan radiation sources have been inadvertently incorporated into scrap metal and traces of radioactive residues have appeared in finished metal products causing public anxiety, despair in industry and governmental concern. The international principles of exclusion, exemption and clearance can be used to tackle this problem. They are described in detail, as they are becoming universally established for defining the scope of radiation protection regulations. However, notwithstanding the relevance of these principles, the paper suggests a straightforward professional consensus for discontinuing radiological control of commodities with minute traces of radioactive residues. The consensus should unambiguously specify a generic activity concentration in inedible commodities, including metals, below which radiological control may be effectively relinquished. A subsequent legally binding intergovernmental undertaking could resolve the current regulatory ambiguity, facilitate commercial exchange and ensure adequate public protection. For metals, it might take the form of a 'Codex Metallarius' (similar to the existing Codex Alimentarius for edible commodities) establishing a generic level of radiological acceptability for finished metal products. Furthermore, it is proposed that there should be an international convention to prevent radioactive sources becoming orphaned from regulatory control and then inadvertently appearing in trash and scrap. (author)

Scrap is no crap

DEFF Research Database (Denmark)

Wenzel, Henrik

2009-01-01

Scrap is good business for the environment. When we recycle metal - meaning to collect, sort and melt it down - we emit much less CO2 than when we extract metal from the ground. The environmental benefit applies to all metals and is gained every time we recycle them. That is a positive message in...... in a world where we search for methods to reduce our CO2 emission. And the environmental potential is big: There are no upper limits for how many times we can recycle metals, which makes recycling an important part of the fight against global warming....

Hydrogen isotope storage in zircaloy scrap

Energy Technology Data Exchange (ETDEWEB)

Lee, H. S.; Kuk, I. H.; Chung, H.; Paek, S. W.; Kang, H. S

1999-08-01

8 MCi of tritium a year will be produced after wolsong TRF is in operation. The metal hydride form is one of useful tritium storage. The metals in use for metal hydride are uranium, titanium, etc., however uranium is limited to use by regulation, and titanium is relatively costly. Both metals are not produced in country but whole amount is imported. On the other hand 2,000kg of zircaloy scrap is produced by CANDU nuclear fuel fabrication process, which is also useful for hydrogen storage. The purpose of this study is to evaluation of hydrogen absorption capacity for zircaloy scrap that is produced as waste by CANDU nuclear fuel fabrication process. The sample evacuated for an hour at 1000 deg C. The strip showed higher capacity : 0.7 at 25 deg C, 2.0 at 200 deg C, 2.0 at 200 deg C, 2.0 at 400 deg C, respectively. The H/M values for commercial zircaloy sponge were 2.0 at 25 deg C and 2.0 at 400 deg C.

Hydrogen isotope storage in zircaloy scrap

International Nuclear Information System (INIS)

Lee, H. S.; Kuk, I. H.; Chung, H.; Paek, S. W.; Kang, H. S.

1999-08-01

8 MCi of tritium a year will be produced after wolsong TRF is in operation. The metal hydride form is one of useful tritium storage. The metals in use for metal hydride are uranium, titanium, etc., however uranium is limited to use by regulation, and titanium is relatively costly. Both metals are not produced in country but whole amount is imported. On the other hand 2,000kg of zircaloy scrap is produced by CANDU nuclear fuel fabrication process, which is also useful for hydrogen storage. The purpose of this study is to evaluation of hydrogen absorption capacity for zircaloy scrap that is produced as waste by CANDU nuclear fuel fabrication process. The sample evacuated for an hour at 1000 deg C. The strip showed higher capacity : 0.7 at 25 deg C, 2.0 at 200 deg C, 2.0 at 200 deg C, 2.0 at 400 deg C, respectively. The H/M values for commercial zircaloy sponge were 2.0 at 25 deg C and 2.0 at 400 deg C

Immobilisation of Cu, Pb and Zn in Scrap Metal Yard Soil Using Selected Waste Materials.

Science.gov (United States)

Kamari, A; Putra, W P; Yusoff, S N M; Ishak, C F; Hashim, N; Mohamed, A; Isa, I M; Bakar, S A

2015-12-01

Immobilisation of heavy metals in a 30-year old active scrap metal yard soil using three waste materials, namely coconut tree sawdust (CTS), sugarcane bagasse (SB) and eggshell (ES) was investigated. The contaminated soil was amended with amendments at application rates of 0 %, 1 % and 3 % (w/w). The effects of amendments on metal accumulation in water spinach (Ipomoea aquatica) and soil metal bioavailability were studied in a pot experiment. All amendments increased biomass yield and reduced metal accumulation in the plant shoots. The bioconcentration factor and translocation factor values of the metals were in the order of Zn > Cu > Pb. The addition of ES, an alternative source of calcium carbonate (CaCO3), has significantly increased soil pH and resulted in marked reduction in soil metal bioavailability. Therefore, CTS, SB and ES are promising low-cost immobilising agents to restore metal contaminated land.

Recovery of gold from electronic scrap by hydrometallurgical processes

Energy Technology Data Exchange (ETDEWEB)

Lee, Churl Kyoung; Rhee, Kang-In [Korea Institute of Geology Mining and Materials, Taejon (Korea, Republic of); Sohn, Hun Joon [Seoul National University, Seoul (Korea, Republic of)

1997-09-30

A series of processes has been developed to recover the gold from electronic scrap containing about 200{approx}600 ppm Au. First, mechanical beneficiation including shredding, crushing and screening was employed. Results showed that 99 percent of gold component leaves in the fraction of under 1 mm of crushed scrap and its concentration was enriched to about 800 ppm without incineration. The crushed scrap was leached in 50% aqua regia solution and gold was completely dissolved at 60 deg. C within 2 hours. Other valuable metals such as silver, copper, nickel and iron were also dissolved. The resulting solution was boiled to remove nitrous compounds in the leachate. Finally, a newly designed electrolyzer was tested to recover the gold metal. More than 99% of gold and silver were recovered within an hour by electrowinning process. (author). 10 refs., 5 tabs., 6 figs.

Options for the disposition of current inventory of Rocky Flats Plant residues. Revision 1

International Nuclear Information System (INIS)

Chang, L.

1994-01-01

With the end of the Cold War, much concern has been directed towards the accumulation of special nuclear material resulting from the dismantlement of a large number of nuclear weapons. This concern has opened up a debate over the final disposition of the large inventory of weapons-capable plutonium. Technologies for the conversion of plutonium into acceptable forms will need to be assessed and evaluated. Candidate strategies for interim and final disposition include a variety of immobilization techniques (vitrification in glass, ceramic, or metal), conversion to reactor fuel, or direct discard as waste. The selected disposition strategy will be chosen based upon a range of decision metrics such as expected conversion costs, equipment requirements, and waste generation. To this end, a systems analysis approach is necessary for the evaluation and comparison of the different disposition strategies. Current data on inventory of plutonium, such as that at the Rocky Flats Plant (RFP), may be useful for the evaluation and selection of candidate disposition technologies. A preliminary analysis of the residues of scrap at Rocky Flats was performed to establish a foundation for comparison of candidate strategies. About 3 metric tons of plutonium and 270 metric tons of other wastes remain in the inventory at Rocky Flats. Estimates on the equipment, facility, manpower, and cost requirements to process this inventory over a proposed 10-year cleanup campaign will provide a benchmark for comparison and assessment of proposed disposition technologies

Radioactive metal scrap recycling by melting process at the Chernobyl site

International Nuclear Information System (INIS)

Steinwarz, W.

1995-01-01

Within its TACIS programme the European Union ordered a feasibility study on the cleaning-up of the Chernobyl area from radioactively contaminated metallic material. The study was performed by a Ukrainian German Working Group under the leadership of Siempelkamp and finalized at the end of March 1994. The on-site evaluation for the 30 km exclusion zone showed an overall mass of metal scrap of min. 100,000 Mg with a maximum specific activity of 400 Bq/g based on 48 open depositories within the restricted area. Dominant radionuclides were Cs-137 and Sr-90 accompanied by a very low proportion of α-activity. The study report showed the technical feasibility of a melting plant designed with a throughput of 10'000 Mg per year and its suitability for the overall concept to handle the Chernobyl waste. The main task for the near future can be identified as the establishing of a sound financial concept. (author) 5 figs., 3 tabs., 2 refs

Approach and issues toward development of risk-based release standards for radioactive scrap metal recycle and reuse

International Nuclear Information System (INIS)

Chen, S.Y.; Nieves, L.A.; Nabelssi, B.K.; LePoire, D.J.

1994-01-01

The decontamination and decommissioning of nuclear facilities is expected to generate large amounts of slightly radioactive scrap metal (RSM). It is likely that some of these materials will be suitable for recycling and reuse. The amount of scrap steel from DOE facilities, for instance, is estimated to be more than one million tons (Hertzler 1993). However, under current practice and without the establishment of acceptable recycling standards, the RSM would be disposed of primarily as radioactive low-level waste (LLW). In the United States, no specific standards have been developed for the unrestricted release of bulk contaminated materials. Although standards for unrestricted release of radioactive surface contamination (NRC 1974) have existed for about 20 years, the release of materials is not commonly practiced because of the lack of risk-based justifications. Recent guidance from international bodies (IAEA 1988) has established a basis for deriving risk-based release limits for radioactive materials. It is important, therefore, to evaluate the feasibility of recycling and associated issues necessary for the establishment of risk-based release limits for the radioactive metals

Lead scrap processing in rotary furnaces: a review

Energy Technology Data Exchange (ETDEWEB)

Rousseau, M

1987-01-01

Formerly, the lead scrap had been processed mainly in reverberatory and shaft furnaces or, even, in rotary furnaces (R.F.). The direct smelting of battery scrap entrains an expensive pollution control and high operating costs because of slag recirculation, coke consumption, losses in slag and matte. Nowadays, mechanized battery wrecking plants allow selective separation of casings and separators from metallic Pb (grids, poles, solders) as well as lead in non-metallic form (PbSO/sub 4/, PbO, PbO/sub 2/, contaminated with some Sb) frequently called paste. Because of their high performance and flexibility in metallurgical processing (melting, reducing, oxidizing and selective pouring) the R.F. supersedes the reverberatory furnace worldwide.

Radiation survey of aircraft and heavy machinery scrap

International Nuclear Information System (INIS)

Idriss, Hajo; Salih, Isam; Gumaa, Elsadig; Yassin, Abbas; Yousif, E.H.; Abdel Hamid, Saad Eldeen M.; Sam, A.K.

2012-01-01

This study was conducted primarily to survey aircraft and heavy machinery at 30 locations within Khartoum State using handheld radiation survey meters to detect and identify any radiation sources that might be present and to estimate radiation dose levels. The survey has resulted in detection of 16 sealed sources of 90 Sr and one of 226 Ra in aircraft scrap. Of course, 90 Sr sources are used in military aircraft as temperature sensors while 226 Ra is used for indicating fuel levels. These sources were found intact without spreading radioactivity contamination; however, none was detected in heavy machine scrap. The levels of radiation dose measured at 0.1 m from the source fall within the range of 25.1–40.2 μSv/h with an average value of 33.52±4.06 μSv/h. These orphan sources have been separated from the scrap, tested for possible leakage, conditioned and stored in waste management facility. The result of this study has revealed without doubt that the scrap constitute a serious source of public exposure and highlights the importance of legislation making radiation monitoring of scrap in the country mandatory before it is sold to metal industry for reprocessing. - Highlights: ► Sealed radioactive sources ( 90 Sr and 226 Ra) were detected in aircraft scrap. ► No source was detected in heavy machine scrap. ► Radiation dose measured at 0.1 m from the source can be used to estimate exposure to public. ► Monitoring of scrap was found to be useful for protection (from orphan sources).

Developments in radioactive scrap monitoring

International Nuclear Information System (INIS)

Bellian, J.G.

1997-01-01

Over the past ten years there have been major developments in radiation monitoring systems used for detecting shielded radioactive sources in scrap metal. The extent of the problem and industry's awareness of the problem have both grown significantly during that time. The multimillion dollar expenses associated with decontamination after a source passes into the melt and the potential health hazard to employees and the public have added further impetus to the development of monitoring systems. Early attempts at scrap monitoring could detect some radiation, but testing with real life situations showed them to be virtually incapable of detecting shielded sources of radioactivity in incoming vehicles. More sophisticated detector technology and the development of advanced software made useful by more powerful microprocessors led to successive generations of monitoring systems with order-of-magnitude improvement in detection capability. The next generation includes larger detectors and more complex algorithms offering further improvement in truck and rail car monitoring. Complete solutions require monitoring at additional locations within the site, such as the charge bucket and conveyor lines, and at the scrap processor's site

The development of technology for recycling of electronic scrap

Energy Technology Data Exchange (ETDEWEB)

Yu, Hyo-Shin; Kim, Won-Baek; Sohn, Yong-Uhn [Korea Institute of Geology Mining and Materials, Taejon (KR)] (and others)

1999-12-01

Electronic devices, especially computer becomes an essential tools for home and industries entering the information era. The number of computers exceed over 100 million, hence, the amount of end of life(EOL) computer and electronic scrap is increasing. These wastes and scraps include products rejected from manufacturing processes and obstacle computers. Owing to a short life cycle of electronic products and rapid growth of electronic industries, the number of domestic EOL computers goes beyond a million and its disposal causes an environmental problems. Therefore, this recycling is considered to play an important role from the viewpoint of environmental preservation as well as reusable resources. The process development for the recovery of valuable materials and minimization of waste from electronic scrap has been carried out. In the first year of three year project, physical separation such as shredding, crushing, and magnetic separation is established to reclaim valuable materials effectively. Then, hydro- and pyrometallurgical processes are employed to recover valuable metals from electronic scrap. First, metallic and nonmetallic portion are separated from PCBs by a newly designed shredder to prevent hazardous organic materials from further chemical treatment. The optimum conditions for each unit process were found in terms of separation ratio, energy consumption, recovery rate, etc. (author). 92 refs., 24 tabs., 39 figs.

Experience during the monitoring of inactive scrap for the detection of inadvertent presence of radioactivity

International Nuclear Information System (INIS)

Sharma, Ranjit; Kumar, Anoj; Vikas; Patra, R.P.; Kumar, Vikas; Singh, Rajvir; Pradeepkumar, K.S.

2012-01-01

The inspection and certification of scrap material from nuclear facilities is a regulatory requirement to ensure that radioactive material will not reach public domain. Around the world, cases involving radioactive contamination of metallic components have occurred due to radioactive sources/contaminated metal scrap reaching the public domain. Radiological monitoring of inactive scrap material is essential as it may get into various usages in public domain where controls cannot be implemented. The method of detection is measurement of gamma dose rates due to any loose/fixed radioactive contamination in the scrap or presence of any radioactive material/source. In addition prevention of any inadvertent/malicious act leading to radioactive material reaching the public domain through scrap being essential, this monitoring gains further importance. This paper describes the methodology and experience in detection of presence of radioactivity at inactive Scrap monitoring facility. Even though radioactive sources of high strength with potential for serious environmental hazard have not been detected, few cases of contaminated material (MS plate/equipments etc with extremely low level of 137 Cs and Uranium contamination) have been detected and identified using portable gamma spectrometer. If proper monitoring is not carried out the dispersal of radioactivity to the environment can be a matter of concern due to metal scrap reaching recycling industry resulting in huge cost of decontamination and waste disposal. These events may also have negative impact on the export from the country resulting in economic losses. The impact of such events can be ruled out by effective scrap monitoring techniques which ensure that even small quantity of radioactivity escaping into public domain can be prevented. The methodology followed for monitoring of inactive scrap is found to be effective even for detection of presence of very low level of radioactivity

Recycling radioactive scrap metal by producing concrete shielding with steel granules

International Nuclear Information System (INIS)

Sappok, M.

1996-01-01

Siempelkamp foundry at Krefeld, Germany, developed a method for recycling radioactively contaminated steel from nuclear installations. The material is melted and used for producing shielding plates, containers, etc., on a cast-iron basis. Because the percentage of stainless steel has recently increased significantly, problems in the production of high-quality cast iron components have also grown. The metallurgy, the contents of nickel and chromium especially, does not allow for the recycling of stainless steel in a percentage to make this process economical. In Germany, the state of the art is to use shielded concrete containers for the transport of low active waste; this concrete is produced by using hematite as an additive for increasing shielding efficiency. The plan was to produce steel granules from radioactive scrap metal as a substitute for hematite in shielding concrete

Plutonium-bearing materials feed report for the DOE Fissile Materials Disposition Program alternatives

International Nuclear Information System (INIS)

Brough, W.G.; Boerigter, S.T.

1995-01-01

This report has identified all plutonium currently excess to DOE Defense Programs under current planning assumptions. A number of material categories win clearly fan within the scope of the MD (Materials Disposition) program, but the fate of the other categories are unknown at the present time. MD planning requires that estimates be made of those materials likely to be considered for disposition actions so that bounding cases for the PEIS (Programmatic Environmental Impact Statement) can be determined and so that processing which may be required can be identified in considering the various alternatives. A systematic analysis of the various alternatives in reachmg the preferred alternative requires an understanding of the possible range of values which may be taken by the various categories of feed materials. One table identifies the current total inventories excess to Defense Program planning needs and represents the bounding total of Pu which may become part of the MD disposition effort for all materials, except site return weapons. The other categories, principally irradiated fuel, rich scrap, and lean scrap, are discussed. Another table summarizes the ranges and expected quantities of Pu which could become the responsibility of the MD program. These values are to be used for assessing the impact of the various alternatives and for scaling operations to assess PEIS impact. Determination of the actual materials to be included in the disposition program will be done later

Bioleaching of electronic scrap by mixed culture of moderately thermophilic microorganisms

Science.gov (United States)

Ivǎnuş, D.; ǎnuş, R. C., IV; Cǎlmuc, F.

2010-06-01

A process for the metal recovery from electronic scrap using bacterial leaching was investigated. A mixed culture of moderately thermophilic microorganisms was enriched from acid mine drainages (AMDs) samples collected from several sulphide mines in Romania, and the bioleaching of electronic scrap was conducted both in shake flask and bioreactor. The results show that in the shake flask, the mixture can tolerate 50 g/L scrap after being acclimated to gradually increased concentrations of scrap. The copper extraction increases obviously in bioleaching of scrap with moderately thermophilic microorganisms supplemented with 0.4 g/L yeast extract at 180 r/min, 74% copper can be extracted in the pulp of 50 g/L scrap after 20 d. Compared with copper extractions of mesophilic culture, unacclimated culture and acclimated culture without addition of yeast extract, that of accliniated culture with addition of yeast extract is increased by 53%, 44% and 16%, respectively. In a completely stirred tank reactor, the mass fraction of copper and total iron extraction reach up to 81% and 56%, respectively. The results also indicate that it is necessary to add a large amount of acid to the pulp to extract copper from electronic scrap effectively.

Radiation survey of aircraft and heavy machinery scrap.

Science.gov (United States)

Idriss, Hajo; Salih, Isam; Gumaa, Elsadig; Yassin, Abbas; Yousif, E H; Abdel Hamid, Saad Eldeen M; Sam, A K

2012-12-01

This study was conducted primarily to survey aircraft and heavy machinery at 30 locations within Khartoum State using handheld radiation survey meters to detect and identify any radiation sources that might be present and to estimate radiation dose levels. The survey has resulted in detection of 16 sealed sources of (90)Sr and one of (226)Ra in aircraft scrap. Of course, (90)Sr sources are used in military aircraft as temperature sensors while (226)Ra is used for indicating fuel levels. These sources were found intact without spreading radioactivity contamination; however, none was detected in heavy machine scrap. The levels of radiation dose measured at 0.1m from the source fall within the range of 25.1-40.2 μSv/h with an average value of 33.52 ± 4.06 μSv/h. These orphan sources have been separated from the scrap, tested for possible leakage, conditioned and stored in waste management facility. The result of this study has revealed without doubt that the scrap constitute a serious source of public exposure and highlights the importance of legislation making radiation monitoring of scrap in the country mandatory before it is sold to metal industry for reprocessing. Copyright © 2012 Elsevier Ltd. All rights reserved.

Legislative and Regulatory Control for the Safety of Radioactively Contaminated Scrap Metals Generated from Mining and Mineral Processing Facilities in South Africa

Energy Technology Data Exchange (ETDEWEB)

Mohajane, E. P.; Shale, K., E-mail: PEMohajane@nnr.co.za [National Nuclear Regulator, Centurion, Gauteng (South Africa)

2011-07-15

In South Africa, enhanced levels of naturally occurring radioactive materials (NORM) are associated with many mining and industrial processes. Significant amounts of waste materials are involved which can result in radiation exposure of the workers and the public particularly through the diversion of materials into the public domain. The following operations have been regulated in South Africa for the past twenty years: operating metallurgical plants utilizing NORM, underground mining operations, scrap recyclers and smelters, and rehabilitation and remediation activities involving the above sites. The radioactively contaminated scrap metal generated from the above mentioned facilities is available for recycling in amounts of thousands of tons. The South African government has, to a certain extent, responded to the above-mentioned challenges by introducing regulatory controls to the affected industries. The existing regulatory controls have, however, not provided absolute answers to all issues associated with the management of scrap. (author)

Development of DOE complexwide authorized release protocols for radioactive scrap metals

International Nuclear Information System (INIS)

Chen, S. Y.

1998-01-01

Within the next few decades, several hundred thousand tons of metal are expected to be removed from nuclear facilities across the U.S. Department of Energy (DOE) complex as a result of decontamination and decommissioning (D and D) activities. These materials, together with large quantities of tools, equipment, and other items that are commonly recovered from site cleanup or D and D activities, constitute non-real properties that warrant consideration for reuse or recycle, as permitted and practiced under the current DOE policy. The provisions for supporting this policy are contained in the Draft Handbook for Controlling Release for Reuse or Recycle of Property Containing Residual Radioactive Material published by DOE in 1997 and distributed to DOE field offices for interim use and implementation. The authorized release of such property is intended to permit its beneficial use across the entire DOE complex. The objective of this study is to develop readily usable computer-based release protocols to facilitate implementation of the Handbook in evaluating the scrap metals for reuse and recycle. The protocols provide DOE with an effective oversight tool for managing release activities

The Study for Recycling NORM - Contaminated Steel Scraps from Steel Industry

International Nuclear Information System (INIS)

Tsai, K. F.; Lee, Y. S.; Chao, H. E.

2003-01-01

Since 1994, most of the major steel industries in Taiwan have installed portal monitor to detect the abnormal radiation in metal scrap feed. As a result, the discovery of NORM (Naturally Occurring Radioactive Material) has increased in recent years. In order to save the natural resources and promote radiation protection, an experimental melting process for the NORM contaminated steel scraps was carried out by the Institute of Nuclear Energy Research (INER) Taiwan, ROC. The experimental melting process has a pretreatment step that includes a series of cutting and removal of scales, sludge, as well as combustible and volatile materials on/in the steel scraps. After pretreatment the surface of the steel scraps are relatively clean. Then the scraps are melted by a pilot-type induction furnace. This experiment finally produced seven ingots with a total weight of 2,849 kg and 96.8% recovery. All of the surface dose rates are of the background values. The activity concentrations of these ingots are also below the regulatory criteria. Thus, these NORM-bearing steel scraps are ready for recycling. This study has been granted by the regulatory authority

Experience during the monitoring of inactive scrap for the detection of inadvertent presence of radioactivity

International Nuclear Information System (INIS)

Sharma, Ranjit; Anoj Kumar; Vikas; Singh, Rajvir; Patra, R.P.; Vikas Kumar; Pradeepkumar, K.S.

2012-01-01

The paper describes about the experience gained during the radiation monitoring of inactive scrap generated at various nuclear facilities. This type surveillance is carried out to prevent the spread of radioactivity in public domain and also as requirement by regulatory authorities. The inspection and certification of scrap material from nuclear facilities is a regulatory requirement to ensure that no radioactive material reaches public domain. This paper describes the methodology and experience in detection of radioactivity at inactive Scrap monitoring facility. Inactive scraps (metallic and non metallic) generated from various nuclear facilities of BARC, Trombay is dispatched to Trombay Village Store (TVS) for temporary storage before auction to the public. The monitoring at the facility includes visual inspection and radiation measurement before loading the scrap in the truck. An online PC based monitoring system and portable monitoring instruments in the range (nSv/h-µSv/h) are used to carry out radiation monitoring of inactive scrap loaded in a vehicle. Radioactive source of high activity with potential for serious environmental hazard has not been detected, but few cases of presence of radioactive/contaminated material (MS plate/equipments with low level of 137 Cs contamination) have been detected and identified using portable gamma spectrometer. Implementation of strict regulatory measures and radiation monitoring at nuclear facilities can minimize the probability of radioactive material reaching the public domain. The methodology followed for monitoring of inactive scrap is found to be effective even for detection of presence of radioactivity in scrap if any. (author)

32 CFR Appendix B to Part 172 - Disposition of Amounts Collected From Successful Bidders

Science.gov (United States)

2010-07-01

... Disposition of: (20%) bid deposit (80%) remaining balance 1. Scrap turned in by industrial fund (IF... (Pre FY 82) property issued under the Military Assistance Program (MAP) and returned as no longer..., “Foreign Military Financing Program” (Effective 1 October 1989 the 11_1080, “Military Assitance,” account...

Summary of industrial impacts from recycled radioactive scrap metals

International Nuclear Information System (INIS)

Dehmel, J.-C.; Harrop, J.; MacKinney, J.A.

1995-01-01

During operation, decontamination, and dismantlement, nuclear facilities are generating significant quantities of radioactive scrap metal (RSM). Future decommissioning will generate even more RSM. The petroleum industry also generates RSM in the form of equipment contaminated with naturally occurring radioactivity. Finally, the accidental melting of radioactive sources in steel mills has generated smaller amounts of contaminated metals. Steel mills, smelters, and foundries could recycle these materials, which might then appear in finished products or as feedstocks used by other industries. If introduced in this manner, residual radioactivity can adversely affect the performance of certain products. Such products include computers and other devices that rely on integrated circuits. The most important effect of residual radioactivity on integrated circuits is a phenomenon known as 'single event upsets or soft errors.' Radioactivity can also adversely affect the performance of products such as photographic film and components designed to measure the presence of radioactivity. Radioactivity that raises background count-rates to higher levels could affect the performance of radiation monitoring systems and analytical equipment. Higher background count-rates would lead to reduced sensitivity and lower resolution in spectroscopic systems. The computer, photographic, and radiation measurement industries have taken steps to minimize the impact of residual radioactivity on their products. These steps include monitoring manufacturing processes, specifying material acceptance standards, and screening suppliers. As RSM is recycled, these steps may become more important and more costly. This paper characterizes potentially impacted industries and vulnerability and effects due to the presence of residual radioactivity. Finally, the paper describes practices used to limit the impact of residual radioactivity. (J.P.N.)

The Influence of Home Scrap on Mechanical Properties of MgAl9Zn1 Alloy Castings

Directory of Open Access Journals (Sweden)

Konopka Z.

2017-06-01

Full Text Available The work presents the results of examinations concerning the influence of various amounts of home scrap additions on the properties of castings made of MgAl9Zn1 alloy. The fraction of home scrap in the metal charge ranged from 0 to 100%. Castings were pressure cast by means of the hot-chamber pressure die casting machine under the industrial conditions in one of the domestic foundries. The examinations consisted in the determination of the following properties: tensile strength Rm, yield strength Rp0.2, and the unit elongation A5, all being measured during the static tensile test. Also, the hardness measurements were taken by the Brinell method. It was found that the mechanical properties (mainly the strength properties are being improved up to the home scrap fraction of 50%. Their values were increased by about 30% over this range. Further rise in the home scrap content, however, brought a definite decrease in these properties. The unit elongation A5 exhibited continual decrease with an increase in the home scrap fraction in the metal charge. A large growth of hardness was noticed for the home scrap fraction increasing up to the value of 50%. Further increasing the home scrap percentage, however, did not result in a significant rise of the hardness value any more.

Conversion of plutonium scrap and residue to boroilicate glass using the GMODS process

International Nuclear Information System (INIS)

Forsberg, C.W.; Beahm, E.C.; Parker, G.W.; Rudolph, J.; Elam, K.R.; Ferrada, J.J.

1995-01-01

Plutonium scrap and residue represent major national and international concerns because (1) significant environmental, safety, and health (ES ampersand H) problems have been identified with their storage; (2) all plutonium recovered from the black market in Europe has been from this category; (3) storage costs are high; and (4) safeguards are difficult. It is proposed to address these problems by conversion of plutonium scrap and residue to a CRACHIP (CRiticality, Aerosol, and CHemically Inert Plutonium) glass using the Glass Material Oxidation and Dissolution System (GMODS). CRACHIP refers to a set of requirements for plutonium storage forms that minimize ES ampersand H concerns. The concept is several decades old. Conversion of plutonium from complex chemical mixtures and variable geometries into a certified, qualified, homogeneous CRACHIP glass creates a stable chemical form that minimizes ES ampersand H risks, simplifies safeguards and security, provides an easy-to-store form, decreases storage costs, and allows for future disposition options. GMODS is a new process to directly convert metals, ceramics, and amorphous solids to glass; oxidize organics with the residue converted to glass; and convert chlorides to borosilicate glass and a secondary sodium chloride stream. Laboratory work has demonstrated the conversion of cerium (a plutonium surrogate), uranium (a plutonium surrogate), Zircaloy, stainless steel, and other materials to glass. GMODS is an enabling technology that creates new options. Conventional glassmaking processes require conversion of feeds to oxide-like forms before final conversion to glass. Such chemical conversion and separation processes are often complex and expensive

OFFGAS GENERATION FROM THE DISPOSITION OF SCRAP PLUTONIUM BY VITRIFICATION SIMULANT TESTS

International Nuclear Information System (INIS)

Zamecnik, J; Patricia Toole, P; David Best, D; Timothy Jones, T; Donald02 Miller, D; Whitney Thomas, W; Vickie Williams, V

2008-01-01

The Department of Energy Office of Environmental Management is supporting R and D for the conceptual design of the Plutonium Disposition Project at the Savannah River Site in Aiken, SC to reduce the attractiveness of plutonium scrap by fabricating a durable plutonium oxide glass form and immobilizing this form within the high-level waste glass prepared in the Defense Waste Processing Facility. A glass formulation was developed that is capable of incorporating large amounts of actinides as well as accommodating many impurities that may be associated with impure Pu feed streams. The basis for the glass formulation was derived from commercial glasses that had high lanthanide loadings. A development effort led to a Lanthanide BoroSilicate (LaBS) glass that accommodated significant quantities of actinides, tolerated impurities associated with the actinide feed streams and could be processed using established melter technologies. A Cylindrical Induction Melter (CIM) was used for vitrification of the Pu LaBS glass. Induction melting for the immobilization of americium and curium (Am/Cm) in a glass matrix was first demonstrated in 1997. The induction melting system was developed to vitrify a non-radioactive Am/Cm simulant combined with a glass frit. Most of the development of the melter itself was completed as part of that work. This same melter system used for Am/Cm was used for the current work. The CIM system used consisted of a 5 inch (12.7 cm) diameter inductively heated platinum-rhodium (Pt-Rh) containment vessel with a control system and offgas characterization. Scrap plutonium can contain numerous impurities including significant amounts of chlorides, fluorides, sodium, potassium, lead, gallium, chromium, and nickel. Smaller amounts of additional elements can also be present. The amount of chlorides present is unusually high for a melter feed. In commercial applications there is no reason to have chloride at such high concentrations. Because the melter operates at

A recovery of gold from electronic scrap by mechanical separation, acid leaching and electrowinning

Energy Technology Data Exchange (ETDEWEB)

Rhee, K.I.; Lee, J.C.; Lee, C.K.; Joo, K.H.; Yoon, J.K.; Kang, H.R.; Kim, Y.S.; Sohn, H.J.

1995-12-31

A series of processes to recover the gold from electronic scrap which contains initially about 200--600 ppm Au have been developed. First, mechanical beneficiation including shredding, crushing and screening was employed. Results showed that 99 percent of gold component leaves in the fraction of under 1 mm of crushed scrap and its concentration was enriched to about 800 ppm without incineration. The scrap was leached in 50% aqua regia solution and gold was dissolved completely at 60 C within 2 hours. Other valuable metals such as silver, copper, nickel and iron were also dissolved. This resulting solution was boiled to remove nitrous compounds in the leachate. Finally, a newly designed electrolyzer was tested to recover the gold metal. More than 99% of gold and silver were recovered within an hour in electrowinning process.

The reuse of scrap and decontamination waste water from decommissioning

International Nuclear Information System (INIS)

Deng Junxian; Li Xin; Xie Xiaolong

2010-01-01

Huge amount of radioactive scrap with low activity will be generated from reactor decommissioning; the decontamination is concentrated in the surface layer of the scrap. The decontaminated substance can be removed by high pressure water jet to appear the base metal and to reuse the metal. Big amount of radioactive waste water will be generated by this decontamination technology; the radioactive of the waste water is mainly caused by the solid particle from decontamination. To remove the solid particle as clean as possible, the waste water can be reused. Different possible technology to remove the solid particle from the water had been investigated, such as the gravity deposit separation, the filtration and the centrifugal separation etc. The centrifugal separation technology is selected; it includes the hydraulic vortex, the centrifugal filtration and the centrifugal deposit. After the cost benefit analysis at last the centrifugal deposit used butterfly type separator is selected. To reuse the waste water the fresh water consumption and the cost for waste water treatment can be reduced. To reuse the radioactive scrap and the waste water from decommissioning will minimize the radioactive waste. (authors)

Institutional disposition and management of end-of-life electronics.

Science.gov (United States)

Babbitt, Callie W; Williams, Eric; Kahhat, Ramzy

2011-06-15

Institutions both public and private face a challenge to develop policies to manage purchase, use, and disposal of electronics. Environmental considerations play an increasing role in addition to traditional factors of cost, performance and security. Characterizing current disposition practices for end-of-life electronics is a key step in developing policies that prevent negative environmental and health impacts while maximizing potential for positive social and economic benefits though reuse. To provide a baseline, we develop the first characterization of quantity, value, disposition, and flows of end-of-life electronics at a major U.S. educational institution. Results of the empirical study indicate that most end-of-first-life electronics were resold through public auction to individuals and small companies who refurbish working equipment for resale or sell unusable products for reclamation of scrap metal. Desktop and laptop computers sold for refurbishing and resale averaged U.S. $20-100 per unit, with computers sold directly to individuals for reuse reaching $250-350 per unit. This detailed assessment was coupled with a benchmarking survey of end-of-life electronics management practices at other U.S. universities. Survey results indicate that while auctions are still commonplace, an increasing number of institutions are responding to environmental concerns by creating partnerships with local recycling and resale entities and mandating domestic recycling. We use the analyses of current disposition practices as input to discuss institutional strategies for managing electronics. One key issue is the tension between benefits of used equipment sales, in terms of income for the institution and increased reuse for society, and the environmental risks because of unknown downstream practices.

Primary Raw Materials for Steelmakers: Scrap and Pig Iron

Directory of Open Access Journals (Sweden)

Cristina Bumbac

2011-10-01

Full Text Available Most of the daily steel we so much need is obtained now in electric furnaces, for which the main raw material is scrap. The scrap market is a very sensitive one, depending very much on internal collect, exports and imports, the market of steel and freight. Commerce with scrap is one of the most intense among all the countries of the world and covers all the routes and regions. Every ten years or so importers become exporters and vice versa, due to the period of life of the metallic products. For example, China was for the last 10 years one of the biggest importers (after Turkey, which is number one in importers' hierarchy, but prognoses tell that in 2-3 years China might become self-sufficient due to the investments which began some 20 years ago. USA was one of the largest exporters, but some 3 years ago some analysts advanced the idea that it may become a net importer (it didn't happened, though. The scrap market is not only important, it is also very interesting, with twisted evolutions and volatile prices in some periods.

Evaluation of Wet Digestion Methods for Quantification of Metal Content in Electronic Scrap Material

Directory of Open Access Journals (Sweden)

Subhabrata Das

2017-11-01

Full Text Available Recent advances in the electronics sector and the short life-span of electronic products have triggered an exponential increase in the generation of electronic waste (E-waste. Effective recycling of E-waste has thus become a serious solid waste management challenge. E-waste management technologies include pyrometallurgy, hydrometallurgy, and bioleaching. Determining the metal content of an E-waste sample is critical in evaluating the efficiency of a metal recovery method in E-waste recycling. However, E-waste is complex and of diverse origins. The lack of a standard digestion method for E-waste has resulted in difficulty in comparing the efficiencies of different metal recovery processes. In this study, several solid digestion protocols including American Society for Testing and Materials (ASTM-D6357-11, United States Environment Protection Agency Solid Waste (US EPA SW 846 Method 3050b, ultrasound-assisted, and microwave digestion methods were compared to determine the metal content (Ag, Al, Au, Cu, Fe, Ni, Pb, Pd, Sn, and Zn of electronic scrap materials (ESM obtained from two different sources. The highest metal recovery (mg/g of ESM was obtained using ASTM D6357-11 for most of the metals, which remained mainly bound to silicate fractions, while a microwave-assisted digestion protocol (MWD-2 was more effective in solubilizing Al, Pb, and Sn. The study highlights the need for a judicious selection of digestion protocol, and proposes steps for selecting an effective acid digestion method for ESM.

The melting treatment of bulk scrap from decommissioning

International Nuclear Information System (INIS)

Deng Junxian; Deng Feng

2014-01-01

Large amount of radioactive scrap will come out from reactor decommissioning. The melting treatment can be used for the volume reduction, the recycle and reuse of the radioactive scrap to reduce the mass of the radioactive waste disposal and to reuse most of the metal. The melting treatment has the advantages in volume reduction, conditioning, radionuclide confinement, reduction of radioactivity concentration, easy monitoring of radioactivity; and the effective of decontamination for several radionuclide. Therefore to use the melting technology other decontamination technology should be performed ahead, the decontamination effect of the melting should be predicted, the utility of recycle and reuse should be defined, and the secondary waste should be controlled effectively. (authors)

The Influence of Home Scrap on Porosity of MgAl9Zn1 Alloy Pressure Castings

Directory of Open Access Journals (Sweden)

Konopka Z.

2017-03-01

Full Text Available The work presents the results of examinations concerning the influence of various amounts of home scrap additions on the porosity of castings made of MgAl9Zn1 alloy. The fraction of home scrap in the metal charge ranged from 0 to 100%. Castings were pressure cast by means of the hot-chamber pressure die casting machine under the industrial conditions in one of the domestic foundries. Additionally, for the purpose of comparison, the porosity of specimens cut out directly of the MgAl9Zn1 ingot alloy was also determined. The examinations consisted in the qualitative assessment of porosity by means of the optical microscopy and its quantitative determination by the method of weighting specimens in air and in water. It was found during the examination that the porosity of castings decreases with an increase in the home scrap fraction in the metal charge. The qualitative examinations confirmed the beneficial influence of the increased home scrap fraction on the porosity of castings. It was concluded that the reusing of home scrap in a foundry can be a good way of reduction of costs related to the production of pressure castings.

Efficient One-Step Electrolytic Recycling of Low-Grade and Post-Consumer Magnesium Scrap

Energy Technology Data Exchange (ETDEWEB)

Adam C. Powell, IV

2012-07-19

Metal Oxygen Separation Technologies, Inc. (abbreviated MOxST, pronounced most) and Boston University (BU) have developed a new low-cost process for recycling post-consumer co-mingled and heavily-oxidized magnesium scrap, and discovered a new chemical mechanism for magnesium separations in the process. The new process, designated MagReGenTM, is very effective in laboratory experiments, and on scale-up promises to be the lowest-cost lowest-energy lowest-impact method for separating magnesium metal from aluminum while recovering oxidized magnesium. MagReGenTM uses as little as one-eighth as much energy as today's methods for recycling magnesium metal from comingled scrap. As such, this technology could play a vital role in recycling automotive non-ferrous metals, particularly as motor vehicle magnesium/aluminum ratios increase in order to reduce vehicle weight and increase efficiency.

German experience in recycling of contaminated scrap by melting

International Nuclear Information System (INIS)

Quade, U.

2003-01-01

Recycling of radioactively contaminated scrap to products for further application in the nuclear cycle is Germany as an economic alternative. It has been shown that recycling within the nuclear industry reduces the collective dose as well as the number of individuals who receive doses. In the future when decommissioning of NPP will increase, a high amount of slightly radioactive steel scrap has to be managed safely. Recycling will play an important role to keep as much of these materials within the nuclear cycle as economically possible. Siempelkamp supplies a broad range of products made of recycled material from the nuclear industry. Containers made of nodular cast iron for transport and storage of radwaste as well as containers made of concrete with iron granules additive to increase the density up to 4 g/cm 3 , are offered. Interim and final disposal volume, having consequences on costs, can be reduced when recycling is applied for slightly contaminated metallic scrap

Remelting of Aluminium by Continuous Submersion of Rolled Scrap

Energy Technology Data Exchange (ETDEWEB)

Farner, Snorre

2000-12-01

When remelting aluminium scrap, metal losses due to dross generation is a common problem. Reduction of these losses will give substantial economic and environmental benefits. Dross is generated when aluminium metal oxidizes and films of oxide envelope molten metal. When a cold metal object is immersed in a melt, the heat of the melt around this is transferred so rapidly into the object that a shell of melt often solidifies to the surface of the object. When scrap with low bulk density is charged to a melt, solidification of melt on the cold scrap prevents melt from entering the cavities in the bulk of the scrap, and the bulk density remains low. Thus the scrap tends to float on the melt surface. Submersion of this scrap is important to avoid oxidation and subsequent dross generation. One solution to this is to roll scrap to a strip and feed it into the melt. This system has been examined by studying feeding of a continuous, thin aluminium plate into molten aluminium. Also, the effect of lacquer was considered, as well as feeding the plate into a launder with melt flowing along the surface of the plate. An analytical, one-dimensional, steady-state model has been developed to describe the melting and the melting mechanisms. It is based on a shell solidifying on the plate surface and a gap introducing a thermal resistance 1/h{sub g} between the shell and the plate. The thermal resistance 1/h{sub l} of the boundary layer of the melt is included. Depending on these resistances, the initial temperature of the plate and the melt temperature, a shell will form, and the plate will penetrate a distance P into the melt before it melts away. An experimental apparatus was designed and constructed to feed aluminium plate from a coil into a melt bath at a specified velocity. The plate could be withdrawn rapidly to ''freeze'' the situation like it was below the melt surface. The penetration depth P of the plate could be measured and shell formation observed

Issues in recycling galvanized scrap

Energy Technology Data Exchange (ETDEWEB)

Koros, P.J. [LTV Steel Co., Inc., Cleveland, OH (United States); Hellickson, D.A. [General Motors Corp., Detroit, MI (United States); Dudek, F.J. [Argonne National Lab., IL (United States)

1995-02-10

The quality of the steel used for most galvanizing (and tinplate) applications makes scrap derived from their production and use a premier solid charge material for steelmaking. In 1989 the AISI created a Task Force to define the issues and to recommend technologically and economically sound approaches to assure continued, unhindered recyclability of the growing volume of galvanized scrap. The AISI program addressed the treatment of full-sized industrial bales of scrap. The current, on-going MRI (US)--Argonne National Laboratory program is focused on ``loose`` scrap from industrial and post-consumer sources. Results from these programs, issues of scrap management from source to steel melting, the choices for handling zinc in iron and steelmaking and the benefits/costs for removal of zinc (and lead) from scrap prior to melting in BOF and foundry operations are reviewed in this paper.

Radioactive materials in recycled metals.

Science.gov (United States)

Lubenau, J O; Yusko, J G

1995-04-01

In recent years, the metal recycling industry has become increasingly aware of an unwanted component in metal scrap--radioactive material. Worldwide, there have been 35 instances where radioactive sources were unintentionally smelted in the course of recycling metal scrap. In some cases contaminated metal consumer products were distributed internationally. In at least one case, serious radiation exposures of workers and the public occurred. Radioactive material appearing in metal scrap includes sources subject to licensing under the Atomic Energy Act and also naturally occurring radioactive material. U.S. mills that have smelted a radioactive source face costs resulting from decontamination, waste disposal, and lost profits that range from 7 to 23 million U.S. dollars for each event. To solve the problem, industry and the government have jointly undertaken initiatives to increase awareness of the problem within the metal recycling industry. Radiation monitoring of recycled metal scrap is being performed increasingly by mills and, to a lesser extent, by scrap processors. The monitoring does not, however, provide 100% protection. Improvements in regulatory oversight by the government could stimulate improved accounting and control of licensed sources. However, additional government effort in this area must be reconciled with competing priorities in radiation safety and budgetary constraints. The threat of radioactive material in recycled metal scrap will continue for the foreseeable future and, thus, poses regulatory policy challenges for both developed and developing nations.

Process for using lead battery scrap. Verfahren zum Verarbeiten von Bleiakkumulatorenschrott

Energy Technology Data Exchange (ETDEWEB)

Sycev, A P; Kim, G V; Larin, V F; Sidorova, G D; Vicharev, I G; Kuur, V P; Achmetov, R S; Moiseev, G L; Maslov, V I; Kabacek, V G

1986-06-26

The process for using lead battery scrap is such that it leads to an increase of lead metal without the use of fluxes for forming the melt. According to the invention, the battery scrap is broken up, dangerous parts (organic substances containing chlorine) are removed and large pieces of lead (pole bridges, grids, contact pins) are sorted out. The remainder is chopped up into pieces less than 10 mm in size. The small pieces are melted by the suspension melting process at a temperature of 1300 to 1500/sup 0/C in an oxidising atmosphere (air or oxygen) without using any fuel. As the small pieces contain parts of the battery case (= organic substances free of chlorine), they burn in air generating heat, which is then used to melt the sulphate oxide lead compounds. The previously sorted large lead parts are then added to the lead oxide melt. Finally, the lead oxide is reduced to lead metal with coke in a furnace. After the reduction of lead oxide to lead, less than 0.2% of the initial lead content in the battery scrap being processed is lost in the dumped slag.

Effective regeneration of anode material recycled from scrapped Li-ion batteries

Science.gov (United States)

Zhang, Jin; Li, Xuelei; Song, Dawei; Miao, Yanli; Song, Jishun; Zhang, Lianqi

2018-06-01

Recycling high-valuable metal elements (such as Li, Ni, Co, Al and Cu elements) from scrapped lithium ion batteries can bring significant economic benefits. However, recycling and reusing anode material has not yet attracted wide attention up to now, due to the lower added-value than the above valuable metal materials and the difficulties in regenerating process. In this paper, a novel regeneration process with significant green advance is proposed to regenerate anode material recycled from scrapped Li-ion batteries for the first time. After regenerated, most acetylene black (AB) and all the styrene butadiene rubber (SBR), carboxymethylcellulose sodium (CMC) in recycled anode material are removed, and the surface of anode material is coated with pyrolytic carbon from phenolic resin again. Finally, the regenerated anode material (graphite with coating layer, residual AB and a little CMC pyrolysis product) is obtained. As expected, all the technical indexs of regenerated anode material exceed that of a midrange graphite with the same type, and partial technical indexs are even closed to that of the unused graphite. The results indicate the effective regeneration of anode material recycled from scrapped Li-ion batteries is really achieved.

Palladium and gold removal and recovery from precious metal solutions and electronic scrap leachates by Desulfovibrio desulfuricans.

Science.gov (United States)

Creamer, Neil J; Baxter-Plant, Victoria S; Henderson, John; Potter, M; Macaskie, Lynne E

2006-09-01

Biomass of Desulfovibrio desulfuricans was used to recover Au(III) as Au(0) from test solutions and from waste electronic scrap leachate. Au(0) was precipitated extracellularly by a different mechanism from the biodeposition of Pd(0). The presence of Cu(2+) ( approximately 2000 mg/l) in the leachate inhibited the hydrogenase-mediated removal of Pd(II) but pre-palladisation of the cells in the absence of added Cu(2+) facilitated removal of Pd(II) from the leachate and more than 95% of the Pd(II) was removed autocatalytically from a test solution supplemented with Cu(II) and Pd(II). Metal recovery was demonstrated in a gas-lift electrobioreactor with electrochemically generated hydrogen, followed by precipitation of recovered metal under gravity. A 3-stage bioseparation process for the recovery of Au(III), Pd(II) and Cu(II) is proposed.

Metal recycling experience at Los Alamos National Laboratory. Reuse, release, and recycle of metals from radiological control areas

International Nuclear Information System (INIS)

Gogol, S.

1997-01-01

Approximately 15% of the Low-Level Waste (LLW) produced at Los Alamos consists of scrap metal equipment and materials. The majority of this material is produced by decommissioning and the modification of existing facilities. To reduce this waste stream, Department of Energy Headquarters, EM-77 Office, sponsored the Reuse, Recycle, and Release of Metals from Radiological Control Areas High Return on Investment (ROI) Project to implement recycle, reuse, and release of scrap metal at the laboratory. The goal of this project was to develop cost effective alternatives to LLW disposal of scrap metal and to avoid the disposal of 2,400 m 3 of scrap metal. The ROI for this project was estimated at 948%. The ROI project was funded in March 1996 and is scheduled for completion by October 1997. At completion, a total of 2,400 m 3 of LLW avoidance will have been accomplished and a facility to continue recycling activities will be operational. This paper will present the approach used to develop effective alternatives for scrap metal at Los Alamos and then discuss the tasks identified in the approach in detail. Current scrap metal inventory, waste projections, alternatives to LLW disposal, regulatory guidance, and efforts to institutionalize the alternatives to LLW disposal will be discussed in detail

Design requirements for a metal-smelting facility

International Nuclear Information System (INIS)

Williams, L.C.; Mack, J.E.

1982-01-01

Functional requirements for the smelting of metal scrap contaminated with low-enriched uranium in a Metal Smelting Faclity (MSF) have been determined. The process will be designed to smelt ferrous metal scrap that has accumulated at the Oak Ridge Gaseous Diffusion Plant (ORGDP) into one-ton ingots at a rate of 40 ingots per day (10,000 tons/year). Total scrap inventories at the ORGDP are currently estimated at 28,000 tons. The diffusion plant scrap is primarily contaminated with 100 to 200 ppm U at an enrichment of 0.5 to 1.5% 235 U. The scrap is considered special nuclear material (SNM) and cannot be handled by commercial smelters without specific licensing. Slagging will be performed to remove contaminants from the metal and concentrate them in the slag. Process systems will include scrap handling, size reduction, preheating and charging, melting and slagging, ingot casting and storage, and fume exhaust. The MSF has been proposed for FY 1984 line item funding

Study of silver removal from scrap jewellery by way of the flotation process

Directory of Open Access Journals (Sweden)

B. Oleksiak

2012-01-01

Full Text Available This article is a discussion on the proposed solution of using the fl otation process to separate metals from non-metallic components present in the scrap generated while jewellery goods are being ground. For the sake of the studies analysed, a dedicated laboratory station was established.

Testing of wet scrap recovery equipment for mixed oxide scrap reprocessing

International Nuclear Information System (INIS)

Demiter, J.A.; Klem, M.J.; Owen, T.J.

1984-08-01

The Wet Scrap Recovery (WSR) program was initiated at the Hanford Engineering Development Laboratory (HEDL) by Westinghouse Hanford Company in Richland, Washington to demonstrate fuel fabrication scrap recovery and reconversion to fuel grade oxide powder using the continuous coprecipitation-calcination (COPRECAL) conversion process. Advancements in process control equipment and instrumentation were also developed and demonstrated

Beneficial reuse `96: The fourth annual conference on the recycle and reuse of radioactive scrap metal

Energy Technology Data Exchange (ETDEWEB)

NONE

1997-02-01

From October 22-24, 1996 the University of Tennessee`s Energy, Environment and Resources Center and the Oak Ridge National Laboratory`s Center for Risk Management cosponsored Beneficial Reuse `96: The Fourth Annual Conference on the Recycle and Reuse of Radioactive Materials. Along with the traditional focus on radioactive scrap metals, this year`s conference included a wide range of topics pertaining to naturally occurring radioactive materials (NORM), and contaminated concrete reuse applications. As with previous Beneficial Reuse conferences, the primary goal of this year`s conference was to bring together stakeholder representatives for presentations, panel sessions and workshops on significant waste minimization issues surrounding the recycle and reuse of contaminated metals and other materials. A wide range of industry, government and public stakeholder groups participated in this year`s conference. An international presence from Canada, Germany and Korea helped to make Beneficial Reuse `96 a well-rounded affair. Selected papers have been processed separately for inclusion in the Energy Science and Technology Database.

A methodology for estimating potential doses and risks from recycling U.S. Department of Energy radioactive scrap metals

International Nuclear Information System (INIS)

MacKinney, J.A.

1995-01-01

The U.S. Environmental Protection Agency (EPA) is considering writing regulations for the controlled use of materials originating from radioactively contaminated zones which may be recyclable. These materials include metals, such as steel (carbon and stainless), nickel, copper, aluminum and lead, from the decommissioning of federal, and non-federal facilities. To develop criteria for the release of such materials, a risk analysis of all potential exposure pathways should be conducted. These pathways include direct exposure to the recycled material by the public and workers, both individual and collective, as well as numerous other potential exposure pathways in the life of the material. EPA has developed a risk assessment methodology for estimating doses and risks associated with recycling radioactive scrap metals. This methodology was applied to metal belonging to the U.S. Department of Energy. This paper will discuss the draft EPA risk assessment methodology as a tool for estimating doses and risks from recycling. (author)

Developing methods for detecting radioactive scrap

International Nuclear Information System (INIS)

Bellian, J.G.; Johnston, J.G.

1995-01-01

During the last 10 years, there have been major developments in radiation detection systems used for catching shielded radioactive sources in scrap metal. The original testing required to determine the extent of the problem and the preliminary designs of the first instruments will be discussed. Present systems available today will be described listing their advantages and disadvantages. In conclusion, the newest developments and state of the art equipment will also be included describing the limits and most appropriate locations for the systems

Fabrication of metallic alloy powder (Ni{sub 3}Fe) from Fe–77Ni scrap

Energy Technology Data Exchange (ETDEWEB)

Seo, Inseok [ES Materials Research Center, Research Institute of Industrial Science and Technology, Incheon 406-840 (Korea, Republic of); Shin, Shun-Myung [Extractive Metallurgy Department, Korea Institute of Geoscience and Mineral Resources, Deajeon 305-350 (Korea, Republic of); Ha, Sang-An [Department of Environmental Engineering, Silla University, Busan 46958 (Korea, Republic of); Wang, Jei-Pil, E-mail: jpwang@pknu.ac.kr [Department of Metallurgical Engineering, Pukyong National University, Busan 608-739 (Korea, Republic of)

2016-06-15

The oxidation behavior of Fe–77Ni alloy scrap was investigated at an oxygen partial pressure of 0.2 atm and temperatures ranging from 400 °C to 900 °C. The corresponding oxidation rate increased with increasing temperature and obeyed the parabolic rate law, as evidenced by its linear proportionality to the temperature. In addition, surface morphologies, cross-sectional views, compositions, structural properties were examined by scanning electron microscopy (SEM), energy dispersive spectroscopy (EDS), and X-ray diffraction (XRD). Diffusion through either the spinel structure or the NiO layer, which were both present in the alloy during oxidation at elevated temperatures, was deemed the rate-limiting step of the reaction. The oxide powder less than 10 μm was obtained from Fe–77Ni alloy scrap was obtained using ball-milling and sieving processes. In fact, 15 h of milling yielded a recovery ratio of 97%. Using hydrogen gas, the oxide powder was successfully reduced to an alloy powder of Ni{sub 3}Fe and reduction rates of ∼97% were achieved after 3 h at 1000 °C. - Highlights: • The oxidation behavior of Fe–77Ni alloy scrap was investigated. • The oxide powder less than 10 μm was obtained from Fe–77Ni alloy scrap. • Using hydrogen gas, the oxide powder was successfully reclaimed. • Reduction rates of ∼97% were achieved after 3 h at 1000 °C.

7 CFR 29.2277 - Leaf scrap.

Science.gov (United States)

2010-01-01

... 7 Agriculture 2 2010-01-01 2010-01-01 false Leaf scrap. 29.2277 Section 29.2277 Agriculture Regulations of the Department of Agriculture AGRICULTURAL MARKETING SERVICE (Standards, Inspections, Marketing... scrap. A byproduct of unstemmed tobacco. Leaf scrap results from handling unstemmed tobacco and consists...

7 CFR 29.3526 - Leaf scrap.

Science.gov (United States)

2010-01-01

... 7 Agriculture 2 2010-01-01 2010-01-01 false Leaf scrap. 29.3526 Section 29.3526 Agriculture Regulations of the Department of Agriculture AGRICULTURAL MARKETING SERVICE (Standards, Inspections, Marketing... Type 95) § 29.3526 Leaf scrap. A byproduct of unstemmed tobacco Leaf scrap results from handling...

7 CFR 29.3034 - Leaf scrap.

Science.gov (United States)

2010-01-01

... 7 Agriculture 2 2010-01-01 2010-01-01 false Leaf scrap. 29.3034 Section 29.3034 Agriculture Regulations of the Department of Agriculture AGRICULTURAL MARKETING SERVICE (Standards, Inspections, Marketing... Leaf scrap. A by-product of unstemmed tobacco. Leaf scrap results from handling unstemmed tobacco and...

7 CFR 29.6022 - Leaf scrap.

Science.gov (United States)

2010-01-01

... 7 Agriculture 2 2010-01-01 2010-01-01 false Leaf scrap. 29.6022 Section 29.6022 Agriculture Regulations of the Department of Agriculture AGRICULTURAL MARKETING SERVICE (Standards, Inspections, Marketing... INSPECTION Standards Definitions § 29.6022 Leaf scrap. A byproduct of unstemmed tobacco Leaf scrap results...

Leaching behaviour of different scrap materials at recovery and recycling companies: full-, pilot- and lab-scale investigation.

Science.gov (United States)

Blondeel, E; Chys, M; Depuydt, V; Folens, K; Du Laing, G; Verliefde, A; Van Hulle, S W H

2014-12-01

Scrap material recovery and recycling companies are confronted with waste water that has a highly fluctuating flow rate and composition. Common pollutants, such as COD, nutrients and suspended solids, potentially toxic metals, polyaromatic hydrocarbons and poly chlorinated biphenyls can exceed the discharge limits. An analysis of the leaching behaviour of different scrap materials and scrap yard sweepings was performed at full-scale, pilot-scale and lab-scale in order to find possible preventive solutions for this waste water problem. The results of these leaching tests (with concentrations that frequently exceeded the Flemish discharge limits) showed the importance of regular sweeping campaigns at the company, leak proof or covered storage of specific scrap materials and oil/water separation on particular leachates. The particulate versus dissolved fraction was also studied for the pollutants. For example, up to 98% of the polyaromatic hydrocarbons, poly chlorinated biphenyls and some metals were in the particulate form. This confirms the (potential) applicability of sedimentation and filtration techniques for the treatment of the majority of the leachates, and as such the rainwater run-off as a whole. Copyright © 2014 Elsevier Ltd. All rights reserved.

Characterization of naturally occurring radioactive materials and Cobald-60 contaminated ferrous scraps from steel industries

International Nuclear Information System (INIS)

Chao, H.E.; Chiu, H.S.; Hunga, J.Y.; His, H.W.; Chen, Y.B.

2002-01-01

Since the occurrence of radioactively contaminated rebar incident in 1992, steel industries in Taiwan were encouraged by Atomic Energy Council (AEC) to install portal monitor to detect the abnormal radiation in shipments of metal scrap feed. From 1994 through 1999, there were 53 discoveries of radioactivity in ferrous scraps by steel companies. These include 15 orphan radioactive sources, 16 cobalt-60 contaminated rebars, 20 Naturally Occurring Radioactive Material (NORM) contaminated scraps, and two unknowns. Most NORM-contaminated scraps were from abroad. The NORM and cobalt-60 contaminated scraps were taken from the steel mills and analyzed in laboratory. The analytical results of scales and sludge sampled from NORM-contaminated scraps combining with the circumstantial evidences indicate that five possible industrial processes may be involved. They are oil production and treatment, heavy mineral sand benefication and rare earth processing, copper mining and processing, recovery of ammonium chloride by lime adsorption in Ammonium-soda process, and tailing of uranium enrichment process. The cobalt-60 activity and trace elements concentrations of contaminated rebars confirm that all of them were produced domestically in the period from Oct. 1982 to Jan. 1983, when the cobalt-60 sources were lost and entered the electric arc furnace to produce the contaminated rebars. (author)

A Pilot Assessment of Occupational Health Hazards in the US Electronic Scrap Recycling Industry.

Science.gov (United States)

Ceballos, Diana M; Gong, Wei; Page, Elena

2015-01-01

The National Institute for Occupational Safety and Health (NIOSH) surveyed a randomly selected sample of electronic scrap (e-scrap) recycling facilities nationwide to characterize work processes, exposures, and controls. Despite multiple attempts to contact 278 facilities, only 47 responded (17% response rate). Surveyed facilities reported recycling a wide variety of electronics. The most common recycling processes were manual dismantling and sorting. Other processes included shredding, crushing, and automated separation. Many facilities reported that they had health and safety programs in place. However, some facilities reported the use of compressed air for cleaning, a practice that can lead to increased employee dust exposures, and some facilities allowed food and drinks in the production areas, a practice that can lead to ingestion of contaminants. Although our results may not be generalizable to all US e-scrap recycling facilities, they are informative regarding health and safety programs in the industry. We concluded that e-scrap recycling has the potential for a wide variety of occupational exposures particularly because of the frequent use of manual processes. On-site evaluations of e-scrap recyclers are needed to determine if reported work processes, practices, and controls are effective and meet current standards and guidelines. Educating the e-scrap recycling industry about health and safety best practices, specifically related to safe handling of metal dust, would help protect employees.

Monitoring system with integrated measuring sensors for radioactively contaminated iron and non-iron scrap metal (MerEN). Final report; Ueberwachungssystem mit integrierter Messsensorik fuer radioaktiv belastete Eisen- und Nichteisenschrotte (MerEN). Abschlussbericht

Energy Technology Data Exchange (ETDEWEB)

Celebic, Enis; Gentes, Sascha [Karlsruher Institut fuer Technologie (KIT), Karlsruhe (Germany). Inst. fuer Technologie und Management im Baubetrieb; Rutschmann, Michael; Goerisch, Uwe [Prof. Dr.-Ing. Uwe Goerisch GmbH Ingenieurbuero fuer Abfallwirtschaft, Karlsruhe (Germany); Wetzel, Ramona [Schrott Wetzel GmbH, Mannheim (Germany)

2015-08-15

Radioactive sources are used in the industry, in nuclear medicine, the military, as well as in research. Accidents and losses rarely occur, a proper and responsible handling of those sources provided. Radioactive sources represent a risk when divulged, moved, passed on without authorization or lost. Time and again, radioactive sources are found at scrap yards and metal processing facilities. The supervision of these radioactive materials is gaining importance in the light of the worldwide import and export of ferrous and non-ferrous scrap. The aim of the project was to develop a space monitoring system for radioactively contaminated ferrous and non-ferrous scrap, so it can be removed from the operating range and to protect staff. The monitoring system combines technical and application-specific requirements. As part of the research project, the system was designed based on the operational framework conditions, technical and economic possibilities, and the findings from the experimental phase. The prototype mainly consists of a mainframe computer, stationary and mobile detection units, and the data transfer technology. This has successfully been tested at a scrap yard. The effects of vibrations that occur on scrapyards were investigated. This was necessary to obtain functionality of the hardware. The experimental phase was carried out based on a pre-defined set-up. The aim was to test the individual scenarios, processing and logging of the date as well to interpret the test results. In the event of radioactive sources being found in discarded metal, a standard sequence of actions was designed to protect the yard's processes and its personnel against further radioactive damage. For the first time, active radiation monitoring was performed on scrap-processing machines and in the working range of mobile devices. With this, scrap yard operators will have the opportunity to detect radioactively contaminated material at an early stage and before radiation sources are

Lithium Carbonate Recovery from Cathode Scrap of Spent Lithium-Ion Battery: A Closed-Loop Process.

Science.gov (United States)

Gao, Wenfang; Zhang, Xihua; Zheng, Xiaohong; Lin, Xiao; Cao, Hongbin; Zhang, Yi; Sun, Zhi

2017-02-07

A closed-loop process to recover lithium carbonate from cathode scrap of lithium-ion battery (LIB) is developed. Lithium could be selectively leached into solution using formic acid while aluminum remained as the metallic form, and most of the other metals from the cathode scrap could be precipitated out. This phenomenon clearly demonstrates that formic acid can be used for lithium recovery from cathode scrap, as both leaching and separation reagent. By investigating the effects of different parameters including temperature, formic acid concentration, H 2 O 2 amount, and solid to liquid ratio, the leaching rate of Li can reach 99.93% with minor Al loss into the solution. Subsequently, the leaching kinetics was evaluated and the controlling step as well as the apparent activation energy could be determined. After further separation of the remaining Ni, Co, and Mn from the leachate, Li 2 CO 3 with the purity of 99.90% could be obtained. The final solution after lithium carbonate extraction can be further processed for sodium formate preparation, and Ni, Co, and Mn precipitates are ready for precursor preparation for cathode materials. As a result, the global recovery rates of Al, Li, Ni, Co, and Mn in this process were found to be 95.46%, 98.22%, 99.96%, 99.96%, and 99.95% respectively, achieving effective resources recycling from cathode scrap of spent LIB.

7 CFR 29.1169 - Scrap (S Group).

Science.gov (United States)

2010-01-01

... 7 Agriculture 2 2010-01-01 2010-01-01 false Scrap (S Group). 29.1169 Section 29.1169 Agriculture Regulations of the Department of Agriculture AGRICULTURAL MARKETING SERVICE (Standards, Inspections, Marketing... INSPECTION Standards Grades § 29.1169 Scrap (S Group). A byproduct of stemmed and unstemmed tobacco. Scrap...

7 CFR 29.2441 - Scrap (S Group).

Science.gov (United States)

2010-01-01

... 7 Agriculture 2 2010-01-01 2010-01-01 false Scrap (S Group). 29.2441 Section 29.2441 Agriculture Regulations of the Department of Agriculture AGRICULTURAL MARKETING SERVICE (Standards, Inspections, Marketing... INSPECTION Standards Grades § 29.2441 Scrap (S Group). A byproduct of unstemmed and stemmed tobacco. Scrap...

Spent lithium-ion battery recycling - Reductive ammonia leaching of metals from cathode scrap by sodium sulphite.

Science.gov (United States)

Zheng, Xiaohong; Gao, Wenfang; Zhang, Xihua; He, Mingming; Lin, Xiao; Cao, Hongbin; Zhang, Yi; Sun, Zhi

2017-02-01

Recycling of spent lithium-ion batteries has attracted wide attention because of their high content of valuable and hazardous metals. One of the difficulties for effective metal recovery is the separation of different metals from the solution after leaching. In this research, a full hydrometallurgical process is developed to selectively recover valuable metals (Ni, Co and Li) from cathode scrap of spent lithium ion batteries. By introducing ammonia-ammonium sulphate as the leaching solution and sodium sulphite as the reductant, the total selectivity of Ni, Co and Li in the first-step leaching solution is more than 98.6% while it for Mn is only 1.36%. In detail understanding of the selective leaching process is carried out by investigating the effects of parameters such as leaching reagent composition, leaching time (0-480min), agitation speed (200-700rpm), pulp density (10-50g/L) and temperature (323-353K). It was found that Mn is primarily reduced from Mn 4+ into Mn 2+ into the solution as [Formula: see text] while it subsequently precipitates out into the residue in the form of (NH 4 ) 2 Mn(SO 3 ) 2 ·H 2 O. Ni, Co and Li are leached and remain in the solution either as metallic ion or amine complexes. The optimised leaching conditions can be further obtained and the leaching kinetics is found to be chemical reaction control under current leaching conditions. As a result, this research is potentially beneficial for further optimisation of the spent lithium ion battery recycling process after incorporating with metal extraction from the leaching solution. Copyright © 2016 Elsevier Ltd. All rights reserved.

Advanced methods for incineration of solid, burnable LLW and melting for recycling of scrap metals

International Nuclear Information System (INIS)

Krause, G.; Lorenzen, J.; Lindberg, M.; Olsson, L.; Wirendal, B.

2003-01-01

Radioactive contaminated waste is a great cost factor for nuclear power plants and other nuclear industry. On the deregulated electricity market the price on produced kWh is an important competition tool. Therefore the waste minimisation and volume reduction has given highest priority by many power producers in the process to achieve savings and hence low production cost. Studsvik RadWaste AB in Nykoeping, Sweden, is a company specialised in volume reduction of LLW, as solid combustible waste and as scrap metal for melting and recycling. The treatment facility in Sweden offers this kind of services - together with segmentation and decontamination when necessary - for several customers from Europe, Japan and USA. In addition to these treatment services a whole spectrum of services like transportation, measurement and safeguard, site assistance, industrial cleaning and decontamination in connection with demolition at site is offered from the Studsvik company. (orig.)

Quality- and dilution losses in the recycling of ferrous materials from end-of-life passenger cars: input-output analysis under explicit consideration of scrap quality.

Science.gov (United States)

Nakamura, Shinichiro; Kondo, Yasushi; Matsubae, Kazuyo; Nakajima, Kenichi; Tasaki, Tomohiro; Nagasaka, Tetsuya

2012-09-04

Metals can in theory be infinitely recycled in a closed-loop without any degradation in quality. In reality, however, open-loop recycling is more typical for metal scrap recovered from end-of-life (EoL) products because mixing of different metal species results in scrap quality that no longer matches the originals. Further losses occur when meeting the quality requirement of the target product requires dilution of the secondary material by adding high purity materials. Standard LCA usually does not address these losses. This paper presents a novel approach to quantifying quality- and dilution losses, by means of hybrid input-output analysis. We focus on the losses associated with the recycling of ferrous materials from end-of-life vehicle (ELV) due to the mixing of copper, a typical contaminant in steel recycling. Given the quality of scrap in terms of copper density, the model determines the ratio by which scrap needs to be diluted in an electric arc furnace (EAF), and the amount of demand for EAF steel including those quantities needed for dilution. Application to a high-resolution Japanese IO table supplemented with data on ferrous materials including different grades of scrap indicates that a nationwide avoidance of these losses could result in a significant reduction of CO(2) emissions.

The Spanish system for the radiological surveillance and control of scrap and the products resulting from its processing

International Nuclear Information System (INIS)

Gil, E.

2001-01-01

Despite the fact that the use of radiation technologies has always been subjected to strict controls in most countries, the presence of radioactive materials in scrap has been detected relatively often in recent years. This has led to the implementation of a series of international initiatives aimed at detecting and preventing illicit international trafficking with radioactive material, intentional or otherwise. The Spanish iron and steel industry is one of the most important industrial sectors in the country, and depends to a large extent on the importing of a significant proportion of the scrap its uses as raw material. Experience has shown that that countries that import large quantities of scrap should complement the aforementioned international initiatives with others of national scope, in order to reduce the risks arising from the presence of radioactive material in scrap. In this context, the Spanish radiological protection authorities, along with the business associations involved in the metal recovery and smelting industry, have established a national system for the radiological surveillance and control of scrap and of the products resulting from its processing. The system consists of a set of legal bases, the installation of specific radiological surveillance equipment and the enhancement of other general purpose equipment that existed prior to these initiatives, the development of radiological training and information plans for the professionals involved in the metal recovery and smelting sectors and improvement to the national radiological emergency response system. (author)

Uranium decontamination of common metals by smelting, a review (handbook)

International Nuclear Information System (INIS)

Mautz, E.W.; Briggs, G.G.; Shaw, W.E.; Cavendish, J.H.

1975-01-01

The published and unpublished literature relating to the smelting of common metals scrap contaminated with uranium-bearing compounds has been searched and reviewed. In general, standard smelting practice produces ingots having a low uranium content, particularly for ferrous, nickel, and copper metals or alloys. Aluminum recovered from uranium contaminated scrap shows some decontamination by smelting but the uranium content is not as low as for other metals. Due to the heterogeneous nature and origin of scrap metals contaminated with uranium, information is frequently missing as to the extent of the initial contamination and the degree of decontamination obtained. The uranium content of the final cast ingots is generally all that is available. Results are summarized below by the primary composition of the uranium contaminated scrap metal. (U.S.)

Recycling of rare earths from Hg-containing fluorescent lamp scraps by solid state chlorination

International Nuclear Information System (INIS)

Lorenz, Tom; Froehlich, Peter; Bertau, Martin; Golon, Katja

2015-01-01

Solid state chlorination with NH 4 Cl comprises a method for rare earth recycling apart from pyro- or hydrometallurgical strategies. The examined partially Hg-containing fluorescent lamp scraps are rich in rare earths like La, Ce, Tb and Gd, but especially in Y and Eu. By mixing with NH 4 Cl and heating up to NH 4 Cl decomposition temperature in a sublimation reactor, Y and Eu could be transferred selectively into their respective metal chlorides with high yields. The yield and selectivity depend on temperature and the ratio of NH 4 Cl to fluorescent lamp scraps, which were varied systematically.

Overview of flow studies for recycling metal commodities in the United States

Science.gov (United States)

Sibley, Scott F.

2011-01-01

Metal supply consists of primary material from a mining operation and secondary material, which is composed of new and old scrap. Recycling, which is the use of secondary material, can contribute significantly to metal production, sometimes accounting for more than 50 percent of raw material supply. From 2001 to 2011, U.S. Geological Survey (USGS) scientists studied 26 metals to ascertain the status and magnitude of their recycling industries. The results were published in chapters A-Z of USGS Circular 1196, entitled, "Flow Studies for Recycling Metal Commodities in the United States." These metals were aluminum (chapter W), antimony (Q), beryllium (P), cadmium (O), chromium (C), cobalt (M), columbium (niobium) (I), copper (X), germanium (V), gold (A), iron and steel (G), lead (F), magnesium (E), manganese (H), mercury (U), molybdenum (L), nickel (Z), platinum (B), selenium (T), silver (N), tantalum (J), tin (K), titanium (Y), tungsten (R), vanadium (S), and zinc (D). Each metal commodity was assigned to a single year: chapters A-M have recycling data for 1998; chapters N-R and U-W have data for 2000, and chapters S, T, and X-Z have data for 2004. This 27th chapter of Circular 1196 is called AA; it includes salient data from each study described in chapters A-Z, along with an analysis of overall trends of metals recycling in the United States during 1998 through 2004 and additional up-to-date reviews of selected metal recycling industries from 1991 through 2008. In the United States for these metals in 1998, 2000, and 2004 (each metal commodity assigned to a single year), 84 million metric tons (Mt) of old scrap was generated. Unrecovered old scrap totaled 43 Mt (about 51 percent of old scrap generated, OSG), old scrap consumed was 38 Mt (about 45 percent of OSG), and net old scrap exports were 3.3 Mt (about 4 percent of OSG). Therefore, there was significant potential for increased recovery from scrap. The total old scrap supply was 88 Mt, and the overall new-to-old-scrap

WINCO Metal Recycle annual report, FY 1993

International Nuclear Information System (INIS)

Bechtold, T.E.

1993-12-01

This report is a summary of the first year progress of the WINCO Metal Recycle Program. Efforts were directed towards assessment of radioactive scrap metal inventories, economics and concepts for recycling, technology development, and transfer of technology to the private sector. Seven DOE laboratories worked together to develop a means for characterizing scrap metal. Radioactive scrap metal generation rates were established for several of these laboratories. Initial cost estimates indicate that recycle may be preferable over burial if sufficient decontamination factors can be achieved during melt refining. Radiation levels of resulting ingots must be minimized in order to keep fabrication costs low. Industry has much of the expertise and capability to execute the recycling of radioactive scrap metal. While no single company can sort, melt, refine, roll and fabricate, a combination of two to three can complete this operation. The one process which requires development is in melt refining for removal of radionuclides other than uranium. WINCO is developing this capability in conjunction with academia and industry. This work will continue into FY-94

WINCO Metal Recycle annual report, FY 1993

Energy Technology Data Exchange (ETDEWEB)

Bechtold, T.E. [ed.

1993-12-01

This report is a summary of the first year progress of the WINCO Metal Recycle Program. Efforts were directed towards assessment of radioactive scrap metal inventories, economics and concepts for recycling, technology development, and transfer of technology to the private sector. Seven DOE laboratories worked together to develop a means for characterizing scrap metal. Radioactive scrap metal generation rates were established for several of these laboratories. Initial cost estimates indicate that recycle may be preferable over burial if sufficient decontamination factors can be achieved during melt refining. Radiation levels of resulting ingots must be minimized in order to keep fabrication costs low. Industry has much of the expertise and capability to execute the recycling of radioactive scrap metal. While no single company can sort, melt, refine, roll and fabricate, a combination of two to three can complete this operation. The one process which requires development is in melt refining for removal of radionuclides other than uranium. WINCO is developing this capability in conjunction with academia and industry. This work will continue into FY-94.

Recycling of contaminated scrap by melting 10 years of experience in Germany

International Nuclear Information System (INIS)

Hamm, M.; Kreh, R.; Quade, U.

2000-01-01

Recycling of slightly radioactively contaminated steel scrap from nuclear installations has been developed in Germany since the early 80's. 14,000 t of steel scrap were melted in the single purpose melting plant CARLA at Siempelkamp, Krefeld, up to now. As much material as possible is used for recycling to cast iron containers, shieldings or to replace iron ore in heavy concrete shieldings by iron granules. By this well developed recycling technique within the nuclear cycle radiation exposure of the general public could be avoided. Due to the max. achievable volume reduction, 80 % of final disposal volume have been saved so far. To manage the upcoming metallic waste from decommissioning of nuclear power plants, this recycling path will play an important role in the future. (authors)

Process evaluations for uranium recovery from scrap material

International Nuclear Information System (INIS)

Westphal, B.R.; Benedict, R.W.

1992-01-01

The integral Fast Reactor (IFR) concept being developed by Argonne National Laboratory is based on pyrometallurgical processing of spent nuclear metallic fuel with subsequent fabrication into new reactor fuel by an injection casting sequence. During fabrication, a dilute scrap stream containing uranium alloy fines and broken quartz (Vycor) molds in produced. Waste characterization of this stream, developed by using present operating data and chemical analysis was used to evaluate different uranium recovery methods and possible process variations for the return of the recovered metal. Two methods, comminution with size separation and electrostatic separation, have been tested and can recover over 95% of the metal. Recycling the metal to either the electrochemical process or the injection casting was evaluated for the different economic and process impacts. The physical waste parameters and the important separation process variables are discussed with their effects on the viability of recycling the material. In this paper criteria used to establish the acceptable operating limits is discussed

United States copper metal and scrap use and trade patterns, 1995‒2014

Science.gov (United States)

Goonan, Thomas G.

2016-06-17

In 1995, China accounted for 10 percent of world copper consumption. By 2014, China accounted for about 49 percent of world copper consumption. This change has affected global copper and copper scrap prices, the sources of copper supply, and U.S. trade of copper-containing materials.

Structure of the AZ91 alloy pressure castings fabricated of home scrap containing charge

Directory of Open Access Journals (Sweden)

Z. Konopka

2011-04-01

Full Text Available The influence of the AZ91 alloy home scrap addition to the metal charge on both the structure and the selected mechanical propertiesof pressure castings was examined in this article. Two heats were made using different components, the first with only pure AZ91 alloyingots in the charge, and the second containing 30 wt % of home scrap. The hot chamber 3 MN machine was used for casting. Thestructures of the castings and their Brinell hardness were examined for both cases. A strong refinement of crystals was observed in castings made with the contribution of the recycled material. Any significant differences in castings hardness were not observed.

Measures to detect and control radioactive contaminated metallurgical scrap at border checkpoints in Poland

International Nuclear Information System (INIS)

Smagala, G.

1999-01-01

The issue of radioactive contaminated metallurgical scrap has never received a high priority in Poland and in the international community. Since the dissolution of the former Soviet Union a higher attention has been given to the problem. Poland which is located between the West and East Europe has the obligation to develop and implement an effective prevention and detection system. The reasons to increase national control and detection system at the border checkpoints in Poland are to avoid the following risks: post Chernobyl contamination transports of commodities; transport of contaminated metal scrap; transfer of radioactive waste for their disposal or utilization; high risk of becoming a transit country of illicit trafficking of nuclear materials and radioactive sources. In order to avoid the above-mentioned risks, Poland initiated in 1990, a deployment of the portable radiation devices at the border checkpoints and, as of 1998, the number of installed instruments exceeded a hundred. This paper presents Poland's activities to detect contaminated scrap at its border checkpoints. (author)

The new MAW scrap processing facility

International Nuclear Information System (INIS)

Kueppers, L.

1994-01-01

The shielded bunker for heat-generating waste attached to the MAW scrap processing cell will be modified and extended to comprise several MAW scrap processing cells of enhanced throughput capacity, and a new building to serve as an airlock and port for acceptance of large shipping casks (shipping cask airlock, TBS). The new facility is to process scrap from decommissioned nuclear installations, and in addition radwaste accrued at operating plants of utilities. This will allow efficient and steady use of the new MAW scrap processing facility. The planning activities for modification and extension are based on close coordination between KfK and the GNS mbH, in order to put structural dimensioning and capacity planning on a realistic basis in line with expected amounts of radwaste from operating nuclear installations of utilities. The paper indicates the currently available waste amount assessments covering solid radwaste (MAW) from the decommissioning of the WAK, MZFR, and KNK II, and existing waste amounts consisting of core internals of German nuclear power plant. The figures show that the MAW scrap processing facility will have to process an overall bulk of about 1100 Mg of solid waste over the next ten years to come. (orig./HP) [de

Rapid Separation Methods to Characterize Actinides and Metallic Impurities in Plutonium Scrap Materials at SRS

International Nuclear Information System (INIS)

Maxwell, S.L. III; Jones, V.D.

1998-07-01

The Nuclear Materials Stabilization and Storage Division at SRS plans to stabilize selected plutonium scrap residue materials for long term storage by dissolution processing and plans to stabilize other plutonium vault materials via high-temperature furnace processing. To support these nuclear material stabilization activities, the SRS Analytical Laboratories Department (ALD) will provide characterization of materials required prior to the dissolution or the high-firing of these materials. Lab renovations to install new analytical instrumentation are underway to support these activities that include glove boxes with simulated-process dissolution and high- pressure microwave dissolution capability. Inductively-coupled plasma atomic emission spectrometry (ICP-AES), inductively- coupled mass spectrometry (ICP-MS) and thermal-ionization mass spectrometry (TIMS) will be used to measure actinide isotopics and metallic impurities. New high-speed actinide separation methods have been developed that will be applied to isotopic characterization of nuclear materials by TIMS and ICP-MS to eliminate isobaric interferences between Pu-238 /U- 238 and Pu-241/Am-241. TEVA Resin, UTEVA Resin, and TRU Resin columns will be used with vacuum-assisted flow rates to minimize TIMS and ICP-MS sample turnaround times. For metallic impurity analysis, rapid column removal methods using UTEVA Resin, AGMP-1 anion resin and AG MP-50 cation resin have also been developed to remove plutonium and uranium matrix interferences prior to ICP-AES and ICP- MS measurements

7 CFR 29.2529 - Leaf scrap.

Science.gov (United States)

2010-01-01

... 7 Agriculture 2 2010-01-01 2010-01-01 false Leaf scrap. 29.2529 Section 29.2529 Agriculture Regulations of the Department of Agriculture AGRICULTURAL MARKETING SERVICE (Standards, Inspections, Marketing... tobacco. Leaf scrap results from handling unstemmed tobacco and consists of loose and tangled whole or...

Modeling the energy content of combustible ship-scrapping waste at Alang-Sosiya, India, using multiple regression analysis.

Science.gov (United States)

Reddy, M Srinivasa; Basha, Shaik; Joshi, H V; Sravan Kumar, V G; Jha, B; Ghosh, P K

2005-01-01

Alang-Sosiya is the largest ship-scrapping yard in the world, established in 1982. Every year an average of 171 ships having a mean weight of 2.10 x 10(6)(+/-7.82 x 10(5)) of light dead weight tonnage (LDT) being scrapped. Apart from scrapped metals, this yard generates a massive amount of combustible solid waste in the form of waste wood, plastic, insulation material, paper, glass wool, thermocol pieces (polyurethane foam material), sponge, oiled rope, cotton waste, rubber, etc. In this study multiple regression analysis was used to develop predictive models for energy content of combustible ship-scrapping solid wastes. The scope of work comprised qualitative and quantitative estimation of solid waste samples and performing a sequential selection procedure for isolating variables. Three regression models were developed to correlate the energy content (net calorific values (LHV)) with variables derived from material composition, proximate and ultimate analyses. The performance of these models for this particular waste complies well with the equations developed by other researchers (Dulong, Steuer, Scheurer-Kestner and Bento's) for estimating energy content of municipal solid waste.

Weapons-grade plutonium dispositioning. Volume 2: Comparison of plutonium disposition options

International Nuclear Information System (INIS)

Brownson, D.A.; Hanson, D.J.; Blackman, H.S.

1993-06-01

The Secretary of Energy requested the National Academy of Sciences (NAS) Committee on International Security and Arms Control to evaluate disposition options for weapons-grade plutonium. The Idaho National Engineering Laboratory (INEL) offered to assist the NAS in this evaluation by investigating the technical aspects of the disposition options and their capability for achieving plutonium annihilation levels greater than 90%. This report was prepared for the NAS to document the gathered information and results from the requested option evaluations. Evaluations were performed for 12 plutonium disposition options involving five reactor and one accelerator-based systems. Each option was evaluated in four technical areas: (1) fuel status, (2) reactor or accelerator-based system status, (3) waste-processing status, and (4) waste disposal status. Based on these evaluations, each concept was rated on its operational capability and time to deployment. A third rating category of option costs could not be performed because of the unavailability of adequate information from the concept sponsors. The four options achieving the highest rating, in alphabetical order, are the Advanced Light Water Reactor with plutonium-based ternary fuel, the Advanced Liquid Metal Reactor with plutonium-based fuel, the Advanced Liquid Metal Reactor with uranium-plutonium-based fuel, and the Modular High Temperature Gas-Cooled Reactor with plutonium-based fuel. Of these four options, the Advanced Light Water Reactor and the Modular High Temperature Gas-Cooled Reactor do not propose reprocessing of their irradiated fuel. Time constraints and lack of detailed information did not allow for any further ratings among these four options. The INEL recommends these four options be investigated further to determine the optimum reactor design for plutonium disposition

Weapons-grade plutonium dispositioning. Volume 2: Comparison of plutonium disposition options

Energy Technology Data Exchange (ETDEWEB)

Brownson, D.A.; Hanson, D.J.; Blackman, H.S. [and others

1993-06-01

The Secretary of Energy requested the National Academy of Sciences (NAS) Committee on International Security and Arms Control to evaluate disposition options for weapons-grade plutonium. The Idaho National Engineering Laboratory (INEL) offered to assist the NAS in this evaluation by investigating the technical aspects of the disposition options and their capability for achieving plutonium annihilation levels greater than 90%. This report was prepared for the NAS to document the gathered information and results from the requested option evaluations. Evaluations were performed for 12 plutonium disposition options involving five reactor and one accelerator-based systems. Each option was evaluated in four technical areas: (1) fuel status, (2) reactor or accelerator-based system status, (3) waste-processing status, and (4) waste disposal status. Based on these evaluations, each concept was rated on its operational capability and time to deployment. A third rating category of option costs could not be performed because of the unavailability of adequate information from the concept sponsors. The four options achieving the highest rating, in alphabetical order, are the Advanced Light Water Reactor with plutonium-based ternary fuel, the Advanced Liquid Metal Reactor with plutonium-based fuel, the Advanced Liquid Metal Reactor with uranium-plutonium-based fuel, and the Modular High Temperature Gas-Cooled Reactor with plutonium-based fuel. Of these four options, the Advanced Light Water Reactor and the Modular High Temperature Gas-Cooled Reactor do not propose reprocessing of their irradiated fuel. Time constraints and lack of detailed information did not allow for any further ratings among these four options. The INEL recommends these four options be investigated further to determine the optimum reactor design for plutonium disposition.

Melting metal waste for volume reduction and decontamination

International Nuclear Information System (INIS)

Copeland, G.L.; Heshmatpour, B.; Heestand, R.L.

1980-01-01

Melt-slagging was investigated as a technique for volume reduction and decontamination of radioactively contaminated scrap metals. Experiments were conducted using several metals and slags in which the partitioning of the contaminant U or Pu to the slag was measured. Concentrations of U or Pu in the metal product of about 1 ppM were achieved for many metals. A volume reduction of 30:1 was achieved for a typical batch of mixed metal scrap. Additionally, the production of granular products was demonstrated with metal shot and crushed slag

Beneficial reuse of a national resource from the nuclear enterprise

International Nuclear Information System (INIS)

Large, D.

1993-01-01

The purpose of this paper is to describe a vital national resource existing within and being generated by the US nuclear enterprise and current and planned technologies and techniques for its beneficial use. Several million tons of radioactively contaminated metals, considered scrap and waste, have been identified at the many commercial and federal sites involved in the nuclear enterprise. Both the public and private sectors have several concerns regarding the disposition of existing inventories and potential generation of contaminated scrap metals. In the past, good metal has been buried as waste. The time has come and is long overdue for that practice to cease. In the late eighties, the US Department of Energy's (DOE's) Oak Ridge office pioneered the move to involve private industry in dealing with the contaminated scrap metal under its purview. Consequently, the Scientific Ecology Group, Inc. (SEG) emerged as the leader in processing contaminated metal for beneficial reuse. To use and advance the technologies and techniques for disposal of radioactively contaminated metals, SEG has built and operates in Oak Ridge, Tennessee, a metal processing facility (MPF). This MPF is used to process radioactively contaminated metals, rid them of most of the contamination, and form them into customized shield blocks and other beneficial-use items. Significant volume reduction for scrap metals (estimated to be in excess of 20 to 1) is achieved with metal-melting services

Exclusion, Exemption and Clearance in the Frame of the Control and Management of Inadvertent Radioactive Material in Scrap Metal

International Nuclear Information System (INIS)

Gonzalez, Abel J.

2011-01-01

Radioactive substances are incorporated into materials, goods, merchandises, products and in scrap and, as scrap would recycle into new produce, the process of introduction of radioactive susbtanaces into commodities will continue. The situation is unstoppable and requires straightforward solutions. The problem is global and therefore the solution(s) should be global. A clear intergovernmental agreement is needed establishing to what extent commodities should be regulated

X-ray Fluorescence in Member States: Ghana. The Use of XRF for Contaminated Site Assessment in Ghana. 2. Estimation of Heavy Metals Contamination at Agbogbloshie E-scrap Yard Using EDXRF Technique

International Nuclear Information System (INIS)

Atiemo, S.M.; Ofosu, F.G.; Aboh, I.J. Kwame

2012-01-01

The emergence of the digital age has underscored the important role that electrical and electronic equipment (EEE) plays in a nation's socioeconomic development, including education, health delivery and communications, as well as global connectivity. In 2003 Ghana formulated its policy on information and communications technology (ICT) for accelerated development, with the understanding for instance, that Ghana's accelerated development would not be possible without an ICT-driven development agenda. The demand for EEE in Ghana grows by the day with a corresponding high rate of waste electrical and electronic (WEEE) generation. The WEEE industry in Ghana is a very vibrant one, growing at an amazing rate year after year. Ghana currently imports about 215 000 tonnes of electrical and electronic equipment per annum out of which an estimated 70% are second hand products. About 60-70% of the second hand products arrive in good working condition, 20-30% can be repaired or refurbished to get them functioning and 10-20% are junk and sent directly for the informal recycling. The Agbogbloshie scrap market in Accra came into the limelight following the publication of the report entitled 'Poisoning the Poor' by Greenpeace International. The report gave a damning revelation about the activities of scrap dealers and recyclers at the market. It was noted from the report that surface dust samples contained high concentrations of both heavy metals and persistent organic pollutants due to the unsafe and crude means of retrieving metals and components from the WEEE. This project was therefore designed to determine the heavy metal concentration of surface dust using the EDXRF and estimate the degree of contamination of the dust samples. Surface dust samples were collected from various vicinities within the scrap yard using the methods described above.

Technical Review of the Characteristics of Spent Nuclear Fuel Scrap

International Nuclear Information System (INIS)

Kuhn, William L.; Abrefah, John; Pitner, Allen L.; Damschen, Dennis W.

2000-01-01

Spent Nuclear Fuel scrap generated while washing the SNF in Hanford's K-Basins to prepare it for cold vacuum drying differed significantly from that envisioned during project design. Therefore, a technical review panel evaluated the new information about the physical characteristics of scrap generated during processing by characterizing it based on measured weights and digital photographic images. They examined images of the scrap and from them estimated the volume and hence the masses of inert material and of large fragments of spent fuel. The panel estimated the area of these particles directly from images and by fitting a lognormal distribution to the relative number particles in four size ranges and then obtaining the area-to-volume ratio from the distribution. The estimated area is 0.3 m2 for the mass of scrap that could be loaded into a container for drying, which compares to a value of 4.5 m2 assumed for safe operation of the baseline process. The small quantity of scrap genera ted is encouraging. However, the size and mass of the scrap depend both on processes degrading the fuel while in the basin and on processes catching the scrap during washing, the latter including essentially unintentional filtration as debris accumulates. Therefore, the panel concluded that the estimated surface area meets the criterion for loading scrap into an MCO for drying, but because it did not attempt to evaluate the criterion itself, it is not in a position to actually recommend loading the scrap. Further, this is not a sufficiently strong technical position from which to extrapolate the results from the examined scrap to all future scrap generated by the existing process

Leaching of DOC, DN, and inorganic constituents from scrap tires.

Science.gov (United States)

Selbes, Meric; Yilmaz, Ozge; Khan, Abdul A; Karanfil, Tanju

2015-11-01

One concern for recycle and reuse of scrap tires is the leaching of tire constituents (organic and inorganic) with time, and their subsequent potential harmful impacts in environment. The main objective of this study was to examine the leaching of dissolved organic carbon (DOC), dissolved nitrogen (DN), and selected inorganic constituents from scrap tires. Different sizes of tire chips and crumb rubber were exposed to leaching solutions with pH's ranging from 3.0 to 10.0 for 28days. The leaching of DOC and DN were found to be higher for smaller size tire chips; however, the leaching of inorganic constituents was independent of the size. In general, basic pH conditions increased the leaching of DOC and DN, whereas acidic pH conditions led to elevated concentrations of metals. Leaching was minimal around the neutral pH values for all the monitored parameters. Analysis of the leaching rates showed that components associated with the rubbery portion of the tires (DOC, DN, zinc, calcium, magnesium, etc.) exhibited an initial rapid followed by a slow release. On the other hand, a constant rate of leaching was observed for iron and manganese, which are attributed to the metal wires present inside the tires. Although the total amounts that leached varied, the observed leaching rates were similar for all tire chip sizes and leaching solutions. Operation under neutral pH conditions, use of larger size tire chips, prewashing of tires, and removal of metal wires prior to application will reduce the impact of tire recycle and reuse. Copyright © 2015 Elsevier Ltd. All rights reserved.

Evaluation of workability and strength of green concrete using waste steel scrap

Science.gov (United States)

Neeraja, D.; Arshad, Shaik Mohammed; Nawaz Nadaf, Alisha K.; Reddy, Mani Kumar

2017-11-01

This project works on the study of workability and mechanical properties of concrete using waste steel scrap from the lathe industry. Lathe industries produce waste steel scrap from the lathe machines. In this study, an attempt is made to use this waste in concrete, as accumulation of waste steel scrap cause disposal problem. Tests like compressive test, split tensile test, NDT test (UPV test) were conducted to determine the impact of steel scrap in concrete. The percentages of steel scrap considered in the study were 0%, 0.5%, 1%, 1.5%, and 2% respectively by volume of concrete, 7 day, 28 days test were conducted to find out strength of steel scrap concrete. It is observed that split tensile strength of steel scrap concrete is increased slightly. Split tensile strength of Steel scrap concrete is found to be maximum with volume fraction of 2.0% steel scrap. The steel scrap gives good result in split tensile strength of concrete. From the study concluded that steel scrap can be used in concrete to reduce brittleness of concrete to some extent.

Processing capabilties for the elimination of contaminated metal scrapyards at DOE/ORO-managed sites

International Nuclear Information System (INIS)

Mack, J.E.; Williams, L.C.

1982-01-01

Capabilities exist for reducing all the contaminated nickel, aluminum, and copper scrap to ingot form by smelting. Processing these metals at existing facilities could be completed in about 5 or 6 years. However, these metals represent only about 20% of the total metal inventories currently on hand at the DOE/ORO-managed sites. No provisions have been made for the ferrous scrap. Most of the ferrous scrap is unclassified and does not require secured storage. Also, the potential resale value of the ferrous scrap at about $100 per ton is very low in comparison. Consequently, this scrap has been allowed to accumulate. With several modifications and equipment additions, the induction melter at PGDP could begin processing ferrous scrap after its commitment to nickel and aluminum. The PGDP smelter is a retrofit installation, and annual throughput capabilities are limited. Processing of the existing ferrous scrap inventories would not be completed until the FY 1995-2000 time frame. An alternative proposal has been the installation of induction melters at the other two enrichment facilities. Conceptual design of a generic metal smelting facility is under way. The design study includes capital and operating costs for scrap preparation through ingot storage at an annual throughput of 10,000 tons per year. Facility design includes an induction melter with the capability of melting both ferrous and nonferrous metals. After three years of operation with scrapyard feed, the smelter would have excess capacity to support on-site decontamination and decomissioning projects or upgrading programs. The metal smelting facility has been proposed for FY 1984 line item funding with start-up operations in FY 1986

Detection of radioactivity in scrap in Germany

International Nuclear Information System (INIS)

Kugeler, E.; Thierfeldt, S.; Sefzig, R.; Weimer, G.

1999-01-01

Although Germany's scrap export exceeds the import, the imports of scrap amount to more than one million Mg per year. Radioactivity has been found mainly in imported scrap in Germany. This radioactivity can consist of surface contamination in scrap e.g. from the oil and gas industry, nuclear and other technical applications or of radiation sources, e.g. from medical or technical irradiation devices where the source has not been removed prior to scrapping. Fortunately really large sources have been involved in only very few occasions. More serious incidents have, however, been reported from other countries. Today, measurement facilities have been installed at the entrances to virtually all German foundries and larger scrap yards. These measurement facilities allow the swift measurement of whole lorry or freight car loads. The lower limit of detection is for some devices as low as ca. 5 nSv/h (dose rate increase above background at the detector) which is achieved by very advanced hardware and software. Additionally, simplified dose rate measurements are performed by German customs officials at the eastern borders for scrap loads to be imported into Germany. When activity is detected in a load, several options exist, like e.g.: (i) sending the scrap back to the sender; (ii) allowing the whole load to be melted down; (iii) careful unloading and separating the load with the aim of localizing and removing the contamination. This paper analyses these various options after detection, discusses the role of the competent authorities and evaluates the possible radiological consequences. Realistic dose calculations show that it is possible that a person may receive doses of several mSv or even 10 mSv if precautionary measures are neglected or if a larger source is not detected at all. This paper further addresses which types and amounts of radioactivity may be detected and which conclusions can be drawn from the dose rate at the detector. The continuous increase in the number

REMOVING ZINC FROM GALVANIZED STEEL SCRAP TO FEASIBLE THE BOF SLUDGE RECYCLING

Directory of Open Access Journals (Sweden)

Mônica Marques Caetano de Lima

2013-06-01

Full Text Available Galvanized steel scraps generated at Usiminas Ipatinga are recycled in BOF converters. Although they are noble products, they contain a significant quantity of zinc that escapes from the bath due to its high vapor pressure and is captured by the gas control system, appearing in BOF sludge. As BOF sludge contains high iron content, it could be recycled to the process, but due to its zinc content, it is disposed in landfills. For this reason, this study aimed to treat these scraps to remove zinc layer using a thermal treatment process. The samples were fed to a rotative furnace in an inert ambient. It was tested the hot dip galvanized and eletrogalvanized scraps, varying the zinc coating weight between 20g/m2 and 150g/m2, temperature between 700°C and 900°C and time between 3 minutes and 10 minutes. Considering these conditions, it is verified that more than 70% of the zinc layer is removed at 700°C, in 10 minutes. Dust captured is about 60% of metallic zinc and 40% as zinc oxide. Based on these results, the recycling of BOF sludge can be feasible to the ironmaking process.

Cost-assessment Analysis of Local Vehicle Scrapping Facility

Science.gov (United States)

Grabowski, Lukasz; Gliniak, Maciej; Polek, Daria; Gruca, Maria

2017-12-01

The purpose of the paper was to analyse the costs of recycling vehicles at local vehicle scrapping facility. The article contains regulations concerning vehicle decommissioning, describes the types of recovery, vehicles recycling networks, analyses the structure of a disassembly station, as well as the financial and institutional system in charge of dealing with the recycling of vehicles in Poland. The authors present the number of scrapped vehicles at local recycling company and the level of achieved recovery and recycling. The research presented in the article shows financial situation of the vehicle scrapping industry. In addition, it has been observed that the number of subsidies are directly proportional to the number of scrapped vehicles, and achieved levels of recycling and recovery depends on the percentage of incomplete vehicles.

Phase equilibrium of the system Ag-Fe-Nd, and Nd extraction from magnet scraps using molten silver

International Nuclear Information System (INIS)

Takeda, O.; Okabe, T.H.; Umetsu, Y.

2004-01-01

To develop a new recycling process, we examined the direct extraction of neodymium (Nd) metal from Nd-Fe-B magnet scraps using molten silver (Ag) as an extraction medium. Prior to the extraction experiment, the phase equilibrium of the system Ag-Fe-Nd was investigated to estimate the theoretical extraction limit. It was observed that the Fe/Nd 2 Fe 17 mixture equilibrates with the molten Ag-Nd alloy containing 50-52 mol% Nd (57-59 mass% Nd) at 1363 K. The experimental results were in good agreement with the thermodynamic calculation based on literature values. By reacting Nd-Fe-B magnet scraps with molten silver at 1273 K, more than 90% of the neodymium in the scrap was extracted, and an Ag-Nd alloy containing 40-50 mass% Nd was obtained. The neodymium in the Ag-Nd alloy was separated from silver as Nd 2 O 3 by oxidizing the obtained alloy in air. Although the wettability of Nd 2 O 3 with molten silver caused some difficulties in the separation of neodymium from silver, molten silver is shown to be an effective medium for neodymium extraction from magnet scrap

European Legislation to Prevent Loss of Control of Sources and to Recover Orphan Sources, and Other Requirements Relevant to the Scrap Metal Industry

Energy Technology Data Exchange (ETDEWEB)

Janssens, A.; Tanner, V.; Mundigl, S., E-mail: augustin.janssens@ec.europa.eu [European Commission (Luxembourg)

2011-07-15

European legislation (Council Directive 2003/122/EURATOM) has been adopted with regard to the control of high-activity sealed radioactive sources (HASS). This Directive is now part of an overall recast of current radiation protection legislation. At the same time the main Directive, 96/29/EURATOM, laying down Basic Safety Standards (BSS) for the health protection of the general public and workers against the dangers of ionizing radiation, is being revised in the light of the new recommendations of the International Commission on Radiological Protection (ICRP). The provisions for exemption and clearance are a further relevant feature of the new BSS. The current issues emerging from the revision and recast of the BSS are discussed, in the framework of the need to protect the scrap metal industry from orphan sources and to manage contaminated metal products. (author)

49 CFR 173.218 - Fish meal or fish scrap.

Science.gov (United States)

2010-10-01

... 49 Transportation 2 2010-10-01 2010-10-01 false Fish meal or fish scrap. 173.218 Section 173.218... Fish meal or fish scrap. (a) Except as provided in Column (7) of the HMT in § 172.101 of this subchapter, fish meal or fish scrap, containing at least 6%, but not more than 12% water, is authorized for...

Scrap uranium recycling via electron beam melting

International Nuclear Information System (INIS)

McKoon, R.

1993-11-01

A program is underway at the Lawrence Livermore National Laboratory (LLNL) to recycle scrap uranium metal. Currently, much of the material from forging and machining processes is considered radioactive waste and is disposed of by oxidation and encapsulation at significant cost. In the recycling process, uranium and uranium alloys in various forms will be processed by electron beam melting and continuously cast into ingots meeting applicable specifications for virgin material. Existing vacuum processing facilities at LLNL are in compliance with all current federal and state environmental, safety and health regulations for the electron beam melting and vaporization of uranium metal. One of these facilities has been retrofitted with an auxiliary electron beam gun system, water-cooled hearth, crucible and ingot puller to create an electron beam melt furnace. In this furnace, basic process R ampersand D on uranium recycling will be performed with the goal of eventual transfer of this technology to a production facility

Radioactive scrap metal (RSM) inventory ampersand tracking system and prototype RSM field survey

International Nuclear Information System (INIS)

Thomas, T.R.

1994-09-01

Based on very preliminary information, it has been estimated that the radioactive scrap metal (RSM) inventories at DOE facilities amount to about 1.5 million tons and a much larger amount will be generated from decontamination and decommissioning of surplus DOE facilities. To implement a national DOE program for beneficial reuse of RSM, it will be necessary to known the location and characteristics of RSM inventories that are available and will be generated to match them with product demands. It is the intent of this task to provide a standardized methodology via a RSM database for recording, tracking, and reporting data on RSM inventories. A multiple relational database in dBASE IV was designed and a PC-based code was written in Clipper 5.0 syntax to expedite entry, editing, querying, and reporting of RSM survey data. The PC based-code, the multiple relational database files, and other external files used by the code to generate reports and queries constitute a customized software application called the RSM Inventory ampersand Tracking System (RSM I ampersand TS). A prototype RSM field survey was conducted at the Nevada Test Site (NTS) to demonstrate the field use of the RSM I ampersand TS and logistics of conducting the survey. During the demonstration, about 50 tons of RSM were sized, characterized, sorted, and packaged in transport containers

“When a breach arises”: Good burocratic action and informal scrap metal collection in Northern Italy

Directory of Open Access Journals (Sweden)

Elisabeth Tauber

2017-12-01

Full Text Available This paper analyses affirmative bureaucratic intervention into the informal commercial practices of scrap metal collection among the Sinti in a North-Italian province. To contextualize these events it is vital to examine institutional logics, and how they resonate with public officials’ sense of self as well as political loyalties. In everyday bureaucracy Gypsies are considered to be perplexing subjects, provoking contrasting images of poverty and excess. These cultural representations are the opposite of the idea of a decent social-work client. Hence, bureaucratic intervention on behalf of the Sinti put the former in a deontological and moral limbo, one which stimulates them to navigate the political and organisational structures of their organisations in a creative way. This paper aims to bring a positive example of where the social and institutional discrimination against Roma and Sinti in Italy and Europe can be broken. Even if it is not possible to reverse this discrimination, it at least introduces affirmative bureaucratic action as an enlightening direction for anthropological study.

Thermodynamic Considerations of Direct Oxygen Removal from Titanium by Utilizing the Deoxidation Capability of Rare Earth Metals

Science.gov (United States)

Okabe, Toru H.; Zheng, Chenyi; Taninouchi, Yu-ki

2018-06-01

Oxygen removal from metallic Ti is extremely difficult and, currently, there is no commercial process for effectively deoxidizing Ti or its alloys. The oxygen concentration in Ti scraps is normally higher than that in virgin metals such as in Ti sponges produced by the Kroll process. When scraps are remelted with virgin metals for producing primary ingots of Ti or its alloys, the amount of scrap that can be used is limited owing to the accumulation of oxygen impurities. Future demands of an increase in Ti production and of mitigating environmental impacts require that the amount of scrap recycled as a feed material of Ti ingots should also increase. Therefore, it is important to develop methods for removing oxygen directly from Ti scraps. In this study, we evaluated the deoxidation limit for β-Ti using Y or light rare earth metals (La, Ce, Pr, or Nd) as a deoxidant. Thermodynamic considerations suggest that extra-low-oxygen Ti, with an oxygen concentration of 100 mass ppm or less can be obtained using a molten salt equilibrating with rare earth metals. The results presented herein also indicate that methods based on molten salt electrolysis for producing rare earth metals can be utilized for effectively and directly deoxidizing Ti scraps.

The steel scrap age.

Science.gov (United States)

Pauliuk, Stefan; Milford, Rachel L; Müller, Daniel B; Allwood, Julian M

2013-04-02

Steel production accounts for 25% of industrial carbon emissions. Long-term forecasts of steel demand and scrap supply are needed to develop strategies for how the steel industry could respond to industrialization and urbanization in the developing world while simultaneously reducing its environmental impact, and in particular, its carbon footprint. We developed a dynamic stock model to estimate future final demand for steel and the available scrap for 10 world regions. Based on evidence from developed countries, we assumed that per capita in-use stocks will saturate eventually. We determined the response of the entire steel cycle to stock saturation, in particular the future split between primary and secondary steel production. During the 21st century, steel demand may peak in the developed world, China, the Middle East, Latin America, and India. As China completes its industrialization, global primary steel production may peak between 2020 and 2030 and decline thereafter. We developed a capacity model to show how extensive trade of finished steel could prolong the lifetime of the Chinese steelmaking assets. Secondary steel production will more than double by 2050, and it may surpass primary production between 2050 and 2060: the late 21st century can become the steel scrap age.

Metals, scraps and opportunities; Metales, chatarras y oportunidades

Energy Technology Data Exchange (ETDEWEB)

Roman Ortega, F.

2003-07-01

This article attempts to focus on the vision that recuperation and recycling of metals is an activity which must attract attention of Mine Engineers, as much for its increasing importance as the fact that the techniques involved are not anything else but adaptation, in certain conditions of the ones used in the treatment and benefit of the metallic ores. (Author)

Properties of concrete containing scrap-tire rubber--an overview.

Science.gov (United States)

Siddique, Rafat; Naik, Tarun R

2004-01-01

Solid waste management is one of the major environmental concerns in the United States. Over 5 billion tons of non-hazardous solid waste materials are generated in USA each year. Of these, more than 270 million scrap-tires (approximately 3.6 million tons) are generated each year. In addition to this, about 300 million scrap-tires have been stockpiled. Several studies have been carried out to reuse scrap-tires in a variety of rubber and plastic products, incineration for production of electricity, or as fuel for cement kilns, as well as in asphalt concrete. Studies show that workable rubberized concrete mixtures can be made with scrap-tire rubber. This paper presents an overview of some of the research published regarding the use of scrap-tires in portland cement concrete. The benefits of using magnesium oxychloride cement as a binder for rubberized concrete mixtures are also presented. The paper details the likely uses of rubberized concrete.

Six-kilogram-scale electrorefining of plutonium metal

International Nuclear Information System (INIS)

Mullins, L.J.; Morgan, A.N.; Apgar, S.A. III; Christensen, D.C.

1982-09-01

The electrorefining of metallic plutonium scrap to produce high purity metal has been an established procedure at Los Alamos since 1964. This is a batch process and was limited to 4-kg plutonium because of criticality safety considerations. Improvements in critical mass measurements have permitted us to develop a process for 6-kg plutonium. The 6-kg process is now operational. The increased size of the process, together with other improvements which have been made, makes plutonium electrorefining the principal industrial tool for processing and purifying metallic plutonium scrap

An assessment of the potential radiation exposure from residual radioactivity in scrap metal for recycling

International Nuclear Information System (INIS)

Lee, Sang Yoon; Lee, Kun Jai

1997-01-01

With current waste monitoring technology it is reasonable to assume that much of the material designated as low level waste (LLW), generated within nuclear facilities, is in fact uncontaminated. This may include operational wastes, metal and rubble, office waste and discrete items from decommissioning or decontamination operations. Materials that contain only trivial quantities of radionuclides could realistically be exempted or released from regulatory control for recycle or reuse. A criterion for uncontrolled disposal of low-level radioactive contaminated waste is that the radiation exposure of the public and of each individual caused by this disposal is so low that radiation protection measures need not be taken. The International Atomic Energy Agency (IAEA) suggests an annual effective doses of 10 μ Sv as a limit for the individual radiation dose. In 1990, new recommendation on radiation protection standards was developed by International Commission on Radiological Protection (ICRP) to take into account new biological information related to the detriment associated with radiation exposure. Adoption of these recommendations necessitated a revision of the Commission's secondary limits contained in Publication 30, Parts 1 ∼ 4. This study summarized the potential radiation exposure from valuable scrap metal considered to uncontrolled recycle by new ICRP recommendations. Potential exposure pathways to people following were analyzed and relevant models developed. Finally, concentrations leading to an individual dose of 10 μ Sv/yr were calculated for 14 key radionuclides. These potential radiation exposures are compared with the results of an IAEA study. 12 refs., 6 tabs., figs

Spark Plasma Sintering As a Solid-State Recycling Technique: The Case of Aluminum Alloy Scrap Consolidation

Directory of Open Access Journals (Sweden)

Dimos Paraskevas

2014-08-01

Full Text Available Recently, “meltless” recycling techniques have been presented for the light metals category, targeting both energy and material savings by bypassing the final recycling step of remelting. In this context, the use of spark plasma sintering (SPS is proposed in this paper as a novel solid-state recycling technique. The objective is two-fold: (I to prove the technical feasibility of this approach; and (II to characterize the recycled samples. Aluminum (Al alloy scrap was selected to demonstrate the SPS effectiveness in producing fully-dense samples. For this purpose, Al alloy scrap in the form of machining chips was cold pre-compacted and sintered bellow the solidus temperature at 490 °C, under elevated pressure of 200 MPa. The dynamic scrap compaction, combined with electric current-based joule heating, achieved partial fracture of the stable surface oxides, desorption of the entrapped gases and activated the metallic surfaces, resulting in efficient solid-state chip welding eliminating residual porosity. The microhardness, the texture, the mechanical properties, the microstructure and the density of the recycled specimens have been investigated. An X-ray computed tomography (CT analysis confirmed the density measurements, revealing a void-less bulk material with homogeneously distributed intermetallic compounds and oxides. The oxide content of the chips incorporated within the recycled material slightly increases its elastic properties. Finally, a thermal distribution simulation of the process in different segments illustrates the improved energy efficiency of this approach.

Melting of contaminated metallic waste

International Nuclear Information System (INIS)

Lee, Y.-S.; Cheng, S.-Y.; Kung, H.-T.; Lin, L.-F.

2004-01-01

Approximately 100 tons of contaminated metallic wastes were produced each year due to maintenance for each TPC's nuclear power reactor and it was roughly estimated that there will be 10,000 tons of metallic scraps resulted from decommissioning of each reactor in the future. One means of handling the contaminated metal is to melt it. Melting process owns not only volume reduction which saves the high cost of final disposal but also resource conservation and recycling benefits. Melting contaminated copper and aluminum scraps in the laboratory scale have been conducted at INER. A total of 546 kg copper condenser tubes with a specific activity of about 2.7 Bq/g was melted in a vacuum induction melting facility. Three types of products, ingot, slag and dust were derived from the melting process, with average activities of 0.10 Bq/g, 2.33 Bq/g and 84.3 Bq/g respectively. After the laboratory melting stage, a pilot plant with a 500 kg induction furnace is being designed to melt the increasingly produced contaminated metallic scraps from nuclear facilities and to investigate the behavior of different radionuclides during melting. (author)

Refining technology for the recycling of stainless steel radioactive scrap metals, FY 94 bi-annual report

International Nuclear Information System (INIS)

Mizia, R.E.; Atteridge, D.G.; Buckentin, J.; Carter, J.; Davis, H.L.; Devletian, J.H.; Scholl, M.R.; Turpin, R.B.; Webster, S.L.

1994-08-01

The research addressed under this project is the recycling of metallic nuclear-related by-product materials under the direction of Westinghouse Idaho Nuclear Company (WINCO). The program addresses the recycling of radioactive scrap metals (RSM) for beneficial re-use within the DOE complex; in particular, this program addresses the recycling of stainless steel RSM. It is anticipated that various stainless steel components under WINCO control at the Idaho Falls Engineering Laboratory (INEL), such as fuel pool criticality barriers and fuel storage racks will begin to be recycled in FY94-95. The end product of this recycling effort is expected to be waste and overpack canisters for densified high level waste for the Idaho Waste Immobilization Facility and/or the Universal Canister System for dry (interim) storage of spent fuel. The specific components of this problem area that are presently being, or have been, addressed by CAAMSEC are: (1) the melting/remelting of stainless steel RSM into billet form; (2) the melting/remelting initial research focus will be on the use of radioactive surrogates to study; (3) the cost effectiveness of RSM processing oriented towards privatization of RSM reuse and/or resale. Other components of this problem that may be addressed under program extension are: (4) the melting/remelting of carbon steel; (5) the processing of billet material into product form which shall meet all applicable ASTM requirements; and, (6) the fabrication of an actual prototypical product; the present concept of an end product is a low carbon Type 304/316 stainless steel cylindrical container for densified and/or vitrified high level radioactive waste and/or the Universal Canister System for dry (interim) storage of spent fuel. The specific work reported herein covers the melting/remelting of stainless steel open-quotes scrapclose quotes metal into billet form and the study of surrogate material removal effectiveness by various remelting techniques

Detection of contaminated metallurgical scrap at borders: a proposal for an 'investigation level'

International Nuclear Information System (INIS)

Duftschmid, K.E.

1999-01-01

In 1995 the IAEA started a program to combat illicit trafficking in nuclear and other radioactive materials which includes the problem of cross-border movement of contaminated metallurgical scrap. A major activity in this program is the elaboration of a Safety Guide on 'Preventing, Detecting and Responding to Illicit Trafficking', co-sponsored by the World Customs Organization (WCO) and INTERPOL. The guide will provide advice to the Member States, in particular on technical and administrative procedures for detection of radioactive materials at borders. Radiation monitoring systems for contaminated scrap metals have been successfully used in steel plants and larger scrap yards since several years and suitable products are on the market today. Using sophisticated software and dynamic scanning techniques such systems allow for detection of an artificial increase in radiation background level as low as by 20%, even if the natural background signal is substantially suppressed by the vehicle itself entering the monitor. However, the measurement conditions at borders are essentially different from those in plants. Large traffic crossing major borders limits the time for detection and response to a few seconds and multiple checks are nearly impractical. Shielded radioactive sources - even of high activity - which are deeply buried in scrap, cannot be detected without unloading the vehicle, a procedure generally ruled out at borders. Highly sensitive monitoring systems necessarily cause frequent false alarms or nuisance alarms due to innocent radioactive materials such as naturally occurring radioactivity e.g. in fertilizers, scale in pipes used in the oil industry or medical radioisotopes. A particular, rather frequent problem is the unnecessary reject of scrap transports on borders due to the inherent low level contamination of steel with 60 Co, even in sheet metal used for lorries or railroad cars. Such contamination can easily be caused by the routine method to control

What do we know about metal recycling rates?

Science.gov (United States)

Graedel, T.E.; Allwood, J.; Birat, J.-P.; Buchert, M.; Hageluken, C.; Reck, B.K.; Sibley, S.F.; Sonnemann, G.

2011-01-01

The recycling of metals is widely viewed as a fruitful sustainability strategy, but little information is available on the degree to which recycling is actually taking place. This article provides an overview on the current knowledge of recycling rates for 60 metals. We propose various recycling metrics, discuss relevant aspects of recycling processes, and present current estimates on global end-of-life recycling rates (EOL-RR; i.e., the percentage of a metal in discards that is actually recycled), recycled content (RC), and old scrap ratios (OSRs; i.e., the share of old scrap in the total scrap flow). Because of increases in metal use over time and long metal in-use lifetimes, many RC values are low and will remain so for the foreseeable future. Because of relatively low efficiencies in the collection and processing of most discarded products, inherent limitations in recycling processes, and the fact that primary material is often relatively abundant and low-cost (which thereby keeps down the price of scrap), many EOL-RRs are very low: Only for 18 metals (silver, aluminum, gold, cobalt, chromium, copper, iron, manganese, niobium, nickel, lead, palladium, platinum, rhenium, rhodium, tin, titanium, and zinc) is the EOL-RR above 50% at present. Only for niobium, lead, and ruthenium is the RC above 50%, although 16 metals are in the 25% to 50% range. Thirteen metals have an OSR greater than 50%. These estimates may be used in considerations of whether recycling efficiencies can be improved; which metric could best encourage improved effectiveness in recycling; and an improved understanding of the dependence of recycling on economics, technology, and other factors. ?? 2011 by Yale University.

Example of establishing the recycling of scrap metal as a waste management option within German regulations

International Nuclear Information System (INIS)

Bodenstein, Matthias; Delfs, Johannes; Karschnick, Oliver

2014-01-01

The German Atomic Energy Act (Atomgesetz, AtG) specifies the German nuclear licensing and supervising regulations. On that basis the German federal states are responsible for licensing and supervising of nuclear power plants (NPPs) located in that state. The Ministry of Energy, Agriculture, the Environment and Rural Areas (MELUR) is the authority responsible for the state Schleswig-Holstein, in which the NPPs Brokdorf, Brunsbuettel, Kruemmel and the research reactor HZG are located. In the licensing and supervisory procedures the authority may consult authorized experts. In addition to the AtG, the German Radiation Protection Ordinance (Strahlenschutzverordnung, StrlSchV) specifies regulations for clearance according to the 10 μSv-concept. The clearance of metal by recycling / melting is one option within the regulations of the StrlSchV. For a clearance an additional license given by the MELUR is necessary. In that license and the application documents as well as in the supervisory procedures very specific regulations are implemented. This includes regulations for clearance at third parties in foreign countries. In this talk a short introduction to the German regulations focussed on clearance according to the 10 μSv-concept will be given. The specific regulations in the license of clearance will be presented and also the application documents for NPPs in Schleswig-Holstein will be discussed. Furthermore it will be illustrated on what terms the MELUR decided to agree upon the recycling of scrap metal with the aim of clearance according to Radiation Protection 89 in foreign countries along with the German regulatory framework. (authors)

Recycling of rare earth magnet scraps: Carbon and oxygen removal from Nd magnet scraps

International Nuclear Information System (INIS)

Saguchi, A.; Asabe, K.; Fukuda, T.; Takahashi, W.; Suzuki, R.O.

2006-01-01

The decarburization and deoxidation technique for permanent Nd-Fe-B magnet scrap is investigated. The carbon and oxygen contamination damage the magnetic properties. The carbon content decreased less than 0.001% by heating in air. The two stage deoxidation is applied, iron oxides are reduced by heating in hydrogen thereafter rare earth oxides are removed by Ca-reduction and leaching. The appropriate conditions for deoxidation in the Ca-reduction and suppressing the re-oxidation in the leaching are investigated. The heating pattern in Ca-reduction and the leaching condition for the mixture composed of Ca compounds and Nd-Fe-B alloy powder greatly affects the oxygen content of recycled material. The decarburized and deoxidized Nd-Fe-B magnet scrap can be recycled as alloying elements by melting

Synthesis of high-surface-area γ-Al2O3 from aluminum scrap and its use for the adsorption of metals: Pb(II), Cd(II) and Zn(II)

International Nuclear Information System (INIS)

Asencios, Yvan J.O.; Sun-Kou, María R.

2012-01-01

Highlights: ► Aluminum hydroxide obtained from aluminum scrap led to the formation of gamma alumina. ► Acidic pH of precipitation favored the formation of small particles of high surface areas. ► Higher aging temperature favored the formation of large structures of large pore sizes. ► Higher aging temperature generated symmetrical solids of regular hexagonal prism forms. ► Aluminas of large pores adsorbed metals as following: Pb (1.75 Å) > Cd (1.54 Å) > Zn (1.38 Å). - Abstract: Several types of alumina were synthesized from sodium aluminate (NaAlO 2 ) by precipitation with sulfuric acid (H 2 SO 4 ) and subsequently calcination at 500 °C to obtain γ-Al 2 O 3 . The precursor aluminate was derived from aluminum scrap. The various γ-Al 2 O 3 synthesized were characterized by Fourier-transform infrared spectroscopy (FTIR), X-ray diffraction (XRD), adsorption–desorption of N 2 (S BET ) and scanning electron microscopy (SEM). XRD revealed that distinct phases of Al 2 O 3 were formed during thermal treatment. Moreover, it was observed that conditions of synthesis (pH, aging time and temperature) strongly affect the physicochemical properties of the alumina. A high-surface-area alumina (371 m 2 g −1 ) was synthesized under mild conditions, from inexpensive raw materials. These aluminas were tested for the adsorption of Cd(II), Zn(II) and Pb(II) from aqueous solution at toxic metal concentrations, and isotherms were determined.

Survey on the scrap iron and steel recycling in Thailand and Indonesia; Hatten tojokoku (Tai Indonesia) ni okeru tetsu scrap saiseiyo ni kansuru chosa

Energy Technology Data Exchange (ETDEWEB)

NONE

1997-03-01

This report describes the survey results of the scrap iron and steel recycling industries in Thailand and Indonesia. The purpose of this survey is to extract problems obstructing the scrap iron and steel recycling, to recognize the present situation and predict the future situation, and to examine the possibility of international cooperation. As a result of the survey, it was found that the quality of scrap collected in the domestic market is poor as it contains too many impurities for it to be utilized for the manufacture of many higher quality iron and steel products. The actual quantity of domestically collected scrap is too low to support the expected growth in demand in each nation. Current environmental management practices are largely concerned with the construction of wastewater treatment facilities and the extraction of furnace dust. However, the lack of enforcement of environmental regulations does not encourage companies to implement sound environmental practices. Neither government actively promotes and investigates iron and steel recycling in the domestic, commercial or industrial sectors. Collaboration with overseas nations having more advanced iron and steel industries could be helpful to the scrap recycling industry in both nations. 6 figs., 21 tabs.

Volatilisation and oxidation of aluminium scraps fed into incineration furnaces

International Nuclear Information System (INIS)

Biganzoli, Laura; Gorla, Leopoldo; Nessi, Simone; Grosso, Mario

2012-01-01

Highlights: ► Aluminium packaging partitioning in MSW incineration residues is evaluated. ► The amount of aluminium packaging recoverable from the bottom ashes is evaluated. ► Aluminium packaging oxidation rate in the residues of MSW incineration is evaluated. ► 80% of aluminium cans, 51% of trays and 27% of foils can be recovered from bottom ashes. - Abstract: Ferrous and non-ferrous metal scraps are increasingly recovered from municipal solid waste incineration bottom ash and used in the production of secondary steel and aluminium. However, during the incineration process, metal scraps contained in the waste undergo volatilisation and oxidation processes, which determine a loss of their recoverable mass. The present paper evaluates the behaviour of different types of aluminium packaging materials in a full-scale waste to energy plant during standard operation. Their partitioning and oxidation level in the residues of the incineration process are evaluated, together with the amount of potentially recoverable aluminium. About 80% of post-consumer cans, 51% of trays and 27% of foils can be recovered through an advanced treatment of bottom ash combined with a melting process in the saline furnace for the production of secondary aluminium. The residual amount of aluminium concentrates in the fly ash or in the fine fraction of the bottom ash and its recovery is virtually impossible using the current eddy current separation technology. The average oxidation levels of the aluminium in the residues of the incineration process is equal to 9.2% for cans, 17.4% for trays and 58.8% for foils. The differences between the tested packaging materials are related to their thickness, mechanical strength and to the alloy.

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

Feed Materials Production Center waste management plan (Revision to NLCO-1100, R.6)

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 wastes 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

Scrapping of student bursaries confirmed.

Science.gov (United States)

Longhurst, Chris

2016-07-27

Student bursaries for nurses will be scrapped from next year, the government has confirmed. Undergraduate nursing and midwifery students in England will now face tuition fees and student loans from August 2017.

Process options and projected mass flows for the HTGR refabrication scrap recovery system

International Nuclear Information System (INIS)

Tiegs, S.M.

1979-03-01

The two major uranium recovery processing options reviewed are (1) internal recovery of the scrap by the refabrication system and (2) transfer to and external recovery of the scrap by the head end of the reprocessing system. Each option was reviewed with respect to equipment requirements, preparatory processing, and material accountability. Because there may be a high cost factor on transfer of scrap fuel material to the reprocessing system for recovery, all of the scrap streams will be recycled internally within the refabrication system, with the exception of reject fuel elements, which will be transferred to the head end of the reprocessing system for uranium recovery. The refabrication facility will be fully remote; thus, simple recovery techniques were selected as the reference processes for scrap recovery. Crushing, burning, and leaching methods will be used to recover uranium from the HTGR refabrication scrap fuel forms, which include particles without silicon carbide coatings, particles with silicon carbide coatings, uncarbonized fuel rods, carbon furnace parts, perchloroethylene distillation bottoms, and analytical sample remnants. Mass flows through the reference scrap recovery system were calculated for the HTGR reference recycle facility operating with the highly enriched uranium fuel cycle. Output per day from the refabrication scrap recovery system is estimated to be 4.02 kg of 2355 U and 10.85 kg of 233 U. Maximum equipment capacities were determined, and future work will be directed toward the development and costing of the scrap recovery system chosen as reference

Scrap automotive electronics: A mini-review of current management practices.

Science.gov (United States)

Cucchiella, Federica; D'Adamo, Idiano; Rosa, Paolo; Terzi, Sergio

2016-01-01

End-of-life vehicles, together with waste from electric and electronic equipment, are known as an important source of secondary raw materials. For many years, their recovery has allowed the restoring of great amounts of metals for new cars production. This article provides a comprehensive mini-review on the end-of-life vehicles recycling topic between 2000 and 2014, with a particular focus on automotive electronics recycling. In fact, in the last years, experts focused their attention on a better exploitation of automotive shredder residue fraction, but not sufficiently on eventual electronic scraps embedded in it. Hence, studies assessing the value embedded in these scraps are rarely available in literature, causing an important gap in both recycling policies and research. The fact that, at present, the management of electronic control units (the most valuable component among automotive electronic equipment) is, as yet, off the radar in both end-of-life vehicles and waste from electric and electronic equipment Directives demonstrates the theory. Of course, their recycling would not contribute in a relevant way to reach the weighted-based recycling and recovery targets characterising current regulations, but would be very important under a critical raw materials recovery view. Results coming from the literature analysis confirm these assumptions. © The Author(s) 2015.

Beneficial Re-Use of Metal from Decommissioning of Power Reactors

International Nuclear Information System (INIS)

Eshleman, Troy; Raw, Graham; Moloney, Barry

2014-01-01

Utilities and contractors decommissioning nuclear power reactors can recycle a high proportion of the scrap metal generated during dismantling either by free release for general re-use directly from the point of generation, or by recycling off-site at facilities specifically licensed for radioactive material. The worldwide commercial vendors operate different commercial models of volumetric decontamination of ferrous metals by thermal treatment. Some aim to achieve free release of output metals for general use, while others accept higher activity metals as feedstock for the manufacture of steel products which contain residual radioactivity, which we term 'Beneficial Re-use'. It is estimated that 10-30% of metals from light water reactor decommissioning have been exposed to neutron radiation (activated) and/or are contaminated to such an extent that free release is not achievable. This paper outlines a cost-effective alternative to managed storage or disposal for lightly activated or contaminated metal, utilising a 'Beneficial Re-Use' programme which has been in routine operation in the United States for over 20 years. 'Beneficial Re-Use' describes the manufacture of products such as radiation shielding from radioactive scrap metal. Unlike recycling practised in Europe, such products remain under control in licensed facilities and the metal does not find its way into general circulation or consumer products. Since 1992, EnergySolutions and its predecessor Duratek has been melting scrap at their Bear Creek, Tennessee facility to produce shield blocks for use in high energy research facilities. Over 62,300 t of scrap steel have been re-used, and the demand for shielding products continues long into the future. 3,000 t of this feedstock originated outside the US. This paper proposes the potential for activated steel that will not be acceptable at European recycling facilities to enter the Beneficial Re-use programme. Acceptance criteria

Economic feasibility of radioactive scrap steel recycling

International Nuclear Information System (INIS)

Nichols, F.; Balhiser, R.; Rosholt, D.

1995-01-01

In the past, government and commercial nuclear operators treated radioactive scrap steel (RSS) as a liability and disposed of it by burial; this was an accepted and economical solution at that time. Today, environmental concerns about burial are changing the waste disposal picture by (a) causing burial costs to soar rapidly, (b) creating pressure to close existing burial sites, and (c) making it difficult and expensive to open and operate burial facilities. To exacerbate the problem, planned dismantling of nuclear facilities will substantially increase volumes of RSS open-quotes wasteclose quotes over the next 30 yr. This report describes a project with the intention of integrating the current commercial mini-mill approach of recycling uncontaminated steel with radiological controls to design a system that can process contaminated metals at prices significantly below the current processors or burial costs

Gold and palladium adsorption from leached electronic scrap using ordered mesoporous carbon nanoscaffolds

Energy Technology Data Exchange (ETDEWEB)

McDowell, Rocklan; Dutech, Guy

2014-09-01

Ordered mesoporous carbon (OMC) nanoscaffolds are engineered agglomerates of carbon nanotubes held together by small carbon nanofibers with uniform pore sizes, high pore volume, and high channel permeability. These materials exhibit very high affinity for the adsorption of gold from aqueous acidic mixtures. The efficiency of gold recovery is comparable to those typically accomplished using biopolymer-based adsorbents. The adsorption efficiency for other precious metals such as palladium and platinum is lower. Studies on the precious metal (Au, Pd) adsorption on OMC materials from actual liquors of leached electronics will be presented. Adsorption properties will be compared for several different sorbents used for the recovery of precious metals. The leach liquor compositions for three different types of electronic scrap materials (personal computer board, cell phone and tv input/output board) will be presented. The sorption efficiencies for Au, Pd, together with a spectrum of competing and non-competing metals, from such leach mixtures will be compared.

Gold and palladium adsorption from leached electronic scrap using ordered mesoporous carbon nanoscaffolds

International Nuclear Information System (INIS)

McDowell, Rocklan; Dutech, Guy

2014-01-01

Ordered mesoporous carbon (OMC) nanoscaffolds are engineered agglomerates of carbon nanotubes held together by small carbon nanofibers with uniform pore sizes, high pore volume, and high channel permeability. These materials exhibit very high affinity for the adsorption of gold from aqueous acidic mixtures. The efficiency of gold recovery is comparable to those typically accomplished using biopolymer-based adsorbents. The adsorption efficiency for other precious metals such as palladium and platinum is lower. Studies on the precious metal (Au, Pd) adsorption on OMC materials from actual liquors of leached electronics will be presented. Adsorption properties will be compared for several different sorbents used for the recovery of precious metals. The leach liquor compositions for three different types of electronic scrap materials (personal computer board, cell phone and tv input/output board) will be presented. The sorption efficiencies for Au, Pd, together with a spectrum of competing and non-competing metals, from such leach mixtures will be compared.

Evaluation of segmented gamma scanner measurements on cans of recoverable scrap

International Nuclear Information System (INIS)

Shull, A.H.; Weber, J.H.; MacMurdo, K.W.; Baker, L.B.

1991-01-01

Savannah River Site (SRS) has had a long-standing concern about the inability to measure recoverable scrap. A segmented gamma scanner (SGS) was evaluated for use in measuring cans of scrap materials. Four scrap cans were selected and re-packaged into containers that could be measured using calorimetry and gamma spectrometry. These scrap cans were later used as working standards for the SGS. In addition, replicate measurements were made on all cans of scrap currently stored with estimated values. Before accepting the SGS measurements on the cans, data from the replicate measurements of the standards and a limited number of process cans were analyzed to determine if there was a significant bias between the SGS and the calorimeter-gamma spectrometer measurements, if the random replication error would be acceptable for accountability, to set control limits for the workings standards, and to determine acceptable differences between replicate measurements. After completing the measurement of all process scrap cans in the inventory, the the final data were analyzed and estimates based on the two sets of data compared. The methodology used to determine the appropriate measurement error model, to estimate the measurement errors, to set control limits, and to determine the significance of the bias will be described as well as a comparison of the error estimates based on the preliminary versus final data

State of the art of smelting lead-acid battery scrap

Energy Technology Data Exchange (ETDEWEB)

Melin, A

1977-02-01

A discussion is given of the economic importance of lead recovery and of scrap recycling in the battery industry. Various possibiliies of processing battery scrap, either by direct smelting or by smelting after preparaton are discussed, and the BBU, the Stolberger, and the Tonnolli methods are compared

Recycling of rare earths from Hg-containing fluorescent lamp scraps by solid state chlorination; Rueckgewinnung Seltener Erden aus quecksilberbelasteten Leuchtstoffen mittels Feststoffchlorierung

Energy Technology Data Exchange (ETDEWEB)

Lorenz, Tom; Froehlich, Peter; Bertau, Martin [TU Bergakademie Freiberg (Germany); Golon, Katja [FNE Entsorgungsdienste GmbH, Freiberg (Germany)

2015-10-15

Solid state chlorination with NH{sub 4}Cl comprises a method for rare earth recycling apart from pyro- or hydrometallurgical strategies. The examined partially Hg-containing fluorescent lamp scraps are rich in rare earths like La, Ce, Tb and Gd, but especially in Y and Eu. By mixing with NH{sub 4}Cl and heating up to NH{sub 4}Cl decomposition temperature in a sublimation reactor, Y and Eu could be transferred selectively into their respective metal chlorides with high yields. The yield and selectivity depend on temperature and the ratio of NH{sub 4}Cl to fluorescent lamp scraps, which were varied systematically.

Enhanced high-solids anaerobic digestion of waste activated sludge by the addition of scrap iron.

Science.gov (United States)

Zhang, Yaobin; Feng, Yinghong; Yu, Qilin; Xu, Zibin; Quan, Xie

2014-05-01

Anaerobic digestion of waste activated sludge usually requires pretreatment procedure to improve the bioavailability of sludge, which involves considerable energy and high expenditures. This study proposes a cost-effective method for enhanced anaerobic digestion of sludge without a pretreatment by directly adding iron into the digester. The results showed that addition of Fe(0) powder could enhance 14.46% methane yield, and Fe scrap (clean scrap) could further enhance methane yield (improving rate 21.28%) because the scrap has better mass transfer efficiency with sludge and liquid than Fe(0) powder. The scrap of Fe with rust (rusty scrap) could induce microbial Fe(III) reduction, which resulted in achieving the highest methane yield (improving rate 29.51%), and the reduction rate of volatile suspended solids (VSS) was also highest (48.27%) among Fe powder, clean scrap and rusty scrap. PCR-DGGE proved that the addition of rusty scrap could enhance diversity of acetobacteria and enrich iron-reducing bacteria to enhance degradation of complex substrates. Copyright © 2014 Elsevier Ltd. All rights reserved.

Volatilisation and oxidation of aluminium scraps fed into incineration furnaces

Energy Technology Data Exchange (ETDEWEB)

Biganzoli, Laura, E-mail: laura.biganzoli@mail.polimi.it [Politecnico di Milano, Piazza L. Da Vinci 32, 20133 Milano (Italy); Gorla, Leopoldo; Nessi, Simone; Grosso, Mario [Politecnico di Milano, Piazza L. Da Vinci 32, 20133 Milano (Italy)

2012-12-15

Highlights: Black-Right-Pointing-Pointer Aluminium packaging partitioning in MSW incineration residues is evaluated. Black-Right-Pointing-Pointer The amount of aluminium packaging recoverable from the bottom ashes is evaluated. Black-Right-Pointing-Pointer Aluminium packaging oxidation rate in the residues of MSW incineration is evaluated. Black-Right-Pointing-Pointer 80% of aluminium cans, 51% of trays and 27% of foils can be recovered from bottom ashes. - Abstract: Ferrous and non-ferrous metal scraps are increasingly recovered from municipal solid waste incineration bottom ash and used in the production of secondary steel and aluminium. However, during the incineration process, metal scraps contained in the waste undergo volatilisation and oxidation processes, which determine a loss of their recoverable mass. The present paper evaluates the behaviour of different types of aluminium packaging materials in a full-scale waste to energy plant during standard operation. Their partitioning and oxidation level in the residues of the incineration process are evaluated, together with the amount of potentially recoverable aluminium. About 80% of post-consumer cans, 51% of trays and 27% of foils can be recovered through an advanced treatment of bottom ash combined with a melting process in the saline furnace for the production of secondary aluminium. The residual amount of aluminium concentrates in the fly ash or in the fine fraction of the bottom ash and its recovery is virtually impossible using the current eddy current separation technology. The average oxidation levels of the aluminium in the residues of the incineration process is equal to 9.2% for cans, 17.4% for trays and 58.8% for foils. The differences between the tested packaging materials are related to their thickness, mechanical strength and to the alloy.

Titanium recycling in the United States in 2004, chap. Y of Sibley, S.F., ed., Flow studies for recycling metal commodities in the United States

Science.gov (United States)

Goonan, Thomas G.

2010-01-01

As one of a series of reports that describe the recycling of metal commodities in the United States, this report discusses the titanium metal fraction of the titanium economy, which generates and uses titanium metal scrap in its operations. Data for 2004 were selected to demonstrate the titanium flows associated with these operations. This report includes a description of titanium metal supply and demand in the United States to illustrate the extent of titanium recycling and to identify recycling trends. In 2004, U.S. apparent consumption of titanium metal (contained in various titanium-bearing products) was 45,000 metric tons (t) of titanium, which was distributed as follows: 25,000 t of titanium recovered as new scrap, 9,000 t of titanium as titanium metal and titanium alloy products delivered to the U.S. titanium products reservoir, 7,000 t of titanium consumed by steelmaking and other industries, and 4,000 t of titanium contained in unwrought and wrought products exported. Titanium recycling is concentrated within the titanium metals sector of the total titanium market. The titanium market is otherwise dominated by pigment (titanium oxide) products, which generate dissipative losses instead of recyclable scrap. In 2004, scrap (predominantly new scrap) was the source of roughly 54 percent of the titanium metal content of U.S.-produced titanium metal products.

Statistical modeling to management and treatment of scrap with low and very low residual activity

International Nuclear Information System (INIS)

Garcia-Bermejo Fernandez, R.; Anaya Lazaro, M.

2011-01-01

The experience of recent years on the management of scrap metal containing residual activity have allowed the development of a simple statistical model for the management of these materials. This statistical model includes a breakdown of the various processing operations to which these materials undergo and the effects in the process of radiological controls associated to the control of declassification that defines disposal (recycled by smelting, reclamation, temporary storage the plant or sent to final storage of radioactive waste.

High Value Scrap Tire Recycle

Energy Technology Data Exchange (ETDEWEB)

Bauman, B. D.

2003-02-01

The objectives of this project were to further develop and scale-up a novel technology for reuse of scrap tire rubber, to identify and develop end uses for the technology (products), and to characterize the technology's energy savings and environmental impact.

Surplus plutonium disposition draft environmental impact statement. Summary

International Nuclear Information System (INIS)

1998-07-01

On May 22, 1997, DOE published a Notice of Intent (NOI) in the Federal Register (62 Federal Register 28009) announcing its decision to prepare an environmental impact statement (EIS) that would tier from the analysis and decisions reached in connection with the Storage and Disposition of Weapons-Usable Fissile Materials Final Programmatic EIS (Storage and Disposition PEIS). DOE's disposition strategy allows for both the immobilization of surplus plutonium and its use as mixed oxide (MOX) fuel in existing domestic, commercial reactors. The disposition of surplus plutonium would also involve disposal of the immobilized plutonium and MOX fuel (as spent nuclear fuel) in a geologic repository. The Surplus Plutonium Disposition Environmental Impact Statement analyzes alternatives that would use the immobilization approach (for some of the surplus plutonium) and the MOX fuel approach (for some of the surplus plutonium); alternatives that would immobilize all of the surplus plutonium; and the No Action Alternative. The alternatives include three disposition facilities that would be designed so that they could collectively accomplish disposition of up to 50 metric tons (55 tons) of surplus plutonium over their operating lives: (1) the pit disassembly and conversion facility would disassemble pits (a weapons component) and convert the recovered plutonium, as well as plutonium metal from other sources, into plutonium dioxide suitable for disposition; (2) the immobilization facility would include a collocated capability for converting nonpit plutonium materials into plutonium dioxide suitable for immobilization and would be located at either Hanford or SRS. DOE has identified SRS as the preferred site for an immobilization facility; (3) the MOX fuel fabrication facility would fabricate plutonium dioxide into MOX fuel

Complex deformation routes for direct recycling aluminium alloy scrap via industrial hot extrusion

Science.gov (United States)

Paraskevas, Dimos; Kellens, Karel; Kampen, Carlos; Mohammadi, Amirahmad; Duflou, Joost R.

2018-05-01

This paper presents the final results of an industrial project, aiming for direct hot extrusion of wrought aluminium alloy scrap at an industrial scale. Two types of complex deformation/extrusion routes were tested for the production of the same profile, starting from AA6060 scrap in form of machining chips. More specifically scrap-based billets were extruded through: a 2-porthole and a 4-porthole die-set, modified for enhanced scrap consolidation and grain refinement. For comparison reasons, cast billets of the same alloy were extruded through the modified 2-porthole die set. The tensile testing results as well as microstructural investigations show that the 4-porthole extrusion route further improves scrap consolidation compared to the 2-porthole die output. The successful implementation of solid state recycling, directly at industrial level, indicates the technological readiness level of this research.

Design concept for maximized use of recycled scrap in the production of storage packages

International Nuclear Information System (INIS)

Bounin, D.; Kleinkroeger, W.; Schreiber, D.

2004-01-01

In the decommissioning of nuclear plants large quantities of radioactively contaminated waste metal have to be disposed of. An economic alternative to final storage is the recycling of the scrap metal in the production of transport and storage containers for low and medium active waste made of nodular graphite ductile cast iron. In the particular case of the CARLA plant operated by Siempelkamp, scrap metal with an activity of up to 200 Bq/g is accepted for processing. This covers the vast majority of the metals of a plant to be decommissioned. The composition of the waste metals varies greatly, depending on the different origins like structural or stainless steels After solidification of the high-carbon, high-silicon cast iron melt, the carbon has formed nodular graphite particles embedded in the metal matrix. Nodular cast iron has high strength and elongation. A further advantage of this material are its good radiation shielding properties. Fracture toughness is an important material property in the design of containers for final storage. In the particular case of containers that have to meet the specifications for final storage these must withstand accident loadings from a height of up 5 m at temperatures of -20 C without crack initiation. Containers for final storage do not have the benefit of impact limiters. The fracture toughness of cast iron depends primarily on the microstructure of the metal matrix. A ferritic microstructure has a higher fracture toughness than a pearlitic microstructure. Carbides in the matrix lead to further embrittlement. The metals to be recycled in the decommissioning of a nuclear installation have marked contents of elements like manganese (Mn) in structural steels, chromium (Cr), nickel (Ni) and molybdenum (Mo) in stainless steels and copper (Cu) in special steels. These elements lead to a pearlitic microstructure and to carbides, even at low contents in the melt. With a rising content of pearlite and carbides, the tensile and yield

Nickel recycling in the United States in 2004

Science.gov (United States)

Goonan, Thomas G.

2009-01-01

As one of a series of reports that describe the recycling of metal commodities in the United States, this report discusses the flow of nickel from production through distribution and use, with particular emphasis on the recycling of industrial scrap (new scrap) and used products (old scrap) in 2004. This materials flow study includes a description of nickel supply and demand for the United States to illustrate the extent of nickel recycling and to identify recycling trends. Understanding how materials flow from a source through disposition can aid in improving the management of natural resource delivery systems. In 2004, the old scrap recycling efficiency for nickel was estimated to be 56.2 percent. In 2004, nickel scrap consumption in the United States was as follows: new scrap containing 13,000 metric tons (t) of nickel (produced during the manufacture of products), 12 percent; and old scrap containing 95,000 t of nickel (articles discarded after serving a useful purpose), 88 percent. The recycling rate for nickel in 2004 was 40.9 percent, and the percentage of nickel in products attributed to nickel recovered from nickel-containing scrap was 51.6 percent. Furthermore, U.S. nickel scrap theoretically generated in 2004 had the following distribution: scrap to landfills, 24 percent; recovered and used scrap, 50 percent; and unaccounted for scrap, 26 percent. Of the 50 percent of old scrap generated in the United States that was recovered and then used in 2004, about one-third was exported and two-thirds was consumed in the domestic production of nickel-containing products.

Inspection and control of recycling metals in Iran

International Nuclear Information System (INIS)

Rostampour Samarin, A.

2002-01-01

Full text: Recently, the metal recycling industries have become aware of radioactive materials in metal scrap. There have been some cases where radiation sources were unintentionally smelted in the course of recycling metal scrap internationally. To solve the problem, industry and Regulatory Authority have jointly undertaken initiatives to increase awareness of the problem within the industry. Radiation detection systems have been installed by custom services and mills to lessen the potential for the risk to public health from radiation contamination and for financial losses. Based on above matters, the article presents how National Radiation Protection Department (NRPD) can lessen the imports of potential contamination through several means, such as the installation of monitoring system, and implementation of prevention measures. (author)

Detecting the presence of abnormal radioactivity in scrap using the statistical method

International Nuclear Information System (INIS)

Baillet, G.

1999-01-01

The radiological protection criteria recommended for recycling of metals (as in the paper 'Radiation protection 89') cannot be used when scrap is checked on arrival at steel plants. In the event of an incident, neither the nature of the radioelements that may be present in the scrap, nor their level of activity, nor their physical form, are known. In practice abnormal radioactivity in scrap is detected by comparison with ambient radioactivity. However, ambient radioactivity cannot be regarded as a threshold of acceptability which applies to all products . Its level varies substantially from one place to another. All products display natural radioactivity: its level varies greatly, but in some cases it significantly supplements ambient radioactivity, though this does not mean that the products must be considered dangerous (the classic example is that of some granites and some refractory materials). In our arrival checks on scrap-carrying vehicles (lorries and wagons) using gantries, we focus on changes in the measured ambient radioactivity, expressed in impulses per second, which arise from the presence of the vehicle between the sensor and the ambient radioactivity. For each vehicle, this shielding effect is expressed in terms of the ratio between the level measured in the presence of the vehicle and the level measured immediately before its arrival. The result is therefore a dimensionless number. We carried out a statistical analysis of the results of lorry checks at three sites where the checking equipment is identical, but the natural ambient radioactivity levels very different. We observed that the distributions of the values of this ratio were identical for all the sites, and relate very well to a Gaussian distribution with a mean value of 0.71 and a standard deviation of 0.06. Hence these values are characteristic of the dispersion of the shielding effect of the population of 'scrap-carrying lorries checked with a specific type of checking equipment

Catalytic extraction processing of contaminated scrap metal

International Nuclear Information System (INIS)

Griffin, T.P.; Johnston, J.E.; Payea, B.M.; Zeitoon, B.M.

1995-01-01

Molten Metal Technology was awarded a contract to demonstrate the applicability of the Catalytic Extraction Process, a proprietary process that could be applied to US DOE's inventory of low level mixed waste. This paper is a description of that technology, and included within this document are discussions of: (1) Program objectives, (2) Overall technology review, (3) Organic feed conversion to synthetic gas, (4) Metal, halogen, and transuranic recovery, (5) Demonstrations, (6) Design of the prototype facility, and (7) Results

Dispositional logic

Science.gov (United States)

Le Balleur, J. C.

1988-01-01

The applicability of conventional mathematical analysis (based on the combination of two-valued logic and probability theory) to problems in which human judgment, perception, or emotions play significant roles is considered theoretically. It is shown that dispositional logic, a branch of fuzzy logic, has particular relevance to the common-sense reasoning typical of human decision-making. The concepts of dispositionality and usuality are defined analytically, and a dispositional conjunctive rule and dispositional modus ponens are derived.

AIR EMISSIONS FROM SCRAP TIRE COMBUSTION

Science.gov (United States)

The report discusses air emissions from two types of scrap tire combustion: uncontrolled and controlled. Uncontrolled sources are open tire fires, which produce many unhealthful products of incomplete combustion and release them directly into the atmosphere. Controlled combustion...

Scrap of gloveboxes No. 801-W and No. 802-W

CERN Document Server

Ohuchi, S; Kurosawa, M; Okane, S; Usui, T

2002-01-01

Both gloveboxes No. 801-W for measuring samples of uranium or plutonium and No. 802-W for analyzing the quantity of uranium or plutonium are established at twenty five years ago in the analyzing room No. 108 of Plutonium Fuel Research Facility. It was planned to scrap the gloveboxes and to establish new gloveboxes. This report describes the technical view of the scrapping works.

Radioactivity in the scrap recycling process: Radiation protection aspects and experimental monitoring problems

International Nuclear Information System (INIS)

Sacco, D.; Ruggeri, F.; Bindi, G.; Bonanni, A.; Casciardi, S.; Delia, R.; Loppa, A.; Rossi, P.; Venturini, L.

1996-01-01

The steel scrap recycling by steel mill is increasing moved by profits and by purpose of protection of environmental resources. Besides the use of radioactive sources in several fields (medical, industrial and in scientific researches) on one hand, and the disposal of made radioactive materials from nuclear reactors on the other one, makes the likelihood no more negligible that some radionuclides could be found, accidental y or fraudulently, in steel recycling scrap. Radiation protection problems for surveillance both employees in the production cycle and of people and environment in general arose. First of all, we characterize different type of radioactive materials that can found in scraps, pointing out the potential hazards from exposure of workers and people and from environmental contamination, related to physical and chemical specifications of the involved radionuclides. Some suitable monitoring equipment for scrap recycling facilities are discussed, related to the different step of production cycle (transport, storage, manipulation and melting). At last experimental data, taken in some periods of the monitoring campaign made at the Italian border on imported scraps, are presented. (author)

Plutonium scrap processing at the Los Alamos Scientific Laboratory

International Nuclear Information System (INIS)

Nixon, A.E.; McKerley, B.J.; Christensen, E.L.

1980-01-01

The Los Alamos Scientific Laboratory currently has the newest plutonium handling facility in the nation. Los Alamos has been active in the processing of plutonium almost since the discovery of this man-made element in 1941. One of the functions of the new facility is the processing of plutonium scrap generated at LASL and other sites. The feed for the scrap processing program is extremely varied, and a wide variety of contaminants are often encountered. Depending upon the scrap matrix and contaminants present, the majority of material receives a nitric acid/hydrofluoric acid or nitric acid/calcium fluoride leach. The plutonium nitrate solutions are then loaded onto an anion exchange column charged with DOWEX 1 x 4, 50 to 100 mesh, nitrate form resin. The column is eluted with 0.48 M hydroxyl amine nitrate. The Pu(NO 3 ) 3 is then precipitated as plutonium III oxalate which is calcined at 450 to 500 0 C to yield a purified PuO 2 product

Impact on Sensex of Scrapping Double Taxation of Dividends

OpenAIRE

Ragunathan V; Varma, Jayanth R.

1997-01-01

The taxation of dividends has generated an active debate in recent months in the media. While the industry representatives have been critical of the double taxation of dividends, the Government seems to be questioning the very premise that dividends are double taxed in India. The argument that scrapping the double taxation of dividends will give the Sensex a much needed boost seems to have tilted the scales. What will be the impact of scrapping of dividend tax on Sensex? One finds that the st...

Metal recycling technology and related issues in the United States, a BNFL perspective

International Nuclear Information System (INIS)

Bradbury, P.; Dam, S.; Starke, W.

1995-01-01

Radioactively contaminated metallic materials comprise a large part of the potential waste products which result from nuclear facility repair, refurbishment, and decommissioning. United States Government (Departments of Energy and Defense) facilities, U.S. nuclear power plants, and other commercial nuclear fuel cycle facilities have large inventories of radioactive scrap metal which could be decontaminated and recycled into useful radioactive and non-radioactive products. Residual radioactivity and recycling criteria is needed to avoid the high cost of disposal and the waste of natural resources. In the United Kingdom, BNFL has decommissioned the gaseous diffusion plant at Capenhurst and has recycled a large fraction of the metallic scrap into the metals market. Other structural materials have also been released as uncontaminated scrap. U.K. release criteria for residual radionuclide contamination have been applied to these operations. A variety of techniques were utilized to size reduce large components, to remove radioactivity, and to survey and release these materials. These methods and the application of release criteria has a direct relationship to methods which would be applicable in the U.S. and in other countries. This paper will describe the specific U.K. technology and experience in the decontamination, recycle, and release of scrap metal. It will also describe the U.S. environment for metal recycle, including the volumes and levels of contamination, and the current and proposed release criteria. Comparisons will be presented between the U.S. and U.K., both in technology and methodology for recycle and in regulatory criteria for residual radioactivity and material release and for ultimate decommissioning. The paper will then provide suggested approaches and criteria for U.S. recycling and decommissioning. (author)

German experience in recycling of ferrous metallic residues from nuclear decommissioning by melting

International Nuclear Information System (INIS)

Quade, U.; Kluth, Th.

2008-01-01

Due to the delay of commissioning of final depositories for nuclear waste on the one hand and the increasing amount of steel scrap resulting from operation and decommissioning of nuclear facilities on the other hand, recycling of ferrous metal scrap to packagings made of ductile cast iron becomes more and more economical. A pool of know-how from waste managers, radiation protection experts, metallurgists and foundry experts and their teamwork is required to run this recycling path successfully. Siempelkamp provides this combination of experience by operating a melting facility for slightly radioactive contaminated scrap as well as a foundry for manufacturing of ductile cast iron products for the nuclear industry, both licensed by the German Radiation Protection Ordinance. In 1989, the CARLA plant (Centrale Anlage zum Rezyklieren von leichtradioaktiven Abfollen) started operation. A medium frequency induction furnace with a capacity of 3,2 t is core of the plant. Tools for dismantling and cutting components to chargeable sizes are available. From the total of 23000 t of melted scrap, 12000 t have been recycled to the manufacturing of containers for transport and storage of medium- and high active waste and for shielding plates. Manufacture of the castings takes place in the Siempelkamp foundry located at the same site. 8000 t of melted scrap could be released for industrial recycling. Scrap metal which does not meet the metallurgical specification for cast iron, is converted into iron granules. Up to now more than 2000 t of iron granules have been recycled as additive for heavy concrete containers. This production is in cooperation with an external partner. With regard to the German situation, the cost for recycling is only half compared to high pressure compaction, long-term interim storage and final disposal. The advantage of recycling is approx. 90 % less volume compared to the volume resulting from other disposal paths. It can be concluded that the German

41 CFR 109-27.5107 - Recovery of silver from used hypo solution and scrap film.

Science.gov (United States)

2010-07-01

... used hypo solution and scrap film. 109-27.5107 Section 109-27.5107 Public Contracts and Property... § 109-27.5107 Recovery of silver from used hypo solution and scrap film. The requirements for the recovery of silver from used hypo solution and scrap film are contained in § 109-45.1003 of this chapter. ...

Representing dispositions

Directory of Open Access Journals (Sweden)

Röhl Johannes

2011-08-01

Full Text Available Abstract Dispositions and tendencies feature significantly in the biomedical domain and therefore in representations of knowledge of that domain. They are not only important for specific applications like an infectious disease ontology, but also as part of a general strategy for modelling knowledge about molecular interactions. But the task of representing dispositions in some formal ontological systems is fraught with several problems, which are partly due to the fact that Description Logics can only deal well with binary relations. The paper will discuss some of the results of the philosophical debate about dispositions, in order to see whether the formal relations needed to represent dispositions can be broken down to binary relations. Finally, we will discuss problems arising from the possibility of the absence of realizations, of multi-track or multi-trigger dispositions and offer suggestions on how to deal with them.

The Spanish Protocol for Collaboration on the Radiological Surveillance of Metallic Materials

Energy Technology Data Exchange (ETDEWEB)

Redondo, J.M., E-mail: jmredondo@mityc.es [Ministry of Industry, Tourism and Trade (Spain)

2011-07-15

In recent years the presence of radioactive material in scrap metal has been detected relatively often. This can cause the contamination of people or of the environment, as well as of the industrial facilities and of the product. The Spanish iron and steel industry is one of the most important industrial sectors in the country, and depends to a large extent on the importation of a significant proportion of the scrap used as raw material. Experience has shown that countries that import large quantities of scrap for their industries are more exposed to the existence of orphan radioactive sources and therefore, they have to adopt measures to reduce the risks arising from their presence. In 1999, the Spanish authorities, along with the business associations involved in the metal recovery and smelting industry, and the radioactive waste management agency, established a national system for the radiological surveillance and control of scrap metal and the products resulting from its processing. Since then, the most relevant trade unions and others in the industrial sector have also joined the system. It is based on the existence of a legal framework and on a set of voluntary commitments taken on by the involved parties. It is known as the Protocol for Collaboration for the Radiological Surveillance of Metallic Materials and is implemented by the installation of specific radiological surveillance equipment, the development of radiological training and information plans for the staff involved in the metal recovery and smelting sectors, the definition of a fully operational system to safely manage the materials detected, and a general improvement of the national radiological emergency system. (author)

The effect of material productivity on scrap reduction on aluminum reduction pot process

Science.gov (United States)

Huda, L. N.

2018-02-01

Scrap in the production process is defined as part of production that can not be accepted as the final product due to production failure. The amount of scarp occurring in the reduction pot production process of one of the aluminum smelting furnaces exceeds the acceptance standard of 5 to 10%. This affects the amount of production produced. The purpose of this study is to reduce the amount of scrap produced to increase the productivity of the materials used. The solution is carried-out by making improvements using Lean Six Sigma method. In the initial calculation, material productivity ranged from 0.88. Based on the study, the factors that cause the high amount of scrap produced is the use of Na2O which is inserted into the alumina is different in size and the influence of noise that occurs in pots that are difficult to control. The analysis base on Lean Six Sigma obtained process cycle efficiency (PCE) equal to 86,92% for actual condition. Process improvement is carried-out through define, measure, analyze, improve and control procedure on Na2O feeding process and PCE value decrease 6,05%. This indicates that increased process capability will reduce scrap. A decrease in scrap amount of about 6% will be able to increase material productivity by 0.05%. This indicates that continuous process control is needed to decrease the number of scraps and increase productivity.

Recovery of uranium from (U,Gd)O{sub 2} nuclear fuel scrap using dissolution and precipitation in carbonate media

Energy Technology Data Exchange (ETDEWEB)

Kim, Kwang-Wook, E-mail: nkwkim@kaeri.re.kr [Korea Atomic Energy Research Institute, 1045 Daedeok daero, Yuseong, Daejeon 305-353 (Korea, Republic of); KEPCO NF 1047 Daedeok daero, Yuseong, Daejeon 305-353 (Korea, Republic of); Hyun, Jun-Taek; Lee, Eil-Hee; Park, Geun-Il; Lee, Kune-Woo [Korea Atomic Energy Research Institute, 1045 Daedeok daero, Yuseong, Daejeon 305-353 (Korea, Republic of); Yoo, Myung-June [KEPCO NF 1047 Daedeok daero, Yuseong, Daejeon 305-353 (Korea, Republic of); Song, Kee-Chan; Moon, Jei-Kwon [Korea Atomic Energy Research Institute, 1045 Daedeok daero, Yuseong, Daejeon 305-353 (Korea, Republic of)

2011-11-15

Highlights: > A treatment of (U,Gd)O{sub 2} scrap with a dissolution in carbonate solution with H{sub 2}O{sub 2}. > Partial dissolution of Gd together with uranium in carbonate solution. > Solubilities of Gd in solutions with and without carbonate at several pHs. > Purification of Gd-contaminated UO{sub 4} by dissolution and precipitation of UO{sub 4}. - Abstract: This work studied a process to recover uranium from contaminated (U,Gd)O{sub 2} scraps generated from nuclear fuel fabrication processes by using the dissolution of (U,Gd)O{sub 2} scraps in a carbonate with H{sub 2}O{sub 2} and the precipitation of the dissolved uranium as UO{sub 4}. The dissolution characteristics of uranium, Gd, and impurity metal oxides were tested, and the behaviors of UO{sub 4} precipitation and Gd solubility were evaluated with changes of the pH of the solution. A little Gd was entrained in the UO{sub 4} precipitate to contaminate the uranium precipitate. Below a pH of 3, the uranium dissolved in the form of uranyl peroxo-carbonato complex ions in the carbonate solution was precipitated as UO{sub 4} with a high precipitation yield, and the Gd had a very high solubility. Using these characteristics, the Gd-contaminated UO{sub 4} could be purified using dissolution in a 1-M HNO{sub 3} solution with heating and re-precipitation upon addition of H{sub 2}O{sub 2} to the solution. Finally, an environmentally friendly and economical process to recover pure uranium from contaminated (U,Gd)O{sub 2} scraps was suggested.

Investigation of fatigue and mechanical properties of the pipe grade poly(vinyl chloride using recycled scraps

Directory of Open Access Journals (Sweden)

J-M. Lee

2015-04-01

Full Text Available In this paper, the effect of using pre-consumer PVC scraps on static and long-term mechanical properties is studied. The degradation characteristics of mixing virgin PVC with crushed pre-consumer and PVC pipe scraps are analyzed using various tools including Gel Permeation Chromatography (GPC, Thermogravimetric Analysis (TGA, X-ray fluorescence (XRF and Fourier Transform Infrared (FTIR spectroscopy. The variation of static mechanical properties as a function of adding pre-consumer PVC pipe scraps is investigated using the degradation analyses of recycled PVC scraps. In addition, fatigue tests are executed to evaluate the long-term durability of blending virgin PVC and recycled PVC scraps, and the fracture surface is investigated in detail to reveal the variation of the fracture mechanisms.

Scrap supply in Bosnian after war situation - sources, quality, regulation and control

International Nuclear Information System (INIS)

Pihura, Dervis

1999-01-01

Before the war, the Bosnian foundry and steel industry were supplied with scrap partly from domestic sources but mainly from foreign market. The annual steel production before the war recorded 130,000 tonnes of casting and 2,000.000 tonnes of crude steel. Most of the scrap was imported to secure and stabilize the production. During and after the war, despite a significant loss of production, efforts have been made to return to the normal production level in many ways. In the wake of the war, there has been a growing concern over the import of radioactive contaminated metallurgical scrap or low quality raw materials which are uncontrolled or of unidentified sources. In this regard, it is urgently required to establish an effective system to prevent from, to detect and to control the flow of the radioactive contaminated metallurgical scrap. The system should be established in such a way that all sorts of radioactive metallurgical elements should be controlled and prevented from use in all the metallurgical manufacturing processes, ferrous and non-ferrous alike. The coverage of control should start from the border or (air) port checkpoint where the flow of the scrap begins to the final steel product. The control system should take a form of internationally common and acceptable standards and regulations. Equipments and measurement techniques should also be internationally common. (author)

Disposition of excess fissile materials in deep boreholes

International Nuclear Information System (INIS)

Halsey, W.G.; Danker, W.; Morley, R.

1995-09-01

As a result of recent changes throughout the world, a substantial inventory of excess separated plutonium is expected to result from dismantlement of US nuclear weapons. The safe and secure management and eventual disposition of this plutonium, and of a similar inventory in Russia, is a high priority. A variety of options (both interim and permanent) are under consideration to manage this material. The permanent solutions can be categorized into two broad groups: direct disposal and utilization. Plutonium utilization options have in common the generation of high-level radioactive waste which will be disposed of in a mined geologic disposal system to be developed for spent reactor fuel and defense high level waste. Other final disposition forms, such as plutonium metal, plutonium oxide and plutonium immobilized without high-level radiation sources may be better suited to placement in a custom facility. This paper discusses a leading candidate for such a facility; deep (several kilometer) borehole disposition. The deep borehole disposition concept involves placing excess plutonium deep into old stable rock formations with little free water present. The safety argument centers around ancient groundwater indicating lack of migration, and thus no expected communication with the accessible environment until the plutonium has decayed

Investigation of impurities present in recycling and reusing of scrap lead for accumulator industry

International Nuclear Information System (INIS)

Farooq, A.; Irfan, N.; Chaudhry, M.M.; Nawab, S.

2012-01-01

Recycling and reusing are the basic strategies of reducing solid waste generated from industries. Millions of batteries containing toxic metals and poisonous wastes are discarded every year in Pakistan. Battery waste deposited in landfills increases the concentration of toxic metals in leachates obtained from landfill base. For this reason, recycling of locally available scrap lead has been focused. During reduction and refining stages, samples were obtained at various stages from a five ton lead smelting pot of an accumulator industry. Various impurities present were determined and removed in order to reuse in accumulators. X-ray fluorescence (XRF) and atomic absorption spectroscopy (AAS) techniques were used to analyze the samples obtained at various stages of recycling. This work has been carried out to reduce these impurities and the refining process has thus been optimized. The lead thus obtained is 99.98 % pure. (author)

A model for recovery of scrap monolithic uranium molybdenum fuel by electrorefining

Science.gov (United States)

Van Kleeck, Melissa A.

The goal of the Reduced Enrichment for Research and Test Reactors program (RERTR) is toreduce enrichment at research and test reactors, thereby decreasing proliferation risk at these facilities. A new fuel to accomplish this goal is being manufactured experimentally at the Y12 National Security Complex. This new fuel will require its own waste management procedure,namely for the recovery of scrap from its manufacture. The new fuel is a monolithic uraniummolybdenum alloy clad in zirconium. Feasibility tests were conducted in the Planar Electrode Electrorefiner using scrap U-8Mo fuel alloy. These tests proved that a uranium product could be recovered free of molybdenum from this scrap fuel by electrorefining. Tests were also conducted using U-10Mo Zr clad fuel, which confirmed that product could be recovered from a clad version of this scrap fuel at an engineering scale, though analytical results are pending for the behavior of Zr in the electrorefiner. A model was constructed for the simulation of electrorefining the scrap material produced in the manufacture of this fuel. The model was implemented on two platforms, Microsoft Excel and MatLab. Correlations, used in the model, were developed experimentally, describing area specific resistance behavior at each electrode. Experiments validating the model were conducted using scrap of U-10Mo Zr clad fuel in the Planar Electrode Electrorefiner. The results of model simulations on both platforms were compared to experimental results for the same fuel, salt and electrorefiner compositions and dimensions for two trials. In general, the model demonstrated behavior similar to experimental data but additional refinements are needed to improve its accuracy. These refinements consist of a function for surface area at anode and cathode based on charge passed. Several approximations were made in the model concerning areas of electrodes which should be replaced by a more accurate function describing these areas.

Characterization of Irradiated and Non-Irradiated Rubber from Automotive Scrap Tires

Science.gov (United States)

Souza, Clécia Moura; Silva, Leonardo G.

The aim of this work was to characterize the samples of irradiated and non-irradiated rubber from automotive scrap tires. Rubber samples from scrap tires were irradiated at irradiation doses of 200, 400 and 600kGy in an electron beam accelerator. Subsequently, both the irradiated and non-irradiated samples were characterized by thermogravimetry (TG), differential scanning calorimetry (DSC), tensile strength mechanical test, and Fourier transform infrared (FTIR) spectrophotometry.

Sulfur dioxide leaching of spent zinc-carbon-battery scrap

Energy Technology Data Exchange (ETDEWEB)

Avraamides, J.; Senanayake, G.; Clegg, R. [A.J. Parker Cooperative Research Centre for Hydrometallurgy, Murdoch University, Perth, WA 6150 (Australia)

2006-09-22

Zinc-carbon batteries, which contain around 20% zinc, 35% manganese oxides and 10% steel, are currently disposed after use as land fill or reprocessed to recover metals or oxides. Crushed material is subjected to magnetic separation followed by hydrometallurgical treatment of the non-magnetic material to recover zinc metal and manganese oxides. The leaching with 2M sulfuric acid in the presence of hydrogen peroxide recovers 93% Zn and 82% Mn at 25{sup o}C. Alkaline leaching with 6M NaOH recovers 80% zinc. The present study shows that over 90% zinc and manganese can be leached in 20-30min at 30{sup o}C using 0.1-1.0M sulfuric acid in the presence of sulfur dioxide. The iron extraction is sensitive to both acid concentration and sulfur dioxide flow rate. The effect of reagent concentration and particle size on the extraction of zinc, manganese and iron are reported. It is shown that the iron and manganese leaching follow a shrinking core kinetic model due to the formation of insoluble metal salts/oxides on the solid surface. This is supported by (i) the decrease in iron and manganese extraction from synthetic Fe(III)-Mn(IV)-Zn(II) oxide mixtures with increase in acid concentration from 1M to 2M, and (ii) the low iron dissolution and re-precipitation of dissolved manganese and zinc during prolonged leaching of battery scrap with low sulfur dioxide. (author)

The Research of Scrapped Automobiles Recycling and Disassembling Industry Development Based on Auto Industry Chain

Directory of Open Access Journals (Sweden)

linhua Pang

2015-01-01

Full Text Available The number of China’s scrapped car is on an explosively growing trend, and the development of scrapped car recycling industry has a golden prospect. The current scrapped car recycling system is not perfect in our country, because related industries driven by market develop slowly, and there are some outstanding problems such as potential safety risks, environmental pollution and resource waste. The paper analyzes and studies the existing problems and countermeasures to investigate the development strategy of scrapped car recycling industry according to the whole automobile industry chain construction, technology and equipment conditions, policy guidance, etc. and at last explore the new industrial development pattern of serving automobile reverse design.

The Relevance of Metal Recycling for Nuclear Industry Decommissioning Programmes

Energy Technology Data Exchange (ETDEWEB)

O' Sullivan, P.J., E-mail: nea@nea.fr [OECD Nuclear Energy Agency, Paris (France)

2011-07-15

The large amount of scrap metal arising from the decommissioning of nuclear facilities may present significant problems in the event that the facility owners seek to implement a management strategy based largely or fully on disposal in dedicated disposal facilities. Depending on whether disposal facilities currently exist or need to be developed, this option can be very expensive. Also, public reluctance to accept the expansion of existing disposal facilities, or the siting of new ones, mean that the disposal option should be used only after a wide consideration of all available management options. A comparison of health, environmental and socio-economic impacts of the recycling of lightly contaminated scrap metal, as compared with equivalent impacts associated with the production of replacement material, suggests that recycling has significant overall advantages. With present-day technologies, a large proportion of the metal waste from decommissioning can be decontaminated to clearance levels because most of the contamination is on or near the surface of the metal. In purely economic terms, it makes little sense for lightly contaminated scrap metal from decommissioning, which tends to be of high quality, to be removed from the supply chain and replaced with metal from newly-mined ore. In many countries, the metal recycling industry remains reluctant to accept metal from decommissioning. In Germany, the recycling industry and the decommissioning industry have worked together to develop an approach whereby such material is accepted for melting and the recycled material and is then used for certain defined end uses. Sweden also uses dedicated melting facilities for the recycling of metal from the nuclear industry. Following this approach, the needs of the decommissioning industry are being met in a way that also addresses the needs of the recycling industry. (author)

Recycled tetrahedron-like CuCl from waste Cu scraps for lithium ion battery anode.

Science.gov (United States)

Hou, Hongying; Yao, Yuan; Liu, Song; Duan, Jixiang; Liao, Qishu; Yu, Chengyi; Li, Dongdong; Dai, Zhipeng

2017-07-01

The wide applications of metal Cu inevitably resulted in a large quantity of waste Cu materials. In order to recover the useful Cu under the mild conditions and reduce the environmental emission, waste Cu scraps were recycled in the form of CuCl powders with high economic value added (EVA) via the facile hydrothermal route. The recycled CuCl powders were characterized in terms of scanning electron microscopy (SEM), energy dispersive X-ray spectroscopy (EDX) and X-ray diffraction (XRD). The results suggested that the recycled CuCl powders consisted of many regular tetrahedron-like micro-particles. Furthermore, in order to reduce the cost of lithium ion battery (LIB) anode and build the connection of waste Cu scraps and LIB, the recycled CuCl powders were evaluated as the anode active material of LIB. As expected, the reversible discharge capacity was about 171.8mAh/g at 2.0C even after 50 cycles, implying the satisfactory cycle stability. Clearly, the satisfactory results may open a new avenue to develop the circular economy and the sustainable energy industry, which would be very important in terms of both the resource recovery and the environmental protection. Copyright © 2017. Published by Elsevier Ltd.

Surplus plutonium disposition draft environmental impact statement. Volume 1, Part A

International Nuclear Information System (INIS)

1998-07-01

On May 22, 1997, DOE published a Notice of Intent (NOI) in the Federal Register (62 Federal Register 28009) announcing its decision to prepare an environmental impact statement (EIS) that would tier from the analysis and decisions reached in connection with the Storage and Disposition of Weapons-Usable Fissile Materials Final Programmatic EIS (Storage and Disposition PEIS). DOE's disposition strategy allows for both the immobilization of surplus plutonium and its use as mixed oxide (MOX) fuel in existing domestic, commercial reactors. The disposition of surplus plutonium would also involve disposal of the immobilized plutonium and MOX fuel (as spent nuclear fuel) in a geologic repository. The Surplus Plutonium Disposition Environmental Impact Statement analyzes alternatives that would use the immobilization approach (for some of the surplus plutonium) and the MOX fuel approach (for some of the surplus plutonium); alternatives that would immobilize all of the surplus plutonium; and the No Action Alternative. The alternatives include three disposition facilities that would be designed so that they could collectively accomplish disposition of up to 50 metric tons (55 tons) of surplus plutonium over their operating lives: (1) the pit disassembly and conversion facility would disassemble pits (a weapons component) and convert the recovered plutonium, as well as plutonium metal from other sources, into plutonium dioxide suitable for disposition; (2) the immobilization facility would include a collocated capability for converting nonpit plutonium materials into plutonium dioxide suitable for immobilization and would be located at either Hanford or SRS. DOE has identified SRS as the preferred site for an immobilization facility; (3) the MOX fuel fabrication facility would fabricate plutonium dioxide into MOX fuel. This volume includes background information; purpose of and need for the proposed action; alternatives for disposition of surplus weapons useable plutonium; and

Surplus plutonium disposition draft environmental impact statement. Volume 2

International Nuclear Information System (INIS)

1998-07-01

On May 22, 1997, DOE published a Notice of Intent (NOI) in the Federal Register (62 Federal Register 28009) announcing its decision to prepare an environmental impact statement (EIS) that would tier from the analysis and decisions reached in connection with the Storage and Disposition of Weapons-Usable Fissile Materials Final Programmatic EIS (Storage and Disposition PEIS). DOE's disposition strategy allows for both the immobilization of surplus plutonium and its use as mixed oxide (MOX) fuel in existing domestic, commercial reactors. The disposition of surplus plutonium would also involve disposal of the immobilized plutonium and MOX fuel (as spent nuclear fuel) in a geologic repository. The Surplus Plutonium Disposition Environmental Impact Statement analyzes alternatives that would use the immobilization approach (for some of the surplus plutonium) and the MOX fuel approach (for some of the surplus plutonium); alternatives that would immobilize all of the surplus plutonium; and the No Action Alternative. The alternatives include three disposition facilities that would be designed so that they could collectively accomplish disposition of up to 50 metric tons (55 tons) of surplus plutonium over their operating lives: (1) the pit disassembly and conversion facility would disassemble pits (a weapons component) and convert the recovered plutonium, as well as plutonium metal from other sources, into plutonium dioxide suitable for disposition; (2) the immobilization facility would include a collocated capability for converting nonpit plutonium materials into plutonium dioxide suitable for immobilization and would be located at either Hanford or SRS. DOE has identified SRS as the preferred site for an immobilization facility; (3) the MOX fuel fabrication facility would fabricate plutonium dioxide into MOX fuel. Volume 2 contains the appendices to the report and describe the following: Federal Register notices; contractor nondisclosure statement; adjunct melter

Life Cycle Analysis for D and D Decision Making: Disposition of Hanford Railcars

Energy Technology Data Exchange (ETDEWEB)

Yuracko, K.L.

2001-01-11

This report summarizes a joint venture between the U.S. Department of Energy (DOE) Deactivation and Decommissioning Focus Area and the Oak Ridge Operations Assets Utilization (AU) Facilities and Materials Reuse Division (FMRD) in its role as the DOE National Center of Excellence for Metals Recycle (NMR), to better address problems in the DOE complex. This task was initially developed to meet a request from the Richland Operations Office (RL) to AU FMRD for assistance in analyzing equipment reuse and metals recycling opportunities at RL, utilizing expertise and experience related to life cycle analysis (LCA), technology, and planning. Oak Ridge National Laboratory (ORNL) has developed an LCA system to assist DOE in identifying and analyzing opportunities for equipment and materials reuse and recycle. This report presents the use of the LCA system to identify and analyze methods for disposition of surplus railcars at the Hanford site. Alternative possible disposition pathways were evaluated for their financial, health and safety, environmental, programmatic, and institutional impacts; and a preferred disposition pathway was identified.

Thermogravimetric characteristics and kinetics of scrap tyre and Juglans regia shell co-pyrolysis.

Science.gov (United States)

Uzun, B B; Yaman, E

2014-10-01

The degradation kinetics of Juglans regia shell, scrap tyre and their blends were investigated using a thermogravimetric analysis method. Experiments were performed under dynamic conditions and a nitrogen atmosphere in the range 293 to 973 K at different heating rates. During pyrolysis of J. regia shell three mass loss zones were specified as removal of water, decomposition of hemicelluloses and cellulose, and decomposition of lignin. The degradation curves of scrap tyre showed merely one stage which was due to decomposition of styrene butadiene rubber. The kinetic parameters were calculated using both Arrhenius and Coats-Redfern methods. By adopting the Arrhenius method, the average value of activation energies of J. regia shell, scrap tyre and their 1 : 1 blends were found to be 69.22, 71.48 and 47.03 kJ mol(-1), respectively. Additionally, by using the Coats-Redfern method, the average value of activation energies of J. regia shell, scrap tyre and their 1 : 1 blend were determined as 99.85, 78.72 and 63.81 kJ mol(-1), respectively. The addition of J. regia shell to scrap tyre caused a reduction in the activation energies. The difference of weight loss was measured to examine interactions between raw materials. The maximum difference between experimental and theoretical mass loss was 5% at about 648 K with a heating rate of 20 K min(-1). These results indicated a significant synergistic effect was available during co-pyrolysis of J. regia shell and scrap tyre in the high temperature region. © The Author(s) 2014.

Fully automated laboratory for the assay of plutonium in wastes and recoverable scraps

International Nuclear Information System (INIS)

Guiberteau, P.; Michaut, F.; Bergey, C.; Debruyne, T.

1990-01-01

To determine the plutonium content of wastes and recoverable scraps in intermediate size containers (ten liters) an automated laboratory has been carried out. Two passive methods of measurement are used. Gamma ray spectrometry allows plutonium isotopic analysis, americium determination and plutonium assay in wastes and poor scraps. Calorimetry is used for accurate (± 3%) plutonium determination in rich scraps. A full automation was realized with a barcode management and a supply robot to feed the eight assay set-ups. The laboratory works on a 24 hours per day and 365 days per year basis and has a capacity of 8,000 assays per year

A strategy for the unrestricted release of metallic scrap from decommissioned nuclear facilities, integrating quality planning with the effective use of non-destructive assay instrumentation

International Nuclear Information System (INIS)

Gunn, R.; Troughten, N.; Warran, C.

2000-01-01

The key component of any release operation is its quality plan. This plan is a step by step procedure which describes all the actions which are required during the entire process and also the information required at every stage of the process. Once drafted the quality plan will enable operators to determine at what stages it is necessary to measure the parameters required to allow the process to progress. The objective of the radiometric system is to provide the auditable proof that material has been surveyed, the record of the survey and the evidence that the system was operating within its design parameters during the survey. Typical radiometric instruments which have been deployed to provide the information requirements of the quality plan are described in this paper. These include the IonSens TM Conveyor, conveyorized survey monitor used to provide high throughout clearance surveys of removed metallic scrap. The IonSens TM Pipe, cut pipe monitor is used to survey interiors and exteriors of long lengths of removed pipe-work. The IonSens TM 208 large Item monitor is used to survey removed pieces of vessels and ductwork which may have convoluted shapes and finally the DrumScan TM system is used to survey 200 litre drums containing cut up pieces of metal. (author)

EFFICIENCY OF METAL SCRAP SEPARATION IN EDDY CURRENT SEPARATOR

Directory of Open Access Journals (Sweden)

Gordan Bedeković

2008-11-01

Full Text Available Eddy-current separation is most often method used for the recovery of non-ferrous metals (Al, Cu, Zn, Pb from solid wastes and also for separating non-ferrous metals from each other. The feed material comes to rotary drum and magnetic field by belt conveyer. The changing magnetic field induce eddy currents in conductive (metallic particles. Because interaction between this currents and the magnetic field electrodynamic forces will act on conductive particles. Therefore the trajectories of conductive particles will be different from the trajectories of the non-conductive ones. Separation is a result of the combined actions of several forces (electrodynamic, gravitational and frictional. The paper presents results of aluminium recovery from mixture of metallic particles in eddy current separator. Testing were conducted under field condition. Results shows that is possible achieve recovery of 99 % and concentrate quality of 89 % of aluminium (the paper is published in Croatian.

Economic and policy instrument analyses in support of the scrap tire recycling program in Taiwan.

Science.gov (United States)

Chang, Ni-Bin

2008-02-01

Understanding the cost-effectiveness and the role of economic and policy instruments, such as the combined product tax-recycling subsidy scheme or a tradable permit, for scrap tire recycling has been of crucial importance in a market-oriented environmental management system. Promoting product (tire) stewardship on one hand and improving incentive-based recycling policy on the other hand requires a comprehensive analysis of the interfaces and interactions in the nexus of economic impacts, environmental management, environmental valuation, and cost-benefit analysis. This paper presents an assessment of the interfaces and interactions between the implementation of policy instruments and its associated economic evaluation for sustaining a scrap tire recycling program in Taiwan during the era of the strong economic growth of the late 1990s. It begins with an introduction of the management of the co-evolution between technology metrics of scrap tire recycling and organizational changes for meeting the managerial goals island-wide during the 1990s. The database collected and used for such analysis covers 17 major tire recycling firms and 10 major tire manufacturers at that time. With estimates of scrap tire generation and possible scale of subsidy with respect to differing tire recycling technologies applied, economic analysis eventually leads to identify the associated levels of product tax with respect to various sizes of new tires. It particularly demonstrates a broad perspective of how an integrated econometric and engineering economic analysis can be conducted to assist in implementing policy instruments for scrap tire management. Research findings indicate that different subsidy settings for collection, processing, and end use of scrap tires should be configured to ameliorate the overall managerial effectiveness. Removing the existing boundaries between designated service districts could strengthen the competitiveness of scrap tires recycling industry, helping to

Effective Technology for Recycling Metal. Proceedings of Two Special Workshops.

Science.gov (United States)

National Association of Secondary Material Industries, Inc., New York, NY.

The National Association of Secondary Material Industries (NASMI) and the Bureau of Mines have cooperated to sponsor two technically-oriented workshops related to the role of metals recycling and air pollution control technology. The proceedings of these workshops, "Effective Technology and Research for Scrap Metal Recycling" and "Air Pollution…

Foucaults Dispositive

DEFF Research Database (Denmark)

Raffnsøe, Sverre; Gudmand-Høyer, Marius T.; Thaning, Morten Sørensen

2016-01-01

While Foucault’s work has had a crucial impact on organizational research, the analytical potential of the dispositive has not been sufficiently developed. The purpose of this article is to reconstruct the notion of the dispositive as a key conception in Foucault’s thought, particularly in his...

Surplus plutonium disposition draft environmental impact statement. Volume 1, Part B

International Nuclear Information System (INIS)

1998-07-01

On May 22, 1997, DOE published a Notice of Intent (NOI) in the Federal Register (62 Federal Register 28009) announcing its decision to prepare an environmental impact statement (EIS) that would tier from the analysis and decisions reached in connection with the Storage and Disposition of Weapons-Usable Fissile Materials Final Programmatic EIS (Storage and Disposition PEIS). DOE's disposition strategy allows for both the immobilization of surplus plutonium and its use as mixed oxide (MOX) fuel in existing domestic, commercial reactors. The disposition of surplus plutonium would also involve disposal of the immobilized plutonium and MOX fuel (as spent nuclear fuel) in a geologic repository. The Surplus Plutonium Disposition Environmental Impact Statement analyzes alternatives that would use the immobilization approach (for some of the surplus plutonium) and the MOX fuel approach (for some of the surplus plutonium); alternatives that would immobilize all of the surplus plutonium; and the No Action Alternative. The alternatives include three disposition facilities that would be designed so that they could collectively accomplish disposition of up to 50 metric tons (55 tons) of surplus plutonium over their operating lives: (1) the pit disassembly and conversion facility would disassemble pits (a weapons component) and convert the recovered plutonium, as well as plutonium metal from other sources, into plutonium dioxide suitable for disposition; (2) the immobilization facility would include a collocated capability for converting nonpit plutonium materials into plutonium dioxide suitable for immobilization and would be located at either Hanford or SRS. DOE has identified SRS as the preferred site for an immobilization facility; (3) the MOX fuel fabrication facility would fabricate plutonium dioxide into MOX fuel. This volume has chapters on environmental consequences; environmental regulations, permits, and consultations; a glossary; list of preparers; distribution list

Alternative technical summary report for direct disposition in deep boreholes: Direct disposal of plutonium metal/plutonium dioxide in compound canisters, Version 4.0. Fissile Materials Disposition Program

Energy Technology Data Exchange (ETDEWEB)

Wijesinghe, A.M.

1996-08-23

This report summarizes and compares the Immobilized and Direct Beep Borehole Disposition Alternatives. The important design concepts, facility features and operational procedures are briefly described, and a discussion of the issues that affect the evaluation of each alternative against the programmatic assessment criteria that have been established for selecting the preferred alternatives for plutonium disposition.

Transformations of highly enriched uranium into metal or oxide

International Nuclear Information System (INIS)

Nollet, P.; Sarrat, P.

1964-01-01

The enriched uranium workshops in Cadarache have a double purpose on the one hand to convert uranium hexafluoride into metal or oxide, and on the other hand to recover the uranium contained in scrap materials produced in the different metallurgical transformations. The principles that have been adopted for the design and safety of these workshops are reported. The nuclear safety is based on the geometrical limitations of the processing vessels. To establish the processes and the technology of these workshops, many studies have been made since 1960, some of which have led to original achievements. The uranium hexafluoride of high isotopic enrichment is converted either by injection of the gas into ammonia or by an original process of direct hydrogen reduction to uranium tetrafluoride. The uranium contained m uranium-zirconium metal scrap can be recovered by combustion with hydrogen chloride followed treatment of the uranium chloride by fluorine in order to obtain the uranium in the hexafluoride state. Recovery of the uranium contained m various scrap materials is obtained by a conventional refining process combustion of metallic scrap, nitric acid dissolution of the oxide, solvent purification by tributyl phosphate, ammonium diuranate precipitation, calcining, reduction and hydro fluorination into uranium tetrafluoride, bomb reduction by calcium and slag treatment. Two separate workshops operate along these lines one takes care of the uranium with an isotopic enrichment of up to 3 p. 100, the other handles the high enrichments. The handling of each step of this process, bearing in mind the necessity for nuclear safety, has raised some special technological problems and has led to the conception of new apparatus, in particular the roasting furnace for metal turnings, the nitric acid dissolution unit, the continuous precipitator and ever safe filter and dryer for ammonium diuranate, the reduction and hydro fluorination furnace and the slag recovery apparatus These are

Weapons-grade plutonium dispositioning. Volume 1: Executive summary

International Nuclear Information System (INIS)

Parks, D.L.; Sauerbrun, T.J.

1993-06-01

The Secretary of Energy requested the National Academy of Sciences (NAS) Committee on International Security and Arms Control to evaluate dispositioning options for weapons-grade plutonium. The Idaho National Engineering Laboratory (INEL) assisted NAS in this evaluation by investigating the technical aspects of the dispositioning options and their capability for achieving plutonium annihilation levels greater than 90%. Additionally, the INEL investigated the feasibility of using plutonium fuels (without uranium) for disposal in existing light water reactors and provided a preconceptual analysis for a reactor specifically designed for destruction of weapons-grade plutonium. This four-volume report was prepared for NAS to document the findings of these studies. Volume 2 evaluates 12 plutonium dispositioning options. Volume 3 considers a concept for a low-temperature, low-pressure, low-power-density, low-coolant-flow-rate light water reactor that quickly destroys plutonium without using uranium or thorium. This reactor concept does not produce electricity and has no other mission than the destruction of plutonium. Volume 4 addresses neutronic performance, fabrication technology, and fuel performance and compatibility issues for zirconium-plutonium oxide fuels and aluminum-plutonium metallic fuels. This volumes gives summaries of Volumes 2--4

Vitrification for stability of scrap and residue

Energy Technology Data Exchange (ETDEWEB)

Forsberg, C.W. [Oak Ridge National Lab., TN (United States)

1996-05-01

A conference breakout discussion was held on the subject of vitrification for stabilization of plutonium scrap and residue. This was one of four such sessions held within the vitrification workshop for participants to discuss specific subjects in further detail. The questions and issues were defined by the participants.

Recycling of Metals

DEFF Research Database (Denmark)

Damgaard, Anders; Christensen, Thomas Højlund

2011-01-01

Metals like iron and aluminium are produced from mineral ore and used for a range of products, some of which have very short lifetimes and thus constitute a major fraction of municipal waste. Packaging in terms of cans, foils and containers are products with a short lifetime. Other products like...... appliances, vehicles and buildings, containing iron and aluminium metals, have long lifetimes before they end up in the waste stream. The recycling of production waste and postconsumer metals has a long history in the metal industry. Some metal smelters are today entirely based on scarp metals. This chapter...... describes briefly how iron and aluminium are produced and how scrap metal is recycled in the industry. Quality requirements and use of recycled products are discussed, as are the resource and environmental issues of metal recycling. Copper and other metals are also found in waste but in much smaller...

Assessment of heavy metal concentration in soil and leaves of tree ...

African Journals Online (AJOL)

The gaseous emissions from scrap metal recycling factory could cause pollution to the environment if the concentrations are substantial and not properly controlled. This study determined the concentration of some heavy metals (Iron, Copper, Lead and Cadmium) in the leaves of selected tree species and soils around the ...

Progress toward uranium scrap recycling via electron beam cold hearth refining

International Nuclear Information System (INIS)

McKoon, R.H.

1994-01-01

A 250 kW electron beam cold hearth refining (EBCHR) melt furnace at Lawrence Livermore National Laboratory (LLNL) has been in operation for over a year producing 5.5 in.-diameter ingots of various uranium alloys. Production of in-specification uranium-6%-niobium (U-6Nb) alloy ingots has been demonstrated using Virgin feedstock. A vibratory scrap feeder has been installed on the system and the ability to recycle chopped U-6Nb scrap has been established. A preliminary comparison of vacuum arc remelted (VAR) and electron beam (EB) melted product is presented

Progress toward uranium scrap recycling via Electron Cold Hearth Refining (EBCHR)

International Nuclear Information System (INIS)

McKoon, R.H.

1994-01-01

A 250 kW electron beam cold hearth refining (EBCHR) melt furnace at Lawrence Livermore National Laboratory (LLNL) has been in operation for over a year producing 5.5 in.-diameter ingots of various uranium alloys. Production of in-specification uranium-6% - niobium (U-6Nb) alloy ingots has been demonstrated using virgin feedstock. A vibratory scrap feeder has been installed on the system and the ability to recycle chopped U-6Nb scrap has been established. A preliminary comparison of vacuum arc remelted (VAR) and electron beam (EB) melted product is presented

Disposition of excess weapon grade plutonium: Status of the Russian program

Energy Technology Data Exchange (ETDEWEB)

Diyakov, Anatoly [Center for Arms Control, Energy and Environmental Studies, Moscow (Russian Federation)

2015-07-01

During the Cold War, the Soviet Union and United States produced huge quantities of plutonium for weapons. Substantial cuts in their nuclear arsenals released of huge amounts of weapon grade nuclear materials. This put into the agenda the problem what to do with the excess weapon materials. In 2000 Russia and the United States concluded a Plutonium Management and Disposition Agreement (PMDA), committing each to eliminate 34 tons of excess weapon plutonium. It was expected that the implementation of the PMDA Agreement will start in the second half of the year 2009 and the disposition programs finalized in 2025. But from the very beginning the practical implementation of the PMDA agreement met with substantial difficulties. After the consultations held in 2006-2007 the PMDA Agreement was modified. In compliance with the modified Agreement each side pledged to start the disposition of 34 tons of excess plutonium (25 tons in the form of metal and 9 tons in dioxide) in 2018 and to finalize the process in 15 years. Both sides were supposed to use the same disposition method through use in the MOX fuel and its subsequent irradiation in civil nuclear reactors: in light reactors for the USA and in fast neutron reactors for Russia. The presentation is going to provide the current status of the disposition program.

Recycling and processing of several typical crosslinked polymer scraps with enhanced mechanical properties based on solid-state mechanochemical milling

Energy Technology Data Exchange (ETDEWEB)

Lu, Canhui; Zhang, Xinxing; Zhang, Wei [State Key Laboratory of Polymer Materials Engineering, Polymer Research Institute, Sichuan University, Chengdu 610065 (China)

2015-05-22

The partially devulcanization or de-crosslinking of ground tire rubber (GTR), post-vulcanized fluororubber scraps and crosslinked polyethylene from cable scraps through high-shear mechanochemical milling (HSMM) was conducted by a modified solid-state mechanochemical reactor. The results indicated that the HSMM treated crosslinked polymer scraps can be reprocessed as virgin rubbers or thermoplastics to produce materials with high performance. The foamed composites of low density polyethylene/GTR and the blend of post-vulcanized flurorubber (FKM) with polyacrylate rubber (ACM) with better processability and mechanical properties were obtained. The morphology observation showed that the dispersion and compatibility between de-crosslinked polymer scraps and matrix were enhanced. The results demonstrated that HSMM is a feasible alternative technology for recycling post-vulcanized or crosslinked polymer scraps.

Recycling and processing of several typical crosslinked polymer scraps with enhanced mechanical properties based on solid-state mechanochemical milling

Science.gov (United States)

Lu, Canhui; Zhang, Xinxing; Zhang, Wei

2015-05-01

The partially devulcanization or de-crosslinking of ground tire rubber (GTR), post-vulcanized fluororubber scraps and crosslinked polyethylene from cable scraps through high-shear mechanochemical milling (HSMM) was conducted by a modified solid-state mechanochemical reactor. The results indicated that the HSMM treated crosslinked polymer scraps can be reprocessed as virgin rubbers or thermoplastics to produce materials with high performance. The foamed composites of low density polyethylene/GTR and the blend of post-vulcanized flurorubber (FKM) with polyacrylate rubber (ACM) with better processability and mechanical properties were obtained. The morphology observation showed that the dispersion and compatibility between de-crosslinked polymer scraps and matrix were enhanced. The results demonstrated that HSMM is a feasible alternative technology for recycling post-vulcanized or crosslinked polymer scraps.

Recycling and processing of several typical crosslinked polymer scraps with enhanced mechanical properties based on solid-state mechanochemical milling

International Nuclear Information System (INIS)

Lu, Canhui; Zhang, Xinxing; Zhang, Wei

2015-01-01

The partially devulcanization or de-crosslinking of ground tire rubber (GTR), post-vulcanized fluororubber scraps and crosslinked polyethylene from cable scraps through high-shear mechanochemical milling (HSMM) was conducted by a modified solid-state mechanochemical reactor. The results indicated that the HSMM treated crosslinked polymer scraps can be reprocessed as virgin rubbers or thermoplastics to produce materials with high performance. The foamed composites of low density polyethylene/GTR and the blend of post-vulcanized flurorubber (FKM) with polyacrylate rubber (ACM) with better processability and mechanical properties were obtained. The morphology observation showed that the dispersion and compatibility between de-crosslinked polymer scraps and matrix were enhanced. The results demonstrated that HSMM is a feasible alternative technology for recycling post-vulcanized or crosslinked polymer scraps

The Dispositions Improvement Process

Science.gov (United States)

Brewer, Robin D.; Lindquist, Cynthia; Altemueller, Lisa

2011-01-01

Globally, teacher dispositions along with knowledge and skills continue to be the focal point of teacher education programs. Teachers influence children's development and therefore dispositions are a universal concern. For the past 20 years in the United States, teacher education programs have assessed dispositions. We, however, must now also use…

Studies and determination of heavy metals in waste tyres and their impacts on the environment

International Nuclear Information System (INIS)

Shakya, P.R.; Shrestha, P.; Tamrakar, C.S.; Bhattarai, P.

2006-01-01

Uncontrolled burning of waste vehicle tyres causing environmental pollution has become a popular practice in developing countries like Nepal. Such activities were banned in many countries considering the environment and public health hazards but the official ban was ignored in many countries like Nepal. An experiment was conducted in a laboratory scale in an attempt to understand the potential discharge of trace metals content in Kathmandu Valley due to scrap tyre fires. For this purpose, four tyre types viz., CYCN, CSKR, BTIN and BBJP were collected representing the first two categories from passenger car and the last two from motorbike. An Atomic Absorption Spectrophotometer (AAS) was used for determination of metal concentration. Among the five heavy metals determined, Zn was detected in significantly high levels in all the tested tyre samples whereas Cd and Cr were found significantly less in many of them. The concentrations of Cd, Cr, Fe, Pb and Zn ranged from 0.020 - 27.1 micro g/g, 0.14 - 1.18 micro g/g, 17.8 - 381 micro g/g, 0.96 - 458 micro g/g and 3.95 - 8.21 micro g/g respectively. It was found that the metal concentration also varied with the tyre types and qualities. The potential discharge of the metals per representative scrap tyre mass was also estimated. Results indicate that the metal pollutants due to the uncontrolled burning of the scrap tyres could significantly contribute to deteriorate the environmental condition of the Valley. (author)

Automobile scrap regulation. Give-away presents. Polluting cars and trade-in for cleaner cars

International Nuclear Information System (INIS)

Annema, J.A.

2010-01-01

A scrap regulation for old vehicles has been in place in the Netherlands for almost one year now. Has it been an effective instrument? What are the societal costs and benefits? Is it a fair regulation? Was it a good idea to introduce the car scrap regulation? The answer to all these questions is: doubtful. [nl

Emergency response during the radiological control of scraps in Cuba

International Nuclear Information System (INIS)

Ramos Viltre, Enma O.; Cardenas Herrera, Juan; Dominguez Ley, Orlando; Capote Ferrera, Eduardo; Fernandez Gomez, Isis M.; Caveda Ramos, Celia; Carrazana, Jorge; Barroso Perez, Idelisa

2008-01-01

In the last few years, in the international scene, incidents have been reported due to the presence of radioactive materials in the scrap. This reality has motivated the adoption of measures of radiological security, due to the implications that these incidents have for the public and the environment, as well as for the international trade. Among theses actions is the implementation of the radiological control of scrap, with the additional requirement that this control has to be implemented in the framework of a Quality Management Program.Taking into account the international experience, our institution designed and organized in 2002 a national service for the radiological monitoring of scrap, being the clients the main exporting and trading enterprises of this material in the country. During these years, several contaminated materials have been detected, causing incidents that activated the radiological emergency response system. In this sense, since some years ago, our country has been working in the implementation of a national and ministerial system for facing and mitigating the consequences of accidental radiological situations, conjugating efforts and wills from different national institutions with the leadership of the Center of Radiation Protection and Hygiene (CPHR) and the Center of Nuclear Security (CNSN) in correspondence with the social responsibility assigned to the them. These incidents propitiate to have not only a system of capacity and quick response oriented to limit the exposure of people, to control the sources, to mitigate the consequences of the accident and to reestablish the conditions of normality, but also a previous adequate planning that guarantees the speed and effectiveness of it. In these work the experiences reached by the specialists of the CPHR from Cuba during the occurrence of an incident in the execution of the service of radiological monitoring of scraps are exposed. (author)

The Scrap Tire Problem: A Preliminary Economic Analysis (1985)

Science.gov (United States)

The purpose of the study was to conduct a preliminary economic analysis of the social benefits of EPA action to require more appropriate disposal of scrap tires versus the social costs of such an action.

Fertility Evaluation of Limed Brazilian Soil Polluted with Scrap Metal Residue

Directory of Open Access Journals (Sweden)

Flávia Almeida Gabos

2013-01-01

Full Text Available The aim of this work was to characterize the main inorganic contaminants and evaluate the effect of lime addition, combined with soil dilution with uncontaminated soil, as a strategy for mitigation of these contaminants present in a soil polluted with auto scrap. The experiment was performed in a greenhouse at Campinas (São Paulo State, Brazil in plastic pots (3 dm−3. Five soil mixtures, obtained by mixing an uncontaminated soil sample with contaminated soil (0, 25, 50, 75, and 100% contaminated soil, were evaluated for soil fertility, availability of inorganic contaminants, and corn development. In addition to the expected changes in soil chemistry due to the addition of lime, only the availability of Fe and Mn in the soil mixtures was affected, while the available contents of Cu, Zn, Cd, Cr, Ni, and Pb increased to some extent in the soil mixtures with higher proportion of contaminated soil. Liming of 10 t ha−1 followed by soil dilution at any proportion studied was not successful for mitigation of the inorganic contaminants to a desired level of soil fertility, as demonstrated by the available amounts extracted by the DTPA method (Zn, Pb, Cu, Ni, Cr, Cd and hot water (B still present in the soil. This fact was also proved by the phytotoxicity observed and caused by high amounts of B and Zn accumulating in the plant tissue.

Guidance document for multi-facility recycle/reuse/free release of metals from radiological control area

International Nuclear Information System (INIS)

Gogol, S.; Starke, T.

1997-01-01

Approximately 15% of the Low Level Waste (LLW) produced at Los Alamos consists of scrap metal equipment and materials. The majority of this material is produced by decommissioning and modification of existing facilities. To address this waste stream, Los Alamos has developed a scrap metal recycling program that is operated by the Environmental Stewardship Office to minimize the amount of LLW metal sent for LLW landfill disposal. Past practice has supported treating all waste metals generated within RCA's as contaminated. Through the metal recycling project, ESO is encouraging the use of alternatives to LLW disposal. Diverting RSM from waste landfill, disposal protects the environment, reduces the cost of operation, and reduces the cost of maintenance and operation at landfill sites. Waste minimization efforts also results in a twofold economic reward: The RSM has a market value and decontamination reduces the volume and therefore the amount of the radioactive waste to be buried within landfills

Recycling of metals: accounting of greenhouse gases and global warming contributions

DEFF Research Database (Denmark)

Damgaard, Anders; Larsen, Anna Warberg; Christensen, Thomas Højlund

2009-01-01

at the MRF as well as indirect downstream activities in terms of reprocessing of the metal scrap and savings in terms of avoided production of virgin metal. The global warming factor (GWF) shows that upstream activities and the MRF causes negligible GHG emissions (12.8 to 52.6 kg CO2-equivalents tonne—1...

Copper Recycling in the United States in 2004

Science.gov (United States)

Goonan, Thomas G.

2009-01-01

As one of a series of reports that describe the recycling of metal commodities in the United States, this report discusses the flow of copper from production through distribution and use, with particular emphasis on the recycling of industrial scrap (new scrap1) and used products (old scrap) in the year 2004. This materials flow study includes a description of copper supply and demand for the United States to illustrate the extent of copper recycling and to identify recycling trends. Understanding how materials flow from a source through disposition can aid in improving the management of natural resource delivery systems. In 2004, the U.S. refined copper supply was 2.53 million metric tons (Mt) of refined unalloyed copper. With adjustment for refined copper exports of 127,000 metric tons (t) of copper, the net U.S. refined copper supply was 2.14 Mt of copper. With this net supply and a consumer inventory decrease of 9,000 t of refined copper, 2.42 Mt of refined copper was consumed by U.S. semifabricators (brass mills, wire rod mills, ingot makers, and foundries and others) in 2004. In addition to the 2.42 Mt of refined copper consumed in 2004, U.S. copper semifabricators consumed 853,000 t of copper contained in recycled scrap. Furthermore, 61,000 t of copper contained in scrap was consumed by noncopper alloy makers, for example, steelmakers and aluminum alloy makers. Old scrap recycling efficiency for copper was estimated to be 43 percent of theoretical old scrap supply, the recycling rate for copper was 30 percent of apparent supply, and the new-scrap-to-old-scrap ratio for U.S. copper product production was 3.2 (76:24).

Demonstration test on manufacturing steel bars for concrete reinforcement for recycling of reactor decommissioning metal scrap

International Nuclear Information System (INIS)

Sakurai, D.; Anabuki, Y.

1993-01-01

To prove the possibility of recycling the steel scrap resulting from decommissioning of a nuclear power plant, this salvaged steel would be formed into steel bars for concrete reinforcement, as the restricted use and limited use at nuclear plants. The shifting behavior of radioactive isotopes (RI) in the melting process was confirmed through the laboratory hot test using the RI. Then, the demonstration cold test for steel bars for reinforcement using the nonradioactive isotope was conducted in on-line production facilities. In this test the quality of steel bars and uniform distribution of RI were proven and material balance and operational data were obtained. These data show the recycling to steel bars for concrete reinforcement is applicable from economical and safety aspects

Morphological and mechanical analyses of laminates manufactured from randomly positioned carbon fibre/epoxy resin prepreg scraps

Science.gov (United States)

Souza, Christiane S. R.; Cândido, Geraldo M.; Alves, Wellington; Marlet, José Maria F.; Rezende, Mirabel C.

2017-10-01

This study aims to contribute to sustainability by proposing the reuse of composite prepreg scrap as an added value from discards. The research evaluates the microstructure and mechanical properties of laminates processed by the reuse of uncured carbon fibre/F155-epoxy resin prepreg scraps, waste from the ply cutting area of an aeronautical industry. The composite scraps were used as collected and were randomly positioned to produce laminates to be cured at an autoclave. The mechanical characterization shows a decrease of 39% for the compression property due to the discontinuous fibres in the laminate and an increase of 34% for the interlaminar shear strength, when compared to continuous fibre laminates. This increase is attributed to the higher crosslink density of the epoxy resin, as a result of the cure temperature used in autoclave (60 °C higher than suggested by supplier) and also to the randomly positioned scraps. Microscopic analyses confirm the consolidation of laminates, although show resin rich areas with different sizes and shapes attributed to the overlapping of the scraps with different sizes and shapes. These resin rich areas may contribute to decrease the mechanical properties of laminates. The correlation between mechanical and morphological results shows potential to be used on non-critical structural application, as composite jigs, contributing to sustainability.

RECYCLING OF SCRAP AND WASTE OF COPPER AND COPPER ALLOYS IN BELARUS

Directory of Open Access Journals (Sweden)

S. L. Rovin

2017-01-01

Full Text Available The construction of a new casting and mechanical shop of unitary enterprise «Tsvetmet» in December 2015 has allowed to solve the complex problem of processing and utilization of scrap and wastes of copper and copper alloys in the Republic of Belarus. The technological processes of fire refinement of copper and manufacturing of copper rod from scrap and production of brass rod by hot pressing (extrusion of the continuously casted round billet have been mastered for the first time in the Republic of Belarus.

Study of scrap recovery for mixed oxide pellet by means of UO2+5wt.%CeO2

International Nuclear Information System (INIS)

Joung, Chang Young; Kim, Si Hyung; Kim, Han Soo; Lee, Yong Woo

2000-01-01

The recovery method of scrap powder was established using UO 2 -5wt.%CeO 2 powder in the way of of technology development of scrap recovery and recycle in the mixed oxide pellet fabrication process. And pellet density and microstructure, which depend on quantity of scrap, powder treatment method, and sintering condition, was analyzed. As a result of oxidation of sintered pellet in the air the powdering at below 400 degrees C occurred smoothly, and at above 400 degrees C powdering process was not proceeding well as temperature increased and powder particle size grew bigger. M 3 O 8 scrap powder which was powdered through oxidation method was added to UO 2 -5wt.%CeO 2 mixed powder. The results after the powder was treated by means of mixing, crushing, attrition milling, pelletizing, and sintering showed that its density and grain size in the case of reductive sintering decreased as scrap addition increased, but the result in the case of crushing showed increase in grain size. In attrition milling case both density and grain size showed the tendency of increase, particularly grain size grew up to 12 μm. In the oxidative sintering with scrap added mixed powder sintering was accelerated under the oxygen environment and the effect of powder treatment showed the tendency of relatively decreasing. (Hong, J. S.)

EFFECTOF ISOLATION WALL USING SCRAP TIRE ON GROUND VIBRATION REDUCTION

Science.gov (United States)

Kashimoto, Takahiko; Kashimoto, Yusuke; Hayakawa, Kiyoshi; Matsui, Tamotsu; Fujimoto, Hiroaki

Some countermeasure methods against the environmental ground vibration caused by some traffic vibrations have been proposed so far. The authors have developed a new type ground vibration isolation wall using scrap tire, and evaluated its effectiveness on the ground vibration reduction by full scale field tests. In this paper, the authors discussed and examined the effectiveness of the developed countermeasure method by two field tests. The one concerns on the effect of scrap tire as soft material of vibration isolation wall, and the other on the effect of the developed countermeasure method practically applied in a residential area close to monorail traffic. As the results, it was elucidated that the ground vibration of 2-3 dB was reduced in case of two times volume of the soft material, the conversion ratio of the vibration energy of the soft material to the kinetic energy was higher than that of the core material of PHC pile, the vibration acceleration of 0.19 - 1.26 gal was reduced by the developed countermeasure method in case of the monorail traffic, and the vibration reduction measured behind the isolation wall agreed well with the proposed theoretical value, together with confirming the effectiveness of the ground vibration isolation wall using scrap tire as the countermeasure method against the environmental ground vibration.

PRODUCTION OF ELECTROTECHNICAL WIRE OF SCRAP AND COPPER WASTES

Directory of Open Access Journals (Sweden)

I. P. Volchok

2006-01-01

Full Text Available Chemical composition, structure and properties of copper upon base steps of wire production technology (melting of anode copper with using of scrap and waste, electrolitical refining, producing of rod by continuous casting, manufacture of electrotechnical wire and fibres is described.

Preparation of High-purity Indium Oxalate Salt from Indium Scrap by Organic Acids

International Nuclear Information System (INIS)

Koo, Su-Jin; Ju, Chang-Sik

2013-01-01

Effect of organic acid on the preparation of indium-oxalate salt from indium scraps generated from ITO glass manufacturing process was studied. Effects of parameters, such as type and concentration of organic acids, pH of reactant, temperature, reaction time on indium-oxalate salt preparation were examined. The impurity removal efficiency was similar for both oxalic acid and citric acid, but citric acid did not make organic acid salt with indium. The optimum conditions were 1.5 M oxalic acid, pH 7, 80 .deg. C, and 6 hours. On the other hand, the recoveries increased with pH, but the purity decreased. The indium-oxalate salt purity prepared by two cycles was 99.995% (4N5). The indium-oxalate salt could be converted to indium oxide and indium metal by substitution reaction and calcination

Influence of bone porcelain scraps on the physical characteristics and phase composition of a hard porcelain body

Energy Technology Data Exchange (ETDEWEB)

Nodeh, A.A.

2017-07-01

Hard porcelain is constituted in the alkali oxides-alumina-silica ternary system, and produced by a mixture of clay-feldspar and silica. The most important properties of this porcelain are high mechanical strength, translucency and whiteness. These properties depend on quality of raw material, firing temperature and soaking time. In bone porcelain bone ash was added to body composition up to 50wt.%. Generally hard porcelain and bone porcelain scrap cannot be reused in body composition. Whereas using these scrap could help natural resources. In this research using bon porcelain scraps in hard porcelain body have been investigated. Results show, this substitution decrease firing temperature, linear expansion and increase glass, probability of deformation and total shrinkage. Using 6wt.% bone porcelain scraps to hard porcelain body composition besides improving some properties, increases 1340°C firing mechanical strength two times and helps natural resources. (Author)

Study of radiation portal monitor and its application to metal recycling industry

International Nuclear Information System (INIS)

Pujol, L.; Lara-Calleja, S.; Suarez-Navarro, M. J.; Gonzalez-Gonzalez, J. A.

2009-01-01

The industry of the iron and the steel in one of the most important sectors in Spain for its economic development. the recycling of metallic materials as well as the import of metallic scrap is very significant. Several reports on accidental dispersion or smelting of radioactive sources in metal recycling industries confirm the possibility that radioactive material might be mixed with scrap. In consequence, this type of accident shows the necessity of a rigorous and specific radiation control of the sector. The control of these materials with radioactive content can be carried out with radiation portal monitors installed at the entrance of these industries. The detection of radioactive materials presents special features as the continuous background acquisition or the minimisation of the relatively large number of innocent/nuisance detections. In the present work, we study a radiation portal monitor, the FHT-1388-T Thermo-Eberline. This is one of the usual radiation portal systems installed at the entrance of the metal recycling industry. Se study the characteristics and parameters of this portal monitor to optimise its use. furthermore, we propose some rapid tests for radiation portal systems in metal recycling industry. (Author) 16 refs

Radioactive contamination of recycled metals

International Nuclear Information System (INIS)

Lubenau, J.O.; Cool, D.A.; Yusko, J.G.

1996-01-01

Radioactive sources commingled with metal scrap have become a major problem for the metals recycling industry worldwide. Worldwide there have been 38 confirmed reports of radioactive sources accidentally smelted with recycled metal. In some instances, contaminated metal products were subsequently distributed. The metal mills, their products and byproducts from the metal making process such as slags, crosses and dusts from furnaces can become contaminated. In the U.S., imported ferrous metal products such as reinforcement bars, pipe flanges, table legs and fencing components have been found contaminated with taco. U.S. steel mills have unintentionally smelted radioactive sources on 16 occasions. The resulting cost for decontamination waste disposal and temporary closure of the steel mill is typically USD 10,000,000 and has been as much as USD 23,000,000. Other metal recycling industries that have been affected by this problem include aluminum, copper, zinc, gold, lead and vanadium. (author)

What is a Dispositive?

DEFF Research Database (Denmark)

Raffnsøe, Sverre; Gudmand-Høyer, Marius T.; Thaning, Morten Sørensen

perspective – indeed it forms a lesser known intermediary between these. Foucault’s dispositional analysis articulates a history of connected social technologies that we have constructed to relate to each other. Expounding these points, the article distinguishes various dispositional prototypes and develops...... key ‘socio-ontological’ implications of the analy-sis. Reinstating the proper analytical status of the dispositive contributes to the reception of the important notion; the interpretation of Foucault’s entire oeuvre; and a resourceful approach to the study of contemporary societal problems....

Recycling of radioactively contaminated scrap from the nuclear cycle and spin-off for other application

Directory of Open Access Journals (Sweden)

Quade, U.

2005-12-01

Full Text Available In the 1980ies, Siempelkamp foundry in Krefeld, Germany, developed a process to melt medium and slightly radioactive metals from decommissioning and maintenance works in nuclear power plants. Since 1989, in the CARLA melting plant which is licensed according to the German radiation protection ordinance (StrlSchV, metals are being molten which, for the largest part, can be reused. Since 1998, in a second plant, the GERTA melting plant, metals with a content of mercury up to 1 weight %, natural radioactivity up to 500 Bq/g and other chemical contaminations are being molten and completely decontaminated, so that these metals can be reused in the steel cycle. The following text is describing the melting process, acceptance criteria for contaminated scrap and recycling paths for the produced ingots and slags.

La fundición Siempelkamp en Krefeld, Alemania, desarrolló, en los años 80, un proceso para fundir metales mediana y levemente radioactivos, procedentes de reparaciones o desmantelamiento de plantas nucleares. En la planta de fundición CARLA, que cumple los requisitos del decreto de protección contra radiaciones de la República Federal de Alemania, se funden metales desde 1989, de los cuales la mayor parte puede ser utilizada nuevamente. Desde 1998, en una segunda planta, fundición GERTA, se funden y descontaminan totalmente, metales de hasta un 1 % de peso de mercurio, con una radioactividad natural de hasta 500 Bq/g y con otros contaminantes químicos. De este modo los metales pueden ser nuevamente utilizados en el ciclo metálico. El texto adjunto describe el método para el fundido, los criterios para aceptar chatarra contaminada y las vías de utilización para los bloques de metal y escorias generadas en el proceso.

Advanced Melting Technologies: Energy Saving Concepts and Opportunities for the Metal Casting Industry

Energy Technology Data Exchange (ETDEWEB)

none,

2005-11-01

The study examines current and emerging melting technologies and discusses their technical barriers to scale-up issues and research needed to advance these technologies, improving melting efficiency, lowering metal transfer heat loss, and reducing scrap.

Development of an integrated MOX-scrap recycling flow-sheet by dry and wet routes using microwave heating techniques

Energy Technology Data Exchange (ETDEWEB)

Mallik, G K; Malav, R K; Karande, A P; Bhargava, V K; Kamath, H S [Advanced Fuel Fabrication Facility, Bhabha Atomic Research Centre, Tarapur (India)

1999-01-01

A simple, short and efficient scrap, recycling flow-sheet, which is exclusively based on microwave heating techniques and, includes both dry and wet routes, for (U,Pu)O{sub 2} fuel scrap recycling has been developed and evaluated. (author) 6 refs., 1 tab.

Solids loading evaluation for HB-line scrap recovery filters

International Nuclear Information System (INIS)

Crowder, M.L.

2000-01-01

The HB-Line Scrap Recovery facility uses wire screen filters to remove solids from plutonium-containing solutions transferred from the slab tank dissolvers. At times, the accumulation of solids is large enough to cause blinding (i.e., pluggage) of the filters. If the solids contain undissolved plutonium, significant accumulation of fissile material could impact operations. To address this potential issue, experiments were performed to define the minimum solids required to completely blind a filter. The solids loading experiments were performed by arranging 25- and 10-microm HB-Line filters in series to simulate the equipment in the scrap recovery process. Separate tests were performed using coarse and fine glass frit and cerium oxide powder suspended in 35 wt% sodium nitrate solution using a small turbine mixer. The solution and solids were transferred from a reservoir through the filter housings by vacuum. In each case, the 25-microm filter blinded first and was full of wet cake. After drying and accounting for the sodium nitrate in the filter cake, the following results were obtained. The results of the solids loading tests demonstrated that at least 800 g of solids accumulated in the filter housing before flow stopped. The actual amount of collected material was dependent upon the physical properties of the solids such as density and particle size. The mass of solids collected by the blinded 25-microm filter increased when successively finer solids were used in the experiments. Based on these results, one should anticipate that filters in the HB-Line Scrap Recovery Facility have the potential to collect similar quantities of material before transfer of solution from the dissolvers is severely impacted

Safeguards and security requirements for weapons plutonium disposition in light water reactors

International Nuclear Information System (INIS)

Thomas, L.L.; Strait, R.S.

1994-10-01

This paper explores the issues surrounding the safeguarding of the plutonium disposition process in support of the United States nuclear weapons dismantlement program. It focuses on the disposition of the plutonium by burning mixed oxide fuel in light water reactors (LWR) and addresses physical protection, material control and accountability, personnel security and international safeguards. The S and S system needs to meet the requirements of the DOE Orders, NRC Regulations and international safeguards agreements. Experience has shown that incorporating S and S measures into early facility designs and integrating them into operations provides S and S that is more effective, more economical, and less intrusive. The plutonium disposition safeguards requirements with which the US has the least experience are the implementation of international safeguards on plutonium metal; the large scale commercialization of the mixed oxide fuel fabrication; and the transportation to and loading in the LWRs of fresh mixed oxide fuel. It is in these areas where the effort needs to be concentrated if the US is to develop safeguards and security systems that are effective and efficient

Disposition of Highly Enriched Uranium (HEU) and Pu from nuclear weapons

International Nuclear Information System (INIS)

Neff, T.L.

1992-01-01

Last year, as the Soviet Union began to crumble and the Bush-Gorbachev talks had advanced to consider the dismantling of actual warheads instead of mere delivery systems, Dr. Thomas L. Neff, a senior member of MIT's Center for International Studies, tinkered with the notion that one day soon the US could be buying Russian uranium from scrapped nuclear arms. He also considered the costly business of dismantlement and set to work on an ingenious proposal. The basic idea was simply to purchase the HEU from Russia using funds derived from savings in the US Department of Energy's enrichment enterprise. The proposal, now part of an umbrella agreement between the US and Russia announced in early September, promises large strategic benefits for the US in terms of both financing dismantlement (to the tune of $100 million annually), as well as political oversight for the operation itself. In the words of Dr. Neff, who made briefings to both governments on the proposal, open-quotes It's a budget-neutral, win-win solution.close quotes What follows is an illustrated, step-by-step analysis of the proposal, as well as a reprint of Dr. Neff's paper, Disposition of HEU and Pu from Nuclear Weapons, as presented to the Uranium Institute's annual symposium last month

Problems with radioactivity scrap in the iron and steel industry of the Czech and Slovak Republics

International Nuclear Information System (INIS)

Raab, J.; Toman, V.

1999-01-01

During the recent restructuring process, the Czech steel industry has undergone a drastic reduction in the steel production by around 40%. Under such situation, previously exported volumes have been diverted into domestic markets. For the export, the Czech steel industry had to make its efforts in enhancing the quality of products and in improving the technologies in accordance with ISO standards (ISO 9000 and also ISO 14000). Among the various new quality demands in the export market, the radioactive contamination of steel products has received a very high attention. The Czech Iron and Steel Federation has organized a working team specialized in solving the problems arising from radioactive contaminated metallurgical scrap and steel products. The working team is made up of specialists from steel producers and scrap handling firms of the Czech Republic and the Slovak Republic, of experts from the State Office for Nuclear Safety, the Ministry of Industry and Trade and the Metrological Institute. Members of the Inspectorate for Ionizing Radiation and the General Directory for Customs are also included. This working team takes part in the elaboration of the legislative norms in that area. This paper deals with all the detailed functions of the working team. At present, all the major Czech steel producers have installed stationary radiation monitoring systems for detecting the possible radioactivity in all materials entering into factories. Under an agreement arranged between the producers of the Czech Iron and Steel Federation, the tolerable range of radionuclide contents in steel scrap and steel products has been set at the maximum of 100 Bq/kg in ( scrap and steel products. In this respect, the large firms collecting and treating scrap have also installed stationary radiation monitoring systems. In such monitoring systems, the detector will measure and check the values of radioactivity above 10 - 15% higher than the natural background level. In the case that

Direct conversion of plutonium-containing materials to borosilicate glass for storage or disposal

International Nuclear Information System (INIS)

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

1995-01-01

A new process, the Glass Material Oxidation and Dissolution System (GMODS), has been invented for the direct conversion of plutonium metal, scrap, and residue into borosilicate glass. The glass should be acceptable for either the long-term storage or disposition of plutonium. Conversion of plutonium from complex chemical mixtures and variable geometries into homogeneous glass (1) simplifies safeguards and security; (2) creates a stable chemical form that meets health, safety, and environmental concerns; (3) provides an easy storage form; (4) may lower storage costs; and (5) allows for future disposition options. In the GMODS process, mixtures of metals, ceramics, organics, and amorphous solids containing plutonium are fed directly into a glass melter where they are directly converted to glass. Conventional glass melters can accept materials only in oxide form; thus, it is its ability to accept materials in multiple chemical forms that makes GMODS a unique glass making process. Initial proof-of-principle experiments have converted cerium (plutonium surrogate), uranium, stainless steel, aluminum, and other materials to glass. Significant technical uncertainties remain because of the early nature of process development

Optimization of fuel recovery through the stepwise co-pyrolysis of palm shell and scrap tire

International Nuclear Information System (INIS)

Abnisa, Faisal; Wan Daud, Wan Mohd Ashri

2015-01-01

Highlights: • The co-pyrolysis of palm shell and scrap tire was studied. • The effect of stepwise co-pyrolysis temperature was investigated. • Co-pyrolysis successfully improved the quantity and quality of product yields. • Stepwise co-pyrolysis slightly increased oil and gas, and decreased char. • The co-pyrolysis of 50% biomass and 50% scrap tire is recommended. - Abstract: This study optimized the use of biomass waste to generate fuel through co-pyrolysis. In this paper, the effects of stepwise co-pyrolysis temperature and different ratios between palm shells and scrap tires in feedstock were studied to observe any improvements in the quantity and quality of the liquid yield and its byproduct. The ratio of palm shells and scrap tires varied at 100:0, 75:25, 50:50, 25:75, and 0:100. The experiment was conducted in a fixed-bed reactor. The study was divided into two scenarios. The first scenario was performed at the optimum temperature of 500 °C with a reaction time of 60 min. In the second scenario, the temperature was set at 500 °C for 60 min before the temperature was increased to 800 °C with a high heating rate. After the temperature reached 800 °C, the condition was maintained for approximately 45 min. Results showed that an increase in the liquid and gas yields was achieved when the temperature increased after optimum conditions. Increased yield was also obtained when the proportion of scrap tire was increased in the feedstock. Several other important findings are discussed in this paper, including the phases of pyrolysis oil, features of the liquid product, and characteristics of the byproducts. All products from both scenarios were analyzed by various methods to understand their fuel characteristics

Recycling of metals: accounting of greenhouse gases and global warming contributions.

Science.gov (United States)

Damgaard, Anders; Larsen, Anna W; Christensen, Thomas H

2009-11-01

Greenhouse gas (GHG) emissions related to recycling of metals in post-consumer waste are assessed from a waste management perspective; here the material recovery facility (MRF), for the sorting of the recovered metal. The GHG accounting includes indirect upstream emissions, direct activities at the MRF as well as indirect downstream activities in terms of reprocessing of the metal scrap and savings in terms of avoided production of virgin metal. The global warming factor (GWF) shows that upstream activities and the MRF causes negligible GHG emissions (12.8 to 52.6 kg CO(2)-equivalents tonne(-1) recovered metal) compared to the reprocessing of the metal itself (360-1260 kg CO(2)-equivalents tonne(-1) of recovered aluminium and 400- 1020 kg CO(2)-equivalents tonne(- 1) of recovered steel).The reprocessing is however counterbalanced by large savings of avoided virgin production of steel and aluminium. The net downstream savings were found to be 5040-19 340 kg CO(2)-equivalents tonne(-1) of treated aluminium and 560-2360 kg CO(2)-equivalents tonne(-1) of treated steel. Due to the huge differences in reported data it is hard to compare general data on the recovery of metal scrap as they are very dependent on the technology and data choices. Furthermore, the energy used in both the recovery process as well as the avoided primary production is crucial. The range of avoided impact shows that recovery of metals will always be beneficial over primary production, due to the high energy savings, and that the GHG emissions associated with the sorting of metals are negligible.

29 CFR 570.63 - Occupations involved in the operation of paper-products machines, scrap paper balers, and paper...

Science.gov (United States)

2010-07-01

... 29 Labor 3 2010-07-01 2010-07-01 false Occupations involved in the operation of paper-products machines, scrap paper balers, and paper box compactors (Order 12). 570.63 Section 570.63 Labor Regulations... involved in the operation of paper-products machines, scrap paper balers, and paper box compactors (Order...

Incident involving radioactive material in steel scrap

International Nuclear Information System (INIS)

Drabova, D.; Matzner, J.; Prouza, Z.

1998-01-01

In early March of 1996, a wagon with steel scrap heading from the Czech Republic to Italy was returned as a strongly contaminated material. Based on the integral dose (dose rate 650 mGy/h in front of the wagon) and spectrometric measurement and evaluation, it was concluded that an unshielded cobalt-60 source (1.6 TBq) was present. The history of the event (notification, assessment, intervention planning, intervention) is highlighted and the lesson learned from the incident is discussed. (P.A.)

Evaluation of copper for divider subassembly in MCO Mark IA and Mark IV scrap fuel baskets

International Nuclear Information System (INIS)

Graves, C.E.

1997-01-01

The K Basin Spent Nuclear Fuel (SNF) Project Multi-Canister Overpack (MCO) subprojection eludes the design and fabrication of a canister that will be used to confine, contain, and maintain fuel in a critically safe array to enable its removal from the K Basins, vacuum drying, transport, staging, hot conditioning, and interim storage (Goldinann 1997). Each MCO consists of a shell, shield plug, fuel baskets (Mark IA or Mark IV), and other incidental equipment. The Mark IA intact and scrap fuel baskets are a safety class item for criticality control and components necessary for criticality control will be constructed from 304L stainless steel. It is proposed that a copper divider subassembly be used in both Mark IA and Mark IV scrap baskets to increase the safety basis margin during cold vacuum drying. The use of copper would increase the heat conducted away from hot areas in the baskets out to the wall of the MCO by both radiative and conductive heat transfer means. Thus copper subassembly will likely be a safety significant component of the scrap fuel baskets. This report examines the structural, cost and corrosion consequences associated with using a copper subassembly in the stainless steel MCO scrap fuel baskets

Pyrolysis of a waste from the grinding of scrap tyres.

Science.gov (United States)

Fernández, A M; Barriocanal, C; Alvarez, R

2012-02-15

The fibres that are used to reinforce tyres can be recovered as a waste in the process of grinding of scrap tyres. In this paper beneficiation through pyrolysis is studied since the fibres are made up of polymers with a small amount of rubber because the latter is difficult to separate. The experiments were performed at three temperatures (400, 550 and 900°C) in a horizontal oven. The three products - gas, oil and char - obtained from the pyrolysis were investigated. The composition of the gas was analyzed by means of gas chromatography. The oil was studied by gas chromatography and infrared spectroscopy. The char porous structure was determined by N(2) adsorption. In addition, the topography of the chars was studied by means of scanning electron microscopy (SEM). The products resulting from the pyrolysis of the fibres were compared with those obtained from scrap rubber. Copyright © 2011 Elsevier B.V. All rights reserved.

NRC comprehensive records disposition schedule

International Nuclear Information System (INIS)

1992-03-01

Title 44 United States Code, ''Public Printing and Documents,'' regulations cited in the General Services Administration's (GSA) ''Federal Information Resources Management Regulations'' (FIRMR), Part 201-9, ''Creation, Maintenance, and Use of Records,'' and regulation issued by the National Archives and Records Administration (NARA) in 36 CFR Chapter XII, Subchapter B, ''Records Management,'' require each agency to prepare and issue a comprehensive records disposition schedule that contains the NARA approved records disposition schedules for records unique to the agency and contains the NARA's General Records Schedules for records common to several or all agencies. The approved records disposition schedules specify the appropriate duration of retention and the final disposition for records created or maintained by the NRC. NUREG-0910, Rev. 2, contains ''NRC's Comprehensive Records Disposition Schedule,'' and the original authorized approved citation numbers issued by NARA. Rev. 2 totally reorganizes the records schedules from a functional arrangement to an arrangement by the host office. A subject index and a conversion table have also been developed for the NRC schedules to allow staff to identify the new schedule numbers easily and to improve their ability to locate applicable schedules

Radiation accident at Mayapuri scrap market, Delhi, 2010

International Nuclear Information System (INIS)

Dey, A. B.; Mohanan, S.; Damodaran, D.; Soneja, M.; Jain, N.; Mohan, A.; Vikram, N. K.; Sood, R.

2012-01-01

This article reports the accidental public radiation exposure in a scrap market in Delhi (India)), on March 2010. The source, a gamma unit containing Cobalt-60 pencils, was improperly disposed of by a research institution in violation of national regulations for radiation protection and safety of radioactive sources. The unit was sold off to unsuspecting scrap dealers who dismantled the equipment. This event subsequently caused the most severe radiation accident reported in India to date, resulting in seven radiation injuries and one death. The clinical course of five of the patients treated at the All India Inst. of Medical Sciences hospital, New Delhi, is summarised in this report. All five patients suffered from the haematological form of the acute radiation syndrome and local cutaneous radiation injury as well. While four patients exposed to doses between 0.6 and 2.8 Gy survived with intensive or supportive treatment, the patient with the highest exposure of 3.1 Gy died due to acute respiratory distress syndrome and multi-organ failure on Day 16 after hospitalisation. The incident highlights the current gaps in the knowledge, infrastructure and legislation in handling radioactive materials. Medical institutions need to formulate individualised triage and management guidelines to immediately respond to future public radiological accidents. (authors)

Recycling of metals from metal containing industrial wastes by means of plasma

International Nuclear Information System (INIS)

Burkhard, R.

1995-01-01

Recovery of metals from complex mixed wastes is a challenging task of modern material and waste management strategies. Thermal methods are an important tool in this respect. Plasma turned out to be particularly useful for treatment of complex or toxic wastes and residuals. In order to study the recycling parameters and behaviour of different metal containing wastes at reasonable costs, two pilot plasma plants have been used and metal containing, industrial wastes like spent Raney-Nickel catalysts, copper and aluminium drosses, MMC's, scrap, and others were investigated. The heart of the plasma equipment used is the Rotating Hearth (PRH) with a central base orifice. The hearth of the furnace rotates with a speed which prevents the melt from dripping. For pouring, the rotational speed is lowered, which allows the melt to be dripped into a mould. The RIF2 is equipped with a transferred plasma torch which can be operated up to 200 kW. The furnace is equipped with a secondary combustion chamber (SCC). The gases leaving the SCC go through a quench/scrubber. A powerful fan maintains underpressure in the whole system. Waste and additives can be fed through a nitrogen-purged port batchwise or with a screw feeder. The main components of the waste material investigated are nickel and aluminium in Raney-Nickel. The goal to recycle it is to produce NiFe-alloys for further use in the steel industry, or even NiAl-alloy for new catalyst production by using aluminium scrap as reducing and alloying element respectively. Aluminium dross occurs as an unavoidable by-product of all aluminium melting operations. It consists of metallic aluminium, oxides, nitrides, and salts. The separation of the aluminium phase from the oxides is the main task for recycling the aluminium. The general result is: recovery of metals out of complex mixed waste by using plasma rotating hearth technology and appropriate furnace modifications is feasible and ecological-economically interesting. (author) 147

Caltrans use of scrap tires in asphalt rubber products: a comprehensive review

Directory of Open Access Journals (Sweden)

Haiping Zhou

2014-02-01

Full Text Available The California Department of Transportation (Caltrans has been using scrap tire rubber in asphalt pavements since the 1970s in chip seals and the 1980s in rubberized hot mix asphalt(RHMA. Both the wet (field blend and dry processes were used in early trials. Caltrans has also used rubber modified binders containing both crumb rubber modifier and polymer modifier that could be manufactured at a refinery facility, a terminal blend wet process. Since the beginning of this century, Caltrans increased the use of scrap tire rubber in paving projects and invested considerable resources in developing technically sound, cost effective, and environmentally friendly strategies for using scrap tire rubber in roadway applications. By the end of year 2010, approximately 31%of all hot mix asphalt (HMA placed by Caltrans was rubberized HMA, roughly 1.2 million tons. Caltrans efforts in using asphalt rubber products were also demonstrated in its research and technology development. These included the construction of two full-scale field experiments, five warranty projects, and an accelerated pavement study using a heavy vehicle simulator. Additionally, terminal blend asphalt rubber and rubberized warm mix asphalts began to be experimented on trial basis. This paper provides a comprehensive review of Caltrans experience over four decades with asphalt rubber products. Current practices and future outlook are also discussed.

Kinetics of the Thermal Degradation of Granulated Scrap Tyres: a Model-free Analysis

Directory of Open Access Journals (Sweden)

Félix A. LÓPEZ

2013-12-01

Full Text Available Pyrolysis is a technology with a promising future in the recycling of scrap tyres. This paper determines the thermal decomposition behaviour and kinetics of granulated scrap tyres (GST by examining the thermogravimetric/derivative thermogravimetric (TGA/DTG data obtained during their pyrolysis in an inert atmosphere at different heating rates. The model-free methods of Friedman, Flynn-Wall-Ozawa and Coats-Redfern were used to determine the reaction kinetics from the DTG data. The apparent activation energy and pre-exponential factor for the degradation of GST were calculated. A comparison with the results obtained by other authors was made.DOI: http://dx.doi.org/10.5755/j01.ms.19.4.2947

The Effectof Underwater Explosion on the Kinetics of Alkaline Leaching of Roasted Tungsten Carbide Scraps for Recycling

OpenAIRE

BAIK, Seung Woo; SHIBAYAMA, Atsushi; MURATA, Kenji; FUJITA, Toyohisa

2004-01-01

Wasted tungsten scraps are important resources for recycling, however, the mechanical recycle process of tungsten has a difficulty for recycling due to its mechanical strength. Underwater explosion fracturing technique was designed for solving this problem. The kinetics for alkaline leaching of roasted tungsten alloy scraps with different size distribution prepared by two ways of crushing technique has been investigated to evaluate the effect of the underwater explosion-crushing. The merit of...

Scrap Tyre Management Pathways and Their Use as a Fuel—A Review

Directory of Open Access Journals (Sweden)

Amir Rowhani

2016-10-01

Full Text Available This article provides a review of different methods for managing waste tyres. Around 1.5 billion scrap tyres make their way into the environmental cycle each year, so there is an extreme demand to manage and mitigate the environmental impact which occurs from landfilling and burning. Numerous approaches are targeted to recycle and reuse the tyre rubber in various applications. Among them, one of the most important methods for sustainable environmental stewardship is converting tyre rubber components into bio-oil. In this study, scrap tyre management techniques including landfill, retreading, recycling, combustion, and conversion to liquid fuels was reviewed (including gasification, hydrothermal liquefaction, and pyrolysis. The effects of parameters such as reactor types, pyrolysis temperature, and catalyst on the oil, gas and solid products in pyrolysis process were investigated.

Economic feasibility of radioactive scrap steel recycling

International Nuclear Information System (INIS)

Balhiser, R.; Rosholt, D.; Nichols, F.

1995-01-01

The goal of MSE's Radioactive Scrap Steel (RSS) Recycle Program is to develop practical methods for recycling RSS into useful product. This paper provides interim information about ongoing feasibility investigations that are scheduled for completion by September 1995. The project approach, major issues, and cost projections are outlined. Current information indicates that a cost effective RSS Recycling Facility can be designed, built, and in operation by 1999. The RSS team believes that high quality steel plate can be made from RSS at a conversion cost of $1500 per ton or less

Wastes from plutonium conversion and scrap recovery operations

Energy Technology Data Exchange (ETDEWEB)

Christensen, D.C.; Bowersox, D.F.; McKerley, B.J.; Nance, R.L.

1988-03-01

This report deals with the handling of defense-related wastes associated with plutonium processing. It first defines the different waste categories along with the techniques used to assess waste content. It then discusses the various treatment approaches used in recovering plutonium from scrap. Next, it addresses the various waste management approaches necessary to handle all wastes. Finally, there is a discussion of some future areas for processing with emphasis on waste reduction. 91 refs., 25 figs., 4 tabs.

Wastes from plutonium conversion and scrap recovery operations

International Nuclear Information System (INIS)

Christensen, D.C.; Bowersox, D.F.; McKerley, B.J.; Nance, R.L.

1988-03-01

This report deals with the handling of defense-related wastes associated with plutonium processing. It first defines the different waste categories along with the techniques used to assess waste content. It then discusses the various treatment approaches used in recovering plutonium from scrap. Next, it addresses the various waste management approaches necessary to handle all wastes. Finally, there is a discussion of some future areas for processing with emphasis on waste reduction. 91 refs., 25 figs., 4 tabs

CRITICAL ASPECTS IN SCRAPS OF COLD SMOKED SALMON PROCESSING

Directory of Open Access Journals (Sweden)

C. Bernardi

2011-01-01

Full Text Available The aim of the paper was to summarize the critical aspects in the processing of smoked salmon scraps as resulted from seven different lots of samples through microbiological and chemical-physical analysis. Results demonstrate that this product has very variable salt content, high microbial counts influencing the shelf-life, rancidity problems depending on the raw material and is heavily contaminated by Listeria monocytogenes.

Mathematical Modeling and Algebraic Technique for Resolving a Single-Producer Multi-Retailer Integrated Inventory System with Scrap

OpenAIRE

Yuan-Shyi Peter Chiu; Chien-Hua Lee; Nong Pan; Singa Wang Chiu

2013-01-01

This study uses mathematical modeling along with an algebraic technique to resolve the production-distribution policy for a single-producer multi-retailer integrated inventory system with scrap in production. We assume that a product is manufactured through an imperfect production process where all nonconforming items will be picked up and scrapped in each production cycle. After the entire lot is quality assured, multiple shipments will be delivered synchronously to m different retailers in ...

Method for converting uranium oxides to uranium metal

Science.gov (United States)

Duerksen, Walter K.

1988-01-01

A process is described for converting scrap and waste uranium oxide to uranium metal. The uranium oxide is sequentially reduced with a suitable reducing agent to a mixture of uranium metal and oxide products. The uranium metal is then converted to uranium hydride and the uranium hydride-containing mixture is then cooled to a temperature less than -100.degree. C. in an inert liquid which renders the uranium hydride ferromagnetic. The uranium hydride is then magnetically separated from the cooled mixture. The separated uranium hydride is readily converted to uranium metal by heating in an inert atmosphere. This process is environmentally acceptable and eliminates the use of hydrogen fluoride as well as the explosive conditions encountered in the previously employed bomb-reduction processes utilized for converting uranium oxides to uranium metal.

Leaching kinetics of cobalt from the scraps of spent aerospace magnetic materials.

Science.gov (United States)

Zhou, Xuejiao; Chen, Yongli; Yin, Jianguo; Xia, Wentang; Yuan, Xiaoli; Xiang, Xiaoyan

2018-06-01

Based on physicochemical properties of the scraps of spent aerospace magnetic materials, a roasting - magnetic separation followed by sulfuric acid leaching process was proposed to extract cobalt. Roasting was performed at 500 °C to remove organic impurity. Non-magnetic impurities were reduced by magnetic separation and then the raw material was sieved into desired particle sizes. Acid leaching was carried out to extract cobalt from the scraps and experimental parameters included agitation speed, particle size, initial concentration of sulfuric acid and temperature. Agitation speed higher than 300 r/min had a relatively small impact on the cobalt extraction. As the particle size reduced, the content of cobalt in the raw material decreases and the extraction of cobalt by acid leaching increased at first and decreased afterwards. Raising the initial concentration of sulfuric acid and temperature contributed to improve the cobalt extraction and the influence of temperature was more remarkable. SEM image revealed that the spent aerospace magnetic materials mainly existed in the sliced strip flake with a loose surface and porous structure. Under the experimental condition, the leaching rate of cobalt from the scraps in sulfuric acid solution could be expressed as ln(-ln(1 - α)) = lnk + nlnt. The apparent activation energy was found to be 38.33 kJ/mol and it was mainly controlled by the surface chemical reaction. Copyright © 2018 Elsevier Ltd. All rights reserved.

Scrap tire pyrolysis using a new type two-stage pyrolyzer: Effects of dolomite and olivine on producing a low-sulfur pyrolysis oil

International Nuclear Information System (INIS)

Choi, Gyung-Goo; Oh, Seung-Jin; Kim, Joo-Sik

2016-01-01

Scrap tire pyrolysis was performed using a two-stage pyrolyzer consisting of an auger reactor and a fluidized bed reactor to produce a low-sulfur pyrolysis oil. In the experiments, the effect of the residence time of the feed material in the auger reactor was investigated at ∼300 (auger reactor) and 500 °C (fluidized bed reactor). In addition, natural dolomite and olivine and calcined dolomite and olivine were used as the fluidized bed materials to examine their effects on reducing the sulfur content of pyrolysis oil. In the experiments, the yields of the oil from the auger reactor were 1.4–3.7 wt%, and it was enriched with DL-limonene whose content in the oil was 40–50 wt%. The yields of the oil from the fluidized bed reactor were 42–46 wt%. The optimum residence time of the feed material in the auger reactor turned out to be 3.5 min. Calcined dolomite and olivine significantly decreased the sulfur content of pyrolysis oil. Metal oxides of the additives appeared to react with H_2S to form metal sulfides. The sulfur content of pyrolysis oil obtained with calcined olivine was 0.45 wt%. - Highlights: • Scrap tires were successfully pyrolyzed in a new type two-stage pyrolyzer. • The two-stage pyrolyzer is composed of an auger and fluidized bed reactors. • Calcination of olivine and dolomite led to a strong decrease in sulfur. • The lowest sulfur content of pyrolysis oil was 0.45 wt%. • Pyrolysis oil yields from the fluidized bed reactor were 43–46 wt%.

Organic Matter and Barium Absorption by Plant Species Grown in an Area Polluted with Scrap Metal Residue

Directory of Open Access Journals (Sweden)

Cleide Aparecida Abreu

2012-01-01

Full Text Available The effect of organic matter addition on Ba availability to Helianthus annuus L., Raphanus sativus L., and Ricinus communis L. grown on a Neossolo Litólico Chernossólico fragmentário (pH 7.5, contaminated with scrap residue was evaluated. Four rates (0, 20, 40, and 80 Mg ha−1, organic carbon basis of peat or sugar cane filter, with three replicates, were tested. Plant species were grown until the flowering stage. No effect of organic matter addition to soil on dry matter yield of oilseed radish shoots was observed, but there was an increase in sunflower and castor oil plant shoots when sugar cane filter cake was used. The average Ba transferred from roots to shoots was more than 89% for oilseed radish, 71% for castor oil plants, and 59% for sunflowers. Organic matter treatments were not efficient in reducing Ba availability due to soil liming.

Lead scrap use and trade patterns in the United States, 1995-2012

Science.gov (United States)

Wilburn, David R.

2015-09-22

Since 1995, domestic production of lead has increasingly shifted from primary mining and smelting to the recovery of lead-bearing scrap by the secondary lead industry, which accounted for 91 percent of U.S. lead production in 2012. Increasingly stringent environmental regulations for lead emissions in the United States have contributed to the closure of primary lead refineries and the consolidation of the secondary lead industry. Domestic production of lead from the primary and secondary sectors in 2012 is essentially unchanged from the amount produced in 1995. The U.S. secondary industry produced an estimated 145,000 metric tons more refined lead in 2012 than it did in 1995, primarily by recovering lead from battery scrap, allowing the U.S. to maintain production at a level sufficient to supply much of the domestic demand for lead.

Plutonium scrap waste processing based on aqueous nitrate and chloride media

International Nuclear Information System (INIS)

Navratil, J.D.

1985-01-01

A brief review of plutonium scrap aqueous waste processing technology at Rocky Flats is given. Nitric acid unit operations include dissolution and leaching, anion exchange purification and precipitation. Chloride waste processing consists of cation exchange and carbonate precipitation. Ferrite and carrier precipitation waste treatment processes are also described. 3 figs

Direct conversion of plutonium metal, scrap, residue, and transuranic waste to glass

International Nuclear Information System (INIS)

Forsberg, C.W.; Beahm, E.C.; Parker, G.W.; Malling, J.F.; Rudolph, J.

1995-01-01

A method for the direct conversion of metals, ceramics, organics, and amorphous solids to borosilicate glass has been invented. The process is called the Glass Material Oxidation and Dissolution System (GMODS). Traditional glass-making processes can convert only oxide materials to glass. However, many wastes contain complex mixtures of metals, ceramics, organics, and amorphous solids. Conversion of such mixtures to oxides followed by their conversion to glass is often impractical. GMODS may create a practical method to convert such mixtures to glass. Plutonium-containing materials (PCMS) exist in many forms, including metals, ceramics, organics, amorphous solids, and mixtures thereof. These PCMs vary from plutonium metal to filters made of metal, organic binders, and glass fibers. For storage and/or disposal of PCMS, it is desirable to convert PCMs to borosilicate glass. Borosilicate glass is the preferred repository waste form for high-level waste (HLW) because of its properties. PCMs converted to a transuranic borosilicate homogeneous glass would easily pass all waste acceptance and storage criteria. Conversion of PCMs to a glass would also simplify safeguards by conversion of heterogeneous PCMs to homogeneous glass. Thermodynamic calculations and proof-of-principle experiments on the GMODS process with cerium (plutonium surrogate), uranium, stainless steel, aluminum, Zircaloy-2, and carbon were successfully conducted. Initial analysis has identified potential flowsheets and equipment. Major unknowns remain, but the preliminary data suggests that GMODS may be a major new treatment option for PCMs

Derivation of plutonium-239 materials disposition categories

International Nuclear Information System (INIS)

Brough, W.G.

1995-01-01

At this time, the Office of Fissile Materials Disposition within the DOE, is assessing alternatives for the disposition of excess fissile materials. To facilitate the assessment, the Plutonium-Bearing Materials Feed Report for the DOE Fissile Materials Disposition Program Alternatives report was written. The development of the material categories and the derivation of the inventory quantities associated with those categories is documented in this report

Synthesis of high purity tungsten nanoparticles from tungsten heavy alloy scrap by selective precipitation and reduction route

International Nuclear Information System (INIS)

Kamal, S.S. Kalyan; Sahoo, P.K.; Vimala, J.; Shanker, B.; Ghosal, P.; Durai, L.

2016-01-01

In this paper we report synthesis of tungsten nanoparticles of high purity >99.7 wt% from heavy alloy scrap using a novel chemical route of selective precipitation and reduction. The effect of Poly(vinylpyrrolidone) polymer on controlling the particle size is established through FTIR spectra and corroborated with TEM images, wherein the average size decreased form 210 to 45 nm with increasing PVP content from zero to 2 g under different experimental conditions. This process is economical as raw material is a scrap and the efficiency of the reaction is >95%. - Highlights: • Tungsten nanoparticles were synthesized from tungsten heavy alloy scrap. • A novel chemical route of precipitation and reduction with Poly(vinylpyrrolidone) polymer as stabilizer is reported. • The average size decreased form 210 to 45 nm with increasing PVP content from zero to 2 g. • High pure tungsten nanoparticles of >99.7% purity could be synthesized using this route. • Efficiency of the reaction is >95%.

Collection and recycling of electronic scrap: A worldwide overview and comparison with the Brazilian situation

International Nuclear Information System (INIS)

Reis de Oliveira, Camila; Moura Bernardes, Andréa; Gerbase, Annelise Engel

2012-01-01

Highlights: ► Review of the different e-waste collection systems and recycling processes. ► We present the e-waste collection systems used in Europe and in the US. ► We present e-waste collection systems used in Asia and Latin America. ► E-waste management between developed and developing countries is very different. ► We made a comparison of the world situation to the current Brazilian reality. - Abstract: Recycling and the related issue of sustainable development are increasing in importance around the world. In Brazil, the new National Policy on Solid Wastes has prompted discussion on the future of electronic waste (e-waste). Over the last 10 years, different e-waste collection systems and recycling processes have been applied globally. This paper presents the systems used in different countries and compares the world situation to the current Brazilian reality. To establish a recycling process, it is necessary to organize efficient collection management. The main difficulty associated with the implementation of e-waste recycling processes in Brazil is the collection system, as its efficiency depends not only on the education and cooperation of the people but also on cooperation among industrial waste generators, distributors and the government. Over half a million waste pickers have been reported in Brazil and they are responsible for the success of metal scrap collection in the country. The country also has close to 2400 companies and cooperatives involved in recycling and scrap trading. On the other hand, the collection and recycling of e-waste is still incipient because e-wastes are not seen as valuable in the informal sector. The Brazilian challenge is therefore to organize a system of e-waste management including the informal sector without neglecting environmentally sound management principles.

Feasibility analysis of recycling radioactive scrap steel

International Nuclear Information System (INIS)

Nichols, F.; Balhiser, B.; Cignetti, N.

1995-09-01

The purpose of this study is to: (1) establish a conceptual design that integrates commercial steel mill technology with radioactive scrap metal (RSM) processing to produce carbon and stainless steel sheet and plate at a grade suitable for fabricating into radioactive waste containers; (2) determine the economic feasibility of building a micro-mill in the Western US to process 30,000 tons of RSM per year from both DOE and the nuclear utilities; and (3) provide recommendations for implementation. For purposes of defining the project, it is divided into phases: economic feasibility and conceptual design; preliminary design; detail design; construction; and operation. This study comprises the bulk of Phase 1. It is divided into four sections. Section 1 provides the reader with a complete overview extracting pertinent data, recommendations and conclusions from the remainder of the report. Section 2 defines the variables that impact the design requirements. These data form the baseline to create a preliminary conceptual design that is technically sound, economically viable, and capitalizes on economies of scale. Priorities governing the design activities are: (1) minimizing worker exposure to radionuclide hazards, (2) maximizing worker safety, (3) minimizing environmental contamination, (4) minimizing secondary wastes, and (5) establishing engineering controls to insure that the plant will be granted a license in the state selected for operation. Section 3 provides details of the preliminary conceptual design that was selected. The cost of project construction is estimated and the personnel needed to support the steel-making operation and radiological and environmental control are identified. Section 4 identifies the operational costs and supports the economic feasibility analysis. A detailed discussion of the resulting conclusions and recommendations is included in this section

Excess plutonium disposition using ALWR technology

International Nuclear Information System (INIS)

Phillips, A.; Buckner, M.R.; Radder, J.A.; Angelos, J.G.; Inhaber, H.

1993-02-01

The Office of Nuclear Energy of the Department of Energy chartered the Plutonium Disposition Task Force in August 1992. The Task Force was created to assess the range of practicable means of disposition of excess weapons-grade plutonium. Within the Task Force, working groups were formed to consider: (1) storage, (2) disposal,and(3) fission options for this disposition,and a separate group to evaluate nonproliferation concerns of each of the alternatives. As a member of the Fission Working Group, the Savannah River Technology Center acted as a sponsor for light water reactor (LWR) technology. The information contained in this report details the submittal that was made to the Fission Working Group of the technical assessment of LWR technology for plutonium disposition. The following aspects were considered: (1) proliferation issues, (2) technical feasibility, (3) technical availability, (4) economics, (5) regulatory issues, and (6) political acceptance

Melting of Grey Cast Iron Based on Steel Scrap Using Silicon Carbide

Directory of Open Access Journals (Sweden)

Stojczew A.

2014-08-01

Full Text Available The paper presents the issue of synthetic cast iron production in the electric induction furnace exclusively on the steel scrap base. Silicon carbide and synthetic graphite were used as carburizers. The carburizers were introduced with solid charge or added on the liquid metal surface. The chemical analysis of the produced cast iron, the carburization efficiency and microstructure features were presented in the paper. It was stated that ferrosilicon can be replaced by silicon carbide during the synthetic cast iron melting process. However, due to its chemical composition (30% C and 70% Si which causes significant silicon content in iron increase, the carbon deficit can be partly compensated by the carburizer introduction. Moreover it was shown that the best carbon and silicon assimilation rate is obtained where the silicon carbide is being introduced together with solid charge. When it is thrown onto liquid alloy surface the efficiency of the process is almost two times less and the melting process lasts dozen minutes long. The microstructure of the cast iron produced with the silicon carbide shows more bulky graphite flakes than inside the microstructure of cast iron produced on the pig iron base.

The detection and assessment of radioactive parts in scrap - a technical and legal challenge

International Nuclear Information System (INIS)

Rieck, W.

1999-01-01

According to the requirements of the European steel industry, delivery of radioactive contaminated metallurgical scrap in excess of natural level has to be excluded. Therefore, in Germany alone, more than 100 high-sensitive gate monitors were installed during the last few years at steel mills and scrap handling facilities. This has resulted in not only tighter protection from an erroneous melting of radioactive sources but also in a great increase in number of reported findings than before. Aside from a small number of sealed sources, the majority of detections concern natural radioactive scale and contamination, mostly from fission and activation products as well as traces of nuclear fuel. Practical and legal problems regarding the application of the regulations on radioactivity protection are demonstrated and discussed. (author)

Report on joint research in fiscal 1999. Research and development of technology to promote recycling of non-ferrous metal materials (Report on achievement in researches of demonstration tests and total system technology); 1999 nendo hitetsu kinzokukei sozai recycle sokushin gijutsu seika hokokusho. Jissho shiken kenkyu, total system gijutsu

Energy Technology Data Exchange (ETDEWEB)

NONE

2000-03-01

Development has been in progress on promotion of recycling the non-ferrous metal materials, particularly aluminum, base metals and rare metals (such as copper). For aluminum, researches were made on demonstration of the crystal separation process, vacuum deposition process, molten scrap cleaning technology, and residual dross utilizing technology. In the crystal separation process to remove Fe and Si, and the vacuum deposition process to remove Zn, trial operation and adjustments were performed on the demonstration and testing facilities, making simulation in the scale of 1000 tons a month possible. In the molten scrap cleaning technology, discussions were given on a method to install on the trough a filter permitting micro inclusions in the molten scrap, but no results as have been expected were obtained. The residual dross was used on a trial basis for applications such as road aggregate and refractory materials. In the exhaust treatment, it was recognized effective that activated carbon and slaked lime are used simultaneously to remove hydrochloric acid and dioxins. In developing a technology to regenerate high-grade copper from sludge dust, discussions were given on design, fabrication, and trial operation of the demonstration facilities, partly by using a demonstration plant, with regard to the five related technologies including a technology for high precision refining of scraps, and high-speed metal melting technology. (NEDO)

Signs, dispositions, and semiotic scaffolding.

Science.gov (United States)

Fernández, Eliseo

2015-12-01

In theoretical work we distinguish living beings from inanimate objects on the basis of some paramount attributes, such as agency and autonomy. These abstract features are not directly accessible to our scrutiny, but we surmise their nature through observation of the purpose-oriented behavior of organisms. I intend to show that organismal purposefulness springs from the intrinsic, constitutive kind of finality that is the hallmark of all semiotic transactions. To this aim I develop a dispositionalist account of organismal causation based on a distinction between two kinds of causal dispositions: fixed (efficient) dispositions and traveling dispositions. Fixed dispositions are rigidly attached to physical structures and processes; these are the dispositions regularly invoked in current discussions of causal explanation. Traveling dispositions are able to move freely from one location to another by becoming embodied into suitable supporting media. I introduce these notions to articulate a view of semiosis I deem best suited to the life sciences, and contend that sign tokens are vehicles of traveling dispositions. This account places the origin of purposive behavior at the interaction of physical and semiotic causation. To properly motivate the discussion I briefly review some recent developments in the philosophy of science concerning various forms of causation invoked by scientists across disciplines to frame explanations and make predictions. The ensuing discussion gives particular prominence to mechanistic (as distinct from mechanicist) explanatory accounts of biological phenomena. This review is followed by a brief characterization of a "nomological machine," a comprehensive schema introduced and developed by Nancy Cartwright with the goal of explaining causal mechanisms in a general setting. By capitalizing on this model's heuristic virtues I seek to formulate a compelling view of the interactions between physical and semiotic causation at play in semiotic

The personal dispositions of violent extremism

Directory of Open Access Journals (Sweden)

Davydov D.G.

2017-04-01

Full Text Available The paper presents the differences in the nature of extremism and radicalism, and the necessity of introducing the concept of "violent extremism." It is shown that the ideology is the explanation of extremist behavior, rather than its cause. The ideology of extremism often eclectic, contradictory and can easily be transformed by changing the object of hostility, depending on the situation. For the description of the psychological causes of extremism it is proposed to use the concept of personal disposition. Disposition is the preferred way to subjective interpretation of reality and reflects both the specific needs of a person as well the typical social situations where it realized and personal experience. Considered the following dispositions of violent extremism: the Cult of force and aggression, Intolerance, Out-group hostility Conventional coercion, Social pessimism and destructiveness, Mystical, Fighting and overcoming, Nihilism to law, Anti-subjectivism. It is proposed to use these dispositions as diagnostic criteria and for preventing and correcting.

12 CFR 34.83 - Disposition of real estate.

Science.gov (United States)

2010-01-01

... 12 Banks and Banking 1 2010-01-01 2010-01-01 false Disposition of real estate. 34.83 Section 34.83 Banks and Banking COMPTROLLER OF THE CURRENCY, DEPARTMENT OF THE TREASURY REAL ESTATE LENDING AND APPRAISALS Other Real Estate Owned § 34.83 Disposition of real estate. (a) Disposition. A national bank may...

Chemical Disposition of Plutonium in Hanford Site Tank Wastes

Energy Technology Data Exchange (ETDEWEB)

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

2015-05-07

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

Disintegration and size reduction of slags and metals after melt refining of contaminated metallic wastes

International Nuclear Information System (INIS)

Heshmatpour, B.; Copeland, G.L.; Heestand, R.L.

1981-04-01

Melting under an oxidizing slag is an attractive method of decontaminating and reducing the volume of radioactively contaminated metal scrap. The contaminants are concentrated in a relatively small volume of slag, which leaves the metal essentially clean. A potential method of permanently disposing of the resulting slags (and metals if necessary) is emplacing them into deep shale by grout hydrofracture. Suspension in grout mixtures requires that the slag and metal be granular. The feasibility of size-reducing slags and disintegrating metals and subsequently incorporating both into grout mixtures was demonstrated. Various types of slags were crushed with a small jaw crusher into particles smaller than 3 mm. Several metals were also melted and water-blasted into coarse metal powder or shot ranging in size from 0.05 to 3 mm. A simple low-pressure water atomizer having a multiple nozzle with a converging-line jet stream was developed and used for this purpose. No significant slag dust and steam were generated during slag crushing and liquid-metal water-blasting tests, indicating that contamination can be well contained within the system. The crushed slags and the coarse metal powders were suspendable in group fluids, which indicates probable disposability by shale hydrofracture. The granulation of slags and metals facilitates their containment, transport, and storage

Effects of slag composition and process variables on decontamination of metallic wastes by melt refining

International Nuclear Information System (INIS)

Heshmatpour, B.; Copeland, G.L.

1981-01-01

Melt refining has been suggested as an alternative for decontamination and volume reduction of low-level-contaminated metallic wastes. Knowledge of metallurgical and thermochemical aspects of the process is essential for effective treatment of various metals. Variables such as slag type and composition, melting technique, and refractory materials need to be identified for each metal or alloy. Samples of contaminated metals were melted with fluxes by resistance furnace or induction heating. The resulting ingots as well as the slags were analyzed for their nuclide contents, and the corresponding partition ratios were calculated. Compatibility of slags and refractories was also investigated, and proper refractory materials were identified. Resistance furnace melting appeared to be a better melting technique for nonferrous scrap, while induction melting was more suitable for ferrous metals. In general uranium contents of the metals, except for aluminum, could be reduced to as low as 0.01 to 0.1 ppM by melt refining. Aluminum could be decontaminated to about 1 to 2 ppM U when certain fluoride slags were used. The extent of decontamination was not very sensitive to slag type and composition. However, borosilicate and basic oxidizing slags were more effective on ferrous metals and Cu; NaNO 3 -NaCl-NaOH type fluxes were desirable for Zn, Pb, and Sn; and fluoride type slags were effective for decontamination of Al. Recrystallized alumina proved to be the most compatible refractory for melt refining both ferrous and nonferrous metals, while graphite was suitable for nonferrous metal processing. In conclusion, melt refining is an effective technique for volume reduction ad decontamination of contaminated metal scrap when proper slags, melting technique, and refractories are used

Overview of surplus weapons plutonium disposition

Energy Technology Data Exchange (ETDEWEB)

Rudy, G.

1996-05-01

The safe disposition of surplus weapons useable plutonium is a very important and urgent task. While the functions of long term storage and disposition directly relate to the Department`s weapons program and the environmental management program, the focus of this effort is particularly national security and nonproliferation.

NRC comprehensive records disposition schedule. Revision 3

International Nuclear Information System (INIS)

1998-02-01

Title 44 US Code, ''Public Printing and Documents,'' regulations issued by the General Service Administration (GSA) in 41 CFR Chapter 101, Subchapter B, ''Management and Use of Information and Records,'' and regulations issued by the National Archives and Records Administration (NARA) in 36 CFR Chapter 12, Subchapter B, ''Records Management,'' require each agency to prepare and issue a comprehensive records disposition schedule that contains the NARA approved records disposition schedules for records unique to the agency and contains the NARA's General Records Schedules for records common to several or all agencies. The approved records disposition schedules specify the appropriate duration of retention and the final disposition for records created or maintained by the NRC. NUREG-0910, Rev. 3, contains ''NRC's Comprehensive Records Disposition Schedule,'' and the original authorized approved citation numbers issued by NARA. Rev. 3 incorporates NARA approved changes and additions to the NRC schedules that have been implemented since the last revision dated March, 1992, reflects recent organizational changes implemented at the NRC, and includes the latest version of NARA's General Records Schedule (dated August 1995)

NRC comprehensive records disposition schedule. Revision 3

Energy Technology Data Exchange (ETDEWEB)

NONE

1998-02-01

Title 44 US Code, ``Public Printing and Documents,`` regulations issued by the General Service Administration (GSA) in 41 CFR Chapter 101, Subchapter B, ``Management and Use of Information and Records,`` and regulations issued by the National Archives and Records Administration (NARA) in 36 CFR Chapter 12, Subchapter B, ``Records Management,`` require each agency to prepare and issue a comprehensive records disposition schedule that contains the NARA approved records disposition schedules for records unique to the agency and contains the NARA`s General Records Schedules for records common to several or all agencies. The approved records disposition schedules specify the appropriate duration of retention and the final disposition for records created or maintained by the NRC. NUREG-0910, Rev. 3, contains ``NRC`s Comprehensive Records Disposition Schedule,`` and the original authorized approved citation numbers issued by NARA. Rev. 3 incorporates NARA approved changes and additions to the NRC schedules that have been implemented since the last revision dated March, 1992, reflects recent organizational changes implemented at the NRC, and includes the latest version of NARA`s General Records Schedule (dated August 1995).

Considerations for Disposition of Dry Cask Storage System Materials at End of Storage System Life

International Nuclear Information System (INIS)

Howard, Rob; Van den Akker, Bret

2014-01-01

Dry cask storage systems are deployed at nuclear power plants for used nuclear fuel (UNF) storage when spent fuel pools reach their storage capacity and/or the plants are decommissioned. An important waste and materials disposition consideration arising from the increasing use of these systems is the management of the dry cask storage systems' materials after the UNF proceeds to disposition. Thermal analyses of repository design concepts currently under consideration internationally indicate that waste package sizes for the geologic media under consideration may be significantly smaller than the canisters being used for on-site dry storage by the nuclear utilities. Therefore, at some point along the UNF disposition pathway, there could be a need to repackage fuel assemblies already loaded into the dry storage canisters currently in use. In the United States, there are already over 1650 of these dry storage canisters deployed and approximately 200 canisters per year are being loaded at the current fleet of commercial nuclear power plants. There is about 10 cubic meters of material from each dry storage canister system that will need to be dispositioned. The concrete horizontal storage modules or vertical storage overpacks will need to be reused, re-purposed, recycled, or disposed of in some manner. The empty metal storage canister/cask would also have to be cleaned, and decontaminated for possible reuse or recycling or disposed of, likely as low-level radioactive waste. These material disposition options can have impacts of the overall used fuel management system costs. This paper will identify and explore some of the technical and interface considerations associated with managing the dry cask storage system materials. (authors)

Metal recycling - a renewable resource in Gulf Cooperative Countries region

Energy Technology Data Exchange (ETDEWEB)

Kassem, M.E. [Bahrain Univ. (Bahrain). Dept. of Chemical Engineering

1995-12-01

The exhaustion of natural resources and growing environmental awareness highlighted the necessity of metal recycling all over the world. The production/consumption activities in the GCC region do generate annually a huge amount of valuable ferrous and nonferrous metal scrap. This paper deals with the benefits of metal recycling to the GCC region in lights of energetic, environmental and economic points of view. (orig.) [Deutsch] Die abnehmenden Vorraete von Primaermetallen sowie das zunehmende Umweltbewusstsein machen das Metall-Recycling auf der ganzen Welt notwendig. Die Produktions- und Verbrauchsaktivitaeten in der GCC-Region erzeugen jaehrlich riesige Mengen von wertvollem eisen- und nicht eisenhaltigen Schrott. Dieser Beitrag befasst sich mit dem Energie-Verbrauch, dem Umweltschutz und der Wirtschaft des Recycling und stellt dessen Vorteile fuer die GCC-Region vor. (orig.)

Proposed industrial recovered materials utilization targets for the metals and metal-products industry

Energy Technology Data Exchange (ETDEWEB)

None

1979-05-01

The introductory chapter provides a discussion of the factors that affect the recovery and reuse of secondary materials and the competition between the primary and secondary metals industries. It discusses these industries in terms of resource characteristics, industry technology, pollution control requirements, market structure, the economics of recycling, and the issues involved in econometrically estimating scrap supply response behavior. It further presents the methodology established by DOE for the metals, textiles, rubber, and pulp and paper industries. The areas in which government policies might have a significant impact on the utilization of primary and secondary metals and on any recycling targets between now and 1987 are noted. Chapter 3 presents general profiles for the major industrial segments comprising SIC 33. The profiles include such topics as industry structure, process technology, materials and recycling flow, and future trends. Chapter 4 specifically covers the evaluation of recycling targets for the ferrous, aluminum, copper, zinc, and lead industries. (MCW)

The Scrap Collection per Industry Sector and the Circulation Times of Steel in the U.S. between 1900 and 2016, Calculated Based on the Volume Correlation Model

Directory of Open Access Journals (Sweden)

Alicia Gauffin

2018-05-01

Full Text Available On the basis of the Volume Correlation Model (VCM as well as data on steel consumption and scrap collection per industry sector (construction, automotive, industrial goods, and consumer goods, it was possible to estimate service lifetimes of steel in the United States between 1900 and 2016. Input data on scrap collection per industry sector was based on a scrap survey conducted by the World Steel Association for a static year in 2014 in the United States. The lifetimes of steel calculated with the VCM method were within the range of previously reported measured lifetimes of products and applications for all industry sectors. Scrapped (and apparent lifetimes of steel compared with measured lifetimes were calculated to be as follows: a scrapped lifetime of 29 years for the construction sector (apparent lifetime: 52 years compared with 44 years measured in 2014. Industrial goods: 16 (27 years compared with 19 years measured in 2010. Consumer goods: 12 (14 years compared with 13 years measured in 2014. Automotive sector: 14 (19 years compared with 17 years measured in 2011. Results show that the VCM can estimate reasonable values of scrap collection and availability per industry sector over time.

Characteristics of Indium Tin Oxide (ITO Nanoparticles Recovered by Lift-off Method from TFT-LCD Panel Scraps

Directory of Open Access Journals (Sweden)

Dongchul Choi

2014-11-01

Full Text Available In this study, indium-tin-oxide (ITO nanoparticles were simply recovered from the thin film transistor-liquid crystal display (TFT-LCD panel scraps by means of lift-off method. This can be done by dissolving color filter (CF layer which is located between ITO layer and glass substrate. In this way the ITO layer was easily lifted off the glass substrate of the panel scrap without panel crushing. Over 90% of the ITO on the TFT-LCD panel was recovered by using this method. After separating, the ITO was obtained as particle form and their characteristics were investigated. The recovered product appeared as aggregates of particles less than 100 nm in size. The weight ratio of In/Sn is very close to 91/9. XRD analysis showed that the ITO nanoparticles have well crystallized structures with (222 preferred orientation even after recovery. The method described in this paper could be applied to the industrial recovery business for large size LCD scraps from TV easily without crushing the glass substrate.

Linguistic variables, approximate reasoning and dispositions

Energy Technology Data Exchange (ETDEWEB)

Zadeh, L.A.

1983-07-01

Test-score semantics is applied to the representation of meaning of dispositions, that is, propositions with suppressed fuzzy quantifiers, e.g. overeating causes obesity, icy roads are slippery, young men like young women, etc. The concept of a disposition plays an especially important role in the representation of commonsense knowledge. 45 references.

The Dual Effects of Critical Thinking Disposition on Worry

Science.gov (United States)

Sugiura, Yoshinori

2013-01-01

This study investigated the relationship between disposition (people’s consistent motivation) toward critical thinking (CT) and worrying. In spite of its connection to psychopathology, worry is thought to represent an effort at problem-solving. Moreover, worry has been found to be underpinned by cognitive development, leading us to predict a positive relationship between worry and CT disposition. On the other hand, cognitive behavioral therapy, which involves techniques similar to CT, has been shown to be effective in reducing worrying, suggesting that increasing CT disposition decreases worrying. This study attempted to reconcile these seemingly contrasting predictions about the relationship between CT disposition and worrying by using multiple mediator analysis. A model was proposed wherein the mediators, responsibility to continue thinking and detached awareness of negative thinking, were related to two opposing predictions. The former is thought to lead to enhanced worrying and the latter to reduced worrying, with both positively related to CT disposition. A questionnaire study with university students (N = 760) revealed that CT disposition enhanced worrying by obliging people to continue thinking about a problem, but that it also reduced worrying by enhancing the detached and objective awareness of their negative thoughts. This study thus demonstrated the dual effects of CT disposition on worrying through different mediators. Thus, when enhancing CT disposition, it is important for educators to be aware of possible disadvantages apart from its worry-reducing effect. Future studies should therefore examine the underlying mechanisms of these two effects of CT disposition. PMID:24278160

Disposition of excess weapons plutonium from dismantled weapons

International Nuclear Information System (INIS)

Jardine, L.J.

1997-01-01

With the end of the Cold War and the implementation of various nuclear arms reduction agreements, US and Russia have been actively dismantling tens of thousands of nuclear weapons. As a result,large quantities of fissile materials, including more than 100 (tonnes?) of weapons-grade Pu, have become excess to both countries' military needs. To meet nonproliferation goals and to ensure the irreversibility of nuclear arms reductions, this excess weapons Pu must be placed in secure storage and then, in timely manner, either used in nuclear reactors as fuel or discarded in geologic repositories as solid waste. This disposition in US and Russia must be accomplished in a safe, secure manner and as quickly as practical. Storage of this Pu is a prerequisite to any disposition process, but the length of storage time is unknown. Whether by use as fuel or discard as solid waste, disposition of that amount of Pu will require decades--and perhaps longer, if disposition operations encounter delays. Neither US nor Russia believes that long-term secure storage is a substitute for timely disposition of excess Pu, but long-term, safe, secure storage is a critical element of all excess Pu disposition activities

Statistical modeling to management and treatment of scrap with low and very low residual activity; Hacia la modelizacion estadistica de la gestion y tratamiento de chatarras con baja y muy bajo actividad residual

Energy Technology Data Exchange (ETDEWEB)

Garcia-Bermejo Fernandez, R.; Anaya Lazaro, M.

2011-07-01

The experience of recent years on the management of scrap metal containing residual activity have allowed the development of a simple statistical model for the management of these materials. This statistical model includes a breakdown of the various processing operations to which these materials undergo and the effects in the process of radiological controls associated to the control of declassification that defines disposal (recycled by smelting, reclamation, temporary storage the plant or sent to final storage of radioactive waste).

A proposal for prevention of acute radiation hazard and social panic regarding orphan sources in Japan

Energy Technology Data Exchange (ETDEWEB)

Takahash, T. [Research Reactor Institute, Kyoto Univ., Osaka (Japan); Kai, M. [Oita Univ., of Nursing and Health Sciences, Oita (Japan); Yamazaki, K. [Chiyoda Technol Corporation, Tokyo (Japan); Gomi, K. [Japan Radioisotope Association, Tokyo (Japan); Nakazato, K. [School of Medicine, Keio univ., Tokyo (Japan); Iida, T. [Nagoya Univ., Nagoya (Japan)

2002-07-01

To respond to an increase of social problems concerning orphan sources in Japan, a working group was formed in the Japan Health Physics Society. In this working group, we investigated how to prevent acute radiation hazard or social panic regarding orphan sources in scrap metal and detection system for orphan sources brought into scrap yards before recycle. For detection system in a scrap yard we conducted an experiment on detectability of monitoring instrument using a radiation source mixed in scrap metal on a truck. The result showed that it was not easy to detect even a high-level source if it was shielded by scrap metal. We also estimated detection limits for radioactive materials in scrap metal by calculation that was validated with experimental data. We summarized present status about orphan sources in Japan and proposed a categorization of orphan sources according to dose rates to deal with unknown sources in a scrap yard. Our report includes some proposals to the government, industry and academic world for preventing acute radiation hazard and social panic.

A proposal for prevention of acute radiation hazard and social panic regarding orphan sources in Japan

International Nuclear Information System (INIS)

Takahash, T.; Kai, M.; Yamazaki, K.; Gomi, K.; Nakazato, K.; Iida, T.

2002-01-01

To respond to an increase of social problems concerning orphan sources in Japan, a working group was formed in the Japan Health Physics Society. In this working group, we investigated how to prevent acute radiation hazard or social panic regarding orphan sources in scrap metal and detection system for orphan sources brought into scrap yards before recycle. For detection system in a scrap yard we conducted an experiment on detectability of monitoring instrument using a radiation source mixed in scrap metal on a truck. The result showed that it was not easy to detect even a high-level source if it was shielded by scrap metal. We also estimated detection limits for radioactive materials in scrap metal by calculation that was validated with experimental data. We summarized present status about orphan sources in Japan and proposed a categorization of orphan sources according to dose rates to deal with unknown sources in a scrap yard. Our report includes some proposals to the government, industry and academic world for preventing acute radiation hazard and social panic

Proliferation resistance criteria for fissile material disposition

International Nuclear Information System (INIS)

Close, D.A.; Fearey, B.L.; Markin, J.T.; Rutherford, D.A.; Duggan, R.A.; Jaeger, C.D.; Mangan, D.L.; Moya, R.W.; Moore, L.R.; Strait, R.S.

1995-04-01

The 1994 National Academy of Sciences study open-quotes Management and Disposition of Excess Weapons Plutoniumclose quotes defined options for reducing the national and international proliferation risks of materials declared excess to the nuclear weapons program. This report proposes criteria for assessing the proliferation resistance of these options. The criteria are general, encompassing all stages of the disposition process from storage through intermediate processing to final disposition including the facilities, processing technologies and materials, the level of safeguards for these materials, and the national/subnational threat to the materials

Evaluation of Calcine Disposition Path Forward

International Nuclear Information System (INIS)

Birrer, S.A.; Heiser, M.B.

2003-01-01

This document describes an evaluation of the baseline and two alternative disposition paths for the final disposition of the calcine wastes stored at the Idaho Nuclear Technology and Engineering Center at the Idaho National Engineering and Environmental Laboratory. The pathways are evaluated against a prescribed set of criteria and a recommendation is made for the path forward

USING THE SCRAP TIRES TO PRODUCE A FLEXIBLE COUPLER

OpenAIRE

Tahsean A. Hussain

2018-01-01

The scrap tires considered a problematic source of waste, the old rubber tires causes a big environmental problem that is need much money and effort to disposes it safely. In Iraq there are more than two million used tires disposed to the environment annually. one of the tire’s recycling methods is the use of tire layers to produce a new rubber parts used in the engineering and industrial purposes as the bridges and machines dampers, this trend of recycling doesn’t take a sufficient care comp...

50 CFR 30.2 - Disposition of surplus range animals.

Science.gov (United States)

2010-10-01

... 50 Wildlife and Fisheries 6 2010-10-01 2010-10-01 false Disposition of surplus range animals. 30.2... (CONTINUED) THE NATIONAL WILDLIFE REFUGE SYSTEM RANGE AND FERAL ANIMAL MANAGEMENT Range Animals § 30.2 Disposition of surplus range animals. Disposition shall be made only during regularly scheduled disposal...

DISPOSITION PATHS FOR ROCKY FLATS GLOVEBOXES: EVALUATING OPTIONS

International Nuclear Information System (INIS)

Lobdell, D.; Geimer, R.; Larsen, P.; Loveland, K.

2003-01-01

The Kaiser-Hill Company, LLC has the responsibility for closure activities at the Rocky Flats Environmental Technology Site (RFETS). One of the challenges faced for closure is the disposition of radiologically contaminated gloveboxes. Evaluation of the disposition options for gloveboxes included a detailed analysis of available treatment capabilities, disposal facilities, and lifecycle costs. The Kaiser-Hill Company, LLC followed several processes in determining how the gloveboxes would be managed for disposition. Currently, multiple disposition paths have been chosen to accommodate the needs of the varying styles and conditions of the gloveboxes, meet the needs of the decommissioning team, and to best manage lifecycle costs. Several challenges associated with developing a disposition path that addresses both the radiological and RCRA concerns as well as offering the most cost-effective solution were encountered. These challenges included meeting the radiological waste acceptance criteria of available disposal facilities, making a RCRA determination, evaluating treatment options and costs, addressing void requirements associated with disposal, and identifying packaging and transportation options. The varying disposal facility requirements affected disposition choices. Facility conditions that impacted decisions included radiological and chemical waste acceptance criteria, physical requirements, and measurement for payment options. The facility requirements also impacted onsite activities including management strategies, decontamination activities, and life-cycle cost

Fuzzy chance constrained linear programming model for scrap charge optimization in steel production

DEFF Research Database (Denmark)

Rong, Aiying; Lahdelma, Risto

2008-01-01

the uncertainty based on fuzzy set theory and constrain the failure risk based on a possibility measure. Consequently, the scrap charge optimization problem is modeled as a fuzzy chance constrained linear programming problem. Since the constraints of the model mainly address the specification of the product...

Application and feasibility of coal fly ash and scrap tire fiber as wood wall insulation supplements in residential buildings

Energy Technology Data Exchange (ETDEWEB)

Van de Lindt, J.W.; Carraro, J.A.H.; Heyliger, P.R.; Choi, C. [Colorado State University, Department of Civil and Environmental Engineering, Fort Collins, CO (United States)

2008-08-15

Each year, nearly 55% of the fly ash (FA) produced by coal burning power plants in the United States is disposed of in landfills and ash ponds, while the amount of recycled fiber from scrap tires that is beneficially used in end-user markets is virtually negligible. This paper presents the results of a study carried out to investigate whether it might be possible to increase the thermal efficiency of a light-frame residential structure through addition of a fly ash-scrap tire fiber composite to traditional fiberglass insulation in light-frame wood residential construction. This type of construction represents more than 80% of the building stock in North America. The results of this study suggest that the fly ash-scrap tire fiber composite provides a sustainable supplement to traditional insulation that not only increases the efficiency of traditional insulation but can also help significantly reduce the environmental issues associated with disposal of these waste products. (author)

Application and feasibility of coal fly ash and scrap tire fiber as wood wall insulation supplements in residential buildings

International Nuclear Information System (INIS)

Van de Lindt, J.W.; Carraro, J.A.H.; Heyliger, P.R.; Choi, C.

2008-01-01

Each year, nearly 55% of the fly ash (FA) produced by coal burning power plants in the United States is disposed of in landfills and ash ponds, while the amount of recycled fiber from scrap tires that is beneficially used in end-user markets is virtually negligible. This paper presents the results of a study carried out to investigate whether it might be possible to increase the thermal efficiency of a light-frame residential structure through addition of a fly ash-scrap tire fiber composite to traditional fiberglass insulation in light-frame wood residential construction. This type of construction represents more than 80% of the building stock in North America. The results of this study suggest that the fly ash-scrap tire fiber composite provides a sustainable supplement to traditional insulation that not only increases the efficiency of traditional insulation but can also help significantly reduce the environmental issues associated with disposal of these waste products. (author)

The regulatory action in the problem of radioactive sources processed as scrap

International Nuclear Information System (INIS)

Truppa, Walter Adrian; Cateriano, Miguel Angel

2005-01-01

The loss of control of a radioactive source can result in a radiological emergency, especially if that source is treated as scrap. This paper presents a case registered in Argentina about discovery of a radioactive source of Kr-85, 9.25 GBq, used in a computer for industrial measurement of thickness. The radioactive source, without registration or identification, was registered by a portal for detection of radioactive material in the middle of the scrap that entered daily in the oven of a important steel company. From there, the Nuclear Regulatory Authority (RNA) conducted an investigation to determine the origin of the radioactive source, and in parallel made, in the laboratories of measurement, identification of radioactive material inside the source. This led to a company in financial and judicial bankruptcy, which had not notified the RNA about this situation, and also possessed, according to records, other eleven sources with similar characteristics. Finally the actions and regulatory effort allowed the localization of all the radioactive sources of this company, and its storage and deposit in an authorised repository

The association between resting functional connectivity and dispositional optimism.

Science.gov (United States)

Ran, Qian; Yang, Junyi; Yang, Wenjing; Wei, Dongtao; Qiu, Jiang; Zhang, Dong

2017-01-01

Dispositional optimism is an individual characteristic that plays an important role in human experience. Optimists are people who tend to hold positive expectations for their future. Previous studies have focused on the neural basis of optimism, such as task response neural activity and brain structure volume. However, the functional connectivity between brain regions of the dispositional optimists are poorly understood. Previous study suggested that the ventromedial prefrontal cortex (vmPFC) are associated with individual differences in dispositional optimism, but it is unclear whether there are other brain regions that combine with the vmPFC to contribute to dispositional optimism. Thus, the present study used the resting-state functional connectivity (RSFC) approach and set the vmPFC as the seed region to examine if differences in functional brain connectivity between the vmPFC and other brain regions would be associated with individual differences in dispositional optimism. The results found that dispositional optimism was significantly positively correlated with the strength of the RSFC between vmPFC and middle temporal gyrus (mTG) and negativly correlated with RSFC between vmPFC and inferior frontal gyrus (IFG). These findings may be suggested that mTG and IFG which associated with emotion processes and emotion regulation also play an important role in the dispositional optimism.

The association between resting functional connectivity and dispositional optimism.

Directory of Open Access Journals (Sweden)

Qian Ran

Full Text Available Dispositional optimism is an individual characteristic that plays an important role in human experience. Optimists are people who tend to hold positive expectations for their future. Previous studies have focused on the neural basis of optimism, such as task response neural activity and brain structure volume. However, the functional connectivity between brain regions of the dispositional optimists are poorly understood. Previous study suggested that the ventromedial prefrontal cortex (vmPFC are associated with individual differences in dispositional optimism, but it is unclear whether there are other brain regions that combine with the vmPFC to contribute to dispositional optimism. Thus, the present study used the resting-state functional connectivity (RSFC approach and set the vmPFC as the seed region to examine if differences in functional brain connectivity between the vmPFC and other brain regions would be associated with individual differences in dispositional optimism. The results found that dispositional optimism was significantly positively correlated with the strength of the RSFC between vmPFC and middle temporal gyrus (mTG and negativly correlated with RSFC between vmPFC and inferior frontal gyrus (IFG. These findings may be suggested that mTG and IFG which associated with emotion processes and emotion regulation also play an important role in the dispositional optimism.

Dispositions, Emotions, Episodes and the Autonomous Learner.

Science.gov (United States)

Wesson, Anthony J.

1986-01-01

Explores the relationship between dispositions (i.e., continuities of inclinations and habits), episodic behavior, emotions, and desires; and the development of moral autonomy. Argues that autonomy requires a settled disposition toward the good. Contrasts theories of autonomy based on wants/desires and on ideals. (AYC)

Classification of scrap material from nuclear power plants as acceptable for recirculation

International Nuclear Information System (INIS)

Bergman, C.

1983-06-01

The Swedish National Institute of Radiation Protection has in a principal decision accepted that scrap material from nuclear power plants, that contains or may contain radioactive material, can be recirculated. The document is an English translation of the background material for the Board meeting decision and gives some guide-lines for the authority when dealing with this questions. (author)

Method of handling of scrap lead from lead-acid batteries

Energy Technology Data Exchange (ETDEWEB)

Sytschev, A P; Kim, G V; Larin, V F; Sidorova, G D; Vicharev, I G; Kuur, V P; Achmetov, R S; Moiseev, G L; Maslov, V I; Kabatschek, V G

1979-12-13

Scrap lead and the casings of accumulators are mined and molten together in oxidixing atmosphere at a temperature of 1300 to 1500/sup 0/C. The lead oxide contained in the melt is then reduced to blue lead. Due to the combustion of the accumulator casings consisting of organic substances the fuel consumption in the melting process is reduced in accordance. The oxidizing atmosphere in the melting process is produced by use of air or oxygen.

Dispositional Optimism and Therapeutic Expectations in Early Phase Oncology Trials

Science.gov (United States)

Jansen, Lynn A.; Mahadevan, Daruka; Appelbaum, Paul S.; Klein, William MP; Weinstein, Neil D.; Mori, Motomi; Daffé, Racky; Sulmasy, Daniel P.

2016-01-01

Purpose Prior research has identified unrealistic optimism as a bias that might impair informed consent among patient-subjects in early phase oncology trials. Optimism, however, is not a unitary construct – it can also be defined as a general disposition, or what is called dispositional optimism. We assessed whether dispositional optimism would be related to high expectations for personal therapeutic benefit reported by patient-subjects in these trials but not to the therapeutic misconception. We also assessed how dispositional optimism related to unrealistic optimism. Methods Patient-subjects completed questionnaires designed to measure expectations for therapeutic benefit, dispositional optimism, unrealistic optimism, and the therapeutic misconception. Results Dispositional optimism was significantly associated with higher expectations for personal therapeutic benefit (Spearman r=0.333, poptimism was weakly associated with unrealistic optimism (Spearman r=0.215, p=0.005). In multivariate analysis, both dispositional optimism (p=0.02) and unrealistic optimism (poptimism (p=.0001), but not dispositional optimism, was independently associated with the therapeutic misconception. Conclusion High expectations for therapeutic benefit among patient-subjects in early phase oncology trials should not be assumed to result from misunderstanding of specific information about the trials. Our data reveal that these expectations are associated with either a dispositionally positive outlook on life or biased expectations about specific aspects of trial participation. Not all manifestations of optimism are the same, and different types of optimism likely have different consequences for informed consent in early phase oncology research. PMID:26882017

Health physics challenges during decontamination for safe disposal of low level liquid effluent tank as inactive scrap

International Nuclear Information System (INIS)

Akila, R.; Sultan, Bajeer; Sarangapani, R.; Jose, M.T.

2018-01-01

The Low-level Liquid waste (LLW) generated during the regeneration of mixed bed column of KAMINI reactor is collected in the SS Delay Tanks located on the western side of RML building. It was proposed to dismantle and dispose the tank as solid waste. The tank weighs about 2 ton. An attempt was made to decontaminate the tank to levels below the exempt quantity so as to qualify it as scrap of unrestricted release. This is first time in IGCAR wherein a material used in a radioactive facility for storing LLW is being released as scrap of unrestricted release and this paper discusses about the same

Measuring the Multicultural Dispositions of Preservice Teachers

Science.gov (United States)

Jensen, Bryant; Whiting, Erin Feinauer; Chapman, Sara

2018-01-01

Claims abound in the research literature regarding multicultural teacher dispositions, including how to foster them in teacher preparation programs. However, measures of multicultural dispositions of teachers that (a) capture the range of conceptually rich constructs and (b) demonstrate strong psychometric properties are not represented in the…

Metal Vapor Arcing Risk Assessment Tool

Science.gov (United States)

Hill, Monika C.; Leidecker, Henning W.

2010-01-01

The Tin Whisker Metal Vapor Arcing Risk Assessment Tool has been designed to evaluate the risk of metal vapor arcing and to help facilitate a decision toward a researched risk disposition. Users can evaluate a system without having to open up the hardware. This process allows for investigating components at risk rather than spending time and money analyzing every component. The tool points to a risk level and provides direction for appropriate action and documentation.

Development for recycle of dismantled metal wastes by decommissioning of NPP

International Nuclear Information System (INIS)

Asami, Tomohiro; Sato, Hiroshi; Hatakeyama, Mutsuo

2007-01-01

For recycle of dismantled metal wastes generated by the decommissioning of nuclear power plant, we examined a melting test for melting characterization of stainless steel scrap, designed the conceptual process to produce the recycle products, and developed a recycle cost evaluation code which is useful to make a rational planning for the waste management program (cost, determination of process, etc.) of these metal wastes. This report gives the summary of these development carried out from 2001 to 2005. This work was performed under the sponsorship of Ministry of Education, Culture, Sports, Science and Technology of Japan. (author)

31 CFR 501.727 - Motion for summary disposition.

Science.gov (United States)

2010-07-01

... party's arguments. Any party opposing a motion for summary disposition must file a statement setting... be supported by evidence of the same type as that submitted with the motion for summary disposition...

Experience with melting beta and gamma contaminated metals

International Nuclear Information System (INIS)

Feaugas, J.; Laplante, D.; Puechlong, Y.; Barbusse, R.

1994-01-01

Following a description of the melting facility operated for purposes of decommissioning the G2 and G3 gas-cooled reactors at Marcoule, the physical and radiological characteristics of 4070 tonnes of metal processed to date in the furnace are discussed. Considerable data have been recorded regarding operating and measurement procedures; the results show that secondary wastes account for less than 5 wt% of the processed scrap metal, and that all the 137 Cs is transferred to the dust and slag. During the last two months of 1993, the ingot mold line was replaced by rails on which dollies carrying integral work-form molds can be moved into position beneath the casting ladle. (authors). 21 figs

Obtaining of barium sulfate from solution formed after desulfation of the active mass of scrap lead-acid batteries

Directory of Open Access Journals (Sweden)

O. A. Kalko

2014-03-01

Full Text Available Analyses of literature data about processes for solution utilization formed after desulfation of the active mass of scrap lead-acid batteries is performed. Optimal conditions for obtaining of barium sulfate sediment from ammonium sulfate solute and chemically pure Ba(OH2×8H2O и BaCl2×2H2O were found experimentally. In laboratory the commercial barium sulfate from sulfate solutions, that are waste of recycling process of battery scrap, with application of chloride and barium hydroxide was production. The possibility of using this product were discussed.

Dispositions in Education: Nonentities Worth Talking about

Science.gov (United States)

Splitter, Laurance J.

2010-01-01

The concept of dispositions has commanded considerable attention in both philosophy and education. In this essay, Laurance Splitter draws on philosophy to take a fresh look at dispositions in education, specifically teacher education. Bypassing the pitfalls of both subjectivity and crude behaviorism, he proposes a conceptual framework in which…

Dispositional optimism and coping with pain.

Science.gov (United States)

Bargiel-Matusiewicz, K; Krzyszkowska, A

2009-12-07

The aim of this article is to analyze the relation between dispositional optimism and coping with chronic pain. The study seeks to define the relation between life orientation (optimism vs. pessimism) and coping with pain (believes about pain control and the choice of coping strategy). The following questionnaires were used: LOT-R - Life Orientation Test, BPCQ - The Beliefs about Pain Control Questionnaire and CSQ - The Pain Coping Strategies Questionnaire. The results show that dispositional optimism correlates positively with: internal locus of pain control r=0.6, Pr=0.38, Pr = 0.93, Pr = 0.82, Pr = -0.28, P<0.05. We conclude that dispositional optimism plays a key role in forming the mechanisms of coping with chronic pain and thereby in improving the psychophysical comfort of patients.

Dispositional optimism and therapeutic expectations in early-phase oncology trials.

Science.gov (United States)

Jansen, Lynn A; Mahadevan, Daruka; Appelbaum, Paul S; Klein, William M P; Weinstein, Neil D; Mori, Motomi; Daffé, Racky; Sulmasy, Daniel P

2016-04-15

Prior research has identified unrealistic optimism as a bias that might impair informed consent among patient-subjects in early-phase oncology trials. However, optimism is not a unitary construct; it also can be defined as a general disposition, or what is called dispositional optimism. The authors assessed whether dispositional optimism would be related to high expectations for personal therapeutic benefit reported by patient-subjects in these trials but not to the therapeutic misconception. The authors also assessed how dispositional optimism related to unrealistic optimism. Patient-subjects completed questionnaires designed to measure expectations for therapeutic benefit, dispositional optimism, unrealistic optimism, and the therapeutic misconception. Dispositional optimism was found to be significantly associated with higher expectations for personal therapeutic benefit (Spearman rank correlation coefficient [r], 0.333; Poptimism was found to be weakly associated with unrealistic optimism (Spearman r, 0.215; P = .005). On multivariate analysis, both dispositional optimism (P = .02) and unrealistic optimism (Poptimism (P = .0001), but not dispositional optimism, was found to be independently associated with the therapeutic misconception. High expectations for therapeutic benefit among patient-subjects in early-phase oncology trials should not be assumed to result from misunderstanding of specific information regarding the trials. The data from the current study indicate that these expectations are associated with either a dispositionally positive outlook on life or biased expectations concerning specific aspects of trial participation. Not all manifestations of optimism are the same, and different types of optimism likely have different consequences for informed consent in early-phase oncology research. © 2016 American Cancer Society.

Mission Need Statement: Calcine Disposition Project Major Systems Acquisition Project

International Nuclear Information System (INIS)

J. T. Beck

2007-01-01

This document identifies the need to establish the Calcine Disposition Project to determine and implement the final disposition of calcine including characterization, retrieval, treatment (if necessary), packaging, loading, onsite interim storage pending shipment to a repository or interim storage facility, and disposition of related facilities

Design and development of a cross-cultural disposition inventory

Science.gov (United States)

Davies, Randall; Zaugg, Holt; Tateishi, Isaku

2015-01-01

Advances in technology have increased the likelihood that engineers will have to work in a global, culturally diverse setting. Many schools of engineering are currently revising their curricula to help students to develop cultural competence. However, our ability to measure cultural dispositions can be a challenge. The purpose of this project was to develop and test an instrument that measures the various aspects of cultural disposition. The results of the validation process verified that the hypothesised model adequately represented the data. The refined instrument produced a four-factor model for the overall construct. The validation process for the instrument verified the existence of specific subcomponents that form the overall cultural disposition construct. There also seems to be a hierarchical relationship within the subcomponents of cultural disposition. Additional research is needed to explore which aspects of cultural disposition affect an individual's ability to work effectively in a culturally diverse engineering team.

Risk-based waste clearance concept for the D ampersand D program

International Nuclear Information System (INIS)

Chen, S.Y.; Bhattacharyya, S.K.

1996-01-01

Large amounts of radioactively contaminated wastes are expected to result from decontamination and decommissioning (D ampersand D) activities at nuclear facilities. Many of the waste materials, such as concrete rubble and scrap metals, are only slightly contaminated and can be recycled to minimize waste streams, resulting in substantial savings from reducing conventional waste disposal costs and recovering the values of the raw materials. For instance, a recent projection indicates that recycling an estimated 30 million tonnes of radioactive scrap metal (RSM) worldwide, having a corresponding recoverable value of about $10 billion to $20 billion, would avoid an estimated $5 billion in disposal costs. As an average heuristic, waste disposition constitutes ∼50% of total D ampersand D costs. There is thus a strong incentive to minimize the waste from D ampersand D activities. In the United States, no specific standards have been developed for the unrestricted release of bulk contaminated materials, although standards for the unrestricted release of radioactive surface contamination have existed for ∼20 yr. Materials are not commonly released because of the lack of risk-based justifications. Recent guidance from international bodies has established a basis for deriving risk-based release limits for radioactive materials. It is important, therefore, to evaluate the feasibility of recycling, because if it is feasible, risk-based release limits for the reusable materials will need to be established

Application of vacuum metallurgy to separate pure metal from mixed metallic particles of crushed waste printed circuit board scraps.

Science.gov (United States)

Zhan, Lu; Xu, Zhenming

2008-10-15

The principle of separating pure metal from mixed metallic particles (MMPs) byvacuum metallurgy is that the vapor pressures of various metals at the same temperature are different As a result, the metal with high vapor pressure and low boiling point can be separated from the mixed metals through distillation or sublimation, and then it can be recycled through condensation under a certain condition. The vacuum metallurgy separation (VMS) of MMPs of crushed waste printed circuit boards (WPCBs) has been studied in this paper. Theoretical analyses show that the MMPs (copper, zinc, bismuth, lead, and indium, for example) can be separated by vacuum metallurgy. The copper particles (0.15-0.20 mm) and zinc particles (<0.30 mm) were chosen to simulate the MMPs of crushed WPCBs. Experimental results show that the separated efficiency of zinc in the copper-rich particles achieves 96.19 wt % when the vacuum pressure is 0.01-0.10 Pa, the heating temperature is 1123 K, and the heating time is 105 min. Under this operation condition, the separated efficiency of zinc in the copper-rich particles from crushed WPCBs achieves 97.00 wt % and the copper purity increases from 90.68 to 99.84 wt %.

What’s in a Dog’s Breakfast? Considering the Social, Veterinary and Environmental Implications of Feeding Food Scraps to Pets Using Three Australian Surveys

Directory of Open Access Journals (Sweden)

Kirrilly Thompson

2015-06-01

Full Text Available Diverting food waste away from landfills is one way to minimise its serious environmental impact. Given that over a third of Australian households have at least one pet, the feeding of food waste to dogs constitutes one potentially significant waste diversion path. However, the proportion of dog owners that feed food waste to their pets is unknown. Moreover, there has been no investigation into any relationship between practices of feeding scraps to pets and the animals’ body condition, living arrangements (inside or outside and exercise regime. To provide some insight, this paper presents findings from three surveys across two Australian studies. The first reports both pet and dog-specific findings from two surveys within a wider food waste research project (n = 1017, establishing that 28% of respondents fed leftovers to pets as a main food waste minimization strategy, yet in only 5% of households did this constitute more than half of the household’s food scraps. This modest diversion of food scraps from landfill to feeding pets was reflected in the finding that there was no significant difference seen in the claimed level of food discards to the waste stream for households feeding food scraps to dogs and those that did not. The second—a dog owner specific study (n = 355—found that almost half (44% of respondents reported feeding table scraps to dogs. They were more likely to be females, owners of medium sized dogs, and in larger households. There was no significant difference in self-rated dogs’ body condition scores between respondents who fed table scraps to their dog and those who did not. Further multidisciplinary research is recommended to reconcile the social, veterinary and environmental risks and benefits of feeding food waste to animals.

The Relationship between Critical Thinking Disposition and Self-Esteem

Directory of Open Access Journals (Sweden)

Shirin Iranfar

2013-12-01

Full Text Available Introduction: Critical Thinking Disposition indicates individual’s inclination to Critical Thinking, which is one of the domains of personality. Individual characteristics are important and influential factors in the growth and development of students’ Critical Thinking. One of these influential characteristics might be self-esteem, thus this study was to determine the correlation between Critical Thinking Disposition and self-esteem in medical students. Methods: In an analytical cross-sectional study, 289 medical students were selected through stratified random sampling method in Kermanshah University of Medical Sciences in 2011. The instrument for data collection was a questionnaire containing 3 parts: demographic data, California Critical Thinking Disposition Inventory, and Cooper-Smith Self-Esteem Inventory. The results were analyzed by SPSS-16 using descriptive statistics, Pearson and Spearman Correlation Coefficient, ANOVA, Chi-Square and Fisher exact test. Results: Results showed that 98.6% (285 of students had deficiency, 1.4% (4 ambivalence and nobody had positive critical thinking disposition. There was a significantly negative correlation between Critical Thinking Disposition and self-esteem (r=-0.462, P<0.001. Also, there was no a significant relationship between two groups of low self-esteem , high self-esteem , negative and ambivalent Critical Thinking Disposition. Conclusion: It seems that Critical Thinking Disposition, like other psychological variables, is influenced by social factors and social environment plays a role in promoting or undermining it. So, similar studies are recommended to investigate the factors affecting Critical Thinking in medical students.

Accessing and assessing young learner’s mathematical dispositions

Directory of Open Access Journals (Sweden)

mellony Graven

2012-07-01

Full Text Available It is argued in this paper that there is an absence of literature relating to research on learner mathematical dispositions, particularly with young learners. Drawing on Kilpatrick, Swafford and Findell’s (2001 five interrelated strands of mathematical proficiency, which include: conceptual understanding, procedural fluency, strategic competence, adaptive reasoning and productive disposition, it is argued that there has been little engagement with productive disposition in the field of mathematics education and how we might access and assess this strand. Despite competence in all strands being essential for mathematical proficiency, literature and assessments that seek to establish learner levels of mathematical proficiency have tended to focus on the first four and have neglected the last; productive disposition. Finding ways in which to access student mathematical learning dispositions can be challenging, especially with young learners who struggle to articulate their views. An instrument is shared that the author has designed with doctoral fellow, Debbie Stott, in order to access and assess the productive disposition of learners participating in maths clubs run within the South African Numeracy Chair. The findings that emerge in one Grade 3 club with six learners is shared. These findings are related to the data collected through instruments that assess the other four strands of mathematical proficiency. This enables a holistic picture of learner’s mathematical proficiency as intended in the conceptualisation of the interrelated five strands of proficiency.

Critical Thinking Dispositions of Pre-Service Teachers

Science.gov (United States)

Bakir, Selda

2015-01-01

This study investigated the critical thinking dispositions of pre-service teachers in terms of various variables. The study included 1106 participants and used the survey model and the Turkish version (CCTDI-T) of the California Critical Thinking Disposition Inventory (CCTDI). The reliability of the scale for this study was found to be 0.82. The…

Characterizing Surplus US Plutonium for Disposition - 13199

Energy Technology Data Exchange (ETDEWEB)

Allender, Jeffrey S. [Savannah River National Laboratory, Aiken SC 29808 (United States); Moore, Edwin N. [Moore Nuclear Energy, LLC, Savannah River Site, Aiken SC 29808 (United States)

2013-07-01

The United States (US) has identified 61.5 metric tons (MT) of plutonium that is permanently excess to use in nuclear weapons programs, including 47.2 MT of weapons-grade plutonium. Surplus inventories will be stored safely by the Department of Energy (DOE) and then transferred to facilities that will prepare the plutonium for permanent disposition. The Savannah River National Laboratory (SRNL) operates a Feed Characterization program for the Office of Fissile Materials Disposition (OFMD) of the National Nuclear Security Administration (NNSA) and the DOE Office of Environmental Management (DOE-EM). SRNL manages a broad program of item tracking through process history, laboratory analysis, and non-destructive assay. A combination of analytical techniques allows SRNL to predict the isotopic and chemical properties that qualify materials for disposition through the Mixed Oxide (MOX) Fuel Fabrication Facility (MFFF). The research also defines properties that are important for other disposition paths, including disposal to the Waste Isolation Pilot Plant (WIPP) as transuranic waste (TRUW) or to high-level waste (HLW) systems. (authors)

Proliferation resistance criteria for fissile material disposition issues

International Nuclear Information System (INIS)

Rutherford, D.A.; Fearey, B.L.; Markin, J.T.; Close, D.A.; Tolk, K.M.; Mangan, D.L.; Moore, L.

1995-01-01

The 1994 National Acdaemy of Sciences study ''Management and Disposition of Excess Weapons Plutonium'' defined options for reducing the national and international proliferation risks of materials declared excess to the nuclear weapons program. This paper proposes criteria for assessing the proliferation resistance of these options as well defining the ''Standards'' from the report. The criteria are general, encompassing all stages of the disposition process from storage through intermediate processing to final disposition including the facilities, processing technologies and materials, the level of safeguards for these materials, and the national/subnational threat to the materials

Study of carbon black obtained by pyrolysis of waste scrap tyres

Czech Academy of Sciences Publication Activity Database

Mikulová, Z.; Šeděnková, Ivana; Matějová, Lenka; Večeř, M.; Dombek, V.

2013-01-01

Roč. 111, č. 2 (2013), s. 1475-1481 ISSN 1388-6150. [Central and Eastern European Conference on Thermal Analysis and Calorimetry /1./ - CEEC-TAC1. Craiova, 07.09.2011-10.09.2011] R&D Projects: GA ČR GA104/09/0972 Institutional research plan: CEZ:AV0Z40500505; CEZ:AV0Z40720504 Keywords : scrap tyres * carbon black * thermogravimetry Subject RIV: CI - Industrial Chemistry, Chemical Engineering Impact factor: 2.206, year: 2013

16 CFR 300.29 - Garments or products composed of or containing miscellaneous cloth scraps.

Science.gov (United States)

2010-01-01

... 16 Commercial Practices 1 2010-01-01 2010-01-01 false Garments or products composed of or containing miscellaneous cloth scraps. 300.29 Section 300.29 Commercial Practices FEDERAL TRADE COMMISSION... chiefly woolen fibers with the balance of undetermined mixtures of cotton, rayon or other non-woolen...

Salt disposition alternatives filtration at SRTC

International Nuclear Information System (INIS)

Walker, B. W.; Hobbs, D.

2000-01-01

Several of the prospective salt disposition alternative technologies require a monosodium titanate (MST) contact to remove strontium and actinides from inorganic salt solution feedstock. This feedstock also contains sludge solids from waste removal operations and may contain defoamers added in the evaporator systems. Filtration is required to remove the sludge and MST solids before sending the salt solution for further processing. This report describes testing performed using the Parallel Theological Experimental Filter (PREF). The PREF contains two single tube Mott sintered metal crossflow filters. For this test one filter was isolated so that the maximum velocities could be achieved. Previous studies showed slurries of MST and sludge in the presence of sodium tetraphenylborate (NaTPB) were filterable since the NaTPB slurry formed a filter cake which aided in removing the smaller MST and sludge particles. Some of the salt disposition alternative technologies do not use NaTPB raising the question of how effective crossflow filtration is with a feed stream containing only sludge and MST. Variables investigated included axial velocity, transmembrane pressure, defoamer effects, and solids concentration (MST and sludge). Details of the tests are outlined in the technical report WSRC-RP-98-O0691. Key conclusions from this study are: (1) Severe fouling of the Mott sintered metal filter did not occur with any of the solutions filtered. (2) The highest fluxes, in the range of .46 to 1.02 gpm/f 2 , were obtained when salt solution decanted from settled solids was fed to the filter. These fluxes would achieve 92 to 204 gpm filtrate production for the current ITP filters. The filtrate fluxes were close to the flux of 0.42 gpm/f 2 reported for In Tank Precipitation Salt Solution by Morrisey. (3) For the range of solids loading studied, the filter flux ranged from .04 to .17 gpm/f 2 which would result in a filtrate production rate of 9 to 31 gpm for the current HP filter. (4

Direct regeneration of recycled cathode material mixture from scrapped LiFePO4 batteries

Science.gov (United States)

Li, Xuelei; Zhang, Jin; Song, Dawei; Song, Jishun; Zhang, Lianqi

2017-03-01

A new green recycling process (named as direct regeneration process) of cathode material mixture from scrapped LiFePO4 batteries is designed for the first time. Through this direct regeneration process, high purity cathode material mixture (LiFePO4 + acetylene black), anode material mixture (graphite + acetylene black) and other by-products (shell, Al foil, Cu foil and electrolyte solvent, etc.) are recycled from scrapped LiFePO4 batteries with high yield. Subsequently, recycled cathode material mixture without acid leaching is further directly regenerated with Li2CO3. Direct regeneration procedure of recycled cathode material mixture from 600 to 800 °C is investigated in detail. Cathode material mixture regenerated at 650 °C display excellent physical, chemical and electrochemical performances, which meet the reuse requirement for middle-end Li-ion batteries. The results indicate the green direct regeneration process with low-cost and high added-value is feasible.

EPA and GSA Webinar: E Scrap Management, Computers for Learning and the Federal Green Challenge

Science.gov (United States)

EPA and the General Services Administration (GSA) are hosting a webinar on May 2, 2018. Topics will include policies and procedures on E Scrap management, a review of the Computers For Leaning Program, and benefits of joining the Federal Green Challenge.

NRC comprehensive records disposition schedule

International Nuclear Information System (INIS)

1982-07-01

Effective January 1, 1982, NRC will institute records retention and disposal practices in accordance with the approved Comprehensive Records Disposition Schedule (CRDS). CRDS is comprised of NRC Schedules (NRCS) 1 to 4 which apply to the agency's program or substantive records and General Records Schedules (GRS) 1 to 22 which apply to housekeeping or facilitative records. The schedules are assembled functionally/organizationally to facilitate their use. Preceding the records descriptions and disposition instructions for both NRCS and GRS, there are brief statements on the organizational units which accumulate the records in each functional area, and other information regarding the schedules' applicability

Disposition Options for Uranium-233

International Nuclear Information System (INIS)

Beahm, E.C.; Dole, L.R.; Forsberg, C.W.; Icenhour, A.S.; Storch, S.N.

1999-01-01

The U.S. Department of Energy (DOE) Fissile Materials Disposition Program (MD), in support of the U.S. arms-control and nonproliferation policies, has initiated a program to disposition surplus weapons-usable fissile material by making it inaccessible and unattractive for use in nuclear weapons. Weapons-usable fissile materials include plutonium, high-enriched uranium (HEU), and uranium-233 (sup 233)U. In support of this program, Oak Ridge National Laboratory led DOE's contractor efforts to identify and characterize options for the long-term storage and disposal of excess (sup 233)U. Five storage and 17 disposal options were identified and are described herein

Happiness, Dispositions and the Self

DEFF Research Database (Denmark)

Klausen, Søren Harnow

2016-01-01

I argue that happiness is an exclusively categorical mental state. Daniel Haybron’s inclusion of dispositions into his emotional state theory rests of a confusion of constituents of happiness in the narrow psychological sense with objects of prudential concern, to which obviously belong “mood...... propensities” and other dispositional states. I further argue that while it is probably correct to require of a constituent of happiness that it must in some sense be “deep” and belong to, or directly impact on, a persons’ self, the importance of depth may be overrated by the emotional state theory, which also...

24 CFR 970.19 - Disposition of property; use of proceeds.

Science.gov (United States)

2010-04-01

... advertised for bid, HUD may accept a reasonable valuation of the property. (e) A PHA shall use net proceeds... 24 Housing and Urban Development 4 2010-04-01 2010-04-01 false Disposition of property; use of... Disposition of property; use of proceeds. (a) Where HUD approves the disposition of real property of a...

Treatment of Ni-EDTA containing wastewater by electrocoagulation using iron scraps packed-bed anode.

Science.gov (United States)

Ye, Xiaokun; Zhang, Junya; Zhang, Yan; Lv, Yuancai; Dou, Rongni; Wen, Shulong; Li, Lianghao; Chen, Yuancai; Hu, YongYou

2016-12-01

The unique electrocoagulator proposed in this study is highly efficient at removing Ni-EDTA, providing a potential remediation option for wastewater containing lower concentrations of Ni-EDTA (Ni ≤ 10 mg L -1 ). In the electrocoagulation (EC) system, cylindrical graphite was used as a cathode, and a packed-bed formed from iron scraps was used as an anode. The results showed that the removal of Ni-EDTA increased with the application of current and favoured acidic conditions. We also found that the iron scrap packed-bed anode was superior in its treatment ability and specific energy consumption (SECS) compared with the iron rod anode. In addition, the packed density and temperature had a large influence on the energy consumption (ECS). Over 94.3% of Ni and 95.8% of TOC were removed when conducting the EC treatment at an applied current of 0.5 A, initial pH of 3, air-purged rate 0.2 L min -1 , anode packed density of 400 kg m -3 temperature of 313 K and time of 30 min. SEM analysis of the iron scraps indicated that the specific area of the anode increased after the EC. The XRD analysis of flocs produced during EC revealed that hematite (α-Fe 2 O 3 ) and magnetite (Fe 3 O 4 ) were the main by-products under aerobic and anoxic conditions, respectively. A kinetic study demonstrated that the removal of Ni-EDTA followed a first-order model with the current parameters. Moreover, the removal efficiency of real wastewater was essentially consistent with that of synthetic wastewater. Copyright © 2016 Elsevier Ltd. All rights reserved.

Assessment of dose level of ionizing radiation in army scrap

International Nuclear Information System (INIS)

Abdel Hamid, S. M.

2010-12-01

Radiation protection is the science of protecting people and the environment from the harmful effects of ionizing radiation, which includes both particle radiation and high energy radiation. Ionizing radiation is widely used in industry and medicine. Any human activity of nuclear technologies should be linked to the foundation of scientific methodology and baseline radiation culture to avoid risk of radiation and should be working with radioactive materials and expertise to understand, control practices in order to avoid risks that could cause harm to human and environment. The study was conducted in warehouses and building of Sudan air force Khartoum basic air force during September 2010. The goal of this study to estimate the radiation dose and measurement of radioactive contamination of aircraft scrap equipment and increase the culture of radiological safety as well as the concept of radiation protection. The results showed that there is no pollution observed in the contents of the aircraft and the spire part stores outside, levels of radiation dose for the all contents of the aircraft and spire part within the excitable level, except temperature sensors estimated radiation dose about 43 μSv/h outside of the shielding and 12 μSv/h inside the shielding that exceeded the internationally recommended dose level. One of the most important of the identification of eighteen (18) radiation sources used in temperature and fuel level sensors. These are separated from the scrap, collected and stored in safe place. (Author)

Fatal chlorine gas exposure at a metal recycling facility: Case report.

Science.gov (United States)

Harvey, Robert R; Boylstein, Randy; McCullough, Joel; Shumate, Alice; Yeoman, Kristin; Bailey, Rachel L; Cummings, Kristin J

2018-06-01

At least four workers at a metal recycling facility were hospitalized and one died after exposure to chlorine gas when it was accidentally released from an intact, closed-valved cylinder being processed for scrap metal. This unintentional chlorine gas release marks at least the third such incident at a metal recycling facility in the United States since 2010. We describe the fatal case of the worker whose clinical course was consistent with acute respiratory distress syndrome (ARDS) following exposure to high concentrations of chlorine gas. This case report emphasizes the potential risk of chlorine gas exposure to metal recycling workers by accepting and processing intact, closed-valved containers. The metal recycling industry should take steps to increase awareness of this established risk to prevent future chlorine gas releases. Additionally, public health practitioners and clinicians should be aware that metal recycling workers are at risk for chlorine gas exposure. © 2018 Wiley Periodicals, Inc.

Decontamination of transuranic contaminated metals by melt refining

International Nuclear Information System (INIS)

Heshmatpour, B.; Copeland, G.L.; Heestand, R.L.

1983-01-01

Melt refining of transuranic contaminated metals is a possible decontamination process with the potential advantages of producing metal for reuse and of simplifying chemical analyses. By routinely achieving the 10 nCi/g( about0.1ppm) level by melt refining, scrap metal can be removed from the transuranic waste category. (To demonstrate the effectiveness of this melt refining process, mild steel, stainless steel, nickel, and copper were contaminated with 500 ppm (μg/g) PuO 2 and melted with various fluxes. The solidified slags and metals were analyzed for their plutonium contents, and corresponding partition ratios for plutonium were calculated. Some metals were double refined in order to study the effect of secondary slag treatment. The initial weight of the slags was also varied to investigate the effect of slag weight on the degree of plutonium removal. In general, all four metals could be decontaminated below 1 ppm (μg/g) Pu ( about100 nCi/g) by a single slag treatment. Doubling the slag weight did not improve decontamination significantly; however, double slag treatment using 5 wt.% slag did decontaminate the metals to below 0.1 ppm (μg/g) Pu (10 nCi/g).)

30 CFR 879.15 - Disposition of reclaimed land.

Science.gov (United States)

2010-07-01

... 30 Mineral Resources 3 2010-07-01 2010-07-01 false Disposition of reclaimed land. 879.15 Section 879.15 Mineral Resources OFFICE OF SURFACE MINING RECLAMATION AND ENFORCEMENT, DEPARTMENT OF THE INTERIOR ABANDONED MINE LAND RECLAMATION ACQUISITION, MANAGEMENT, AND DISPOSITION OF LANDS AND WATER § 879...

Disposition of surplus fissile materials via immobilization

International Nuclear Information System (INIS)

Gray, L.W.; Kan, T.; Sutcliffe, W.G.; McKibben, J.M.; Danker, W.

1995-01-01

In the Cold War aftermath, the US and Russia have agreed to large reductions in nuclear weapons. To aid in the selection of long-term management options, the USDOE has undertaken a multifaceted study to select options for storage and disposition of surplus plutonium (Pu). One disposition alternative being considered is immobilization. Immobilization is a process in which surplus Pu would be embedded in a suitable material to produce an appropriate form for ultimate disposal. To arrive at an appropriate form, we first reviewed published information on HLW immobilization technologies to identify forms to be prescreened. Surviving forms were screened using multi-attribute utility analysis to determine promising technologies for Pu immobilization. We further evaluated the most promising immobilization families to identify and seek solutions for chemical, chemical engineering, environmental, safety, and health problems; these problems remain to be solved before we can make technical decisions about the viability of using the forms for long-term disposition of Pu. All data, analyses, and reports are being provided to the DOE Office of Fissile Materials Disposition to support the Record of Decision that is anticipated in Summer of 1996

Legacy sample disposition project. Volume 2: Final report

International Nuclear Information System (INIS)

Gurley, R.N.; Shifty, K.L.

1998-02-01

This report describes the legacy sample disposition project at the Idaho Engineering and Environmental Laboratory (INEEL), which assessed Site-wide facilities/areas to locate legacy samples and owner organizations and then characterized and dispositioned these samples. This project resulted from an Idaho Department of Environmental Quality inspection of selected areas of the INEEL in January 1996, which identified some samples at the Test Reactor Area and Idaho Chemical Processing Plant that had not been characterized and dispositioned according to Resource Conservation and Recovery Act (RCRA) requirements. The objective of the project was to manage legacy samples in accordance with all applicable environmental and safety requirements. A systems engineering approach was used throughout the project, which included collecting the legacy sample information and developing a system for amending and retrieving the information. All legacy samples were dispositioned by the end of 1997. Closure of the legacy sample issue was achieved through these actions

The metal failure cases discussed

Energy Technology Data Exchange (ETDEWEB)

Gupton, P

1978-06-05

The metal failure cases discussed by P. Gupton (Monsanto Chem. Co.) at a joint meeting of the American Society of Metals (ASM) and the National Association of Corrosion Engineers Calgary Section (Calgary 1978) include a high-temperature (1775/sup 0/-1800/sup 0/F) failure in an HK 40 outside heater tube in a synthesis gas steam-methane reformer, resulting in two major fissures caused by carbonization and oxide deposits with high carbon and lead contents due to the use of remelt scrap material with high lead content; separation of a support pad from a 30 in. pipeline due to corrosion caused by molybdenum-peroxide action; oxidation of a section of 180/sup 0/ U-bend in a thermal ethylene cracking furnace due to fluxing reaction of a high sodium and calcium feed which collected in the return bed; stress corrosion cracking of an austenitic stainless cracker tube from high temperature and electrolytic attack; and other cases of metal failure caused by weld quality problems, use of contaminated material and inadequate designs, processing, and fabrication.

Direct Solid-State Conversion of Recyclable Metals and Alloys

Energy Technology Data Exchange (ETDEWEB)

Feng, Z; Manchiraju, K [Southwire Co.

2012-02-22

This project is to develop and demonstrate the concept feasibility of a highly energy-efficient solid-state material synthesis process, friction stir extrusion (FSE) technology. Specifically, the project seeks to explore and demonstrate the feasibility to recycle metals, produce nano-particle dispersion strengthened bulk materials and/or nano-composite materials from powders, chips or other recyclable feedstock metals or scraps through mechanical alloying and thermo-mechanical processing in a single-step. In this study, we focused on metal recycling, producing nano-engineered wires and evaluating their potential use in future generation long-distance electric power delivery infrastructure. More comprehensive R&D on the technology fundamentals and system scale-up toward early-stage applications in two targeted “showcase” fields of use: nano engineered bulk materials and Al recycling will be considered and planned as part of Project Continuation Plan.

Unallocated Off-Specification Highly Enriched Uranium: Recommendations for Disposition

Energy Technology Data Exchange (ETDEWEB)

Bridges, D. N.; Boeke, S. G.; Tousley, D. R.; Bickford, W.; Goergen, C.; Williams, W.; Hassler, M.; Nelson, T.; Keck, R.; Arbital, J.

2002-02-27

The U.S. Department of Energy (DOE) has made significant progress with regard to disposition planning for 174 metric tons (MTU) of surplus Highly Enriched Uranium (HEU). Approximately 55 MTU of this 174 MTU are ''offspec'' HEU. (''Off-spec'' signifies that the isotopic or chemical content of the material does not meet the American Society for Testing and Materials standards for commercial nuclear reactor fuel.) Approximately 33 of the 55 MTU have been allocated to off-spec commercial reactor fuel per an Interagency Agreement between DOE and the Tennessee Valley Authority (1). To determine disposition plans for the remaining {approx}22 MTU, the DOE National Nuclear Security Administration (NNSA) Office of Fissile Materials Disposition (OFMD) and the DOE Office of Environmental Management (EM) co-sponsored this technical study. This paper represents a synopsis of the formal technical report (NNSA/NN-0014). The {approx} 22 MTU of off-spec HEU inventory in this study were divided into two main groupings: one grouping with plutonium (Pu) contamination and one grouping without plutonium. This study identified and evaluated 26 potential paths for the disposition of this HEU using proven decision analysis tools. This selection process resulted in recommended and alternative disposition paths for each group of HEU. The evaluation and selection of these paths considered criteria such as technical maturity, programmatic issues, cost, schedule, and environment, safety and health compliance. The primary recommendations from the analysis are comprised of 7 different disposition paths. The study recommendations will serve as a technical basis for subsequent programmatic decisions as disposition of this HEU moves into the implementation phase.

Dispositional contempt: A first look at the contemptuous person.

Science.gov (United States)

Schriber, Roberta A; Chung, Joanne M; Sorensen, Katherine S; Robins, Richard W

2017-08-01

Contempt is a powerful emotion. Marriages fail (Gottman, 1994), coworkers are shamed (Melwani & Barsade, 2011), terrorism is tended toward (Tausch et al., 2011). Despite its importance, contempt has not been investigated at the level of personality. The present research examines how our contemptuous reactions can be conceptualized and measured as a stable individual-difference variable with a range of theoretically predicted correlates. First, we introduce a measure of dispositional contempt , the tendency to look down on, distance, and derogate others who violate our standards. We then unpack the dynamics of dispositional contempt. Across 6 studies using self-report and emotion elicitation in student and MTurk samples (Ns = 165 to 1,368), we examined its (a) nomological network, (b) personality and behavioral correlates, and (c) implications for relationship functioning. Dispositional contempt was distinguished from tendencies toward related emotions and was most associated with dispositional envy, anger, and hubristic pride. Somewhat paradoxically, dispositional contempt was related to being cold and "superior," with associations found with narcissism, other-oriented perfectionism, and various antisocial tendencies (e.g., Disagreeableness, Machiavellianism, racism), but it was also related to being self-deprecating and emotionally fragile, with associations found with low self-esteem, insecure attachment, and feeling that others impose perfectionistic standards on oneself. Dispositional contempt predicted contemptuous reactions to eliciting film clips, particularly when targets showed low competence/power. Finally, perceiving one's romantic partner as dispositionally contemptuous was associated with lower commitment and satisfaction. Taken together, results give a first look at the contemptuous person and provide a new organizing framework for understanding contempt. (PsycINFO Database Record (c) 2017 APA, all rights reserved).

17 CFR 200.42 - Disposition of business by seriatim Commission consideration.

Science.gov (United States)

2010-04-01

... 17 Commodity and Securities Exchanges 2 2010-04-01 2010-04-01 false Disposition of business by... EXCHANGE COMMISSION ORGANIZATION; CONDUCT AND ETHICS; AND INFORMATION AND REQUESTS Disposition of Commission Business § 200.42 Disposition of business by seriatim Commission consideration. (a) Whenever the...

17 CFR 200.40 - Joint disposition of business by Commission meeting.

Science.gov (United States)

2010-04-01

... 17 Commodity and Securities Exchanges 2 2010-04-01 2010-04-01 false Joint disposition of business... EXCHANGE COMMISSION ORGANIZATION; CONDUCT AND ETHICS; AND INFORMATION AND REQUESTS Disposition of Commission Business § 200.40 Joint disposition of business by Commission meeting. Any meeting of the...

USING THE SCRAP TIRES TO PRODUCE A FLEXIBLE COUPLER

Directory of Open Access Journals (Sweden)

Tahsean A. Hussain

2018-01-01

Full Text Available The scrap tires considered a problematic source of waste, the old rubber tires causes a big environmental problem that is need much money and effort to disposes it safely. In Iraq there are more than two million used tires disposed to the environment annually. one of the tire’s recycling methods is the use of tire layers to produce a new rubber parts used in the engineering and industrial purposes as the bridges and machines dampers, this trend of recycling doesn’t take a sufficient care comparing with the other uses. There are a lot of studies conducted in these field, these studies suggests many methods to manage the huge number of scrap tires, the current paper aims to use the old rubber tires in engineering purposes (especially as a coupler joins the motor or engines with the other equipment as electric dynamo or pumps, the study focusing on the mechanical properties of a strip from a used tires and comparing with one prepared in the lab., and suggesting a new method to use as an engineering parts (for example the coupler lays between the IC engine and the dynamo of an electric generator. One of the results obtained from the experiments, there is no significant difference between the mechanical properties of the old and the new strip, (in the tensile test, the breaking force of the -Lab. tensile specimen- is 137 N whereas the specimen of old tire have a breaking force 113.27 N, but they are same in the elongation. A computational example is suggested to estimate the dimensions of a flexible coupler use an old tire pieces.

Waste forms for plutonium disposition

International Nuclear Information System (INIS)

Johnson, S.G.; O'Holleran, T.P.; Frank, S.M.; Meyer, M.K.; Hanson, M.; Staples, B.A.; Knecht, D.A.; Kong, P.C.

1997-01-01

The field of plutonium disposition is varied and of much importance, since the Department of Energy has decided on the hybrid option for disposing of the weapons materials. This consists of either placing the Pu into mixed oxide fuel for reactors or placing the material into a stable waste form such as glass. The waste form used for Pu disposition should exhibit certain qualities: (1) provide for a suitable deterrent to guard against proliferation; (2) be of minimal volume, i.e., maximize the loading; and (3) be reasonably durable under repository-like conditions. This paper will discuss several Pu waste forms that display promising characteristics

Guide for disposition of radioactive-material sources

International Nuclear Information System (INIS)

Taylor, J.M.; Selby, J.M.

1983-04-01

This guide has been prepared to assist DOE Energy Technology Centers in disposing of radioactive-material sources. The guide describes the steps and requirements necessary to dispose of unwanted sources. The steps include obtaining approvals, source characterization, source disposition, packaging requirements, and shipment preparation. A flow chart is provided in the guide to assist the user in the necessary sequential steps of source disposition

45 CFR 95.707 - Equipment management and disposition.

Science.gov (United States)

2010-10-01

... participation in the costs of replacement equipment shall be limited to the additional outlay. (4) If the... 45 Public Welfare 1 2010-10-01 2010-10-01 false Equipment management and disposition. 95.707... PROGRAMS) Equipment Acquired Under Public Assistance Programs § 95.707 Equipment management and disposition...

Identifying and Assessing Dispositions of Educational Leadership Candidates

Science.gov (United States)

Melton, Teri; Mallory, Barbara J.; Green, James

2010-01-01

The purpose of this study was to identify educational leadership programs' procedures for the identification and assessment of leadership dispositions. The findings of this cross sectional survey indicated that there is little consistency in practice in defining and assessing dispositions of leadership candidates. While findings indicated that the…

38 CFR 12.22 - Disposition of personal property.

Science.gov (United States)

2010-07-01

... converted into cash, except that articles of personal adornment which are obviously of sentimental value... 38 Pensions, Bonuses, and Veterans' Relief 1 2010-07-01 2010-07-01 false Disposition of personal... DISPOSITION OF VETERAN'S PERSONAL FUNDS AND EFFECTS Under Pub. L. 382, 77th Congress, December 26, 1941...

Melting of contaminated steel scrap from the dismantling of the CO2 systems of gas cooled, graphite moderated nuclear reactors

International Nuclear Information System (INIS)

Feaugas, J.; Jeanjacques, M.; Peulve, J.

1994-01-01

G2 and G3 are the natural Uranium cooled reactors Graphite/Gas. The two reactors were designed for both plutonium and electricity production (45 MWe). The dismantling of the reactors at stage 2 has produced more than 4 000 tonnes of contaminated scrap. Because of their large mass and low residual contamination level, the French Atomic Energy Commission (CEA) considered various possibilities for the processing of these metallic products in order to reduce the volume of waste going to be stored. After different studies and tests of several processes and the evaluation of their results, the choice to melt the dismantled pipeworks was taken. It was decided to build the Nuclear Steel Melting Facility known as INFANTE, in cooperation with a steelmaker (AHL). The realization time schedule for the INFANTE lasted 20 months. It included studies, construction and the licensing procedure. (authors). 2 tabs., 3 figs

Radioactive contamination in metal recycling industry - an environmental issue

International Nuclear Information System (INIS)

Agarwal, S.P.

2012-01-01

Metal recycling has become an important industrial activity worldwide; it is seen as being socially and environmentally beneficial because it conserves natural ore resources and saves energy. However, there have been several accidents over the past decades involving orphan radioactive sources or other radioactive material that were inadvertently collected as metal scrap that was destined for recycling. The consequences of these accidents have been serious with regard to the protection of people and the environment from the harmful effects of ionizing radiation as well as from an economic point of view. India produces and exports steel products to various countries. In the recent years there were rejection and return of steel products as they were found to be contaminated with trace quantities of radioactive materials. During investigation of incidents of radioactive contamination in steel products exported from India, it was observed that steel products are contaminated with low level radioactivity. Though radioactivity level in steel products is found to be too low to pose any significant hazards to the handling personnel or to the users or the public at large, its presence is undesirable and need to be probed as to how it has entered in the steel products. Atomic Energy Regulatory Board (AERB) has investigated the incidents of such nature in the recent past and it is gathered that the steel products are made out of steel produced in a foundry where metal scrap containing radioactive material has been used. In this talk, incidents of radioactive contamination, its roots cause, and its radiological impact on person, property and environment, lessons learnt, remedial measures and international concerns will be discussed

INEL metal recycle annual report, FY-94

International Nuclear Information System (INIS)

Bechtold, T.E.

1994-09-01

In 1992, the mission of the Idaho Chemical Processing Plant was changed from reprocessing of spent nuclear fuels to development of technologies for conditioning of spent nuclear fuels and other high-level wastes for disposal in a geologic repository. In addition, the Department of Energy (DOE) directed Idaho National Engineering Laboratory (INEL) to develop a program plan addressing the management of radioactive contaminated scrap metal (RSM) within the DOE complex. Based on discussions with the EM-30 organization, the INEL Metal Recycle program plan was developed to address all issues of RSM management. Major options considered for RSM management were engineered interim storage, land disposal as low-level waste, and beneficial reuse/recycle. From its inception, the Metal Recycle program has emphasized avoidance of storage and disposal costs through beneficial reuse of RSM. The Metal Recycle program plan includes three major activities: Site-by-site inventory of RSM resources; validation of technologies for conversion of RSM to usable products; and identification of parties prepared to participate in development of a RSM recycle business

Contribution of Emotional Intelligence towards Graduate Students’ Critical Thinking Disposition

Directory of Open Access Journals (Sweden)

Fong-Luan Kang

2015-10-01

Full Text Available Good critical thinkers possess a core set of cognitive thinking skills, and a disposition towards critical thinking. They are able to think critically to solve complex, real-world problems effectively. Although personal emotion is important in critical thinking, it is often a neglected issue. The emotional intelligence in this study concerns our sensitivity to and artful handling of our own and others’ emotions. Engaging students emotionally is the key to strengthening their dispositions toward critical thinking. Hence, a study involving 338 male and female graduate students from a public university was carried out. They rated the Emotional Intelligence Scale and Critical Thinking Disposition Scale. Findings suggested that emotional intelligence and critical thinking disposition were positively correlated (r=.609. Differences in terms of age, gender, and course of study also formed part of the analysis. Keywords: emotional intelligence, critical thinking disposition, graduate students

Measuring Teacher Dispositions

Science.gov (United States)

Singh, Delar K.; Stoloff, David L.

2007-01-01

Teacher quality has become a top priority of our national agenda. There is empirical evidence that suggests that teacher inputs have impact on student outcomes. It is also believed that teacher dispositions are as crucial for student achievement as a teacher's pedagogical and content knowledge/skills. The National Council for Accreditation of…

25 CFR 242.5 - Disposition of unmarketable fish.

Science.gov (United States)

2010-04-01

... 25 Indians 1 2010-04-01 2010-04-01 false Disposition of unmarketable fish. 242.5 Section 242.5 Indians BUREAU OF INDIAN AFFAIRS, DEPARTMENT OF THE INTERIOR FISH AND WILDLIFE COMMERCIAL FISHING ON RED LAKE INDIAN RESERVATION § 242.5 Disposition of unmarketable fish. All unmarketable live fish taken...

7 CFR 3565.453 - Disposition of the property.

Science.gov (United States)

2010-01-01

... 7 Agriculture 15 2010-01-01 2010-01-01 false Disposition of the property. 3565.453 Section 3565....453 Disposition of the property. (a) Submission of the liquidation plan. The lender will, within 30... the interest. (3) A full and complete list of all collateral including any personal and corporate...

7 CFR 1779.90 - Disposition of acquired property.

Science.gov (United States)

2010-01-01

... Disposition of acquired property. (a) General. When the lender acquires title to the collateral and the final... 7 Agriculture 12 2010-01-01 2010-01-01 false Disposition of acquired property. 1779.90 Section... develop a plan to fully protect the collateral, and the lender must dispose of the collateral without...

50 CFR 30.12 - Disposition of feral animals.

Science.gov (United States)

2010-10-01

... 50 Wildlife and Fisheries 6 2010-10-01 2010-10-01 false Disposition of feral animals. 30.12... (CONTINUED) THE NATIONAL WILDLIFE REFUGE SYSTEM RANGE AND FERAL ANIMAL MANAGEMENT Feral Animals § 30.12 Disposition of feral animals. Feral animals taken on wildlife refuge areas may be disposed of by sale on the...

Building a Conceptual Framework for Online Educator Dispositions

Science.gov (United States)

Kirwan, Jeral R.; Roumell, Elizabeth Anne

2015-01-01

It has been argued that online instruction is distinctive from the conventional classroom. If an effective online practice is to emerge, the roles, characteristics and dispositions of the educators themselves should be studied more closely. The aim of this paper was to present an online educator dispositions model that addresses the underlying…

Selective Extraction of Rare Earth Elements from Permanent Magnet Scraps with Membrane Solvent Extraction.

Science.gov (United States)

Kim, Daejin; Powell, Lawrence E; Delmau, Lætitia H; Peterson, Eric S; Herchenroeder, Jim; Bhave, Ramesh R

2015-08-18

The rare earth elements (REEs) such as neodymium, praseodymium, and dysprosium were successfully recovered from commercial NdFeB magnets and industrial scrap magnets via membrane assisted solvent extraction (MSX). A hollow fiber membrane system was evaluated to extract REEs in a single step with the feed and strip solutions circulating continuously through the MSX system. The effects of several experimental variables on REE extraction such as flow rate, concentration of REEs in the feed solution, membrane configuration, and composition of acids were investigated with the MSX system. A multimembrane module configuration with REEs dissolved in aqueous nitric acid solutions showed high selectivity for REE extraction with no coextraction of non-REEs, whereas the use of aqueous hydrochloric acid solution resulted in coextraction of non-REEs due to the formation of chloroanions of non-REEs. The REE oxides were recovered from the strip solution through precipitation, drying, and annealing steps. The resulting REE oxides were characterized with XRD, SEM-EDX, and ICP-OES, demonstrating that the membrane assisted solvent extraction is capable of selectively recovering pure REEs from the industrial scrap magnets.

Correlation between Composition and Properties of Composite Material Based on Scrap Tires

OpenAIRE

Mālers, L; Plēsuma, R; Ločmele, L; Kalniņš, M

2010-01-01

Purpose of present work is to investigate mechanical and insulation properties of the composite material based on scrap tires and polyurethane-type binder in correlation with composition of composite material. The studies of material’s hardness must be considered as an express-method for estimation of the selected mechanical properties (E and ccompressive stress) of the composite material without direct experimental testing of given parameters. It was shown that composite material must be r...

Some functional properties of composite material based on scrap tires

Science.gov (United States)

Plesuma, Renate; Malers, Laimonis

2013-09-01

The utilization of scrap tires still obtains a remarkable importance from the aspect of unloading the environment from non-degradable waste [1]. One of the most prospective ways for scrap tires reuse is a production of composite materials [2] This research must be considered as a continuation of previous investigations [3, 4]. It is devoted to the clarification of some functional properties, which are considered important for the view of practical applications, of the composite material. Some functional properties of the material were investigated, for instance, the compressive stress at different extent of deformation of sample (till 67% of initial thickness) (LVS EN 826) [5] and the resistance to UV radiation (modified method based on LVS EN 14836) [6]. Experiments were realized on the purposefully selected samples. The results were evaluated in the correlation with potential changes of Shore C hardness (Shore scale, ISO 7619-1, ISO 868) [7, 8]. The results showed noticeable resistance of the composite material against the mechanical influence and ultraviolet (UV) radiation. The correlation with the composition of the material, activity of binder, definite technological parameters, and the conditions supported during the production, were determined. It was estimated that selected properties and characteristics of the material are strongly dependent from the composition and technological parameters used in production of the composite material, and from the size of rubber crumb. Obtained results show possibility to attain desirable changes in the composite material properties by changing both the composition and technological parameters of examined material.

Comprehensions on the dispositive: from information towards profanation

Directory of Open Access Journals (Sweden)

Jackson da Silva Medeiros

2017-10-01

Full Text Available Introduction: The knowledge communication can be seen in epistemological and institutional conditions of informational cycle mediation, acting as an intervener in the social construction of knowledge, controlled by explicit or implicit rules that awaken or bar the flow of knowledge. Objective: Explore and reflect on dispositive based on the idea that truth is based on actions and practices contextually specific, aiming to discuss and contribute to a systematization of “document” and “information”, understanding and strategizing about power relations. Methodology: Readings and interpretations on dispositive, as presented by Michel Foucault and later interpreted and worked by other authors, undertaking its construction in the conceptual body of information and of document for scientific knowledge access. Results and Conclusions: Still partial, the results point in the direction that dispositives that use the information and the document operate in the control and in the strategies of regulation of the power in the communication of the scientific information. Knowing that scientific knowledge is a construction of a truth, being validated within a community, needing the look on dispositives that desecration the sacred.

Dispositional optimism, self-framing and medical decision-making.

Science.gov (United States)

Zhao, Xu; Huang, Chunlei; Li, Xuesong; Zhao, Xin; Peng, Jiaxi

2015-03-01

Self-framing is an important but underinvestigated area in risk communication and behavioural decision-making, especially in medical settings. The present study aimed to investigate the relationship among dispositional optimism, self-frame and decision-making. Participants (N = 500) responded to the Life Orientation Test-Revised and self-framing test of medical decision-making problem. The participants whose scores were higher than the middle value were regarded as highly optimistic individuals. The rest were regarded as low optimistic individuals. The results showed that compared to the high dispositional optimism group, participants from the low dispositional optimism group showed a greater tendency to use negative vocabulary to construct their self-frame, and tended to choose the radiation therapy with high treatment survival rate, but low 5-year survival rate. Based on the current findings, it can be concluded that self-framing effect still exists in medical situation and individual differences in dispositional optimism can influence the processing of information in a framed decision task, as well as risky decision-making. © 2014 International Union of Psychological Science.

Explanatory style, dispositional optimism, and reported parental behavior.

Science.gov (United States)

Hjelle, L A; Busch, E A; Warren, J E

1996-12-01

The relationship between two cognitive personality constructs (explanatory style and dispositional optimism) and retrospective self-reports of maternal and paternal behavior were investigated. College students (62 men and 145 women) completed the Life Orientation Test, Attributional Style Questionnaire, and Parental Acceptance-Rejection Questionnaire in a single session. As predicted, dispositional optimism was positively correlated with reported maternal and paternal warmth/acceptance and negatively correlated with aggression/hostility, neglect/indifference, and undifferentiated rejection during middle childhood. Unexpectedly, explanatory style was found to be more strongly associated with retrospective reports of paternal as opposed to maternal behavior. The implications of these results for future research concerning the developmental antecedents of differences in explanatory style and dispositional optimism are discussed.

Evaluating awareness and practices pertaining to radioactive waste management among scrap dealers in Delhi, India.

Science.gov (United States)

Makkar, Nayani; Chandra, Tany; Agrawal, Prachi; Bansal, Harshit; Singh, Simranjeet; Anand, Tanu; Gupta, Mannan Kumar; Kumar, Rajesh

2014-01-01

With nuclear technology rapidly taking the spotlight in the last 50 years, radiation accidents seem to be a harsh reality of the modern world. The Mayapuri Radiation accident of 2010 was the worst radiation accident India has yet dealt with. Two years thereafter, we designed a study to assess the awareness and practices regarding radioactive waste among scrap dealers aiming to assess deficiencies in radiation disaster preparedness. A community based cross-sectional study. The study population consisted of 209 volunteers (from 108 scrap dealerships) including 108 shop-owners and 101 workers segregated as Group A consisting of 54 dealerships in Mayapuri and Group B of 54 dealerships from the rest of the city. Subjects were then interviewed using a semi-structured questionnaire. Awareness about radioactive waste varied significantly with level of education (p = 0.024), Kuppuswamy's socio-economic scale (p = 0.005), age of the scrap dealer (p = 0.049) and his work experience (p = 0.045). The larger dealerships in Mayapuri were more aware about radioactive waste (p = 0.0004), the accident in 2010 (p = 0.0002), the symbol for radiation hazard (p = 0.016), as well as the emergency guidelines and the agencies to contact in the event of a radiation accident. Our findings seem to signify that while governmental and non-governmental agencies were successful in implementing prompt disaster response and awareness programs, the community continues to be inadequately prepared. These go on to suggest that though concerted awareness and training programs do benefit the affected community, economic and social development is the key to disaster prevention and mitigation.

Getting the plutonium disposition job done: the concept of a joint-venture disposition enterprise financed by additional sales of highly enriched uranium

International Nuclear Information System (INIS)

Bunn, M.

1996-01-01

The paper gives an outline of a concept which has the potential to provide both substantial financing needed for disposition of plutonium from excess nuclear weapons and the long-term management structure required to implement this effort. The three most important issues were underlined. First, it is urgent to modernize security and accounting systems for all weapon-usable nuclear materials, particularly from former Soviet Union. Second, excess plutonium and Highly Enriched Uranium (HEU) must be brought under international monitoring to ensure irreversibility of nuclear arms reduction. Third, quick move should be done towards actual disposition of excess plutonium and HEU. Technology already exists, but the key issues are how to get finance and manage this operation, particularly given its immense scope and controversial nature. An international joint venture 'Enterprise for nuclear Security' that would build and operate plutonium disposition facilities under stringent non-proliferation controls, financed through additional sales of HEU is a potentially promising approach to addressing the most difficult issues facing the disposition problem