Volume Reduction of Decommissioning Radioactive Burnable and Metal Wastes

Energy Technology Data Exchange (ETDEWEB)

Min, B. Y.; Lee, Y. J.; Yun, G. S.; Lee, K. W.; Moon, J. K. [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of); Choi, Y. K.; Cho, J. H. [SunKwang Atomic Energy Safety Co., Seoul (Korea, Republic of)

2014-10-15

A large quantity of radioactive waste was generated during the decommissioning projects. For the purpose of the volume reduction and clearance for decommissioning wastes from decommissioning projects, the incineration and high melting technology has been selected for the decommissioning wastes treatment. The volume reduction of the combustible wastes through the incineration technologies has merits from the view point of a decrease in the amount of waste to be disposed of resulting in a reduction of the disposal cost. Incineration is generally accepted as a method of reducing the volume of radioactive waste. The incineration technology is an effective treatment method that contains hazardous chemicals as well as radioactive contamination. Incinerator burns waste at high temperature. Incineration of a mixture of chemically hazardous and radioactive materials, known as 'mixed waste,' has two principal goals: to reduce the volume and total chemical toxicity of the waste. Incineration itself does not destroy the metals or reduce the radioactivity of the waste. A proven melting technology is currently used for low-level waste (LLW) at several facilities worldwide. These facilities use melting as a means of processing LLW for unrestricted release of the metal or for recycling within the nuclear sector. About 16.4 tons of decommissioning combustible waste has been treated using Oxygen Enriched incineration. The incineration facility operated quite smoothly through the analysis major critical parameters of off-gas.

Volume Reduction of Decommissioning Radioactive Burnable and Metal Wastes

International Nuclear Information System (INIS)

Min, B. Y.; Lee, Y. J.; Yun, G. S.; Lee, K. W.; Moon, J. K.; Choi, Y. K.; Cho, J. H.

2014-01-01

A large quantity of radioactive waste was generated during the decommissioning projects. For the purpose of the volume reduction and clearance for decommissioning wastes from decommissioning projects, the incineration and high melting technology has been selected for the decommissioning wastes treatment. The volume reduction of the combustible wastes through the incineration technologies has merits from the view point of a decrease in the amount of waste to be disposed of resulting in a reduction of the disposal cost. Incineration is generally accepted as a method of reducing the volume of radioactive waste. The incineration technology is an effective treatment method that contains hazardous chemicals as well as radioactive contamination. Incinerator burns waste at high temperature. Incineration of a mixture of chemically hazardous and radioactive materials, known as 'mixed waste,' has two principal goals: to reduce the volume and total chemical toxicity of the waste. Incineration itself does not destroy the metals or reduce the radioactivity of the waste. A proven melting technology is currently used for low-level waste (LLW) at several facilities worldwide. These facilities use melting as a means of processing LLW for unrestricted release of the metal or for recycling within the nuclear sector. About 16.4 tons of decommissioning combustible waste has been treated using Oxygen Enriched incineration. The incineration facility operated quite smoothly through the analysis major critical parameters of off-gas

TRU Waste Sampling Program: Volume I. Waste characterization

International Nuclear Information System (INIS)

Clements, T.L. Jr.; Kudera, D.E.

1985-09-01

Volume I of the TRU Waste Sampling Program report presents the waste characterization information obtained from sampling and characterizing various aged transuranic waste retrieved from storage at the Idaho National Engineering Laboratory and the Los Alamos National Laboratory. The data contained in this report include the results of gas sampling and gas generation, radiographic examinations, waste visual examination results, and waste compliance with the Waste Isolation Pilot Plant-Waste Acceptance Criteria (WIPP-WAC). A separate report, Volume II, contains data from the gas generation studies

A Study on promotion of utilizing waste energy

Energy Technology Data Exchange (ETDEWEB)

Ahn, Jae Ho [Korea Energy Economics Institute, Euiwang (Korea)

1999-01-01

The utilization of waste energy occupying over 80% of alternative energy has been an important issue with the trend of large-sized waste incinerator. The object of this study is to seek the methods for the active application of waste energy, which is produced at the process of waste generation and disposal. It is expected to help energy saving, foreign currency saving and prevent environmental pollution by utilizing alternative energy actively. It should have basic information, related information for examining technical feasibility, and feasibility examination of the surroundings for developing the demand place. Moreover, it should enhance the energy saving by recommending use of waste energy with introducing recommendation system of installing waste energy collection system. It should also consider the support of the introduction of waste energy system as well as the aspect of regional energy policy. In addition, the development and distribution of applied technology for waste energy are needed. (author). 36 refs., 4 figs., 77 tabs.

Characterization of low-level waste from the industrial sector, and near-term projection of waste volumes and types

International Nuclear Information System (INIS)

MacKenzie, D.R.

1988-01-01

A telephone survey of low-level waste generators has been carried out in order to make useful estimates of the volume and nature of the waste which the generators will be shipping for disposal when the compacts and states begin operating new disposal facilities. Emphasis of the survey was on the industrial sector, since there has been little information available on characteristics of industrial LLW. Ten large industrial generators shipping to Richland, ten shipping to Barnwell, and two whose wastes had previously been characterized by BNL were contacted. The waste volume shipped by these generators accounted for about two-thirds to three-quarters of the total industrial volume. Results are given in terms of the categories of LLW represented and of the chemical characteristics of the different wastes. Estimates by the respondents of their near-term waste volume projections are presented

Characterization of low-level waste from the industrial sector, and near-term projection of waste volumes and types

International Nuclear Information System (INIS)

MacKenzie, D.R.

1988-01-01

A telephone survey of low-level waste generators has been carried out in order to make useful estimates of the volume and nature of the waste which the generators are shipping for disposal when the compacts and states begin operating new disposal facilities. Emphasis of the survey was on the industrial sector, since there has been little information available on characteristics of industrial LLW. Ten large industrial generators shipping to Richland, ten shipping to Barnwell, and two whose wastes had previously been characterized by BNL were contacted. The waste volume shipped by these generators accounted for about two-thirds to three-quarters of the total industrial volume. Results are given in terms of the categories of LLW represented and of the chemical characteristics of the different wastes. Estimates by the respondents of their near-term waste volume projections are presented

Induction melting for volume reduction of metallic TRU wastes

International Nuclear Information System (INIS)

Westsik, J.H. Jr.; Montgomery, D.R.; Katayama, Y.B.; Ross, W.A.

1986-01-01

Volume reduction of metallic transuranic wastes offers economic and safety incentives for treatment of wastes generated at a hypothetical commercial fuel reprocessing facility. Induction melting has been identified as the preferred process for volume reduction of spent fuel hulls, fuel assembly hardware, and failed equipment from a reprocessing plant. Bench-scale melting of Zircaloy and stainless steel mixtures has been successfully conducted in a graphite crucible inside a large vacuum chamber. A low-melting-temperature alloy forms that has demonstrated excellent leach resistance. The alloy can be used to encapsulate other metallic wastes that cannot be melted using the existing equipment design

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

International Nuclear Information System (INIS)

Hulse, R.A.

1991-08-01

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

Containment at the Source during Waste Volume Reduction of Large Radioactive Components Using Oxylance High-Temperature Cutting Equipment - 13595

International Nuclear Information System (INIS)

Keeney, G. Neil

2013-01-01

As a waste-volume reduction and management technique, highly contaminated Control Element Drive Mechanism (CEDM) housings were severed from the Reactor Pressure Vessel Head (RPVH) inside the San Onofre Unit 2 primary containment utilizing Oxylance high-temperature cutting equipment and techniques. Presented are relevant data concerning: - Radiological profiles of the RPVH and individual CEDMs; - Design overviews of the engineering controls and the specialized confinement housings; - Utilization of specialized shielding; - Observations of apparent metallurgical-contamination coalescence phenomena at high temperatures resulting in positive control over loose-surface contamination conditions; - General results of radiological and industrial hygiene air sampling and monitoring; - Collective dose and personnel contamination event statistics; - Lessons learned. (author)

Containment at the Source during Waste Volume Reduction of Large Radioactive Components Using Oxylance High-Temperature Cutting Equipment - 13595

Energy Technology Data Exchange (ETDEWEB)

Keeney, G. Neil [Health Physicist, HazMat CATS, LLC (United States)

2013-07-01

As a waste-volume reduction and management technique, highly contaminated Control Element Drive Mechanism (CEDM) housings were severed from the Reactor Pressure Vessel Head (RPVH) inside the San Onofre Unit 2 primary containment utilizing Oxylance high-temperature cutting equipment and techniques. Presented are relevant data concerning: - Radiological profiles of the RPVH and individual CEDMs; - Design overviews of the engineering controls and the specialized confinement housings; - Utilization of specialized shielding; - Observations of apparent metallurgical-contamination coalescence phenomena at high temperatures resulting in positive control over loose-surface contamination conditions; - General results of radiological and industrial hygiene air sampling and monitoring; - Collective dose and personnel contamination event statistics; - Lessons learned. (author)

Low-level radioactive waste in the northeast: revised waste volume projections

International Nuclear Information System (INIS)

1984-06-01

The volume of low-level radioactive waste generated in the eleven Northeast states has undergone significant change since the inital 1982 analysis and projection. These revised projections incorporate improved data reporting and evidence of sharp declines in certain categories of waste. Volumes in the 1982-1983 period reflect waste shipped for disposal as reported by disposal site operators. Projected waste volumes represent waste intended for disposal. The recent dramatic changes in source reduction and waste management practices underscore the need for annual review of waste volume projections. The volume of waste shipped for off-site disposal has declined approximately 12% in two years, from an average 1,092,500 ft 3 annually in 1979 to 1981 to an average annual 956,500 ft 3 in 1982 to 1983; reactor waste disposal volumes declined by about 39,000 ft 3 or 7% during this period. Non-reactor waste volumes shipped for disposal declined by over 70,000 ft 3 or 15% during this period. The data suggest that generators increased their use of such management practices as source reduction, compaction, or, for carbon-14 and tritium, temporary storage followed by disposal as non-radioactive waste under the NRC de minimus standard effective March 1981. Using the Technical Subcommittee projection methodology, the volume of low-level waste produced annually in the eleven states, individually and collectively, is expected to increase through the year 2000, but at a significantly lower rate of increase than initially projected. By the year 2000, the Northeast is projected to generate 1,137,600 ft 3 of waste annually, an increase of about 20% over 1982 to 1983 average volume

Utilization of mining and mineral wastes

Energy Technology Data Exchange (ETDEWEB)

Park, Kyung Ho; Hong, Seung Woong; Choi, Young Yoon; Kim, Byung Gyu; Park, Je Shin [Korea Institute of Geology Mining and Materials, Taejon (Korea)

1998-12-01

Up to now, it is estimated that more than 50 million tons of mineral wastes have been generated mining industries and deposited on the land in Korea. Much of cultivated land and hilly areas have been occupied by this wastes, which cause pollution of the environment. Utilization of the mineral wastes is preferable to stabilization because full use would both eliminate the waste and broaden the mineral resource base. Therefore, the development of utilization techniques of mineral wastes is very important not only for improving the environment but also for resource conservation. In countries with high population and poor natural resources like Korea, the utilization of these wastes is essential to decrease the environmental problem and the secure the resources and the study on this field play a important part. Therefore, the objective of this study is to develop the utilization techniques of the mineral wastes. In first year's research, the contents and scope of this study are 1) Present condition and Field Survey on the mineral wastes with respect of their utilization, 2) Reviews of Current effects and research to utilize mineral wastes, 3) Characterization of mineral wastes and environmental test, 4) Evaluation and study on the utilization. (author). 67 refs., 25 tabs., 54 figs.

Utilization of mining and mineral wastes

Energy Technology Data Exchange (ETDEWEB)

Park, Kyung Ho; Hong, Seung Woong; Choi, Young Yoon; Kim, Byung Gyu; Park, Je Shin [Korea Institute of Geology Mining and Materials, Taejon (Korea)

1998-12-01

Up to now, it is estimated that more than 50 million tons of mineral wastes have been generated mining industries and deposited on the land in Korea. Much of cultivated land and hilly areas have been occupied by this wastes, which cause pollution of the environment. Utilization of the mineral wastes is preferable to stabilization because full use would both eliminate the waste and broaden the mineral resource base. Therefore, the development of utilization techniques of mineral wastes is very important not only for improving the environment but also for resource conservation. In countries with high population and poor natural resources like Korea, the utilization of these wastes is essential to decrease the environmental problem and the secure the resources and the study on this field play a important part. Therefore, the objective of this study is to develop the utilization techniques of the mineral wastes. In first year's research, the contents and scope of this study are 1) Present condition and Field Survey on the mineral wastes with respect of their utilization, 2) Reviews of Current effects and research to utilize mineral wastes, 3) Characterization of mineral wastes and environmental test, 4) Evaluation and study on the utilization. (author). 67 refs., 25 tabs., 54 figs.

Study on the High Volume Reduction of Radioactive Wastes

Energy Technology Data Exchange (ETDEWEB)

Kim, Ki Hong; Sik, Kang Il; Seok, Hong Dae [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of); Ho, Jeon Gil [RADIN Co. Ltd., Daejeon (Korea, Republic of)

2013-10-15

The solidification of radioactive wastes by the mixing method always increases their volume due to the limitation of incorporation ratio (waste/solidification agent). But if the powdered wastes can be compacted as the high density pellets and also the pellets can be filled up in a waste drum as much as possible while solidifying them with a very sticky solidification agent including a void formed in the filling step of pellets, it might be more desirable to reduce the waste volume as compared with the mixing method. So in this study, we designed and manufactured a high volume reduction machine which has the special size and shape of a pellet pocket, which the pellets can be extracted from easily and filled up in a large amount in drum, a pressurizing device to press 2 rolls, and the uniform feeding device of powder to the roll tyre. Some operational parameters which affect the formation of pellets from a powder were investigated, and then the volume reduction of a powder was evaluated. The briquetting machine, popular in general industry, was modified to apply for the volume reduction of the powered radioactive wastes (dried concentrate, sludge, spent ion-exchange resin, ash, depleted uranium powder, and etc.). In this developed high volume reduction machine, the capacity was 25 ∼ 62.5 kg/h at the optimum conditions, and the estimated volume reduction was about 2.95 (2.74/0.93) on the basis of between a powder (bulk density = 0.93 g/cm{sup 3}) and the pellet (2.74 g/cm{sup 3}). But on the basis of 200L drum, the calculated volume reduction was about 1.34 in consideration of a void volume originated in the filling step of the pellets.

Induction melting for volume reduction of metallic TRU wastes

International Nuclear Information System (INIS)

Westsik, J.H. Jr.; Montgomery, D.R.; Katayama, Y.B.; Ross, W.A.

1986-02-01

Volume reduction of metallic transuranic wastes offers economic and safety incentives for treatment of wastes generated at a hypothetical commercial fuel reprocessing facility. Induction melting has been identified as the preferred process for volume reduction of spent fuel hulls, fuel assembly hardware, and failed equipment from a reprocessing plant. Bench-scale melting of Zircaloy and stainless steel mixtures has been successfully conducted in a graphite crucible inside a large vacuum chamber. A low-melting-temperature alloy forms that has demonstrated excellent leach resistance. The alloy can be used to encapsulate other metallic wastes that cannot be melted using the existing equipment design. 18 refs., 4 figs., 3 tabs

POWER-GEN '90 conference papers: Volume 3 (Environmental trends and issues) and Volume 4 (Case histories - Non-utility power generation)

International Nuclear Information System (INIS)

Anon.

1990-01-01

This is book 2 of a collection of papers presented at the Third International Power Generation Industries Conference on December 4-6, 1990. The book contains Volume 3, Environmental Trends and Issues, and Volume 4, Case Histories - Non-utility Power Generation. The topics of the papers include environmental legislative and regulatory trends, acid rain compliance strategies and technologies, other global environmental concerns, gas fired systems, solid and waste fuels, despatching and wheeling, and strategies for purchasing non-utility power

Technical performance characterization of fourier transform profilometry for quantitative waste volume determination under Hanford waste tank conditions - 16281

International Nuclear Information System (INIS)

Monts, David L.; Jang, Ping-Rey; Long, Zhiling; Norton, Olin P.; Gresham, Lawrence L.; Su, Yi; Lindner, Jeffrey S.

2009-01-01

The Hanford Site in western Washington state is currently in the process of an extensive effort to empty and close its radioactive single-shell and double-shell waste storage tanks. Before this can be accomplished, it is necessary to know how much residual material is left in a given waste tank and the chemical makeup of the residue. The Institute for Clean Energy Technology (ICET) at Mississippi State University is currently developing an quantitative in-tank inspection system based on Fourier Transform Profilometry, FTP. FTP is a non-contact, 3-D shape measurement technique. By projecting a fringe pattern onto a target surface and observing its deformation due to surface irregularities from a different view angle, FTP is capable of determining the height (depth) distribution (and hence volume distribution) of the target surface, thus reproducing the profile of the target accurately under a wide variety of conditions. Hence FTP has the potential to be utilized for quantitative determination of residual wastes within Hanford waste tanks. We report the results of a technical feasibility study to document the accuracy and precision of quantitative volume determination using the Fourier transform profilometry technique under simulated Hanford waste tank conditions. We have initiated a technical feasibility assessment of the Fourier transform profilometry (FTP) technique for determining the volume of residual waste in Hanford radioactive waste tanks; preliminary results to date are presented in this paper. We find that we achieve FTP volume determinations with relatively small errors under conditions corresponding to the most challenging within a Hanford waste tank-viewing non-descript targets at a distance of 16.1 m (53 ft) and an angle of 62 deg.. We have determined that we can minimize measurement uncertainty by maximizing the camera-to-projector distance d, using an optical zoom of at least 5x, and ensuring that FTP images are only recorded after instrumental warm

Volume Reduction of Decommissioning Burnable Waste with Oxygen Enrich Incinerator

International Nuclear Information System (INIS)

Min, B. Y.; Yang, D. S.; Lee, K. W.; Choi, J. W.

2016-01-01

The incineration technology is an effective treatment method that contains hazardous chemicals as well as radioactive contamination. The volume reduction of the combustible wastes through the incineration technologies has merits from the view point of a decrease in the amount of waste to be disposed of resulting in a reduction of the disposal cost. Incineration is generally accepted as a method of reducing the volume of radioactive waste. The incineration technology is an effective treatment method that contains hazardous chemicals as well as radioactive contamination. This paper covers the general facility operation of an oxygen-enriched incinerator for the treatment of decommissioning wastes generated from a decommissioning project. The combustible wastes have been treated by the utilization of incinerator the capacity of the average 20 kg/hr. The decommissioning combustible waste of about 31 tons has been treated using Oxygen Enriched incinerator by at the end of 2016. The off-gas flow and temperature were maintained constant or within the desired range. The measured gases and particulate materials in the stack were considerably below the regulatory limits.

Volume Reduction of Decommissioning Burnable Waste with Oxygen Enrich Incinerator

Energy Technology Data Exchange (ETDEWEB)

Min, B. Y.; Yang, D. S.; Lee, K. W.; Choi, J. W. [KAERI, Daejeon (Korea, Republic of)

2016-05-15

The incineration technology is an effective treatment method that contains hazardous chemicals as well as radioactive contamination. The volume reduction of the combustible wastes through the incineration technologies has merits from the view point of a decrease in the amount of waste to be disposed of resulting in a reduction of the disposal cost. Incineration is generally accepted as a method of reducing the volume of radioactive waste. The incineration technology is an effective treatment method that contains hazardous chemicals as well as radioactive contamination. This paper covers the general facility operation of an oxygen-enriched incinerator for the treatment of decommissioning wastes generated from a decommissioning project. The combustible wastes have been treated by the utilization of incinerator the capacity of the average 20 kg/hr. The decommissioning combustible waste of about 31 tons has been treated using Oxygen Enriched incinerator by at the end of 2016. The off-gas flow and temperature were maintained constant or within the desired range. The measured gases and particulate materials in the stack were considerably below the regulatory limits.

An overview on characterization, utilization and leachate analysis of biomedical waste incinerator ash.

Science.gov (United States)

Rajor, Anita; Xaxa, Monika; Mehta, Ratika; Kunal

2012-10-15

Solid waste management is one of the major global environmental issues, as there is continuous increase in industrial globalization and generation of waste. Solid wastes encompass the heterogeneous mass of throwaways from the urban community as well as the homogeneous accumulations of agricultural, industrial and mineral wastes. Biomedical waste pose a significant impact on health and environment. A proper waste management system should be required to dispose hazardous biomedical waste and incineration should be the best available technology to reduce the volume of this hazardous waste. The incineration process destroys pathogens and reduces the waste volume and weight but leaves a solid material called biomedical waste ash as residue which increases the levels of heavy metals, inorganic salts and organic compounds in the environment. Disposal of biomedical waste ash in landfill may cause contamination of groundwater as metals are not destroyed during incineration. The limited space and the high cost for land disposal led to the development of recycling technologies and the reuse of ash in different systems. In order to minimize leaching of its hazardous components into the environment several studies confirmed the successful utilization of biomedical waste ash in agriculture and construction sector. This paper presents the overview on the beneficial use of ash in agriculture and construction materials and its leachate characteristics. This review also stressed on the need to further evaluate the leachate studies of the ashes and slag for their proper disposal and utilization. Copyright © 2012 Elsevier Ltd. All rights reserved.

Greater-than-Class C low-level radioactive waste characterization: Estimated volumes, radionuclide activities, and other characteristics. Revision 1

Energy Technology Data Exchange (ETDEWEB)

1994-09-01

The Department of Energy`s (DOE`s) planning for the disposal of greater-than-Class C low-level radioactive waste (GTCC LLW) requires characterization of the waste. This report estimates volumes, radionuclide activities, and waste forms of GTCC LLW to the year 2035. It groups the waste into four categories, representative of the type of generator or holder of the waste: Nuclear Utilities, Sealed Sources, DOE-Held, and Other Generator. GTCC LLW includes activated metals (activation hardware from reactor operation and decommissioning), process wastes (i.e., resins, filters, etc.), sealed sources, and other wastes routinely generated by users of radioactive material. Estimates reflect the possible effect that packaging and concentration averaging may have on the total volume of GTCC LLW. Possible GTCC mixed LLW is also addressed. Nuclear utilities will probably generate the largest future volume of GTCC LLW with 65--83% of the total volume. The other generators will generate 17--23% of the waste volume, while GTCC sealed sources are expected to contribute 1--12%. A legal review of DOE`s obligations indicates that the current DOE-Held wastes described in this report will not require management as GTCC LLW because of the contractual circumstances under which they were accepted for storage. This report concludes that the volume of GTCC LLW should not pose a significant management problem from a scientific or technical standpoint. The projected volume is small enough to indicate that a dedicated GTCC LLW disposal facility may not be justified. Instead, co-disposal with other waste types is being considered as an option.

Greater-than-Class C low-level radioactive waste characterization: Estimated volumes, radionuclide activities, and other characteristics. Revision 1

International Nuclear Information System (INIS)

1994-09-01

The Department of Energy's (DOE's) planning for the disposal of greater-than-Class C low-level radioactive waste (GTCC LLW) requires characterization of the waste. This report estimates volumes, radionuclide activities, and waste forms of GTCC LLW to the year 2035. It groups the waste into four categories, representative of the type of generator or holder of the waste: Nuclear Utilities, Sealed Sources, DOE-Held, and Other Generator. GTCC LLW includes activated metals (activation hardware from reactor operation and decommissioning), process wastes (i.e., resins, filters, etc.), sealed sources, and other wastes routinely generated by users of radioactive material. Estimates reflect the possible effect that packaging and concentration averaging may have on the total volume of GTCC LLW. Possible GTCC mixed LLW is also addressed. Nuclear utilities will probably generate the largest future volume of GTCC LLW with 65--83% of the total volume. The other generators will generate 17--23% of the waste volume, while GTCC sealed sources are expected to contribute 1--12%. A legal review of DOE's obligations indicates that the current DOE-Held wastes described in this report will not require management as GTCC LLW because of the contractual circumstances under which they were accepted for storage. This report concludes that the volume of GTCC LLW should not pose a significant management problem from a scientific or technical standpoint. The projected volume is small enough to indicate that a dedicated GTCC LLW disposal facility may not be justified. Instead, co-disposal with other waste types is being considered as an option

The volume reduction of low-activity solid wastes. Report of a panel

International Nuclear Information System (INIS)

Pradel, J.; Parsons, P.J.; Malasek, E.

1970-01-01

The accumulation of large volumes of low-level solid radioactive wastes is a matter of concern to waste management authorities, particularly when the wastes are produced close to urban areas. Some of the older and larger nuclear establishments are situated in relatively sparsely populated regions where the problem of dealing with such wastes can even be solved on-site, usually by burial, with little or no pre-treatment. This is the most economical solution. Now, however, increasing amounts of wastes are being produced in more populated areas, and local storage can constitute a hindrance to urban development. It is therefore often necessary to transport the wastes elsewhere; to effect this economically the volume and, if possible, the weight must be reduced, so that the wastes can be transported in regulation packages. The present report is concerned with the methods by which this can be achieved for a large variety of solid materials that accrue as radioactive wastes. It has been compiled largely from information and experience gained at major establishments dealing with large quantities of waste, but articular attention has been paid to the interests of the waste management specialists working at smaller nuclear centres. The manual supplements the guides which have already appeared in IAEA publications series and have dealt with some specific aspect of waste management and, like them, it is oriented in the operational rather than the research direction

Volume reduction of dry active waste by use of a waste sorting table at the Brunswick nuclear power plant

International Nuclear Information System (INIS)

Snead, P.B.

1988-01-01

Carolina Power and Light Company's Brunswick nuclear power plant has been using a National Nuclear Corporation Model WST-18 Waste Sorting Table to monitor and sort dry active waste for segregating uncontaminated material as a means of low-level waste volume reduction. The WST-18 features 18 large-area, solid scintillation detectors arranged in a 3 x 6 array underneath a sorting/monitoring surface that is shielded from background radiation. An 11-week study at Brunswick showed that the use of the waste sorting table resulted in dramatic improvements in both productivity (man-hours expended per cubic foot of waste processed) and monitoring quality over the previous hand-probe frisking method. Use of the sorting table since the study has confirmed its effectiveness in volume reduction. The waste sorting table paid for its operation in volume reduction savings alone, without accounting for the additional savings from recovering reusable items

Waste minimization handbook, Volume 1

Energy Technology Data Exchange (ETDEWEB)

Boing, L.E.; Coffey, M.J.

1995-12-01

This technical guide presents various methods used by industry to minimize low-level radioactive waste (LLW) generated during decommissioning and decontamination (D and D) activities. Such activities generate significant amounts of LLW during their operations. Waste minimization refers to any measure, procedure, or technique that reduces the amount of waste generated during a specific operation or project. Preventive waste minimization techniques implemented when a project is initiated can significantly reduce waste. Techniques implemented during decontamination activities reduce the cost of decommissioning. The application of waste minimization techniques is not limited to D and D activities; it is also useful during any phase of a facility`s life cycle. This compendium will be supplemented with a second volume of abstracts of hundreds of papers related to minimizing low-level nuclear waste. This second volume is expected to be released in late 1996.

Waste minimization handbook, Volume 1

International Nuclear Information System (INIS)

Boing, L.E.; Coffey, M.J.

1995-12-01

This technical guide presents various methods used by industry to minimize low-level radioactive waste (LLW) generated during decommissioning and decontamination (D and D) activities. Such activities generate significant amounts of LLW during their operations. Waste minimization refers to any measure, procedure, or technique that reduces the amount of waste generated during a specific operation or project. Preventive waste minimization techniques implemented when a project is initiated can significantly reduce waste. Techniques implemented during decontamination activities reduce the cost of decommissioning. The application of waste minimization techniques is not limited to D and D activities; it is also useful during any phase of a facility's life cycle. This compendium will be supplemented with a second volume of abstracts of hundreds of papers related to minimizing low-level nuclear waste. This second volume is expected to be released in late 1996

Waste volume reduction by spray drying

Energy Technology Data Exchange (ETDEWEB)

Toscano, Rodrigo A.; Tello, Clédola C. O. de, E-mail: Rodrigotoscano1@gmail.com, E-mail: tellocc@cdtn.br [Centro de Desenvolvimento da Tecnologia Nuclear (CDTN/CNEN-MG), Belo Horizonte, MG (Brazil)

2017-07-01

The operation of nuclear facilities generates liquid wastes which require treatment to control the chemical compounds and removal of radioactive contaminants. These wastes can come from the cooling of the primary reactor system, from the reactor pool decontamination, washing of contaminated clothing, among others. The ion exchange resin constitutes the largest fraction of this waste, classified as low and intermediate level of radiation. According to CNEN Standard 8.01, the minimization of the volume and activity of the radioactive waste generated in the operation of a nuclear installation, radiative installation, industrial mining installation or radioactive waste deposit should be ensured. In addition, one of the acceptance criteria for wastes in repositories required by CNEN NN 6.09 is that it be solid or solidified. Thus, these wastes must be reduced in volume and solidified to meet the standards and the safety of the population and the environment. The objective of this work is to find a solution that associates the least generation of packaged waste and the acceptance criteria of waste for the deposition in the national repository. This work presents a proposal of reduction of the volume of the liquid wastes generated by nuclear facilities by drying by for reduction of volume for a greater incorporation of wastes in cement. Using spray dryer, an 18% reduction in the production of cemented waste products was observed in relation to the method currently used with compressive strength measurement above the standard, and it is believed that this value may increase in future tests. (author)

Waste volume reduction by spray drying

International Nuclear Information System (INIS)

Toscano, Rodrigo A.; Tello, Clédola C. O. de

2017-01-01

The operation of nuclear facilities generates liquid wastes which require treatment to control the chemical compounds and removal of radioactive contaminants. These wastes can come from the cooling of the primary reactor system, from the reactor pool decontamination, washing of contaminated clothing, among others. The ion exchange resin constitutes the largest fraction of this waste, classified as low and intermediate level of radiation. According to CNEN Standard 8.01, the minimization of the volume and activity of the radioactive waste generated in the operation of a nuclear installation, radiative installation, industrial mining installation or radioactive waste deposit should be ensured. In addition, one of the acceptance criteria for wastes in repositories required by CNEN NN 6.09 is that it be solid or solidified. Thus, these wastes must be reduced in volume and solidified to meet the standards and the safety of the population and the environment. The objective of this work is to find a solution that associates the least generation of packaged waste and the acceptance criteria of waste for the deposition in the national repository. This work presents a proposal of reduction of the volume of the liquid wastes generated by nuclear facilities by drying by for reduction of volume for a greater incorporation of wastes in cement. Using spray dryer, an 18% reduction in the production of cemented waste products was observed in relation to the method currently used with compressive strength measurement above the standard, and it is believed that this value may increase in future tests. (author)

Estimating retained gas volumes in the Hanford tanks using waste level measurements

International Nuclear Information System (INIS)

Whitney, P.D.; Chen, G.; Gauglitz, P.A.; Meyer, P.A.; Miller, N.E.

1997-09-01

The Hanford site is home to 177 large, underground nuclear waste storage tanks. Safety and environmental concerns surround these tanks and their contents. One such concern is the propensity for the waste in these tanks to generate and trap flammable gases. This report focuses on understanding and improving the quality of retained gas volume estimates derived from tank waste level measurements. While direct measurements of gas volume are available for a small number of the Hanford tanks, the increasingly wide availability of tank waste level measurements provides an opportunity for less expensive (than direct gas volume measurement) assessment of gas hazard for the Hanford tanks. Retained gas in the tank waste is inferred from level measurements -- either long-term increase in the tank waste level, or fluctuations in tank waste level with atmospheric pressure changes. This report concentrates on the latter phenomena. As atmospheric pressure increases, the pressure on the gas in the tank waste increases, resulting in a level decrease (as long as the tank waste is open-quotes softclose quotes enough). Tanks with waste levels exhibiting fluctuations inversely correlated with atmospheric pressure fluctuations were catalogued in an earlier study. Additionally, models incorporating ideal-gas law behavior and waste material properties have been proposed. These models explicitly relate the retained gas volume in the tank with the magnitude of the waste level fluctuations, dL/dP. This report describes how these models compare with the tank waste level measurements

Utilization of Wheat Offal-Carried Pineapple Waste in the Diet of ...

African Journals Online (AJOL)

Utilization of Wheat Offal-Carried Pineapple Waste in the Diet of West African Dwarf (WAD) Goats. ... Although, the analysis of blood cells (red blood cell, white blood and packed cell volume counts) were significantly different (p<0.05) among the goats fed experimental diets, the counts fell within the normal physiological ...

Optimization criteria for low temperature waste heat utilization

International Nuclear Information System (INIS)

Kranebitter, F.

1977-01-01

A special case in this field is the utilization of very low temperature waste heat. The temperature level under consideration in this paper is in the range between the body temperature of human beings and their environment. The waste heat from power generation and industrial processes is also considered. Thermal energy conversion will be mainly accomplished by heat cycles where discharged waste heat is reverse proportional to the upper cycle temperature. Limiting this upper cycle temperature by technological reasons the optimization of the heat cycle will depend on the nature of the cycle itself and specially on the temperature selected for the heat discharge. The waste heat discharge is typical for the different kinds of heat cycles and the paper presents the four most important of them. Feasible heat transfer methods and their economic evaluations are discussed and the distillation processes will be the basis for further considerations. The waste heat utilization for distillation purposes could be realized by three different cycles, the open cycle, the closed cycle and the multy cycle. Resulting problems as deaeration of large water streams and removal of the dissolved gases and their solutions are also discussed. (M.S.)

1995 Solid Waste 30-year volume summary

International Nuclear Information System (INIS)

Valero, O.J.; DeForest, T.J.; Templeton, K.J.

1995-06-01

This document, prepared by Pacific Northwest Laboratory (PNL) under the direction of Westinghouse Hanford Company (WHC), provides a description of the annual low-level mixed waste (LLMW) and transuranic/transuranic mixed solid waste (TRU-TRUM) volumes expected to be managed by Hanford's Solid Waste Central Waste Complex (CWC) over the next 30 years. The waste generation sources and waste categories are also described. This document is intended to be used as a reference for short- and long-term planning of the Hanford treatment, storage, and disposal (TSD) activities over the next several decades. By estimating the waste volumes that will be generated in the future, facility planners can determine the timing of key waste management activities, evaluate alternative treatment strategies, and plan storage and disposal capacities. In addition, this document can be used by other waste sites and the general public to gain a better understanding of the types and volumes of waste that will be managed at Hanford

1995 Solid Waste 30-year volume summary

Energy Technology Data Exchange (ETDEWEB)

Valero, O.J. [Westinghouse Hanford Co., Richland, WA (United States); DeForest, T.J.; Templeton, K.J. [Pacific Northwest Lab., Richland, WA (United States)

1995-06-01

This document, prepared by Pacific Northwest Laboratory (PNL) under the direction of Westinghouse Hanford Company (WHC), provides a description of the annual low-level mixed waste (LLMW) and transuranic/transuranic mixed solid waste (TRU-TRUM) volumes expected to be managed by Hanford`s Solid Waste Central Waste Complex (CWC) over the next 30 years. The waste generation sources and waste categories are also described. This document is intended to be used as a reference for short- and long-term planning of the Hanford treatment, storage, and disposal (TSD) activities over the next several decades. By estimating the waste volumes that will be generated in the future, facility planners can determine the timing of key waste management activities, evaluate alternative treatment strategies, and plan storage and disposal capacities. In addition, this document can be used by other waste sites and the general public to gain a better understanding of the types and volumes of waste that will be managed at Hanford.

Waste disposal options report. Volume 2

International Nuclear Information System (INIS)

Russell, N.E.; McDonald, T.G.; Banaee, J.; Barnes, C.M.; Fish, L.W.; Losinski, S.J.; Peterson, H.K.; Sterbentz, J.W.; Wenzel, D.R.

1998-02-01

Volume 2 contains the following topical sections: estimates of feed and waste volumes, compositions, and properties; evaluation of radionuclide inventory for Zr calcine; evaluation of radionuclide inventory for Al calcine; determination of k eff for high level waste canisters in various configurations; review of ceramic silicone foam for radioactive waste disposal; epoxides for low-level radioactive waste disposal; evaluation of several neutralization cases in processing calcine and sodium-bearing waste; background information for EFEs, dose rates, watts/canister, and PE-curies; waste disposal options assumptions; update of radiation field definition and thermal generation rates for calcine process packages of various geometries-HKP-26-97; and standard criteria of candidate repositories and environmental regulations for the treatment and disposal of ICPP radioactive mixed wastes

Waste disposal options report. Volume 2

Energy Technology Data Exchange (ETDEWEB)

Russell, N.E.; McDonald, T.G.; Banaee, J.; Barnes, C.M.; Fish, L.W.; Losinski, S.J.; Peterson, H.K.; Sterbentz, J.W.; Wenzel, D.R.

1998-02-01

Volume 2 contains the following topical sections: estimates of feed and waste volumes, compositions, and properties; evaluation of radionuclide inventory for Zr calcine; evaluation of radionuclide inventory for Al calcine; determination of k{sub eff} for high level waste canisters in various configurations; review of ceramic silicone foam for radioactive waste disposal; epoxides for low-level radioactive waste disposal; evaluation of several neutralization cases in processing calcine and sodium-bearing waste; background information for EFEs, dose rates, watts/canister, and PE-curies; waste disposal options assumptions; update of radiation field definition and thermal generation rates for calcine process packages of various geometries-HKP-26-97; and standard criteria of candidate repositories and environmental regulations for the treatment and disposal of ICPP radioactive mixed wastes.

Waste isolation in the U.S., technical programs and public education. Volume 2 - low level waste, volume reduction methodologies and economics. Vol. 2

International Nuclear Information System (INIS)

Post, R.G.

1984-01-01

This volume presents information regarding low-level waste, volume reduction methodologies and economics. Topics include: public education on nuclear waste; economics of low-level waste management systems; operating experience with advanced volume reduction techniques; solidification of waste; operating experience with advanced volume reduction techniques--incineration; regional plans for the disposal of low-level waste; radwaste system modifications at nuclear power plants; operating experience with advanced volume reduction techniques--operations and on-site storage issues; and economic impact of 10CFR61

Solid waste 30-year volume summary

International Nuclear Information System (INIS)

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

1994-06-01

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

1994 Solid waste forecast container volume summary

International Nuclear Information System (INIS)

Templeton, K.J.; Clary, J.L.

1994-09-01

This report describes a 30-year forecast of the solid waste volumes by container type. The volumes described are low-level mixed waste (LLMW) and transuranic/transuranic mixed (TRU/TRUM) waste. These volumes and their associated container types will be generated or received at the US Department of Energy Hanford Site for storage, treatment, and disposal at Westinghouse Hanford Company's Solid Waste Operations Complex (SWOC) during a 30-year period from FY 1994 through FY 2023. The forecast data for the 30-year period indicates that approximately 307,150 m 3 of LLMW and TRU/TRUM waste will be managed by the SWOC. The main container type for this waste is 55-gallon drums, which will be used to ship 36% of the LLMW and TRU/TRUM waste. The main waste generator forecasting the use of 55-gallon drums is Past Practice Remediation. This waste will be generated by the Environmental Restoration Program during remediation of Hanford's past practice sites. Although Past Practice Remediation is the primary generator of 55-gallon drums, most waste generators are planning to ship some percentage of their waste in 55-gallon drums. Long-length equipment containers (LECs) are forecasted to contain 32% of the LLMW and TRU/TRUM waste. The main waste generator forecasting the use of LECs is the Long-Length Equipment waste generator, which is responsible for retrieving contaminated long-length equipment from the tank farms. Boxes are forecasted to contain 21% of the waste. These containers are primarily forecasted for use by the Environmental Restoration Operations--D ampersand D of Surplus Facilities waste generator. This waste generator is responsible for the solid waste generated during decontamination and decommissioning (D ampersand D) of the facilities currently on the Surplus Facilities Program Plan. The remaining LLMW and TRU/TRUM waste volume is planned to be shipped in casks and other miscellaneous containers

Positive utilization of waste materials from mines and quarries

International Nuclear Information System (INIS)

Blunden, J.R.

1980-01-01

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

Technical Performance Capability of Fourier Transform Profilometry for Quantitative Waste Volume Determination under Hanford Waste Tank Condition

International Nuclear Information System (INIS)

Monts, D.L.; Jang, P.R.; Long, Z.; Norton, O.P.; Okhuysen, W.P.; Su, Y.; Waggoner, Ch.A.

2009-01-01

The Hanford Site is currently in the process of an extensive effort to empty and close its radioactive single-shell and double-shell waste storage tanks. Before this can be accomplished, it is necessary to know how much residual material is left in a given waste tank and the chemical makeup of the residue. The Institute for Clean Energy Technology (ICET) at Mississippi State University is currently developing a quantitative in-tank inspection system based on Fourier Transform Profilometry (FTP). FTP is a non-contact, 3-D shape measurement technique. By projecting a fringe pattern onto a target surface and observing its deformation due to surface irregularities from a different view angle, FTP is capable of determining the height (depth) distribution (and hence volume distribution) of the target surface, thus reproducing the profile of the target accurately under a wide variety of conditions. Hence FTP has the potential to be utilized for quantitative determination of residual wastes within Hanford waste tanks. We report the results of a technical feasibility study to document the accuracy and precision of quantitative volume determination using the Fourier transform profilometry technique under simulated Hanford waste tank conditions. (authors)

Methodology for generating waste volume estimates

International Nuclear Information System (INIS)

Miller, J.Q.; Hale, T.; Miller, D.

1991-09-01

This document describes the methodology that will be used to calculate waste volume estimates for site characterization and remedial design/remedial action activities at each of the DOE Field Office, Oak Ridge (DOE-OR) facilities. This standardized methodology is designed to ensure consistency in waste estimating across the various sites and organizations that are involved in environmental restoration activities. The criteria and assumptions that are provided for generating these waste estimates will be implemented across all DOE-OR facilities and are subject to change based on comments received and actual waste volumes measured during future sampling and remediation activities. 7 figs., 8 tabs

Glass Property Data and Models for Estimating High-Level Waste Glass Volume

Energy Technology Data Exchange (ETDEWEB)

Vienna, John D.; Fluegel, Alexander; Kim, Dong-Sang; Hrma, Pavel R.

2009-10-05

This report describes recent efforts to develop glass property models that can be used to help estimate the volume of high-level waste (HLW) glass that will result from vitrification of Hanford tank waste. The compositions of acceptable and processable HLW glasses need to be optimized to minimize the waste-form volume and, hence, to save cost. A database of properties and associated compositions for simulated waste glasses was collected for developing property-composition models. This database, although not comprehensive, represents a large fraction of data on waste-glass compositions and properties that were available at the time of this report. Glass property-composition models were fit to subsets of the database for several key glass properties. These models apply to a significantly broader composition space than those previously publised. These models should be considered for interim use in calculating properties of Hanford waste glasses.

Glass Property Data and Models for Estimating High-Level Waste Glass Volume

International Nuclear Information System (INIS)

Vienna, John D.; Fluegel, Alexander; Kim, Dong-Sang; Hrma, Pavel R.

2009-01-01

This report describes recent efforts to develop glass property models that can be used to help estimate the volume of high-level waste (HLW) glass that will result from vitrification of Hanford tank waste. The compositions of acceptable and processable HLW glasses need to be optimized to minimize the waste-form volume and, hence, to save cost. A database of properties and associated compositions for simulated waste glasses was collected for developing property-composition models. This database, although not comprehensive, represents a large fraction of data on waste-glass compositions and properties that were available at the time of this report. Glass property-composition models were fit to subsets of the database for several key glass properties. These models apply to a significantly broader composition space than those previously publised. These models should be considered for interim use in calculating properties of Hanford waste glasses.

Current radioactive waste utilization at PA 'MAYAK'

International Nuclear Information System (INIS)

Merkushkin, A.O.

2001-01-01

The Production Association 'Mayak' is one of the largest production union of Nuclear Fuel Cycle (NFC) in Russia. In 1988 the last military reactor, which worked for making military plutonium was stopped. From this time civic history of 'Mayak' was began. Today 'Mayak' is the complex production union of NFC, which utilizes the Radiated Nuclear Fuel (RNF). The combine is dynamically develops, new technologies are domesticate and intrude, large works for liquidation of accidents and mistakes of lapsed years are in progress. The short review of radioactive waste utilization methods is present in this account. (author)

Current radioactive waste utilization at PA 'MAYAK'

Energy Technology Data Exchange (ETDEWEB)

Merkushkin, A O [Ozyorsk Technological Institute of Moscow Physical Engineering Institute (Russian Federation)

2001-07-01

The Production Association 'Mayak' is one of the largest production union of Nuclear Fuel Cycle (NFC) in Russia. In 1988 the last military reactor, which worked for making military plutonium was stopped. From this time civic history of 'Mayak' was began. Today 'Mayak' is the complex production union of NFC, which utilizes the Radiated Nuclear Fuel (RNF). The combine is dynamically develops, new technologies are domesticate and intrude, large works for liquidation of accidents and mistakes of lapsed years are in progress. The short review of radioactive waste utilization methods is present in this account. (author)

Utilities and offsites design baseline. Outside Battery Limits Facility 6000 tpd SRC-I Demonstration Plant. Volume 1

Energy Technology Data Exchange (ETDEWEB)

None

1984-05-25

As part of the overall Solvent Refined Coal (SRC-1) project baseline being prepared by International Coal Refining Company (ICRC), the RUST Engineering Company is providing necessary input for the Outside Battery Limits (OSBL) Facilities. The project baseline is comprised of: design baseline - technical definition of work; schedule baseline - detailed and management level 1 schedules; and cost baseline - estimates and cost/manpower plan. The design baseline (technical definition) for the OSBL Facilities has been completed and is presented in Volumes I, II, III, IV, V and VI. The OSBL technical definition is based on, and compatible with, the ICRC defined statement of work, design basis memorandum, master project procedures, process and mechanical design criteria, and baseline guidance documents. The design basis memorandum is included in Paragraph 1.3 of Volume I. The baseline design data is presented in 6 volumes. Volume I contains the introduction section and utility systems data through steam and feedwater. Volume II continues with utility systems data through fuel system, and contains the interconnecting systems and utility system integration information. Volume III contains the offsites data through water and waste treatment. Volume IV continues with offsites data, including site development and buildings, and contains raw materials and product handling and storage information. Volume V contains wastewater treatment and solid wastes landfill systems developed by Catalytic, Inc. to supplement the information contained in Volume III. Volume VI contains proprietary information of Resources Conservation Company related to the evaporator/crystallizer system of the wastewater treatment area.

Economic evaluation of volume reduction for Defense transuranic waste

International Nuclear Information System (INIS)

Brown, C.M.

1982-03-01

The economics of volume reduction of retrievably stored and newly generated DOE transuranic wastes are evaluated by comparing the costs of reduction of the wastes with the savings possible in transportation and disposal. A general approach to the comparison of TRU waste volume reduction costs and cost savings is developed, an initial set of cost data is established, conclusions to support selecting technologies and facilities for the disposal of DOE transuranic waste are developed. Section I outlines the analysis which considers seven types of volume reduction from incineration and compaction of combustibles to compaction, size reduction, shredding, melting, and decontamination of metals. The study considers the volume reduction of contact-handled, newly generated and retrievably stored DOE transuranic wastes. Section II of this report describes the analytical approach, assumptions, and flow of waste material through sites. Section III presents the waste inventories, disposal and transportation savings, and volume reduction techniques and costs. Section IV contains the results and conclusions of the study. The major conclusions drawn from the study are: For DOE sites with a small amount of waste requiring disposal ( 3 /year) the cost of volume reduction is greater than the transportation and disposal savings from volume reduction provided the waste requires little additional preparation to meet transportation and disposal criteria. Wastes that do not meet these criteria require site specific economic analysis outside the general evaluations of this study. For Idaho National Engineering Laboratory, incineration and metal shredding are cost-effective, provided a facility is to be constructed as a consequence of repackaging the fraction of stored waste which may require repackaging and immobilizing chemical process waste to meet disposal criteria

A State-of-the-Art Report on Technologies of Volume Reduction and Self-Disposal for Large Metal Wastes including the Steam Generator of Nuclear Power Plants

International Nuclear Information System (INIS)

Lee, Kune Woo; Choi, W. K.; Kim, G. Y.

2009-06-01

This report focuses on technologies of volume reduction and self-disposal for large metal wastes including the steam generator of nuclear power plants. This report consists of the cases of treatments and foreign and domestic technologies for steam generator replacement

Characterization of radioactive waste forms. Volume 1

International Nuclear Information System (INIS)

Brodersen, K.; Nilsson, K.

1989-01-01

This document is the second yearbook for Task 3 of the European Communities 1985-89 programme of research on radioactive waste management and disposal carried out by public organizations and private firms in the Community through costsharing contracts with the Commission of the European Communities. The report, in two volumes, describes progress made in 1987 within the field of Task 3: Testing and evaluation of conditioned waste and engineered barriers. The first volume of the report covers Item 3.1 Characterization of low and medium-level radioactive waste forms and Item 3.5 Development of test methods for quality assurance. The second volume covers Item 3.2: High-level and alpha waste characterization and Item 3.3: Other engineered barriers. Item 3.4 on the round robin study will be treated in a separate report

Volume reduction of radioactive concrete waste generated from KRR-2 and UCP

International Nuclear Information System (INIS)

Min, B. Y.; Choi, W. K.; Park, J. W.; Lee, K. W.

2009-01-01

As a part of a technical development for the volume reduction and stabilization of contaminated concrete wastes generated by dismantling a research reactor and uranium conversion plant, we have developed the volume reduction technology and immobilization of fine powder applicable to an activated heavy weight concrete generated by dismantling KRR-2 and a uranium contaminated light weight concrete produced from a UCP decommissioning. During a decommissioning of nuclear plants and facilities, large quantities of contaminated concrete wastes are generated. The decommissioning of the retired TRIGA MARK II and III research reactors and a uranium conversion plant has been under way. In Korea, two decommissioning projects such as the decommissioning of the retired research reactors (KRR-1 and 2) and a uranium conversion plant (UCP) at the Korea Atomic Energy Research Institute (KAERI) has been carried out. By dismantling KRR-2, more than 260 tons of radioactive concrete wastes are generated among the total 2,000 tons of concrete wastes and more than 60 tons of concrete wastes contaminated with uranium compounds are generated in UCP decommissioning up to now. The volume reduction and recycling of the wastes is essential to reduce the waste management cost with expecting that an approximate disposal cost for low level radioactive waste will be more than 5,000 US dollars per 200 liter waste drum in Korea. It is well known that most of the radioactivity exist in cement mortar and paste composed of concrete. In this context, the volume reduction of concrete waste is based on the separation of radioactive concrete into a clean recyclable aggregates and a radioactive fine cement powder, which can be readily performed by heating to weaken the adherence force between the cement matrix and the aggregates followed by mechanical crushing and milling processes. In this study, we have investigated the characteristics of separation of aggregates and the distribution of radioactivity into

Waste volume reduction by acid digestion

International Nuclear Information System (INIS)

Lerch, R.E.; Divine, J.R.

1975-06-01

Acid digestion is a process being developed at the Hanford Engineering Development Laboratory (HEDL) in Richland, Washington, to reduce the volume of alpha-contaminated combustible waste by converting it into a non-combustible residue. Typical waste materials such as polyvinylchloride (PVC), polyethylene, paper and other cellulosic materials, ion exchange resin, all types of rubber, etc., are digested in hot (230 0 C--270 0 C) concentrated sulfuric acid containing nitric acid oxidant to form inert residues generally having less than four percent of their original volume and less than twenty-five percent of their original mass. The process is currently being tested using non-radioactive waste in an Acid Digestion Test Unit (ADTU) with all glass equipment. Engineering tests to date have shown acid digestion to be a potentially attractive method for treating combustible waste materials. Based on results of the engineering tests, an acid digestion pilot unit capable of treating radioactive wastes is being designed and constructed. Design capacity of the pilot unit for radioactive waste will be 100 kg of waste per day. (U.S.)

Characterization of radioactive waste forms. Volume 2

International Nuclear Information System (INIS)

Smith, D.L.; Green, T.H.

1989-01-01

This document is the second yearbook for Task 3 of the European Communities 1985-89 programme of research on radioactive waste management and disposal carried out by public organizations and private firms in the Community through cost-sharing contracts with the Commission of the European Communities. The report, in two volumes, describes progress made in 1987 within the field of Task 3: Testing and evaluation of conditioned waste and engineered barriers. The first volume of the report covers Item 3.1 Characterization of low and medium level radioactive waste forms and Item 3.5. Development of test methods for quality assurance. The second volume covers Item 3.2: High-level and alpha waste characterization and Item 3.3: Other engineered barriers. Item 3.4 on the round robin study will be treated in a separate report

On-site vs off-site management of environmental restoration waste: A cost effectiveness analysis

International Nuclear Information System (INIS)

Morse, M.A.; Aamodt, P.L.; Cox, W.B.

1996-01-01

The Sandia National Laboratories Environmental Restoration Project is expected to generate relatively large volumes of hazardous waste as a result of cleanup operations. These volumes will exceed the Laboratories existing waste management capacity. This paper presents four options for managing remediation wastes, including three alternatives for on-site waste management utilizing a corrective action management unit (CAMU). Costs are estimated for each of the four options based on current volumetric estimates of hazardous waste. Cost equations are derived for each of the options with the variables being waste volumes, the major unknowns in the analysis. These equations provide a means to update cost estimates as volume estimates change. This approach may be helpful to others facing similar waste management decisions

Industrial waste heat utilization for low temperature district heating

International Nuclear Information System (INIS)

Fang, Hao; Xia, Jianjun; Zhu, Kan; Su, Yingbo; Jiang, Yi

2013-01-01

Large quantities of low grade waste heat are discharged into the environment, mostly via water evaporation, during industrial processes. Putting this industrial waste heat to productive use can reduce fossil fuel usage as well as CO 2 emissions and water dissipation. The purpose of this paper is to propose a holistic approach to the integrated and efficient utilization of low-grade industrial waste heat. Recovering industrial waste heat for use in district heating (DH) can increase the efficiency of the industrial sector and the DH system, in a cost-efficient way defined by the index of investment vs. carbon reduction (ICR). Furthermore, low temperature DH network greatly benefits the recovery rate of industrial waste heat. Based on data analysis and in-situ investigations, this paper discusses the potential for the implementation of such an approach in northern China, where conventional heat sources for DH are insufficient. The universal design approach to industrial-waste-heat based DH is proposed. Through a demonstration project, this approach is introduced in detail. This study finds three advantages to this approach: (1) improvement of the thermal energy efficiency of industrial factories; (2) more cost-efficient than the traditional heating mode; and (3) CO 2 and pollutant emission reduction as well as water conservation. -- Highlights: •We review situation of industrial waste heat recovery with a global perspective. •We present a way to analyze the potential to utilize industrial waste heat for DH. •Northern China has huge potential for using low-grade industrial waste heat for DH. •A demonstration project is introduced using the universal approach we propose. •It proves huge benefits for factories, heat-supply companies and the society

Volume reduction and solidification of radioactive waste incineration ash with waste glass

International Nuclear Information System (INIS)

Koyama, Hidemi; Kobayashi, Masayuki

2007-01-01

The low-level radioactive waste generated from research institutions and hospitals etc. is packed into a container and is kept. The volume reduced state or the unprocessed state by incineration or compression processing are used because neither landfill sites nor disposal methods have been fixed. Especially, because the bulk density is low, and it is easy to disperse, the low-level radioactive waste incineration ash incinerated for the volume reduction is a big issue in security, safety, stability in the inventory location. A safe and appropriate disposal processing method is desired. When the low temperature sintering method in the use of the glass bottle cullet was examined, volume reduction and stabilization of low-level radioactive waste incineration ash were verified. The proposed method is useful for the easy treatment of the low-level radioactive waste incineration ash. (author)

New municipal solid waste processing technology reduces volume and provides beneficial reuse applications for soil improvement and dust control

Science.gov (United States)

A garbage-processing technology has been developed that shreds, sterilizes, and separates inorganic and organic components of municipal solid waste. The technology not only greatly reduces waste volume, but the non-composted byproduct of this process, Fluff®, has the potential to be utilized as a s...

Department of Energy plan for recovery and utilization of nuclear byproducts from defense wastes. Volume 2

Energy Technology Data Exchange (ETDEWEB)

1983-08-01

Nuclear wastes from the defense production cycle contain many uniquely useful, intrinsically valuable, and strategically important materials. These materials have a wide range of known and potential applications in food technology, agriculture, energy, public health, medicine, industrial technology, and national security. Furthermore, their removal from the nuclear waste stream can facilitate waste management and yield economic, safety, and environmental advantages in the management and disposal of the residual nuclear wastes that have no redemptive value. This document is the program plan for implementing the recovery and beneficial use of these valuable materials. An Executive Summary of this document, DOE/DP-0013, Vol. 1, January 1983, is available. Program policy, goals and strategy are stated in Section 2. Implementation tasks, schedule and funding are detailed in Section 3. The remaining five sections and the appendixes provide necessary background information to support these two sections. Section 4 reviews some of the unique properties of the individual byproduct materials and describes both demonstrated and potential applications. The amounts of byproduct materials that are available now for research and demonstration purposes, and the amounts that could be recovered in the future for expanded applications are detailed in Section 5. Section 6 describes the effects byproduct recovery and utilization have on the management and final disposal of nuclear wastes. The institutional issues that affect the recovery, processing and utilization of nuclear byproducts are discussed in Section 7. Finally, Section 8 presents a generalized mathematical process by which applications can be evaluated and prioritized (rank-ordered) to provide planning data for program management.

Department of Energy plan for recovery and utilization of nuclear byproducts from defense wastes. Volume 2

International Nuclear Information System (INIS)

1983-08-01

Nuclear wastes from the defense production cycle contain many uniquely useful, intrinsically valuable, and strategically important materials. These materials have a wide range of known and potential applications in food technology, agriculture, energy, public health, medicine, industrial technology, and national security. Furthermore, their removal from the nuclear waste stream can facilitate waste management and yield economic, safety, and environmental advantages in the management and disposal of the residual nuclear wastes that have no redemptive value. This document is the program plan for implementing the recovery and beneficial use of these valuable materials. An Executive Summary of this document, DOE/DP-0013, Vol. 1, January 1983, is available. Program policy, goals and strategy are stated in Section 2. Implementation tasks, schedule and funding are detailed in Section 3. The remaining five sections and the appendixes provide necessary background information to support these two sections. Section 4 reviews some of the unique properties of the individual byproduct materials and describes both demonstrated and potential applications. The amounts of byproduct materials that are available now for research and demonstration purposes, and the amounts that could be recovered in the future for expanded applications are detailed in Section 5. Section 6 describes the effects byproduct recovery and utilization have on the management and final disposal of nuclear wastes. The institutional issues that affect the recovery, processing and utilization of nuclear byproducts are discussed in Section 7. Finally, Section 8 presents a generalized mathematical process by which applications can be evaluated and prioritized (rank-ordered) to provide planning data for program management

Volume reduction options for the management of low-level radioactive wastes

International Nuclear Information System (INIS)

Clark, D.E.; Lerch, R.E.

1979-01-01

Volume reduction options that are now or soon will be available for low-level wastes are examined. These wastes generally are in the form of combustible solids, noncombustible solids, and wet wastes (solid/liquid). Initially, the wastes are collected and stored onsite. Preconditioning may be required, e.g., sorting, shredding, and classifying the solids into combustible and noncombustible fractions. The volume of combustible solids can be reduced by compaction, incineration/pyrolysis, acid digestion, or molten salt combustion. Options for reducing the volume of noncombustible solids include compaction, size reduction and decontamination, meltdown-casting, dissolution and electropolishing. Burnable wet wastes (e.g., organic wastes) can be evaporated or combusted; nonburnable wet wastes can be treated by various evaporative or nonevaporative processes. All radioactive waste processing operations result in some equipment contamination and the production of additional radioactively contaminated wastes (secondary wastes). The additional waste quantities must be considered in evaluating performance and overall volume reduction factors for the various systems. In the selection of an optimum waste management plan for a given facility, other important factors (e.g., relative stability of the waste product form) should be considered along with the savings accrued due to volume reduction

30 CFR 817.87 - Coal mine waste: Burning and burned waste utilization.

Science.gov (United States)

2010-07-01

... 30 Mineral Resources 3 2010-07-01 2010-07-01 false Coal mine waste: Burning and burned waste...-UNDERGROUND MINING ACTIVITIES § 817.87 Coal mine waste: Burning and burned waste utilization. (a) Coal mine... extinguishing operations. (b) No burning or unburned coal mine waste shall be removed from a permitted disposal...

30 CFR 816.87 - Coal mine waste: Burning and burned waste utilization.

Science.gov (United States)

2010-07-01

... 30 Mineral Resources 3 2010-07-01 2010-07-01 false Coal mine waste: Burning and burned waste...-SURFACE MINING ACTIVITIES § 816.87 Coal mine waste: Burning and burned waste utilization. (a) Coal mine... extinguishing operations. (b) No burning or burned coal mine waste shall be removed from a permitted disposal...

Quantitative feasibility study of magnetocaloric energy conversion utilizing industrial waste heat

International Nuclear Information System (INIS)

Vuarnoz, D.; Kitanovski, A.; Gonin, C.; Borgeaud, Y.; Delessert, M.; Meinen, M.; Egolf, P.W.

2012-01-01

Highlights: ► We model magnetic energy conversion machine for the use of industrial waste heat. ► Efficiencies and masses of the system are evaluated by a numerical model. ► Excellent potential of profitability is expected with large low-exergy heat sources. -- Abstract: The main objective of this theoretical study was to investigate under which conditions a magnetic energy conversion device (MECD) – utilizing industrial waste heat – is economically feasible. Furthermore, it was evaluated if magnetic energy conversion (MCE) has the potential of being a serious concurrent to already existing conventional energy conversion technologies. Up-today the availability of magnetocaloric materials with a high Curie temperature and a high magnetocaloric effect is rather limited. Therefore, this study was mainly focused on applications with heat sources of low to medium temperature levels. Magnetic energy conversion machines, containing permanent magnets, are numerically investigated for operation conditions with different temperature levels, defined by industrial waste heat sources and environmental heat sinks, different magnetic field intensities and different frequencies of operation (number of thermodynamic cycles per unit of time). Theoretical modeling and numerical simulations were performed in order to determine thermodynamic efficiencies and the exergy efficiencies as function of different operation conditions. From extracted data of our numerical results, approximate values of the total mass and total volume of magnetic energy conversion machines could be determined. These important results are presented dependent on the produced electric power. An economic feasibility study supplements the scientific study. It shows an excellent potential of profitability for certain machines. The most important result of this article is that the magnetic energy conversion technology can be economically and technically competitive to or even beat conventional energy

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

International Nuclear Information System (INIS)

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

1998-07-01

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

Sea water desalination utilizing waste heat by low temperature evaporation

International Nuclear Information System (INIS)

Raha, A.; Srivastava, A.; Rao, I.S.; Majumdar, M.; Srivastava, V.K.; Tewari, P.K.

2007-01-01

Economics of a process is controlled by management of energy and resources. Fresh water has become most valued resource in industries. Desalination is a process by which fresh water resource is generated from sea water or brackish water, but it is an energy intensive process. The energy cost contributes around 25-40% to the total cost of the desalted water. Utilization of waste heat from industrial streams is one of the ecofriendly ways to produce low cost desalted water. Keeping this in mind Low Temperature Evaporation (LTE) desalination technology utilizing low quality waste heat in the form of hot water (as low as 50 deg C) or low pressure steam (0.13 bar) has been developed for offshore and land based applications to produce high purity water (conductivity < 2μS/cm) from sea water. The probability of the scale formation is practically eliminated by operating it at low temperature and controlling the brine concentration. It also does not require elaborate chemical pretreatment of sea water except chlorination, so it has no environmental impact. LTE technology has found major applications in nuclear reactors where large quantity of low quality waste heat is available to produce high quality desalted water for make up water requirement replacing conventional ion exchange process. Successful continuous operation of 30 Te/day LTE desalination plant utilizing waste heat from nuclear research reactor has demonstrated the safety, reliability, extreme plant availability and economics of nuclear desalination by LTE technology. It is also proposed to utilize waste heat from Main Heat Transport (MHT) purification circuit of Advanced Heavy Water Reactor (AHWR) to produce about 250 Te/ day high quality desalinated water by Low Temperature Evaporation (LTE) process for the reactor make up and plant utilization. Recently we have commissioned a 50 Te/day 2-effect low temperature desalination plant with cooling tower where the specific energy and cooling water requirement are

Low-level waste volume reduction--physicochemical systems

International Nuclear Information System (INIS)

Ferrigno, D.P.

1980-01-01

In some cases, volume reduction (VR) equipment may be called upon to reduce noncombustible liquid wastes to essentially dry salts and/or oxides. In other cases, it may be called upon to reduce combustible solids and liquids to ashes and innocuous gases. In brand terms, four kinds of processes are available to further reduce the volume of waste generated at nuclear facilities. These include high-solids evaporation, alternative evaporative designs, extruders/mixers, and calciner/incinerators. This paper discusses the following VR processes for radioactive wastes at nuclear facilities: evaporator/crystallizer; fluid bed dryer/incinerator; fluid bed calciner/incinerator; inert carrier radwaste processor; and molten glass incinerator

Evaluation of fourier transform profilometry performance: quantitative waste volume determination under simulated Hanford waste tank conditions

International Nuclear Information System (INIS)

Jang, Ping-Rey; Leone, Teresa; Long, Zhiling; Mott, Melissa A.; Perry Norton, O.; Okhuysen, Walter P.; Monts, David L.

2007-01-01

The Hanford Site is currently in the process of an extensive effort to empty and close its radioactive single-shell and double-shell waste storage tanks. Before this can be accomplished, it is necessary to know how much residual material is left in a given waste tank and the chemical makeup of the residue. The objective of Mississippi State University's Institute for Clean Energy Technology's (ICET) efforts is to develop, fabricate, and deploy inspection tools for the Hanford waste tanks that will (1) be remotely operable; (2) provide quantitative information on the amount of wastes remaining; and (3) provide information on the spatial distribution of chemical and radioactive species of interest. A collaborative arrangement has been established with the Hanford Site to develop probe-based inspection systems for deployment in the waste tanks. ICET is currently developing an in-tank inspection system based on Fourier Transform Profilometry, FTP. FTP is a non-contact, 3-D shape measurement technique. By projecting a fringe pattern onto a target surface and observing its deformation due to surface irregularities from a different view angle, FTP is capable of determining the height (depth) distribution (and hence volume distribution) of the target surface, thus reproducing the profile of the target accurately under a wide variety of conditions. Hence FTP has the potential to be utilized for quantitative determination of residual wastes within Hanford waste tanks. We have completed a preliminary performance evaluation of FTP in order to document the accuracy, precision, and operator dependence (minimal) of FTP under conditions similar to those that can be expected to pertain within Hanford waste tanks. Based on a Hanford C-200 series tank with camera access through a riser with significant offset relative to the centerline, we devised a testing methodology that encompassed a range of obstacles likely to be encountered 'in tank'. These test objects were inspected by use

A utility perspective on BRC

International Nuclear Information System (INIS)

Farrell, B.

1988-01-01

The author is program manager for low-level radioactive waste (LLW) for the Utility Nuclear Waste Management Group (UNWMG), an activity funded by 45 utilities with nuclear power programs. The UNWMG represents the utility industry on high-level and low-level radioactive waste issues in legislative, regulatory, and technical proceedings, and therefore has a strong interest in the progress of below-regulatory-concern (BRC) regulations. The author addresses waste disposal volumes prior to discussing recent developments and status of BRC regulations

Research on Recycling and Utilization of Solid Waste in Civil Airport

Science.gov (United States)

Li, Bo; Zhang, Wen; Wang, Jianping; Yi, Wei

2018-05-01

The aviation industry is embracing unprecedented prosperity together with the economic development. Building green airports resource-saving, environment-friendly and sustainable has become the inevitability of the times. The operation of airport will generate the large amount of waste every day, which certainly exposes airports and surrounding regions to waste disposal and ecological environment pressure. Waste disposal directly affects the surrounding environment of airports, which can be effectively mitigated by disposing waste into resources, i.e., sorting and recycling them into renewable materials. The development of green airport can also be promoted in this process. The article elaborates on the current methods of waste disposal adopted by airports. According to the principle of waste reduction, harmlessness, and resource recycling, a set of solid waste recycling and utilization methods suitable for airports are proposed, which can reduce the costs of waste transported to other places and landfilled. Various environmental pollution caused by landfill and other disposal methods can also be contained effectively. At the same time, resources can be fully recycled, converting waste into useful resources in an efficient and environmental-friendly way.

Volume reduction options for the management of low-level radioactive wastes

International Nuclear Information System (INIS)

Clark, D.E.; Lerch, R.E.

1977-01-01

This paper examines volume reduction options that are now or soon will be available for low-level wastes. These wastes generally are in the form of combustible solids, noncombustible solids, and wet wastes (solid/liquid). Initially, the wastes are collected and stored onsite. Preconditioning may be required, e.g., sorting, shredding, and classifying the solids into combustible and noncombustible fractions. The volume of combustible solids can be reduced by compaction, incineration/pyrolysis, acid digestion, or molten salt combustion. Options for reducing the volume of noncombustible solids include compaction, size reduction and decontamination, meltdown-casting, dissolution and electropolishing. Burnable wet wastes (e.g., organic wastes) can be evaporated or combusted; nonburnable wet wastes can be treated by various evaporative or nonevaporative processes. All radioactive waste processing operations result in some equipment contamination and the production of additional radioactively contaminated wastes (secondary wastes). 23 figures

Activity measurements at a waste volume reduction facility

International Nuclear Information System (INIS)

Richardson, J.; Lee, D.A.

1979-01-01

The monitoring program for Ontario Hydro's radioactive waste management site will be described, several aspects of which will be discussed in detail. The program at this facility includes categorization, volume reduction processing, and storage of solid radioactive wastes from nuclear generating stations of the CANDU type. At the present time, two types of volume reduction process are in operation - incineration and compaction. Following categorization and processing, wastes are stored in in-ground concrete trenches or tile-holes, or in above-ground quadricells. The monitoring program is divided into three areas: public safety, worker safety, and structural integrity. Development projects with respect to the monitoring program have been undertaken to achieve activity accounting for the total waste management program. In particular, a field measurement for the radioactivity content of radioactive ash containers and compacted waste drums

Data summary of municipal solid waste management alternatives. Volume 3, Appendix A: Mass burn technologies

Energy Technology Data Exchange (ETDEWEB)

None

1992-10-01

This appendix on Mass Burn Technologies is the first in a series designed to identify, describe and assess the suitability of several currently or potentially available generic technologies for the management of municipal solid waste (MSW). These appendices, which cover eight core thermoconversion, bioconversion and recycling technologies, reflect public domain information gathered from many sources. Representative sources include: professional journal articles, conference proceedings, selected municipality solid waste management plans and subscription technology data bases. The information presented is intended to serve as background information that will facilitate the preparation of the technoeconomic and life cycle mass, energy and environmental analyses that are being developed for each of the technologies. Mass burn has been and continues to be the predominant technology in Europe for the management of MSW. In the United States, the majority of the existing waste-to-energy projects utilize this technology and nearly 90 percent of all currently planned facilities have selected mass burn systems. Mass burning generally refers to the direct feeding and combustion of municipal solid waste in a furnace without any significant waste preprocessing. The only materials typically removed from the waste stream prior to combustion are large bulky objects and potentially hazardous or undesirable wastes. The technology has evolved over the last 100 or so years from simple incineration to the most highly developed and commercially proven process available for both reducing the volume of MSW and for recovering energy in the forms of steam and electricity. In general, mass burn plants are considered to operate reliably with high availability.

Mobile encapsulation and volume reduction system for wet low-level wastes

International Nuclear Information System (INIS)

Buelt, J.L.

1985-08-01

This report describes the results of the program entitled ''A Preconceptual Study for a Transportable Vitrification Process''. The objective of the study is to determine the feasibility of a Mobile Encapsulation and Volume Reduction System (MEVS). The report contains design criteria, a preconceptual design of the system, a comparison of disposal costs with other solidification technologies, and an assessment of utility interests in the transportable volume reduction service MEVS can provide. The MEVS design employs the use of a joule-heated glass melter to convert the wet low-level wastes into glass. The process is self-sufficient, requiring no direct facility services or reactor personnel. It is capable of servicing one waste type from a minimum of three reactors. The design was used to prepare capital and operating cost estimates. The capital cost for the MEVS is $4,680,000, which includes all labor necessary for design, engineering, inspection, and licensing. The operating cost of the system for servicing a minimum of three reactors is $1,530,000/y for resins or $2,280,000/y for concentrated liquids. The cost estimates compared favorably to the more common solidification process of cementation. Total MEVS operating costs which include processing, transportation and burial, are $191 to $218/ft 3 waste, whereas quoted costs for cementation and disposal from reactor operators range from $155 to $350/ft 3 . The report concludes with the requirements for additional development, which can be accomplished for less than one sixth of the capital costs. The report also presents the results of an assessment conducted with utility representatives to obtain their expressions of interest in a service of this type

Comparative assessment of TRU waste forms and processes. Volume II. Waste form data, process descriptions, and costs

International Nuclear Information System (INIS)

Ross, W.A.; Lokken, R.O.; May, R.P.; Roberts, F.P.; Thornhill, R.E.; Timmerman, C.L.; Treat, R.L.; Westsik, J.H. Jr.

1982-09-01

This volume contains supporting information for the comparative assessment of the transuranic waste forms and processes summarized in Volume I. Detailed data on the characterization of the waste forms selected for the assessment, process descriptions, and cost information are provided. The purpose of this volume is to provide additional information that may be useful when using the data in Volume I and to provide greater detail on particular waste forms and processes. Volume II is divided into two sections and two appendixes. The first section provides information on the preparation of the waste form specimens used in this study and additional characterization data in support of that in Volume I. The second section includes detailed process descriptions for the eight processes evaluated. Appendix A lists the results of MCC-1 leach test and Appendix B lists additional cost data. 56 figures, 12 tables

Disposal and utilization of broiler slaughter waste by composting

Directory of Open Access Journals (Sweden)

N Bharathy

2012-12-01

Full Text Available Aim: To know the feasibility of hygienic and environmentally safe method of disposal of broiler slaughter house waste with coir pith and caged layer manure. Materials and Methods: Compost bins (4 feet x 4 feet x 4 feet were established with concrete blocks with air holes to facilitate aerobic composting. The broiler slaughter waste and coconut coir pith waste were collected from the local market, free of cost. The caged layer manure available from poultry farms were utilized as manure substrate. Physical properties and chemical composition of ingredients were analyzed and a suitable compost recipe was formulated (USDA-NRCS, 2000. Two control bins were maintained simultaneously, using caged layer manure with coir pith waste and water in a ratio of 0.8:3:1.2 (T and another one bin using caged layer manure alone(T . 2 3 Results: At the end of composting, moisture content, weight and the Volume of the compost were reduced significantly (P<0.01, pH, EC, TDS, total organic carbon and total nitrogen content were also significantly (P<0.01 reduced at the finishing of composting. Calcium, phosphorous and potassium content was progressively increased during composting period. The finished compost contains undetectable level of salmonella. Cowpea and sorghum seeds showed positive germination percentage when this finished compost was used. It indicated that all of the finished compost was free from phytotoxin substances. Conclusion: The results indicated that, composting of slaughter waste combined with coir pith waste may be a hygienic and environmentally safe method of disposal of broiler slaughter house waste [Vet. World 2012; 5(6.000: 359-361

Optimized waste management: Less volume and less radiotoxicity

International Nuclear Information System (INIS)

Fournier, Ph.; Nigon, J.L.

2001-01-01

This paper describes efforts to optimize fuel cycle back end solid wastes, in order to reduce both volume and radioactivity of final residues. An integrated strategy of standardized conditioning of all residues from reprocessing, called the Universal Canister Strategy, has been adopted. The application of feedback from over 30 years of operating experience and research and development to minimization of waste volume and radioactivity is presented. (author)

77 FR 25760 - Low-Level Radioactive Waste Management and Volume Reduction

Science.gov (United States)

2012-05-01

... NUCLEAR REGULATORY COMMISSION [NRC-2011-0183] Low-Level Radioactive Waste Management and Volume... Radioactive Waste (LLRW) Volume Reduction (Policy Statement). This statement encouraged licensees to take..., the NRC staff issued SECY-10-0043, ``Blending of Low-Level Radioactive Waste'' (ADAMS Accession No...

Energy self-supply of large abattoir by sustainable waste utilization based on anaerobic mono-digestion

International Nuclear Information System (INIS)

Ortner, Markus; Wöss, David; Schumergruber, Alexander; Pröll, Tobias; Fuchs, Werner

2015-01-01

Highlights: • Successful implementation of a new waste and energy concept to large size abattoir. • 85% of slaughterhouse waste accumulated converted to energy by anaerobic digestion. • Coverage of abattoirs’ electrical and thermal energy demand between 50% and 60%. • Reduction of main energy and disposal cost by 63%. • Reduction of greenhouse gas emissions by 79%. - Abstract: Abattoirs have a large number of energy intensive processes. Beside energy supply, disposal costs of animal by-products (ABP) are the main relevant cost drivers. In this study, successful implementation of a new waste and energy management system based on anaerobic digestion is described. Several limitations and technical challenges regarding the anaerobic digestion of the protein rich waste material had to be overcome. The most significant problems were process imbalances such as foaming and floatation as well as high accumulation of volatile fatty acids and low biogas yields caused by lack of essential microelements, high ammonia concentrations and fluctuation in operation temperature. Ultimately, 85% of the waste accumulated during the slaughter process is converted into 2700 MW h thermal and 3200 MW h electrical energy in a biogas combined heat and power (CHP) plant. The thermal energy is optimally integrated into the production process by means of a stratified heat buffer. The energy generated by the biogas CHP-plant can cover a significant share of the energy requirement of the abattoir corresponding to 50% of heat and 60% of electric demand, respectively. In terms of annual cost for energy supply and waste disposal a reduction of 63% from 1.4 Mio € to about 0.5 Mio € could be achieved with the new system. The payback period of the whole investment is approximately 9 years. Beside the economic benefits also the positive environmental impact should be highlighted: a 79% reduction of greenhouse gas emissions from 4.5 Mio kg CO 2 to 0.9 Mio kg CO 2 annually was achieved

Waste heat utilization in the thermal spa of Lavey-les-Bains

International Nuclear Information System (INIS)

2004-01-01

This final report for the Swiss Federal Office of Energy looks at the possibilities for improved waste water utilization in the Lavey-les-Bains thermal spa, Switzerland. According to the regulations in force, the temperature of the waste water rejected into the Rhone river shall not exceed 30 o C, what is currently not the case. Also the operational cost shall be reduced and the waste water quality improved. The installations are presented. From the two geothermal wells, mineral water comes out at an average flow rate of 940 l/min and a temperature of 63 o C. Actual waste water data are reported. The measured thermal water consumption data, including seasonal variations, are analysed by computerized simulation and measures to reduce the consumed volume by the optimization of internal procedures are evaluated. Measures to reduce the quantity of the rejected free chlorine are discussed. Several possible adaptations of the existing space heating, domestic water heating and pools' heating are evaluated, including cost. In addition, extensions of the thermal spa center to recreational activities are discussed, as the construction of a tropical greenhouse is

Asphalt dust waste material as a paste volume in developing sustainable self compacting concrete (SCC)

Science.gov (United States)

Ismail, Isham; Shahidan, Shahiron; Bahari, Nur Amira Afiza Saiful

2017-12-01

Self-compacting concrete (SCC) mixtures are usually designed to have high workability during the fresh state through the influence of higher volumes of paste in concrete mixtures. Asphalt dust waste (ADW) is one of disposed materials obtained during the production of asphalt premix. These fine powder wastes contribute to environmental problems today. However, these waste materials can be utilized in the development of sustainable and economical SCC. This paper focuses on the preliminary evaluations of the fresh properties and compressive strength of developed SCC for 7 and 28 days only. 144 cube samples from 24 mixtures with varying water binder ratios (0.2, 0.3 and 0.4) and ADW volume (0% to 100%) were prepared. MD940 and MD950 showed a satisfactory performance for the slump flow, J-Ring, L-Box and V-Funnel tests at fresh state. The compressive strength after 28 days for MD940 and MD950 was 36.9 MPa and 28.0 MPa respectively. In conclusion, the use of ADW as paste volume should be limited and a higher water binder ratio will significantly reduce the compressive strength.

Mixed waste: An alternative solution. The utility perspective

International Nuclear Information System (INIS)

Seizert, R.D.

1988-01-01

The issue of mixed waste is one of significant interest to the utility industry. The interest is focused on the current regulatory scheme of dual regulation. A fundamental concern of the commercial nuclear utilities resulting from dual regulation is that there are currently no facilities in the US to dispose of mixed low-level radioactive and hazardous waste. The lack of available sites renders mixed waste an orphan, requiring generators of such material to store the waste on-site. This in turn causes commercial nuclear power plants to be subjected to the full gamut of Environmental Protection Agency (EPA) Resource Conservation and Recovery Act (RCRA) regulation in addition to the existing Nuclear Regulatory Commission (NRC) regulations. Superimposing dual regulatory schemes will have impacts which extend far beyond the mere management of mixed waste. Certainly the burdens, complexities and costs of complying with the overlapping regulatory schemes will not have a commensurate increase in protection from the real risks being addressed. For these reasons, the commercial nuclear utility industry is working toward an alternative solution which will protect the public health and the environment from all hazards of mixed waste and will minimize the impacts on both the regulators and the regulated community

High-level waste borosilicate glass: A compendium of corrosion characteristics. Volume 2

International Nuclear Information System (INIS)

Cunnane, J.C.

1994-03-01

The objective of this document is to summarize scientific information pertinent to evaluating the extent to which high-level waste borosilicate glass corrosion and the associated radionuclide release processes are understood for the range of environmental conditions to which waste glass may be exposed in service. Alteration processes occurring within the bulk of the glass (e.g., devitrification and radiation-induced changes) are discussed insofar as they affect glass corrosion.This document is organized into three volumes. Volumes I and II represent a tiered set of information intended for somewhat different audiences. Volume I is intended to provide an overview of waste glass corrosion, and Volume 11 is intended to provide additional experimental details on experimental factors that influence waste glass corrosion. Volume III contains a bibliography of glass corrosion studies, including studies that are not cited in Volumes I and II. Volume I is intended for managers, decision makers, and modelers, the combined set of Volumes I, II, and III is intended for scientists and engineers working in the field of high-level waste

High-level waste borosilicate glass: A compendium of corrosion characteristics. Volume 2

Energy Technology Data Exchange (ETDEWEB)

Cunnane, J.C. [comp.; Bates, J.K.; Bradley, C.R. [Argonne National Lab., IL (United States)] [and others

1994-03-01

The objective of this document is to summarize scientific information pertinent to evaluating the extent to which high-level waste borosilicate glass corrosion and the associated radionuclide release processes are understood for the range of environmental conditions to which waste glass may be exposed in service. Alteration processes occurring within the bulk of the glass (e.g., devitrification and radiation-induced changes) are discussed insofar as they affect glass corrosion.This document is organized into three volumes. Volumes I and II represent a tiered set of information intended for somewhat different audiences. Volume I is intended to provide an overview of waste glass corrosion, and Volume 11 is intended to provide additional experimental details on experimental factors that influence waste glass corrosion. Volume III contains a bibliography of glass corrosion studies, including studies that are not cited in Volumes I and II. Volume I is intended for managers, decision makers, and modelers, the combined set of Volumes I, II, and III is intended for scientists and engineers working in the field of high-level waste.

An experimental study on the excitation of large volume airguns in a small volume body of water

International Nuclear Information System (INIS)

Wang, Baoshan; Yang, Wei; Yuan, Songyong; Ge, Hongkui; Chen, Yong; Guo, Shijun; Xu, Ping

2010-01-01

A large volume airgun array is effective in generating seismic waves, which is extensively used in large volume bodies of water such as oceans, lakes and reservoirs. So far, the application of large volume airguns is subject to the distribution of large volume bodies of water. This paper reports an attempt to utilize large volume airguns in a small body of water as a seismic source for seismotectonic studies. We carried out a field experiment in Mapaoquan pond, Fangshan district, Beijing, during the period 25–30 May 2009. Bolt LL1500 airguns, each with volumes of 2000 in 3 , the largest commercial airguns available today, were used in this experiment. We tested the excitation of the airgun array with one or two guns. The airgun array was placed 7–11 m below the water's surface. The near- and far-field seismic motions induced by the airgun source were recorded by a 100 km long seismic profile composed of 16 portable seismometers and a 100 m long strong motion seismograph profile, respectively. The following conclusions can be drawn from this experiment. First, it is feasible to excite large volume airguns in a small volume body of water. Second, seismic signals from a single shot of one airgun can be recognized at the offset up to 15 km. Taking advantage of high source repeatability, we stacked records from 128 shots to enhance the signal-to-noise ratio, and direct P-waves can be easily identified at the offset ∼50 km in stacked records. Third, no detectable damage to fish or near-field constructions was caused by the airgun shots. Those results suggest that large volume airguns excited in small bodies of water can be used as a routinely operated seismic source for mid-scale (tens of kilometres) subsurface explorations and monitoring under various running conditions

System of large transport containers for waste from dismantling light water and gas-cooled nuclear reactors. Volume 1

International Nuclear Information System (INIS)

Price, M.S.T.; Lafontaine, I.

1985-01-01

The purpose of this volume is to introduce the main types of nuclear reactor in the European Community (EC), select reference plants for further study, estimate the waste streams from the reference reactors, survey the transport regulations and assess existing containers

Removal of basic dye (methylene blue) from wastewaters utilizing beer brewery waste

International Nuclear Information System (INIS)

Tsai, W.-T.; Hsu, H.-C.; Su, T.-Y.; Lin, K.-Y.; Lin, C.-M.

2008-01-01

In the work, the beer brewery waste has been shown to be a low-cost adsorbent for the removal of basic dye from the aqueous solution as compared to its precursor (i.e., diatomite) based on its physical and chemical characterizations including surface area, pore volume, scanning electron microscopy (SEM), and non-mineral elemental analyses. The pore properties of this waste were significantly larger than those of its raw material, reflecting that the trapped organic matrices contained in the waste probably provided additional adsorption sites and/or adsorption area. The results of preliminary adsorption kinetics showed that the diatomite waste could be directly used as a potential adsorbent for removal of methylene blue on the basis of its adsorption-biosorption mechanisms. The adsorption parameters thus obtained from the pseudo-second-order model were in accordance with their pore properties. From the results of adsorption isotherm at 298 K and the applicability examinations in treating industrial wastewater containing basic dye, it was further found that the adsorption capacities of diatomite waste were superior to those of diatomite, which were also in good agreement with their corresponding physical properties. From the results mentioned above, it is feasible to utilize the food-processing waste for removing dye from the industrial dying wastewater

Removal of basic dye (methylene blue) from wastewaters utilizing beer brewery waste.

Science.gov (United States)

Tsai, Wen-Tien; Hsu, Hsin-Chieh; Su, Ting-Yi; Lin, Keng-Yu; Lin, Chien-Ming

2008-06-15

In the work, the beer brewery waste has been shown to be a low-cost adsorbent for the removal of basic dye from the aqueous solution as compared to its precursor (i.e., diatomite) based on its physical and chemical characterizations including surface area, pore volume, scanning electron microscopy (SEM), and non-mineral elemental analyses. The pore properties of this waste were significantly larger than those of its raw material, reflecting that the trapped organic matrices contained in the waste probably provided additional adsorption sites and/or adsorption area. The results of preliminary adsorption kinetics showed that the diatomite waste could be directly used as a potential adsorbent for removal of methylene blue on the basis of its adsorption-biosorption mechanisms. The adsorption parameters thus obtained from the pseudo-second-order model were in accordance with their pore properties. From the results of adsorption isotherm at 298 K and the applicability examinations in treating industrial wastewater containing basic dye, it was further found that the adsorption capacities of diatomite waste were superior to those of diatomite, which were also in good agreement with their corresponding physical properties. From the results mentioned above, it is feasible to utilize the food-processing waste for removing dye from the industrial dying wastewater.

Removal of basic dye (methylene blue) from wastewaters utilizing beer brewery waste

Energy Technology Data Exchange (ETDEWEB)

Tsai, W.-T. [Graduate Institute of Bioresources, National Pingtung University of Science and Technology, Pingtung 912, Taiwan (China)], E-mail: wttsai@mail.npust.edu.tw; Hsu, H.-C.; Su, T.-Y.; Lin, K.-Y.; Lin, C.-M. [Department of Environmental Engineering and Science, Chia Nan University of Pharmacy and Science, Tainan 717, Taiwan (China)

2008-06-15

In the work, the beer brewery waste has been shown to be a low-cost adsorbent for the removal of basic dye from the aqueous solution as compared to its precursor (i.e., diatomite) based on its physical and chemical characterizations including surface area, pore volume, scanning electron microscopy (SEM), and non-mineral elemental analyses. The pore properties of this waste were significantly larger than those of its raw material, reflecting that the trapped organic matrices contained in the waste probably provided additional adsorption sites and/or adsorption area. The results of preliminary adsorption kinetics showed that the diatomite waste could be directly used as a potential adsorbent for removal of methylene blue on the basis of its adsorption-biosorption mechanisms. The adsorption parameters thus obtained from the pseudo-second-order model were in accordance with their pore properties. From the results of adsorption isotherm at 298 K and the applicability examinations in treating industrial wastewater containing basic dye, it was further found that the adsorption capacities of diatomite waste were superior to those of diatomite, which were also in good agreement with their corresponding physical properties. From the results mentioned above, it is feasible to utilize the food-processing waste for removing dye from the industrial dying wastewater.

Analysis of Comprehensive Utilization of Coconut Waste

OpenAIRE

Zheng, Kan; Liang, Dong; Zhang, Xirui

2013-01-01

This paper describes and analyzes the coconut cultivation in China, and the current comprehensive utilization of waste resources generated during cultivation and processing of coconut. The wastes generated in the process of cultivation include old coconut tree trunk, roots, withered coconut leaves, coconut flower and fallen cracking coconut, mainly used for biogas extraction, direct combustion and power generation, brewing, pharmacy, and processing of building materials; the wastes generated ...

Low-level radioactive waste in the northeast: disposal volume projections

International Nuclear Information System (INIS)

1982-10-01

The northeastern states, with support of the Coalition of Northeastern Governors (CONEG), are developing compact(s) for the disposal and management of low-level radioactive waste (LLRW) generated in the eleven northeastern states (Connecticut, Delaware, Maine, Maryland, Massachusetts, New Hampshire, New Jersey, New York, Pennsylvania, Rhode Island, and Vermont). The Technical Subcommittee has made a projection of future low-level radioactive waste to the year 2000 based on existing waste volume data and anticipated growth in the Northeast states. Aware of the difficulties involved with any long range projection - unforeseen events can drastically change projections based on current assumptions - the Technical Subcommittee believes that waste volume projections should be reviewed annually as updated information becomes available. The Technical Subcommittee made the following findings based upon a conservative projection methodology: volumes of low-level waste produced annually in the eleven states individually and collectively are expected to grow continually through the year 2000 with the rate of increase varying by state; by the year 2000, the Northeast is projected to generate 58,000 m 3 of low-level waste annually, about 1.9 times the current average; and based on current estimates, 47% of the total projected waste volume in the year 2000 will be produced by nuclear power plants, compared to the current average of 54%. Non-reactor wastes will equal 53% of the total in the year 2000 compared to the current 46%

Method of reducing the volume of radioactive waste

International Nuclear Information System (INIS)

Buckley, L.P.; Burrill, K.A.; Desjardins, C.D.; Salter, R.S.

1984-01-01

There is provided a method of reducing the volume of radioactive waste, comprising: pyrolyzing the radioactive waste in the interior of a vessel, while passing superheated steam through the vessel at a temperature in the range 500 to 700 degrees C, a pressure in the range 1.0 to 3.5 MPa, and at a flow rate in the range 4 to 50 mL/s/m 3 of the volume of the vessel interior, to cause pyrohydrolysis of the waste and to remove carbon-containing components of the pyrolyzed waste from the vessel as gaseous oxides, leaving an ash residue in the vessel. Entrained particles present with the gaseous oxides are filtered and acidic vapours present with the gaseous oxides are removed by solid sorbent. Steam and any organic substances present with the gaseous oxides are condensed and the ash is removed from the vessel. The radioactive waste may be deposited upon an upper screen in the vessel, so that a substantial portion of the pyrolysis of the radioactive waste takes place while the radioactive waste is on the upper screen, and pyrolyzed waste falls through the upper screen onto a lower screen, where another substantial portion of the pyrohydrolysis takes place. The ash residue falls through the lower screen

Korean working towards low and intermediate level waste volume reduction

International Nuclear Information System (INIS)

Myung-Jae Song; Jong-Kil Park

2001-01-01

The safe management of radioactive waste is a national task required for sustainable generation of nuclear power and for energy self-reliance. This paper describes the results, efforts, and prospects for the safe management of radioactive wastes having been performed by the Nuclear Environment Technology Institute (NETEC) of the Korean Electric Power Corporation (KEPCO). Firstly, KEPCO's efforts and results for waste volume reduction are summarized to show how the number of waste drums generated per reactor-year could be reduced by about 60% during the last 10 years. Secondly, a new treatment technology, a technology for low and intermediate level waste (LILW) vitrification, was introduced to prospect how the technology reduces the waste volume and increases the inherent safety for LILW disposal. It is expected that the vitrification technology will contribute not only to reduce LILW volume to around 1/14 ∼ 1/32 but also to change the 'Not In My Back Yard' (NIMBY) syndrome to the 'Please In My Front Yard' (PIMFY) attitude of local communities/residents for LILW disposal. (author)

Municipal Solid Waste Resources

Energy Technology Data Exchange (ETDEWEB)

None

2016-06-01

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

W-320 waste retrieval sluicing system transfer line flushing volume and frequency calculation

International Nuclear Information System (INIS)

Bailey, J.W.

1997-01-01

The calculations contained in this analysis document establish the technical basis for the volume, frequency, and flushing fluid to be utilized for routine Waste Retrieval Sluicing System (WRSS) process line flushes. The WRSS was installed by Project W-320, Tank 241-C-106 Sluicing. The double contained pipelines being flushed have 4 inch stainless steel primary pipes. The flushes are intended to prevent hydrogen buildup in the transfer lines and to provide ALARA conditions for maintenance personnel

French surface disposal experience. The disposal of large waste

International Nuclear Information System (INIS)

Dutzer, Michel; Lecoq, Pascal; Duret, Franck; Mandoki, Robert

2006-01-01

More than 90 percent of the volume of radioactive waste that are generated in France can be managed in surface disposal facilities. Two facilities are presently operated by ANDRA: the Centre de l'Aube disposal facility that is dedicated to low and intermediate short lived waste and the Morvilliers facility for very low level waste. The Centre de l'Aube facility was designed at the end of the years 1980 to replace the Centre de la Manche facility that ended operation in 1994. In order to achieve as low external exposure as possible for workers it was decided to use remote handling systems as much as possible. Therefore it was necessary to standardize the types of waste containers. But taking into account the fact that these waste were conditioned in existing facilities, it was not possible to change a major part of existing packages. As a consequence, 6 mobile roofs were constructed to handle 12 different types of waste packages in the disposal vaults. The scope of Centre de l'Aube was mainly to dispose operational waste. However some packages, as 5 or 10 m 3 metallic boxes, could be used for larger waste generated by decommissioning activities. The corresponding flow was supposed to be small. After the first years of operations, it appeared interesting to develop special procedures to dispose specific large waste in order to avoid external exposure costly cutting works in the generating facilities. A 40 m 3 box and a large remote handling device were disposed in vaults that were currently used for other types of packages. Such a technique could not be used for the disposal of vessel heads that were replaced in 55 pressurised water power reactors. The duration of disposal and conditioning operation was not compatible with the flow of standard packages that were delivered in the vaults. Therefore a specific type of vault was designed, including handling and conditioning equipment. The first pressure vessel head was delivered on the 29 of July 2004, 6 heads have been

Shredder and incinerator technology for volume reduction of commercial transuranic wastes

International Nuclear Information System (INIS)

Oma, K.H.

1986-06-01

Pacific Northwest Laboratory (PNL) is evaluating alternatives and developing technology for treatment of radioactive wastes generated during commercial nuclear activities. Transuranic wastes that require volume reduction include spent HEPA filters, sample and analytical cell waste, and general process trash. A review of current technologies for volume reduction of these wastes led to the selection and testing of several low-speed shredder systems and three candidate incineration processes. The incinerators tested were the electrically heated control-led-air, gas-heated controlled-air, and rotary kiln. Equipment tests were conducted using simulated commercial transuranic wastes to provide a data base for the comparison of the various technologies. The electrically driven, low-speed shredder process was selected as the preferred method for size reduction of the wastes prior to incineration. All three incinerators effectively reduced the waste volume. Based on a technical and economic evaluation on the incineration processes, the recommended system for the commercial waste application is the gas-heated controlled-air incinerator with a single stage of shredding for feed pretreatment

The problem of large samples. An activation analysis study of electronic waste material

International Nuclear Information System (INIS)

Segebade, C.; Goerner, W.; Bode, P.

2007-01-01

Large-volume instrumental photon activation analysis (IPAA) was used for the investigation of shredded electronic waste material. Sample masses from 1 to 150 grams were analyzed to obtain an estimate of the minimum sample size to be taken to achieve a representativeness of the results which is satisfactory for a defined investigation task. Furthermore, the influence of irradiation and measurement parameters upon the quality of the analytical results were studied. Finally, the analytical data obtained from IPAA and instrumental neutron activation analysis (INAA), both carried out in a large-volume mode, were compared. Only parts of the values were found in satisfactory agreement. (author)

Photogrammetry and Laser Imagery Tests for Tank Waste Volume Estimates: Summary Report

Energy Technology Data Exchange (ETDEWEB)

Field, Jim G. [Washington River Protection Solutions, LLC, Richland, WA (United States)

2013-03-27

Feasibility tests were conducted using photogrammetry and laser technologies to estimate the volume of waste in a tank. These technologies were compared with video Camera/CAD Modeling System (CCMS) estimates; the current method used for post-retrieval waste volume estimates. This report summarizes test results and presents recommendations for further development and deployment of technologies to provide more accurate and faster waste volume estimates in support of tank retrieval and closure.

Photogrammetry and Laser Imagery Tests for Tank Waste Volume Estimates: Summary Report

International Nuclear Information System (INIS)

Field, Jim G.

2013-01-01

Feasibility tests were conducted using photogrammetry and laser technologies to estimate the volume of waste in a tank. These technologies were compared with video Camera/CAD Modeling System (CCMS) estimates; the current method used for post-retrieval waste volume estimates. This report summarizes test results and presents recommendations for further development and deployment of technologies to provide more accurate and faster waste volume estimates in support of tank retrieval and closure

Using Photogrammetry to Estimate Tank Waste Volumes from Video

Energy Technology Data Exchange (ETDEWEB)

Field, Jim G. [Washington River Protection Solutions, LLC, Richland, WA (United States)

2013-03-27

Washington River Protection Solutions (WRPS) contracted with HiLine Engineering & Fabrication, Inc. to assess the accuracy of photogrammetry tools as compared to video Camera/CAD Modeling System (CCMS) estimates. This test report documents the results of using photogrammetry to estimate the volume of waste in tank 241-C-I04 from post-retrieval videos and results using photogrammetry to estimate the volume of waste piles in the CCMS test video.

Using Photogrammetry to Estimate Tank Waste Volumes from Video

International Nuclear Information System (INIS)

Field, Jim G.

2013-01-01

Washington River Protection Solutions (WRPS) contracted with HiLine Engineering and Fabrication, Inc. to assess the accuracy of photogrammetry tools as compared to video Camera/CAD Modeling System (CCMS) estimates. This test report documents the results of using photogrammetry to estimate the volume of waste in tank 241-C-I04 from post-retrieval videos and results using photogrammetry to estimate the volume of waste piles in the CCMS test video

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

Energy Technology Data Exchange (ETDEWEB)

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

2007-02-15

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

Fifteen years of radioactive waste management at Ontario Hydro

International Nuclear Information System (INIS)

Carter, T.J.; Rao, P.K.M.

1985-01-01

Ontario Hydro is a large Canadian utility producing 84% (7394 MWe) of the Nuclear Electricity generated in Canada. The low- and intermediate-level radioactive wastes generated by the Ontario Hydro program are currently being managed at the Bruce Nuclear Power Development with various volume reduction, packaging and interim storage systems. Ontario Hydro also owns and operates a radioactive waste transportation system. Studies are in progress for final disposal of these wastes in a suitable geology in Ontario. Since its inception in 1971, Ontario Hydro's radioactive waste management program has evolved into providing a full fledged radioactive waste management capability to the utility's two nuclear generation centres at Pickering and Bruce, and later in the decade, to Darlington. This paper summarizes the various developments in this program; highlights the major facilities both in-service and planned to be built; reviews the experiences gained over fifteen years of in-house waste management; and discusses the proposed reorientation towards ultimate disposal of these wastes. 2 refs., 8 figs., 1 tab

Developing and Evaluating Prototype of Waste Volume Monitoring Using Internet of Things

Science.gov (United States)

Fathhan Arief, Mohamad; Lumban Gaol, Ford

2017-06-01

In Indonesia, especially Jakarta have a lot of garbage strewn that can be an eyesore and also cause pollution that can carry diseases. Garbage strewn can cause many things, one of her dues is bins are overflowing due to the full so it can not accommodate the waste dumped from other people. Thus, the author created a new method for waste disposal more systematic. In creating new method requires a technology to supports, then the author makes a prototype for waste volume monitoring. By using the internet of things prototype of waste volume monitoring may give notification to the sanitary agency that waste in the trash bin needs to be disposal. In this study, conducted the design and manufactured of prototype waste volume monitoring using LinkItONE board based by Arduino and an ultrasonic sensor for appliance senses. Once the prototype is completed, evaluation in order to determine whether the prototype will function properly. The result showed that the expected function of a prototype waste volume monitoring can work well.

Market forces can help lower waste volumes

International Nuclear Information System (INIS)

Stavins, R.N.

1993-01-01

Market forces can go a long way toward helping communities solve their mounting solid-waste problems. In most communities the increasing costs of solid-waste disposal are invisible to the average homeowner because they are buried in local property tax rates. Even in the few communities that list disposal costs separately on tax bills, individual costs are not related to the volume of waste generated. Fundamental to an effective waste-management strategy is the removal of these distortions by getting the prices right. But even with improved price signals, there is no silver bullet of public policy for solid- and hazardous-waste management. Until the ubiquitous NIMBY (Not In My Backyard) problem is addressed, even the most innovative set of waste management policies will remain, at best, a partial solution

Environmental epidemiology, Volume 1: Public health and hazardous wastes

International Nuclear Information System (INIS)

Anon.

1991-01-01

Environmental Epidemiology, Volume 1, represents the first of several planned volumes on the uses of epidemiologic techniques to study environmental public health issues. This text focuses on environmental epidemiology as it relates to hazardous waste in the United States. This study was commissioned by the Agency for Toxic Substances and Disease Registry to examine available data for evidence of adverse health effects on human populations exposed to hazardous waste. The committee was also asked to identify data gaps which were impediments to analyzing hazardous waste health effects and to suggest ways that such environmental health assessments might be improved. The committee's solution to the paucity of data on this issue was to concentrate in this volume on identifying the available, peer-reviewed data and, consequently, the major data gaps. The study opens with a recapitulation of the context of hazardous waste sites in the United States, the approaches currently used by state and federal epidemiologists in analyzing hazardous waste exposure and effects, and candid assessment of the problems associated with environmental exposure assessment. From that context, the committee then presents the data currently available to assess human exposures through air, domestic water consumption, soil, and the food chain. The general focus here is on biomarker data as the date of choice. As with all NAS reports, this one closes with general conclusions and recommendations. Environmental health risk assessors will find this volume a valuable resource

Utilization of byproducts and waste materials from meat, poultry and fish processing industries: a review.

Science.gov (United States)

Jayathilakan, K; Sultana, Khudsia; Radhakrishna, K; Bawa, A S

2012-06-01

India is bestowed with vast livestock wealth and it is growing at the rate of 6% per annum. The contribution of livestock industry including poultry and fish is increasing substantially in GDP of country which accounts for >40% of total agricultural sector and >12% of GDP. This contribution would have been much greater had the animal by-products been also efficiently utilized. Efficient utilization of by-products has direct impact on the economy and environmental pollution of the country. Non-utilization or under utilization of by-products not only lead to loss of potential revenues but also lead to the added and increasing cost of disposal of these products. Non-utilization of animal by-products in a proper way may create major aesthetic and catastrophic health problems. Besides pollution and hazard aspects, in many cases meat, poultry and fish processing wastes have a potential for recycling raw materials or for conversion into useful products of higher value. Traditions, culture and religion are often important when a meat by-product is being utilized for food. Regulatory requirements are also important because many countries restrict the use of meat by-products for reasons of food safety and quality. By-products such as blood, liver, lung, kidney, brains, spleen and tripe has good nutritive value. Medicinal and pharmaceutical uses of by-product are also highlighted in this review. Waste products from the poultry processing and egg production industries must be efficiently dealt with as the growth of these industries depends largely on waste management. Treated fish waste has found many applications among with which the most important are animal feed, biodiesel/biogas, dietectic products (chitosan), natural pigments (after extraction) and cosmetics (collagen). Available information pertaining to the utilization of by-products and waste materials from meat, poultry and fish and their processing industries has been reviewed here.

Manual on oil-gas industry waste utilization radioecological safety

International Nuclear Information System (INIS)

Kudryashev, V.A.; Lukashenko, S.N.; Tuleushev, A.Zh.; Marabaev, Zh.N.; Pasysaev, V.A.; Kayukov, P.G.; Kozhakhmetov, N.B.; Shevtsov, S.P.

2003-01-01

The development of a new document - 'Manual on radio-ecologically safe utilization of waste from oil-and-gas production' is carried out. This document regulates the whole cycle of environment protection measures at waste utilization for the named industry in Kazakhstan and is aimed on lowering the radiation risks and assurance of radioecological safety both at present and for the future. The document presents a set regulations necessary for radioactive wastes handling in the oil-gas industry. The normative document was agreed in both the Ministry of Health of the Republic of Kazakhstan (RK) and Ministry of Environment Protection of RK

Achievement report in fiscal 1999 on commissioned research project. 'Model project for facilities to effectively utilize wastes from industrial complexes in Thailand' Project for 1999 Volume 3; 1999 nendo seika hokokusho. Tai ni okeru kogyo danchi sangyo haikibutsu yuko riyo setsubi moderu jigyo - 3

Energy Technology Data Exchange (ETDEWEB)

NONE

2001-03-01

With an objective to reuse industrial wastes and effectively utilize them as a petroleum replacing energy resource, and attempt to reduce consumption of fossil fuel in Thailand where increase in discharge of industrial wastes is estimated, a model project for facilities to effectively utilize wastes from industrial complexes has been carried out. This paper reports the achievements in fiscal 1999. Specifically, the project calls for incineration in fluidized bed incinerators of industrial wastes discharged from factories in industrial complexes possessed by the Industrial Estate Authority of Thailand (IEAT), recovery of waste heat from waste heat recovering boilers to generate process steam, which is supplied to the factories in the complexes. The current fiscal year, which is the first current year of the project, has put into order the operations shared by Japan and Thailand, compiled the various procedures and schedules into the form of appendices to the agreement, and executed signing of the agreement. Thereafter, the Japanese side has carried out decision on the specifications of the facilities, the basic designs, the detailed designs of facilities to be arranged by Japan, and the fabrication of some of the devices according to the descriptions of the agreement appendices. The volume 3 summarizes the inspection reports other than those included in the Volume 2. (NEDO)

Solid low level waste management guidelines

International Nuclear Information System (INIS)

Saunders, P.

1995-01-01

In the 1980's the nuclear industry began focusing a great deal of attention on minimizing the volume of low level radioactive waste (LLW) that required disposal. This was driven by several factors including rising disposal costs, increased regulatory pressures, and increased pressure from other organizations such as INPO. In the 1990's most utilities are faced with intense competition in the electrical generation market. The survival of a utility is based on their ability to produce electricity by the most efficient and economical means available. Waste management related costs are a substantial portion of most utilities O ampersand M budgets. Disposal site access denial continues to be a major factor in waste management program decision, and the pressures to minimize waste volumes from outside organizations is greater than ever

Nuclear waste calorimeter for very large drums with 385 litres sample volume

Energy Technology Data Exchange (ETDEWEB)

Jossens, G.; Mathonat, C. [SETARAM Instrumentation, Caluire (France); Bachelet, F. [CEA Valduc, Is sur Tille (France)

2015-03-15

Calorimetry is a very precise and well adapted tool for the classification of drums containing nuclear waste material depending on their level of activities (low, medium, high). A new calorimeter has been developed by SETARAM Instrumentation and the CEA Valduc in France. This new calorimeter is designed for drums having a volume bigger than 100 liters. It guarantees high operator safety by optimizing drum handling and air circulation for cooling, and optimized software for direct measurement of the quantity of nuclear material. The LVC1380 calorimeter makes it possible to work over the range 10 to 3000 mW, which corresponds to approximately 0.03 to 10 g of tritium or 3 to 955 g of {sup 241}Pu in a volume up to 385 liters. This calorimeter is based on the heat flow measurement using Peltier elements which surround the drum in the 3 dimensions and therefore measure all the heat coming from the radioactive stuff whatever its position inside the drum. Calorimeter's insulating layers constitute a thermal barrier designed to filter disturbances until they represent less than 0.001 Celsius degrees and to eliminate long term disturbances associated, for example, with laboratory temperature variations between day and night. A calibration device based on Joule effect has also been designed. Measurement time has been optimized but remains long compared with other methods of measurement such as gamma spectrometry but its main asset is to have a good accuracy for low level activities.

Draft Title 40 CFR 191 compliance certification application for the Waste Isolation Pilot Plant. Volume 4: Appendix BIR Volume 2

International Nuclear Information System (INIS)

1995-01-01

This report consists of the waste stream profile for the WIPP transuranic waste baseline inventory at Lawrence Livermore National Laboratory. The following assumptions/modifications were made by the WTWBIR team in developing the LL waste stream profiles: since only current volumes were provided by LL, the final form volumes were assumed to be the same as the current volumes; the WTWBIR team had to assign identification numbers (IDs) to those LL waste streams not given an identifier by the site, the assigned identification numbers are consistent with the site reported numbers; LL Final Waste Form Groups were modified to be consistent with the nomenclature used in the WTWBID, these changes included word and spelling changes, the assigned Final Waste Form Groups are consistent with the information provided by LL; the volumes for the year 1993 were changed from an annual rate of generation (m 3 /year) to a cumulative value (m 3 )

The economic impact of regional waste disposal on advanced volume reduction technologies

International Nuclear Information System (INIS)

McArthur, W.C.; Kniazewycz, B.G.

1983-01-01

Waste volume reduction has received increased emphasis over the past decade as annual operating costs have risen from $250,000/year to $3,500,000 for 1983. Emphasis has been given to developing and designing into new nuclear plants process and DAW volume reduction technologies such as fluidized-bed dryers incinerators, and evaporative-solidification systems. The basis for these systems was originally the correct perception that a crisis would be reached with the, then available, shallow land disposal sites which would increase costs substantially and possible jeopardize power plant operations. With the passage of the Low-Level Waste Policy Act of 1980 and increased emphasis on interim on-site storage of low-level waste, the ''economics of volume reduction'' are susceptible to increased uncertainties. This paper reviews some previous volume reduction economic analyses and evaluates the revised economics based upon the development of regional waste disposal sites, improved waste generation and processing practices, and the increased use of interim on-site storage. Several case studies are presented

Solid waste treatment volume reduction by compaction or incineration

International Nuclear Information System (INIS)

Vigreux, B.; Carpentier, S.

1985-01-01

A short presentation is made of various techniques available for volume reduction by compaction of solid waste produced during nuclear plant operation. A long industrial experience has been accumulated in France on such compactors. Incineration is the most performing method of volume reduction for combustible waste. The CEA Group and SGN have developed a very reliable, simple and safe incinerator which operates with excess air and at high temperature. Sorting and feeding of the waste, ash discharge and transportation to the conditioning unit, gas treatment, are included in the system. The adding of a programmable controller makes it fully automated. The system is described with some detail and recent performance measurements are given [fr

Solid waste treatment volume reduction by compaction or incineration

International Nuclear Information System (INIS)

Vigreux, B.; Carpentier, S.

1986-01-01

A short presentation is made of various techniques available for volume reduction by compaction of solid waste produced during nuclear plant operation. A long industrial experience has been accumulated in France on such compactors. Incineration is the most performing method of volume reduction for combustible waste. The CEA Group and SGN have developed a very reliable, simple and safe incinerator which operates with excess air and at high temperature. Sorting and feeding of the waste, ash discharge and transportation to the conditioning unit, gas treatment, are included in the system. The adding of a programmable controller makes it fully automated. The system is described with some detail and recent performance measurements are given [fr

Waste volume reduction factors for potential 242-A evaporator feed

International Nuclear Information System (INIS)

Sederburg, J.P.

1995-01-01

Double-shell tank (DST) storage space requirements have been shown to be highly dependent on the end point of 242-A operations. Consequences to the DST of various waste volumes, and concentrations, are evaluated. Only waste streams that are currently planned to be stored in the DST system before the year 2004 are discussed. As of January 1, 1995, approximately 27-million L (7.2-million gal) of dilute wastes are stored in the DSTs available for evaporator processing. Waste streams planned to be transferred to the DSTs before December 31, 2004, are identified. The DST volume for storing slurry from these wastes is presented in this document. At a final slurry specific gravity of -1.35, 22.5-million L (5.93-million gal) of DST space would be needed on December 31, 2004, to store the product from evaporator processing of these feedstocks. The expected volume needed if the resultant slurry were concentrated to the traditional double-shell slurry feed (DSSF) phase boundary (a specific gravity of ∼1.5) would be 17.7-million L (4.67-million gal). An additional 4.8-million L (1.26-million gal) is therefore needed if these wastes are concentrated to a specific gravity of 1.35 instead of the DSSF limit

Volume reduction and solidification of liquid and solid low-level radioactive waste

International Nuclear Information System (INIS)

May, J.R.

1979-01-01

This paper presents a brief background of the development of a method of radioactive waste volume reduction using a unique fluidized bed calciner/incinerator. The volume reduction system is capable of processing a variety of liquid chemical wastes, spent ion exchange resin beads, filter treatment sludges, contaminated lubricating oils, and miscellaneous combustible solids such as paper, rags, protective clothing, wood, etc. All of these wastes are processed in one chemical reaction vessel. Detailed process data is presented that shows the system is capable of reducing the total volume of disposable radioactive waste generated by light water reactors by a factor of 10. Equally important to reducing the volume of power reactor radwaste is the final form of the stored or disposable radwaste. This paper also presents process data related to a new radwaste solidification system, presently being developed, that is particularly suited for immobilizing the granular solids and ashes resulting from volume reduction by calcination and/or incineration

CO2 Mineralization and Utilization using Steel Slag for Establishing a Waste-to-Resource Supply Chain.

Science.gov (United States)

Pan, Shu-Yuan; Chung, Tai-Chun; Ho, Chang-Ching; Hou, Chin-Jen; Chen, Yi-Hung; Chiang, Pen-Chi

2017-12-08

Both steelmaking via an electric arc furnace and manufacturing of portland cement are energy-intensive and resource-exploiting processes, with great amounts of carbon dioxide (CO 2 ) emission and alkaline solid waste generation. In fact, most CO 2 capture and storage technologies are currently too expensive to be widely applied in industries. Moreover, proper stabilization prior to utilization of electric arc furnace slag are still challenging due to its high alkalinity, heavy metal leaching potentials and volume instability. Here we deploy an integrated approach to mineralizing flue gas CO 2 using electric arc furnace slag while utilizing the reacted product as supplementary cementitious materials to establish a waste-to-resource supply chain toward a circular economy. We found that the flue gas CO 2 was rapidly mineralized into calcite precipitates using electric arc furnace slag. The carbonated slag can be successfully utilized as green construction materials in blended cement mortar. By this modulus, the global CO 2 reduction potential using iron and steel slags was estimated to be ~138 million tons per year.

METHODOLOGY AND CALCULATIONS FOR THE ASSIGNMENT OF WASTE GROUPS FOR THE LARGE UNDERGROUND WASTE STORAGE TANKS AT THE HANFORD SITE

Energy Technology Data Exchange (ETDEWEB)

WEBER RA

2009-01-16

The Hanford Site contains 177 large underground radioactive waste storage tanks (28 double-shell tanks and 149 single-shell tanks). These tanks are categorized into one of three waste groups (A, B, and C) based on their waste and tank characteristics. These waste group assignments reflect a tank's propensity to retain a significant volume of flammable gases and the potential of the waste to release retained gas by a buoyant displacement gas release event. Assignments of waste groups to the 177 double-shell tanks and single-shell tanks, as reported in this document, are based on a Monte Carlo analysis of three criteria. The first criterion is the headspace flammable gas concentration following release of retained gas. This criterion determines whether the tank contains sufficient retained gas such that the well-mixed headspace flammable gas concentration would reach 100% of the lower flammability limit if the entire tank's retained gas were released. If the volume of retained gas is not sufficient to reach 100% of the lower flammability limit, then flammable conditions cannot be reached and the tank is classified as a waste group C tank independent of the method the gas is released. The second criterion is the energy ratio and considers whether there is sufficient supernatant on top of the saturated solids such that gas-bearing solids have the potential energy required to break up the material and release gas. Tanks that are not waste group C tanks and that have an energy ratio < 3.0 do not have sufficient potential energy to break up material and release gas and are assigned to waste group B. These tanks are considered to represent a potential induced flammable gas release hazard, but no spontaneous buoyant displacement flammable gas release hazard. Tanks that are not waste group C tanks and have an energy ratio {ge} 3.0, but that pass the third criterion (buoyancy ratio < 1.0, see below) are also assigned to waste group B. Even though the designation as

METHODOLOGY AND CALCULATIONS FOR THE ASSIGNMENT OF WASTE GROUPS FOR THE LARGE UNDERGROUND WASTE STORAGE TANKS AT THE HANFORD SITE

Energy Technology Data Exchange (ETDEWEB)

FOWLER KD

2007-12-27

This document categorizes each of the large waste storage tanks into one of several categories based on each tank's waste characteristics. These waste group assignments reflect a tank's propensity to retain a significant volume of flammable gases and the potential of the waste to release retained gas by a buoyant displacement event. Revision 7 is the annual update of the calculations of the flammable gas Waste Groups for DSTs and SSTs. The Hanford Site contains 177 large underground radioactive waste storage tanks (28 double-shell tanks and 149 single-shell tanks). These tanks are categorized into one of three waste groups (A, B, and C) based on their waste and tank characteristics. These waste group assignments reflect a tank's propensity to retain a significant volume of flammable gases and the potential of the waste to release retained gas by a buoyant displacement gas release event. Assignments of waste groups to the 177 double-shell tanks and single-shell tanks, as reported in this document, are based on a Monte Carlo analysis of three criteria. The first criterion is the headspace flammable gas concentration following release of retained gas. This criterion determines whether the tank contains sufficient retained gas such that the well-mixed headspace flammable gas concentration would reach 100% of the lower flammability limit if the entire tank's retained gas were released. If the volume of retained gas is not sufficient to reach 100% of the lower flammability limit, then flammable conditions cannot be reached and the tank is classified as a waste group C tank independent of the method the gas is released. The second criterion is the energy ratio and considers whether there is sufficient supernatant on top of the saturated solids such that gas-bearing solids have the potential energy required to break up the material and release gas. Tanks that are not waste group C tanks and that have an energy ratio < 3.0 do not have sufficient

Transporting large volumes of residual radioactive material: FUSRAP solutions

International Nuclear Information System (INIS)

Pressnell, T.; McDaniel, P.; Darby, J.

1997-01-01

During the 1940s, 1950s and 1960s, many sites in the United States were used by the Manhattan Engineer District and the Atomic Energy Commission for processing and storing uranium and thorium ores and metals. Some of the sites were owned by the federal government; others were owned by universities or other institutions; and still others, such as chemical plants, were privately owned. The Formerly Utilized Sites Remedial Action Program (FUSRAP) is one of several U.S. Department of Energy programs created to address radioactive contamination in excess of guidelines at these sites. FUSRAP currently includes 46 sites in 14 states. This article includes the following topics in describing FUSRAP work: Logistics challenges; engineering challenges (package inspection, equipment compatability, moisture content requirements, waste volume estimation); Traffic management

Drying of bio fuel utilizing waste heat; Torkning av biobraenslen med spillvaerme

Energy Technology Data Exchange (ETDEWEB)

Johansson, Inge; Larsson, Sara; Wennberg, Olle [S.E.P. Scandinavian Energy Project AB, Goeteborg (Sweden)

2004-10-01

Many industries today have large sources of low grade heat (waste heat), however this energy is mainly lost with effluents to air and water. The aim of this study has been to investigate the technical and economical aspects of utilizing this low grade heat to dry biofuel. The project has been mainly focused towards the forest industry since they have both large amounts of biofuel and waste heat available. Drying of biofuel could generate added revenue (or reduced purchase costs) and through that also create larger incentives for further energy saving modifications to the main process. Due to the higher moisture content together with the risk of frozen bark in the winter time, additional fuels (such as oil) to combust bark in the existing boiler. This is mainly the case when mechanical dewatering is not available. Drying of bark results in an added energy value, which makes it possible to combust the bark without additional fuel. The primary energy demand, in the form of electricity and optional additional heating at load peaks, is low when waste heat is used for the drying process. In this way it is possible to increase the biofuel potential, since the primary energy input to the drying process is essentially lower then the increased energy value of the fuel. Drying also decreases the biological degradation of the fuel. Taking all the above into consideration, waste heat drying could result in a 25 % increase of the biofuel potential in the forest industry in Sweden, without additional cutting of wood. A survey has been done to state which commercial technologies are available for biofuel drying with waste heat. An inquiry was sent out to a number of suppliers and included a few different cases. Relations for approximating investment cost as well as electric power demand were created based on the answers from the inquiry. These relations have then been used in the economical evaluations made for a number of cases representing both sawmills and pulp and paper mills

Estimating Residual Solids Volume In Underground Storage Tanks

International Nuclear Information System (INIS)

Clark, Jason L.; Worthy, S. Jason; Martin, Bruce A.; Tihey, John R.

2014-01-01

The Savannah River Site liquid waste system consists of multiple facilities to safely receive and store legacy radioactive waste, treat, and permanently dispose waste. The large underground storage tanks and associated equipment, known as the 'tank farms', include a complex interconnected transfer system which includes underground transfer pipelines and ancillary equipment to direct the flow of waste. The waste in the tanks is present in three forms: supernatant, sludge, and salt. The supernatant is a multi-component aqueous mixture, while sludge is a gel-like substance which consists of insoluble solids and entrapped supernatant. The waste from these tanks is retrieved and treated as sludge or salt. The high level (radioactive) fraction of the waste is vitrified into a glass waste form, while the low-level waste is immobilized in a cementitious grout waste form called saltstone. Once the waste is retrieved and processed, the tanks are closed via removing the bulk of the waste, chemical cleaning, heel removal, stabilizing remaining residuals with tailored grout formulations and severing/sealing external penetrations. The comprehensive liquid waste disposition system, currently managed by Savannah River Remediation, consists of 1) safe storage and retrieval of the waste as it is prepared for permanent disposition; (2) definition of the waste processing techniques utilized to separate the high-level waste fraction/low-level waste fraction; (3) disposition of LLW in saltstone; (4) disposition of the HLW in glass; and (5) closure state of the facilities, including tanks. This paper focuses on determining the effectiveness of waste removal campaigns through monitoring the volume of residual solids in the waste tanks. Volume estimates of the residual solids are performed by creating a map of the residual solids on the waste tank bottom using video and still digital images. The map is then used to calculate the volume of solids remaining in the waste tank. The ability to

Research and development of improved type radioactive waste volume reduction system

International Nuclear Information System (INIS)

Okamoto, Masahiro; Watanabe, Yoshifumi; Yamaoka, Katsuaki; Masaki, Tetsuo; Akagawa, Yoshihiro; Murakami, Tadashi; Miyake, Takashi.

1985-01-01

Development and research had been conducted since 1978 on an improved type radioactive waste volume reduction system incorporating calcining and incinerating fluidized bed type furnaces. This system can dispose of concentrated liquid wastes, combustible solid wastes, spent ion exchange resins and so forth by calcination or incineration to turn them into reduced-volume products. Recently a pilot test facility has constructed and tests has been conducted to demonstrate actual performance. Representative results of pilot tests are reported in this paper. (author)

Waste heat utilization in agriculture

International Nuclear Information System (INIS)

Horacek, P.

1983-01-01

The Proceedings contain 17 papers presented at meetings of the Working Group for Waste Heat Utilization of the Committee of the European Society of Nuclear Methods in Agriculture of which 7 fall under the INIS scope. The working group met in May 1980 in Brno, Czechoslovakia, in October 1981 in Aberdeen, Scotland and in September 1982 in Brno. (Z.M.)

Safe Management and disposal of nuclear waste. Volume 3

International Nuclear Information System (INIS)

1993-01-01

These proceedings of the international conference Safewaste 93, volume 3 are divided into three poster sessions bearing on: poster session P-1: Radioactive waste management and actinide burning; poster session P-2: Safety aspects of radioactive waste disposal; poster session P-3: Transport and disposal

Utilization of waste expanded polystyrene: Blends with silica-filled natural rubber

International Nuclear Information System (INIS)

Sekharan, Renju Vaikathusseril; Abraham, Beena Thattekatt; Thachil, Eby Thomas

2012-01-01

Highlights: ► Tensile strength of the silica filled blend is comparable with silica filled NR. ► Modulus and compression set were the best for compatibilized NR/EPS blends. ► Tear strength has increased by 25% for compatibilized blends. ► A 5% waste EPS can be incorporated into NR compounds as a waste management measure. -- Abstract: Expanded polystyrene (EPS) constitutes a considerable part of thermoplastic waste in the environment in terms of volume. In this study, this waste material has been utilized for blending with silica-reinforced natural rubber (NR). The NR/EPS (35/5) blends were prepared by melt mixing in a Brabender Plasticorder. Since NR and EPS are incompatible and immiscible a method has been devised to improve compatibility. For this, EPS and NR were initially grafted with maleic anhydride (MA) using dicumyl peroxide (DCP) to give a graft copolymer. Grafting was confirmed by Fourier Transform Infrared Spectroscopy (FTIR) spectroscopy. This grafted blend was subsequently blended with more of NR during mill compounding. Morphological studies using Scanning Electron Microscopy (SEM) showed better dispersion of EPS in the compatibilized blend compared to the noncompatibilized blend. By this technique, the tensile strength, elongation at break, modulus, tear strength, compression set and hardness of the blend were found to be either at par with or better than that of virgin silica filled NR compound. It is also noted that the thermal properties of the blends are equivalent with that of virgin NR. The study establishes the potential of this method for utilising waste EPS.

Alternatives for managing wastes from reactors and post-fission operations in the LWR fuel cycle. Volume 2. Alternatives for waste treatment

International Nuclear Information System (INIS)

1976-05-01

Volume II of the five-volume report is devoted to the description of alternatives for waste treatment. The discussion is presented under the following section titles: fuel reprocessing modifications; high-level liquid waste solidification; treatment and immobilization of chop-leach fuel bundle residues; treatment of noncombustible solid wastes; treatment of combustible wastes; treatment of non-high-level liquid wastes; recovery of transuranics from non-high-level wastes; immobilization of miscellaneous non-high-level wastes; volatile radioisotope recovery and off-gas treatment; immobilization of volatile radioisotopes; retired facilities (decontamination and decommissioning); and, modification and use of selected fuel reprocessing wastes

Alternatives for managing wastes from reactors and post-fission operations in the LWR fuel cycle. Volume 2. Alternatives for waste treatment

Energy Technology Data Exchange (ETDEWEB)

1976-05-01

Volume II of the five-volume report is devoted to the description of alternatives for waste treatment. The discussion is presented under the following section titles: fuel reprocessing modifications; high-level liquid waste solidification; treatment and immobilization of chop-leach fuel bundle residues; treatment of noncombustible solid wastes; treatment of combustible wastes; treatment of non-high-level liquid wastes; recovery of transuranics from non-high-level wastes; immobilization of miscellaneous non-high-level wastes; volatile radioisotope recovery and off-gas treatment; immobilization of volatile radioisotopes; retired facilities (decontamination and decommissioning); and, modification and use of selected fuel reprocessing wastes. (JGB)

The Utilization of Sago Waste as Cattle Feed

Science.gov (United States)

Tiro, B. M. W.; Beding, P. A.; Baliadi, Y.

2018-02-01

This study aimed was to evaluate nutrition value of sago waste and its effect on cattle performance.The collected data were analyzed using analysis of variance. The results of the study showed that of the utilization of sago waste had a positive effect on average daily gain (ADG), where with 2% sago waste of body weight (P2 treatment) gave the highest ADG 0.43 ± 0.02 kg/h/day and cattle which consumed only forage without sago waste (P0) gave the lowest ADG 0.26 ± 0.04 kg/h/day. Statistical analysis showed that the addition of sago waste significantly affected the ADG (P0.05), but significant affect(Pcattle.

Characterization of radioactive waste forms. Progress report for 1986 Volume 1

International Nuclear Information System (INIS)

Glasser, F.P.; McCulloch, C.

1988-01-01

The Council of Ministers of the European Communities adopted the third five-year EC programme of research on radioactive waste management and disposal in March 1985. It was recognized that the inevitable production of radioactive waste required perfecting and demonstrating systems for managing the waste produced by the nuclear industry, ensuring at the various stages the best possible protection of man and the environment. Task 3 of the programme 'evaluation of conditioned waste and qualification of engineered barriers' is subdivided into five sections. This book, in two volumes, is a compilation of reports on the progress achieved in four of the sections during 1986, the first year of the third programme. Volume 1 is concerned with Sections 1 and 5, 'Research on low -and medium- active waste' and 'Quality control methods'. Volume 2 covers Section 2 'HLW form characterization' and Section 3 'Other engineered barriers'. Section 4 'Development of standard test methods' is not included in this edition, as results from an interlaboratory round robin test now in progress will only be available for inclusion for the year 1988

Characterization of radioactive waste forms. Progress report for 1986 Volume 2

International Nuclear Information System (INIS)

Reed, D.L.; Mallinson, L.G.

1988-01-01

The Council of Ministers of the European Communities adopted the third five-year EC programme of research on radioactive waste management and disposal in March 1985. It was recognized that the inevitable production of radioactive waste required perfecting and demonstrating systems for managing the waste produced by the nuclear industry, ensuring at the various stages the best possible protection of man and the environment. Task 3 of the programme 'evaluation of conditioned waste and qualification of engineered barriers' is subdivided into five sections. This book, in two volumes, is a compilation of reports on the progress achieved in four of the sections during 1986, the first year of the third programme. Volume 1 is concerned with Sections 1 and 5, 'Research on low-and medium- active waste' and 'Quality control methods'. Volume 2 covers Section 2 'HLW form characterization' and Section 3 'Other engineered barriers' Section 4 'Development of standard test methods' is not included in this edition, as results from an interlaboratory round robin test now in progress will only be available for inclusion for the year 1988

Volume reduction by crystallization of low-level radioactive wastes

International Nuclear Information System (INIS)

Grant, D.C.; Murray, A.P.

1982-01-01

Low-level radioactive wastes containing boric acid, borax, or sodium sulfate, with radioactive contaminants, are generated during the operation of nuclear power plants. These wastes require disposal, and as such, it is economically and environmentally desirable to reduce their volume. Crystallization was examined in the laboratory as a means of accomplishing this. The crystallizer was operated in both of two modes: evaporative cooling and total evaporation. A 12 wt% boric acid waste feed was concentrated to a 40 to 45 wt% slurry in both modes of operation. Using pure boric acid, a slurry containing over 60 wt% was obtained. An 18.5 wt% borax waste feed was concentrated to 50 wt% in the total evaporative mode and 70 wt% in the evaporatively cooled mode. A 22 wt% sodium sulfate feed was concentrated to a 78 wt% slurry in the total evaporative mode. For all of the feeds, this represents a 4- to 5-fold volume reduction by the crystallizer

Process innovations to minimize waste volumes at Savannah River

International Nuclear Information System (INIS)

Doherty, J.P.

1986-01-01

In 1983 approximately 1.6 x 10 3 m 3 (427,000 gallons) of radioactive salt solution were decontaminated in a full-scale demonstration. The cesium decontamination factor (DF) was in excess of 4 x 10 4 vs. a goal of 1 x 10 4 . Data from this test were combined with pilot data and used to design the permanent facilities currently under construction. Startup of the Salt Decontamination Process is scheduled for 1987 and will decontaminate 2 x 10 4 m 3 (5.2 million gallons) of radioactive salt solution and generate 2 x 10 3 m 3 (520,000 gallons) of concentrated and washed precipitate per year. The Defense Waste Processing Facility (DWPF) will begin processing this concentrate in the Precipitate Hydrolysis Process starting in 1989. Laboratory data using simulated salt solution and nonradioactive cesium are being used to design this process. A 1/5-scale pilot plant is under construction and will be used to gain large-scale operating experience using nonradioactive simulants. This pilot plant is scheduled to startup in early 1987. The incentives to reduce the volume of waste that must be treated are self-evident. At Savannah River process development innovations to minimize the DWPF feed volumes have directly improved the economics of the process. The integrity of the final borosilicate glass water form has not been compromised by these developments. Many of the unit operations are familiar to chemical engineers and were put to use in a unique environment. As a result, tax dollars have been saved, and the objective of safely disposing of the nation's high-level defense waste has moved forward

Solid Waste Integrated Forecast Technical (SWIFT) Report FY 2001 to FY 2046 Volume 2

International Nuclear Information System (INIS)

BARCOT, R.A.

2001-01-01

The SWIFT Report provides up-to-date life cycle information about the radioactive solid waste expected to be managed by Hanford's Waste Management (WM) Project from onsite and offsite generators. This report is a mid-year update to the SWIFT 2001.0 report that was published in August 2000. The data contained in this report is the official data for solid waste forecasting until the SWIFT 2002.0 data is published in August 2001. This particular volume provides the following data reports: Annual volume data by waste generator; Summary volume data by location and DOE Office; Annual container type data by volume and count; and Annual physical waste form and waste specification record volume. This report also includes several minor changes from previous versions in an effort to increase the usability of the data and align with current Hanford Site organization changes. The changes include: Minor changes to waste generator names to make them more recognizable; Grouping of the waste generators into DOE Office and location (e.g, Office of River Protection, Fluor Hanford, Bechtel, etc); Addition of WSRd and Container Count sections; and Elimination of the ''functional group'' organization of the data (e.g., Facilities Transition, Spent Nuclear Fuel, etc)

Radioactive waste package assay facility. Volume 3. Data processing

International Nuclear Information System (INIS)

Creamer, S.C.; Lalies, A.A.; Wise, M.O.

1992-01-01

This report, in three volumes, covers the work carried out by Taylor Woodrow Construction Ltd, and two major sub-contractors: Harwell Laboratory (AEA Technology) and Siemens Plessey Controls Ltd, on the development of a radioactive waste package assay facility, for cemented 500 litre intermediate level waste drums. Volume 3, describes the work carried out by Siemens Plessey Controls Ltd on the data-processing aspects of an integrated waste assay facility. It introduces the need for a mathematical model of the assay process and develops a deterministic model which could be tested using Harwell experimental data. Relevant nuclear reactions are identified. Full implementation of the model was not possible within the scope of the Harwell experimental work, although calculations suggested that the model behaved as predicted by theory. 34 figs., 52 refs., 5 tabs

Amount of radioactive wastes in the Federal Republic of Germany - waste survey for the year 1988

International Nuclear Information System (INIS)

Brennecke, P.; Schumacher, J.

1989-06-01

On December 31, 1988, about 69 800 waste packages - about 40 700 m 3 - were stored in interim storage facilities. The unconditioned radioactive wastes amounted to about 11 700 m 3 . The volume of the conditioned radioactive wastes amounted to about 40 700 m 3 . Of this, the waste from nuclear research centres made up about 16 300 m 3 , the waste from the operation of nuclear power plants about 12 900 m 3 and that from the reprocessing of spent fuel elements about 8 300 m 3 . A prognosis was also made of the future amount of conditioned radioactive wastes. According to this forecast, the cumulated waste package volume of radioactive wastes with negligible heat generation will be approximately in the order of 173 400 m 3 up to the year 2000, whereas for heat-generating radioactive wastes a volume of about 5 800 m 3 is estimated. These figures already express the waste volume reduction according to modern conditioning techniques. In 1988 a capacity of about 123 800 m 3 for the interim storage of radioactive wastes was available in the Federal Republic of Germany. On December 31, 1988, an average of about 37% of this capacity was utilized by unconditioned and conditioned radioactive wastes. From the data on the expected amount of radioactive wastes and on the utilization factor of the interim storage facilities, it may be concluded that, taking an overall view, no bottlenecks in the interim storage of radioactive wastes with negligible heat generation are to be anticipated up to the planned operation of the Konrad repository in 1994. (orig./HP) [de

Radioactive wastes: the challenge of volumes reduction

International Nuclear Information System (INIS)

Lepetit, V.

2005-01-01

The reduction of radioactive waste volumes is a priority for the French atomic energy commission (CEA) and for the Areva group. This article gives a rapid overview of the equipments and processes used to separate the valorizable materials from the ultimate wastes: pulsed separation columns and evaporators for the liquid-liquid extraction, compactification of spent fuel hulls, remote handling systems, recoverable colloid for surface decontamination, decontaminating foam, hydrothermal oxidation of organic and aqueous effluents, cold crucible vitrification etc. (J.S.)

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

Energy Technology Data Exchange (ETDEWEB)

BARCOT, R.A.

2005-04-13

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

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

International Nuclear Information System (INIS)

BARCOT, R.A.

2005-01-01

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

A central solar-industrial waste heat heating system with large scale borehole thermal storage

NARCIS (Netherlands)

Guo, F.; Yang, X.; Xu, L.; Torrens, I.; Hensen, J.L.M.

2017-01-01

In this paper, a new research of seasonal thermal storage is introduced. This study aims to maximize the utilization of renewable energy source and industrial waste heat (IWH) for urban district heating systems in both heating and non-heating seasons through the use of large-scale seasonal thermal

Optimal planning for the sustainable utilization of municipal solid waste.

Science.gov (United States)

Santibañez-Aguilar, José Ezequiel; Ponce-Ortega, José María; Betzabe González-Campos, J; Serna-González, Medardo; El-Halwagi, Mahmoud M

2013-12-01

The increasing generation of municipal solid waste (MSW) is a major problem particularly for large urban areas with insufficient landfill capacities and inefficient waste management systems. Several options associated to the supply chain for implementing a MSW management system are available, however to determine the optimal solution several technical, economic, environmental and social aspects must be considered. Therefore, this paper proposes a mathematical programming model for the optimal planning of the supply chain associated to the MSW management system to maximize the economic benefit while accounting for technical and environmental issues. The optimization model simultaneously selects the processing technologies and their location, the distribution of wastes from cities as well as the distribution of products to markets. The problem was formulated as a multi-objective mixed-integer linear programing problem to maximize the profit of the supply chain and the amount of recycled wastes, where the results are showed through Pareto curves that tradeoff economic and environmental aspects. The proposed approach is applied to a case study for the west-central part of Mexico to consider the integration of MSW from several cities to yield useful products. The results show that an integrated utilization of MSW can provide economic, environmental and social benefits. Copyright © 2013 Elsevier Ltd. All rights reserved.

Incineration as a radioactive waste volume reduction process for CEA nuclear centers

International Nuclear Information System (INIS)

Atabek, R.; Chaudon, L.

1994-01-01

Incineration processes represent a promising solution for waste volume reduction, and will be increasingly used in the future. The features and performance specifications of low-level waste incinerators with capacities ranging from 10 to 20 kg - h -1 at the Fontenay-aux-Roses, Grenoble and Cadarache nuclear centers in France are briefly reviewed. More extensive knowledge of low-level wastes produced in facilities operated by the Commissariat a l'Energie Atomique (CEA) has allowed us to assess the volume reduction obtained by processing combustible waste in existing incinerators. Research and development work is in progress to improve management procedures for higher-level waste and to build facilities capable of incinerating α - contaminated waste. (authors). 6 refs., 5 figs., 1 tab

Volume reduction through incineration of low-activity radioactive wastes

International Nuclear Information System (INIS)

Eymeri, J.; Gauthey, J.C.; Chaise, D.; Lafite, G.

1993-01-01

The aim of the waste treatment plant, designed by Technicatome (CEA) for an Indonesian Nuclear Research Center, is to reduce through incineration the volume of low-activity radioactive wastes such as technological solids (cotton, PVC, paper board), biological solids (animal bones) and liquids (cutting fluids...). The complete combustion is realized with a total air multi-fuel burner (liquid wastes) and flash pyrolysis-complete combustion (solid wastes). A two stage flue gas filtration system, a flue gas washing system, and an ash recovery system are used. A test platform has been built. 3 figs

Ion Recognition Approach to Volume Reduction of Alkaline Tank Waste by Separation and Recycle of Sodium Hydroxide and Sodium Nitrate

International Nuclear Information System (INIS)

Moyer, Bruce A.; Marchand, Alan P.; Bonnesen, Peter V.; Bryan, Jeffrey C.; Haverlock, Tamara J.

2004-01-01

This research was intended to provide the scientific foundation upon which the feasibility of liquid-liquid extraction chemistry for bulk reduction of the volume of high-activity tank waste can be evaluated. Primary focus has been on sodium hydroxide separation, with potential Hanford application. Value in sodium hydroxide separation can potentially be found in alternative flowsheets for treatment and disposal of low-activity salt waste. Additional value can be expected in recycle of sodium hydroxide for use in waste retrieval and sludge washing, whereupon additions of fresh sodium hydroxide to the waste can be avoided. Potential savings are large both because of the huge cost of vitrification of the low-activity waste stream and because volume reduction of high-activity wastes could obviate construction of costly new tanks. Toward these ends, the conceptual development begun in the original proposal was extended with the formulation of eight fundamental approaches that could be undertaken for extraction of sodium hydroxide

Waste acceptance criteria study: Volume 2, Appendixes: Final report

International Nuclear Information System (INIS)

Johnson, E.R.; McLeod, N.B.; McBride, J.A.

1988-09-01

These appendices to the report on Waste Acceptance Criteria have been published as a separate volume for the convenience of the reader. They consist of the text of the 10CFR961 Contract for disposal of spent fuel, estimates of the cost (savings) to the DOE system of accepting different forms of spent fuel, estimates of costs of acceptance testing/inspection of spent fuel, illustrative specifications and procedures, and the resolution of comments received on a preliminary draft of the report. These estimates of costs contained herein preliminary and are intended only to demonstrate the trends in costs, the order of magnitude involved, and the methodology used to develop the costs. The illustrative specifications and procedures included herein have been developed for the purpose of providing a starting point for the development of a consensus on such matters between utilities and DOE

FY 2000 report on the results of the model project on facilities for the effective utilization of industrial waste from industrial complex. Separate Volume 3; 2000 nendo Kogyo danchi sangyo haikibutsu yuko riyo setsubi model jigyo. Dai 3 Bunsatsu

Energy Technology Data Exchange (ETDEWEB)

NONE

2002-03-01

For the purpose of promoting the effective utilization of industrial waste as petroleum substitution energy resource and reducing the consumption of fossil fuels in Thailand, a model project on facilities for the effective utilization of industrial waste from industrial complex was worked on, and the FY 2000 results were reported. In Separate Volume 3, drawings of the following were included: furnace, free board spray nozzle, dispersion air nozzle, secondary burner, sand make-up conveyor, sand discharge gate, boiler, silencer for boiler safety valve, steam header, steam accumulator, gas cooling tower, refuse drainage storage tank, small sized drainage pump, pressure tank, flue gas duct, air damper, incombustible conveyor 2, sand circulation system bag filter, weighing bridge, fan starter panel, control panel, control panel, local switch box, distributed control system, field instrument, flue gas analyzer. (NEDO)

Plastic solid waste utilization technologies: A Review

Science.gov (United States)

Awasthi, Arun Kumar; Shivashankar, Murugesh; Majumder, Suman

2017-11-01

Plastics are used in more number of applications in worldwide and it becomes essential part of our daily life. In Indian cities and villages people use the plastics in buying vegetable as a carry bag, drinking water bottle, use of plastic furniture in home, plastics objects uses in kitchen, plastic drums in packing and storage of the different chemicals for industrial use, use plastic utensils in home and many more uses. After usage of plastics it will become part of waste garbage and create pollution due to presence of toxic chemicals and it will be spread diseases and give birth to uncontrolled issues in social society. In current scenario consumption of plastic waste increasing day by day and it is very difficult to manage the plastic waste. There are limited methodologies available for reutilization of plastic waste again. Such examples are recycling, landfill, incineration, gasification and hydrogenation. In this paper we will review the existing methodologies of utilization of plastic waste in current scenario

Sustainable wood waste management in Nigeria

Directory of Open Access Journals (Sweden)

Owoyemi Jacob Mayowa

2016-09-01

Full Text Available Wood industries produce large volumes of residues which must be utilized, marketed or properly disposed of. Heaps of wood residues are common features in wood industries throughout the year. In Nigeria, this residue is generally regarded as waste and this has led to open burning practices, dumping in water bodies or dumping in an open area which constitutes environmental pollution. Sawmills in Nigeria generated over 1,000,000 m3 of wood waste in 2010 while about 5000 m3 of waste was generated in plywood mills. Nigeria generates about 1.8 million tons of sawdust annually and 5.2 million tons of wood wastes. The impact of improper disposal of waste wood on the environment affects both the aquatic and terrestrial ecosystems. Also burning of waste wood releases greenhouse gases into the atmosphere causing various health issues. Reuse/recycling of these wood residues in Nigeria will reduce the pressure on our ever decreasing forests, reduce environmental pollution, create wealth and employment. The literature available on this subject was reviewed and this article, therefore, focuses on the various methods of wood waste disposal and its utilization in Nigerian wood industries, the effects of wood waste on the environment as well as on human health and the benefits of proper wood waste management practices.

Developing a semi/automated protocol to post-process large volume, High-resolution airborne thermal infrared (TIR) imagery for urban waste heat mapping

Science.gov (United States)

Rahman, Mir Mustafizur

In collaboration with The City of Calgary 2011 Sustainability Direction and as part of the HEAT (Heat Energy Assessment Technologies) project, the focus of this research is to develop a semi/automated 'protocol' to post-process large volumes of high-resolution (H-res) airborne thermal infrared (TIR) imagery to enable accurate urban waste heat mapping. HEAT is a free GeoWeb service, designed to help Calgary residents improve their home energy efficiency by visualizing the amount and location of waste heat leaving their homes and communities, as easily as clicking on their house in Google Maps. HEAT metrics are derived from 43 flight lines of TABI-1800 (Thermal Airborne Broadband Imager) data acquired on May 13--14, 2012 at night (11:00 pm--5:00 am) over The City of Calgary, Alberta (˜825 km 2) at a 50 cm spatial resolution and 0.05°C thermal resolution. At present, the only way to generate a large area, high-spatial resolution TIR scene is to acquire separate airborne flight lines and mosaic them together. However, the ambient sensed temperature within, and between flight lines naturally changes during acquisition (due to varying atmospheric and local micro-climate conditions), resulting in mosaicked images with different temperatures for the same scene components (e.g. roads, buildings), and mosaic join-lines arbitrarily bisect many thousands of homes. In combination these effects result in reduced utility and classification accuracy including, poorly defined HEAT Metrics, inaccurate hotspot detection and raw imagery that are difficult to interpret. In an effort to minimize these effects, three new semi/automated post-processing algorithms (the protocol) are described, which are then used to generate a 43 flight line mosaic of TABI-1800 data from which accurate Calgary waste heat maps and HEAT metrics can be generated. These algorithms (presented as four peer-reviewed papers)---are: (a) Thermal Urban Road Normalization (TURN)---used to mitigate the microclimatic

Development of volume reduction treatment techniques for low level radioactive wastes

International Nuclear Information System (INIS)

Nabatame, Yasuzi

1984-01-01

The solid wastes packed in drums are preserved in the stores of nuclear establishments in Japan, and the quantity of preservation has already reached about 60 % of the capacity. It has become an important subject to reduce the quantity of generation of radioactive wastes and how to reduce the volume of generated wastes. As the result of the research aiming at the development of the solidified bodies which are excellent in the effect of volume reduction and physical properties, it was confirmed that the plastic solidified bodies using thermosetting resin were superior to conventional cement or asphalt solidification. The plastic solidifying system can treat various radioactive wastes. After radioactive wastes are dried and powdered, they are solidified with plastics, therefore, the effect of volume reduction is excellent. The specific gravity, strength and the resistance to water, fire and radiation were confirmed to be satisfacotory. The plastic solidifying system comprises three subsystems, that is, drying system, powder storing and supplying system and plastic solidifying system. Also the granulation technique after drying and powdering, acid decomposition technique, the microwave melting and solidifying technique for incineration ash, plasma melting process and electrolytic polishing decontamination are described. (Kako, I.)

Baseline tests for arc melter vitrification of INEL buried wastes. Volume 1: Facility description and summary data report

International Nuclear Information System (INIS)

Oden, L.L.; O'Connor, W.K.; Turner, P.C.; Soelberg, N.R.; Anderson, G.L.

1993-01-01

This report presents field results and raw data from the Buried Waste Integrated Demonstration (BWID) Arc Melter Vitrification Project Phase 1 baseline test series conducted by the Idaho National Engineering Laboratory (INEL) in cooperation with the U.S. Bureau of Mines (USBM). The baseline test series was conducted using the electric arc melter facility at the USBM Albany Research Center in Albany, Oregon. Five different surrogate waste feed mixtures were tested that simulated thermally-oxidized, buried, TRU-contaminated, mixed wastes and soils present at the INEL. The USBM Arc Furnace Integrated Waste Processing Test Facility includes a continuous feed system, the arc melting furnace, an offgas control system, and utilities. The melter is a sealed, 3-phase alternating current (ac) furnace approximately 2 m high and 1.3 m wide. The furnace has a capacity of 1 metric ton of steel and can process as much as 1,500 lb/h of soil-type waste materials. The surrogate feed materials included five mixtures designed to simulate incinerated TRU-contaminated buried waste materials mixed with INEL soil. Process samples, melter system operations data and offgas composition data were obtained during the baseline tests to evaluate the melter performance and meet test objectives. Samples and data gathered during this program included (a) automatically and manually logged melter systems operations data, (b) process samples of slag, metal and fume solids, and (c) offgas composition, temperature, velocity, flowrate, moisture content, particulate loading and metals content. This report consists of 2 volumes: Volume I summarizes the baseline test operations. It includes an executive summary, system and facility description, review of the surrogate waste mixtures, and a description of the baseline test activities, measurements, and sample collection. Volume II contains the raw test data and sample analyses from samples collected during the baseline tests

An annular BF3 counter of large sensitive volume

International Nuclear Information System (INIS)

Janardhanan, S.; Swaminathan, N.

1975-01-01

An annular neutron counter having a large sensitive volume with inner and outer diameter 31 cms with multiple electrode system fabricated especially to measure the neutron output from fissile region of standard fast reactor fuel of length nearly equivalent to 500 cms is described. The counter efficiency is nearly 0.3% for neutron and sensitivity 0.0018 counts/neutron for (alpha, neutron) and spontaneous fission source. Its other potential applications which are indicated are : (1) quality control of fast reactor fuel pins (2) fuel inventory (3) assessing radioactivity of solid waste packets containing PuO 2 (4) uniformity of fuel loading of a reactor and (5) neutron monitoring in a fuel plant. (M.G.B.)

Transport volume in regions of the Czech Republic in relation to the production of waste

OpenAIRE

Pojkarová, Kateřina; Hruška, Roman

2010-01-01

The article deals with the transport volume in regions of the Czech Republic in relation to the production of waste. On the basis of waste statistics and transport statistics is researched the greatness of the relation between the transport volume and the production of waste in regions of the Czech Republic. The relation is illustrated graphically too. We have many kinds of waste which we can monitor. The most important kinds of waste are municipal waste, industrial waste, construction ...

Technical summary of Groundwater Quality Protection Program at Savannah River Plant. Volume II. Radioactive waste

International Nuclear Information System (INIS)

Stone, J.A.; Christensen, E.J.

1983-12-01

This report (Volume II) presents representative monitoring data for radioactivity in groundwater at SRP. Four major groups of radioactive waste disposal sites and three minor sites are described. Much of the geohydrological and and other background information given in Volume I is applicable to these sites and is incorporated by reference. Several of the sites that contain mixed chemical and radioactive wastes are discussed in both Volumes I and II. Bulk unirradiated uranium is considered primarily a chemical waste which is addressed in Volume I, but generally not in Volume II

Performance Prediction for Large-Scale Nuclear Waste Repositories: Final Report

International Nuclear Information System (INIS)

Glassley, W E; Nitao, J J; Grant, W; Boulos, T N; Gokoffski, M O; Johnson, J W; Kercher, J R; Levatin, J A; Steefel, C I

2001-01-01

The goal of this project was development of a software package capable of utilizing terascale computational platforms for solving subsurface flow and transport problems important for disposal of high level nuclear waste materials, as well as for DOE-complex clean-up and stewardship efforts. We sought to develop a tool that would diminish reliance on abstracted models, and realistically represent the coupling between subsurface fluid flow, thermal effects and chemical reactions that both modify the physical framework of the rock materials and which change the rock mineralogy and chemistry of the migrating fluid. Providing such a capability would enhance realism in models and increase confidence in long-term predictions of performance. Achieving this goal also allows more cost-effective design and execution of monitoring programs needed to evaluate model results. This goal was successfully accomplished through the development of a new simulation tool (NUFT-C). This capability allows high resolution modeling of complex coupled thermal-hydrological-geochemical processes in the saturated and unsaturated zones of the Earth's crust. The code allows consideration of virtually an unlimited number of chemical species and minerals in a multi-phase, non-isothermal environment. Because the code is constructed to utilize the computational power of the tera-scale IBM ASCI computers, simulations that encompass large rock volumes and complex chemical systems can now be done without sacrificing spatial or temporal resolution. The code is capable of doing one-, two-, and three-dimensional simulations, allowing unprecedented evaluation of the evolution of rock properties and mineralogical and chemical change as a function of time. The code has been validated by comparing results of simulations to laboratory-scale experiments, other benchmark codes, field scale experiments, and observations in natural systems. The results of these exercises demonstrate that the physics and chemistry

MICROBIAL TRANSFORMATIONS OF TRU AND MIXED WASTES: ACTINIDE SPECIATION AND WASTE VOLUME REDUCTION.

Energy Technology Data Exchange (ETDEWEB)

FRANCIS, A.J.; DODGE, C.J.

2006-11-16

The overall goals of this research project are to determine the mechanism of microbial dissolution and stabilization of actinides in Department of Energy's (DOE) TRU wastes, contaminated sludges, soils, and sediments. This includes (1) investigations on the fundamental aspects of microbially catalyzed radionuclide and metal transformations (oxidation/reduction reactions, dissolution, precipitation, chelation); (2) understanding of the microbiological processes that control speciation and alter the chemical forms of complex inorganic/organic contaminant mixtures; and (3) development of new and improved microbially catalyzed processes resulting in immobilization of metals and radionuclides in the waste with concomitant waste volume reduction.

MICROBIAL TRANSFORMATIONS OF TRU AND MIXED WASTES: ACTINIDE SPECIATION AND WASTE VOLUME REDUCTION

Energy Technology Data Exchange (ETDEWEB)

Francis, A.J.; Dodge, C.J.

2006-06-01

The overall goals of this research project are to determine the mechanism of microbial dissolution and stabilization of actinides in Department of Energy’s (DOE) TRU wastes, contaminated sludges, soils, and sediments. This includes (i) investigations on the fundamental aspects of microbially catalyzed radionuclide and metal transformations (oxidation/reduction reactions, dissolution, precipitation, chelation); (ii) understanding of the microbiological processes that control speciation and alter the chemical forms of complex inorganic/organic contaminant mixtures; and (iii) development of new and improved microbially catalyzed processes resulting in immobilization of metals and radionuclides in the waste with concomitant waste volume reduction.

MICROBIAL TRANSFORMATIONS OF TRU AND MIXED WASTES: ACTINIDE SPECIATION AND WASTE VOLUME REDUCTION

Energy Technology Data Exchange (ETDEWEB)

Francis, A.J.; Dodge, C.J.

2006-06-01

The overall goals of this research project are to determine the mechanism of microbial dissolution and stabilization of actinides in Department of Energy's (DOE) TRU wastes, contaminated sludges, soils, and sediments. This includes (1) investigations on the fundamental aspects of microbially catalyzed radionuclide and metal transformations (oxidation/reduction reactions, dissolution, precipitation, chelation); (2) understanding of the microbiological processes that control speciation and alter the chemical forms of complex inorganic/organic contaminant mixtures; and (3) development of new and improved microbially catalyzed processes resulting in immobilization of metals and radionuclides in the waste with concomitant waste volume reduction.

METHODOLOGY & CALCULATIONS FOR THE ASSIGNMENT OF WASTE FOR THE LARGE UNDERGROUND WASTE STORAGE TANKS AT THE HANFORD SITE

Energy Technology Data Exchange (ETDEWEB)

TU, T.A.

2007-01-04

Waste stored within tank farm double-shell tanks (DST) and single-shell tanks (SST) generates flammable gas (principally hydrogen) to varying degrees depending on the type, amount, geometry, and condition of the waste. The waste generates hydrogen through the radiolysis of water and organic compounds, thermolytic decomposition of organic compounds, and corrosion of a tank's carbon steel walls. Radiolysis and thermolytic decomposition also generates ammonia. Nonflammable gases, which act as dilutents (such as nitrous oxide), are also produced. Additional flammable gases (e.g., methane) are generated by chemical reactions between various degradation products of organic chemicals present in the tanks. Volatile and semi-volatile organic chemicals in tanks also produce organic vapors. The generated gases in tank waste are either released continuously to the tank headspace or are retained in the waste matrix. Retained gas may be released in a spontaneous or induced gas release event (GRE) that can significantly increase the flammable gas concentration in the tank headspace as described in RPP-7771, Flammable Gas Safety Isme Resolution. Appendices A through I provide supporting information. The document categorizes each of the large waste storage tanks into one of several categories based on each tank's waste and characteristics. These waste group assignments reflect a tank's propensity to retain a significant volume of flammable gases and the potential of the waste to release retained gas by a buoyant displacement event. Revision 6 is the annual update of the flammable gas Waste Groups for DSTs and SSTs.

METHODOLOGY & CALCULATIONS FOR THE ASSIGNMENT OF WASTE GROUPS FOR THE LARGE UNDERGROUND WASTE STORAGE TANKS AT THE HANFORD SITE

Energy Technology Data Exchange (ETDEWEB)

BARKER, S.A.

2006-07-27

Waste stored within tank farm double-shell tanks (DST) and single-shell tanks (SST) generates flammable gas (principally hydrogen) to varying degrees depending on the type, amount, geometry, and condition of the waste. The waste generates hydrogen through the radiolysis of water and organic compounds, thermolytic decomposition of organic compounds, and corrosion of a tank's carbon steel walls. Radiolysis and thermolytic decomposition also generates ammonia. Nonflammable gases, which act as dilutents (such as nitrous oxide), are also produced. Additional flammable gases (e.g., methane) are generated by chemical reactions between various degradation products of organic chemicals present in the tanks. Volatile and semi-volatile organic chemicals in tanks also produce organic vapors. The generated gases in tank waste are either released continuously to the tank headspace or are retained in the waste matrix. Retained gas may be released in a spontaneous or induced gas release event (GRE) that can significantly increase the flammable gas concentration in the tank headspace as described in RPP-7771. The document categorizes each of the large waste storage tanks into one of several categories based on each tank's waste characteristics. These waste group assignments reflect a tank's propensity to retain a significant volume of flammable gases and the potential of the waste to release retained gas by a buoyant displacement event. Revision 5 is the annual update of the methodology and calculations of the flammable gas Waste Groups for DSTs and SSTs.

Optimal planning for the sustainable utilization of municipal solid waste

Energy Technology Data Exchange (ETDEWEB)

Santibañez-Aguilar, José Ezequiel [Chemical Engineering Department, Universidad Michoacana de San Nicolás de Hidalgo, Morelia, Michoacán 58060 (Mexico); Ponce-Ortega, José María, E-mail: jmponce@umich.mx [Chemical Engineering Department, Universidad Michoacana de San Nicolás de Hidalgo, Morelia, Michoacán 58060 (Mexico); Betzabe González-Campos, J. [Institute of Chemical and Biological Researches, Universidad Michoacana de San Nicolás de Hidalgo, Morelia, Michoacán 58060 (Mexico); Serna-González, Medardo [Chemical Engineering Department, Universidad Michoacana de San Nicolás de Hidalgo, Morelia, Michoacán 58060 (Mexico); El-Halwagi, Mahmoud M. [Chemical Engineering Department, Texas A and M University, College Station, TX 77843 (United States); Adjunct Faculty at the Chemical and Materials Engineering Department, Faculty of Engineering, King Abdulaziz University, P.O. Box 80204, Jeddah 21589 (Saudi Arabia)

2013-12-15

Highlights: • An optimization approach for the sustainable management of municipal solid waste is proposed. • The proposed model optimizes the entire supply chain network of a distributed system. • A case study for the sustainable waste management in the central-west part of Mexico is presented. • Results shows different interesting solutions for the case study presented. - Abstract: The increasing generation of municipal solid waste (MSW) is a major problem particularly for large urban areas with insufficient landfill capacities and inefficient waste management systems. Several options associated to the supply chain for implementing a MSW management system are available, however to determine the optimal solution several technical, economic, environmental and social aspects must be considered. Therefore, this paper proposes a mathematical programming model for the optimal planning of the supply chain associated to the MSW management system to maximize the economic benefit while accounting for technical and environmental issues. The optimization model simultaneously selects the processing technologies and their location, the distribution of wastes from cities as well as the distribution of products to markets. The problem was formulated as a multi-objective mixed-integer linear programing problem to maximize the profit of the supply chain and the amount of recycled wastes, where the results are showed through Pareto curves that tradeoff economic and environmental aspects. The proposed approach is applied to a case study for the west-central part of Mexico to consider the integration of MSW from several cities to yield useful products. The results show that an integrated utilization of MSW can provide economic, environmental and social benefits.

Optimal planning for the sustainable utilization of municipal solid waste

International Nuclear Information System (INIS)

Santibañez-Aguilar, José Ezequiel; Ponce-Ortega, José María; Betzabe González-Campos, J.; Serna-González, Medardo; El-Halwagi, Mahmoud M.

2013-01-01

Highlights: • An optimization approach for the sustainable management of municipal solid waste is proposed. • The proposed model optimizes the entire supply chain network of a distributed system. • A case study for the sustainable waste management in the central-west part of Mexico is presented. • Results shows different interesting solutions for the case study presented. - Abstract: The increasing generation of municipal solid waste (MSW) is a major problem particularly for large urban areas with insufficient landfill capacities and inefficient waste management systems. Several options associated to the supply chain for implementing a MSW management system are available, however to determine the optimal solution several technical, economic, environmental and social aspects must be considered. Therefore, this paper proposes a mathematical programming model for the optimal planning of the supply chain associated to the MSW management system to maximize the economic benefit while accounting for technical and environmental issues. The optimization model simultaneously selects the processing technologies and their location, the distribution of wastes from cities as well as the distribution of products to markets. The problem was formulated as a multi-objective mixed-integer linear programing problem to maximize the profit of the supply chain and the amount of recycled wastes, where the results are showed through Pareto curves that tradeoff economic and environmental aspects. The proposed approach is applied to a case study for the west-central part of Mexico to consider the integration of MSW from several cities to yield useful products. The results show that an integrated utilization of MSW can provide economic, environmental and social benefits

Greater-than-Class C low-level waste characterization. Appendix I: Impact of concentration averaging low-level radioactive waste volume projections

International Nuclear Information System (INIS)

Tuite, P.; Tuite, K.; O'Kelley, M.; Ely, P.

1991-08-01

This study provides a quantitative framework for bounding unpackaged greater-than-Class C low-level radioactive waste types as a function of concentration averaging. The study defines the three concentration averaging scenarios that lead to base, high, and low volumetric projections; identifies those waste types that could be greater-than-Class C under the high volume, or worst case, concentration averaging scenario; and quantifies the impact of these scenarios on identified waste types relative to the base case scenario. The base volume scenario was assumed to reflect current requirements at the disposal sites as well as the regulatory views. The high volume scenario was assumed to reflect the most conservative criteria as incorporated in some compact host state requirements. The low volume scenario was assumed to reflect the 10 CFR Part 61 criteria as applicable to both shallow land burial facilities and to practices that could be employed to reduce the generation of Class C waste types

Solid low level waste management guidelines: Final report

International Nuclear Information System (INIS)

Castagnacci, A.; Dalton, D.; Genoa, P.

1994-11-01

Since 1989, the nuclear industry has been moving in the direction of greater minimization of low level radioactive waste (LLW). This has been driven in part by increasing regulatory attention, but it also is in response to the desire on the part of nuclear utilities to be more cost efficient and to be environmentally responsive. Over the past half-dozen years, LLW disposal costs have increased dramatically. In addition, improvements in LLW volume reduction technologies have substantially reduced the volume of LLW that is disposed. At the same time, utilities are implementing aggressive source reduction programs and programs to reuse materials so as to extend the useful life of many materials. Thus, there has been a dramatic change in LLW economics and LLW management practices in just the past few years. This report was developed by utility nuclear experts to provide guidance to all utilities on mechanisms for integrating the program economics, advanced volume reduction techniques, and approaches to source reduction. Thus, utilizes will be able to use this report as a guide to optimizing their LLW program economics and minimizing LLW disposal volumes to the smallest reasonable fraction. This report discusses the implementation of these guidelines, management support, waste materials and waste inventory, radioactive tool and equipment management, protective clothing management, processing and volume reduction, solid LLW tracking, outage LLW management, and interim storage of LLW

Large packages for reactor decommissioning waste

International Nuclear Information System (INIS)

Price, M.S.T.

1991-01-01

This study was carried out jointly by the Atomic Energy Establishment at Winfrith (now called the Winfrith Technology Centre), Windscale Laboratory and Ove Arup and Partners. The work involved the investigation of the design of large transport containers for intermediate level reactor decommissioning waste, ie waste which requires shielding, and is aimed at European requirements (ie for both LWR and gas cooled reactors). It proposes a design methodology for such containers covering the whole lifetime of a waste disposal package. The design methodology presented takes account of various relevant constraints. Both large self shielded and returnable shielded concepts were developed. The work was generic, rather than specific; the results obtained, and the lessons learned, remain to be applied in practice

Technical support for GEIS: radioactive waste isoltaion in geologic formations. Volume 19. Thermal analyses

International Nuclear Information System (INIS)

1978-04-01

This volume, Y/OWI/TM-36/19, ''Thermal Analyses,'' is one of a 23-volume series, ''Technical Support for GEIS: Radioactive Waste Isolation in Geologic Formations,'' Y/OWI/TM-36, which supplements the ''Contribution to Draft Generic Environmental Impact Statement on Commercial Waste Management: Radioactive Waste Isolation in Geologic Formations,'' Y/OWI/TM-44. The series provides a more complete technical basis for the preconceptual designs, resource requirements, and environmental source terms associated with isolating commercial LWR wastes in underground repositories in salt, granite, shale and basalt. Wastes are considered from three fuel cycles: uranium and plutonium recycling, no recycling of spent fuel and uranium-only recycling. This volume discusses the thermal impacts of the isolated high level and spent-fuel wastes in geologic formations. A detailed account of the methodologies employed is given as well as selected results of the analyses

Analysis of the reduction in waste volumes received for disposal at the low-level radioactive waste site in the State of Washington

International Nuclear Information System (INIS)

Ko, S.

1988-01-01

The commercial low-level radioactive waste (LLRW) disposal site at Richland, Washington has been receiving waste from generators nationwide since 1965 and is one of the three sites in the nation currently receiving commercial LLRW for disposal. In the past, volumes of LLRW have been increasing steadily, however, this trend has reversed since 1986. This paper addresses waste volume and activity of the waste disposed, factors which have caused this dramatic reduction in LLRW volume, and regulatory concerns regarding environmental protection, and public and occupational health and safety. Future volumes of LLRW that are disposed at the Richland site depend on economic, technological, political and regulatory variables. Provided there is a continual increase in industrial growth, and a demand for medical research and diagnosis, the volume of LLRW increases. However, this volume also offsets by an increase in demand for volume reduction due to economic and institutional pressures. Yet, if all generators continue to volume reduce their LLRW, some time in future, a limit will be reached when the facility site operator needs to increase the unit disposal cost to cover the fixed cost and maintain a profit margin in order to operate the site

Waste management aspects of entire PWR LOOP decontamination

International Nuclear Information System (INIS)

Murray, A.P.; Roesmer, J.

1988-01-01

The waste management parameters for decontamination of an entire PWR primary circuit have been determined for dilute alkaline-permanganate/citric acid (APCA), LOMI, ozone and cerium acid process variations. APCA processes generate the largest waste volumes; over 140 m 3 (5000 ft 3 ) in some cases. This represents a potential disposal cost of one million dollars. The cation regeneration column makes the greatest contribution to the disposal volume. In contrast, the LOMI process generates approximately half as much waste, but it is expected to contain relatively high metal concentrations (200-800 ppm). The ozone and cerium acid processes product the least waste, usually under 45 m 3 . These waste volume estimates represent considerable fractions of a utility's annual disposal volume. Consequently, improved waste processing technology is required, and several approaches are suggested

Low-level radioactive waste from commercial nuclear reactors. Volume 3. Bibliographic abstracts of significant source documents. Part 1. Open-literature abstracts for low-level radioactive waste

International Nuclear Information System (INIS)

Bowers, M.K.; Rodgers, B.R.; Jolley, R.L.

1986-05-01

The overall task of this program was to provide an assessment of currently available technology for treating commercial low-level radioactive waste (LLRW), to initiate development of a methodology for choosing one technology for a given application, and to identify research needed to improve current treatment techniques and decision methodology. The resulting report is issued in four volumes. Volume 3 of this series is a collection of abstracts of most of the reference documents used for this study. Because of the large volume of literature, the abstracts have been printed in two separate parts. Volume 3, part 1 presents abstracts of the open literature relating to LLRW treatment methodologies. Some of these references pertain to treatment processes for hazardous wastes that may also be applicable to LLRW management. All abstracts have been limited to 21 lines (for brevity), but each abstract contains sufficient information to enable the reader to determine the potential usefulness of the source document and to locate each article. The abstracts are arranged alphabetically by author or organization, and indexed by keyword

Low-level radioactive waste from commercial nuclear reactors. Volume 3. Bibliographic abstracts of significant source documents. Part 1. Open-literature abstracts for low-level radioactive waste

Energy Technology Data Exchange (ETDEWEB)

Bowers, M.K.; Rodgers, B.R.; Jolley, R.L.

1986-05-01

The overall task of this program was to provide an assessment of currently available technology for treating commercial low-level radioactive waste (LLRW), to initiate development of a methodology for choosing one technology for a given application, and to identify research needed to improve current treatment techniques and decision methodology. The resulting report is issued in four volumes. Volume 3 of this series is a collection of abstracts of most of the reference documents used for this study. Because of the large volume of literature, the abstracts have been printed in two separate parts. Volume 3, part 1 presents abstracts of the open literature relating to LLRW treatment methodologies. Some of these references pertain to treatment processes for hazardous wastes that may also be applicable to LLRW management. All abstracts have been limited to 21 lines (for brevity), but each abstract contains sufficient information to enable the reader to determine the potential usefulness of the source document and to locate each article. The abstracts are arranged alphabetically by author or organization, and indexed by keyword.

Liquide waste volume reduction by in-drum drying system

International Nuclear Information System (INIS)

Volaric, B.; Zorko, M.

1998-01-01

The disposal of radioactive waste is becoming increasingly difficult because of the lack of available volume on site, the rising disposal costs and the lack of ultimate disposal sites. Optimized treatment and volume reduction of concentrates and spent resins prior to interim storage, final disposal, and solidification processes are major step to counteract the situation.(author)

The acid digestion process for radioactive waste: The radioactive waste management series. Volume II

International Nuclear Information System (INIS)

Cecille, L.; Simon, R.

1983-01-01

This volume focuses on the acid digestion process for the treatment of alpha combustible solid waste by presenting detailed performance figures for the principal sub-assemblies of the Alona pilot plant, Belgium. Experience gained from the operation of the US RADTU plant, the only other acid digestion pilot plant, is also summarized, and the performances of these two plants compared. In addition, the research and development programmes carried out or supported by the Commission of the European Communities are reviewed, and details of an alternative to acid digestion for waste contamination described. Topics considered include review of the treatment of actinides-bearing radioactive wastes; alpha waste arisings in fuel fabrication; Alona Demonstration Facility for the acid digestion process at Eurochemic Mol (Belgium); the treatment of alpha waste at Eurochemic by acid digestion-feed pretreatment and plutonium recovery; US experience with acid digestion of combustible transuranic waste; and The European Communities R and D actions on alpha waste

The pyrolytic-plasma method and the device for the utilization of hazardous waste containing organic compounds

Energy Technology Data Exchange (ETDEWEB)

Opalińska, Teresa [Tele and Radio Research Institute, Ratuszowa 11, 03-450 Warsaw (Poland); Wnęk, Bartłomiej, E-mail: bartlomiej.wnek@itr.org.pl [Tele and Radio Research Institute, Ratuszowa 11, 03-450 Warsaw (Poland); Witowski, Artur; Juszczuk, Rafał; Majdak, Małgorzata [Tele and Radio Research Institute, Ratuszowa 11, 03-450 Warsaw (Poland); Bartusek, Stanilav [VŠB—Technical University of Ostrava, 17. listopadu 15/2172, 708 33 Ostrava − Poruba Czech Republic (Czech Republic)

2016-11-15

Highlights: • A first stage of the process of waste utilization consisted in pyrolysis of waste. • Then the pyrolytic gas was oxidized with a use of non-equilibrium plasma. • The device for the process implementation was built and characterized. • Correctness of the device operation was proven with a use of the decomposition of PE. • Usefulness of the method was proven in the process of utilization of EW. - Abstract: This paper is focused on the new method of waste processing. The waste, including hazardous waste, contain organic compounds. The method consists in two main processes: the pyrolysis of waste and the oxidation of the pyrolytic gas with a use of non-equilibrium plasma. The practical implementation of the method requires the design, construction and testing of the new device in large laboratory scale. The experiments were carried out for the two kinds of waste: polyethylene as a model waste and the electronic waste as a real waste. The process of polyethylene decomposition showed that the operation of the device is correct because 99.74% of carbon moles contained in the PE samples was detected in the gas after the process. Thus, the PE samples practically were pyrolyzed completely to hydrocarbons, which were completely oxidized in the plasma reactor. It turned out that the device is useful for decomposition of the electronic waste. The conditions in the plasma reactor during the oxidation process of the pyrolysis products did not promote the formation of PCDD/Fs despite the presence of the oxidizing conditions. An important parameter determining the efficiency of the oxidation of the pyrolysis products is gas temperature in the plasma reactor.

Tank Waste Remediation System, Hanford Site, Richland, Washington. Final Environmental Impact Statement. Volume II

International Nuclear Information System (INIS)

1996-08-01

This document, Volume 2, provides the inventory of waste addressed in this Final Environmental Impact Statement (EIS) for the Tank Waste Remediation System, Hanford Site, Richland, Washington. The inventories consist of waste from the following four groups: (1) Tank waste; (2) Cesium (Cs) and Strontium (Sr) capsules; (3) Inactive miscellaneous underground storage tanks (MUSTs); and (4) Anticipated future tank waste additions. The major component by volume of the overall waste is the tank waste inventory (including future tank waste additions). This component accounts for more than 99 percent of the total waste volume and approximately 70 percent of the radiological activity of the four waste groups identified previously. Tank waste data are available on a tank-by-tank basis, but the accuracy of these data is suspect because they primarily are based on historical records of transfers between tanks rather than statistically based sampling and analyses programs. However, while the inventory of any specific tank may be suspect, the overall inventory for all of the tanks combined is considered more accurate. The tank waste inventory data are provided as the estimated overall chemical masses and radioactivity levels for the single-shell tanks (SSTs) and double-shell tanks (DSTs). The tank waste inventory data are broken down into tank groupings or source areas that were developed for analyzing groundwater impacts

Research of the indicators the volume of the biodegradable waste on the landfills

Directory of Open Access Journals (Sweden)

Jana Kotovicová

2005-01-01

Full Text Available The orientation of the research work for the exploitation of the preventive tools for the decrease of bio- degradable waste comes out from the requirements, which are reposed on Czech Republic as a valid member of European Union. The Czech Republic have to follow the legislative requirements, which are defined for the waste treatment, in this case it deals with the EC Landfill Directive (1999/31/ES. The directive undertakes for the EU members to limit the volume of the biodegradable waste on the landfills. The main sense of this restriction is to reduce the volume of the emitted gas, mainly methane, into atmosphere. Therefore, it was assigned the Waste Management Plan of the Czech republic, which states in the interest of the strategic goals (the decrease of the specific waste production independently on the level of the economic growth, the maximal waste exploitation as a reserve of the primary natural resources and the minimalization of negative impacts on human health and environment by the waste treatment the goal achievement in its binding part, whatęs the decrease of maximal volume of the biodegradable municipal waste deposited in landfills, thus the rate of this element will be the most 75% weighted in 2010, the most 50 % weighted in 2013 and the most 35 % weighted from the total volume rised in 1995. One of the ways, how to achieve the required reduction of the waste volume deposited in the landfills, is consistent exercitation of the preventive methods and the sound agricultural and sound operating practice methods. The main goal of the work consists in creation of methodics for the make prognosis of the region development charging by the biodegradable waste in the preventive tool exploitation. I identified the typical sources of biodegradable waste and the key areas of their uprise after the evaluation of environmental gains of the selected preventive projects by the creation of methodics. After this manner of data acquirement, I�

Practical guidelines for small-volume additions of uninhibited water to waste storage tanks

International Nuclear Information System (INIS)

Hsu, T.C.; Wiersma, B.J.; Zapp, P.E.; Pike, J.A.

1994-01-01

Allowable volumes of uninhibited water additions to waste tanks are limited to volumes in which hydroxide and nitrite inhibitors reach required concentrations by diffusion from the bulk waste within five days. This diffusion process was modeled conservatively by Fick's second law of diffusion. The solution to the model was applied to all applicable conditions which exist in the waste tanks. Plant engineers adapted and incorporated the results into a practical working procedure for controlling and monitoring the addition of uninhibited water. Research, technical support, and field engineers worked together to produce an effective solution to a potential waste tank corrosion problem

Waste utilization strategies and markets in Europe, the export potential

International Nuclear Information System (INIS)

Vaeisaenen, P.

2001-01-01

Over 4000 million tons of solid wastes are generated annually in OECD countries, of which the share of EU countries is about 2000 million tons. The share of municipal wastes is about 200 million tons. Germany, France, Great Britain and Spain are the largest producers of wastes in EU. In Eastern Europe Russia, Turkey, Poland and Ukraine are the largest waste producers. Statistics show that at the end of the past decade 60% of wastes produced in EU countries were still dumped in dumping sites. The share of waste incineration was about 20% and that of composting about 6%. The corresponding value of mechanical waste processing was 6% and that of other waste processing methods 8%. The number of dumping sites in the 1995 statistics was 26 169 and the number of waste incineration plants 1258, most of which are small plants. Waste management strategies vary country by country. A common feature for all of these is that several waste processing methods are needed and the relative shares of them depend on the basic solution of waste management. The cities, which incinerated wastes 100 years ago, do the same today and the cities, the waste management of which based on dumping, dump the wastes even to day. In the future the number of dumping sites decreases in all countries, and the share of recycling, incineration and mechanical/biological processing increases. The large variety of waste processing methods in Finland has caused many problems, broad waste management cooperation is difficult, nation-wide information delivery can not be used effectively, terminology is non-uniform, etc. This is reflected to sort separation of wastes for energy purposes. Sorted waste for manufacture of REF can in principle be obtained from two routes: (1) the separated sorting of energy waste, or (2) dry waste, remaining after recovery of materials fraction. Both of the models are in use in Finland in different locations having special features typical for the location. Both of these methods have

Yield of radioactive wastes in the Federal Republic of Germany - waste survey for the year 1986

International Nuclear Information System (INIS)

Brennecke, P.; Schumacher, J.

1987-05-01

On December 31, about 67600 waste packages were stored in interim storage facilities. The unconditioned radioactive wastes amounted to about 6600 m 3 . The volume of the conditioned radioactive wastes amounted to about 33900 m 3 . Thereof the waste from nuclear research establishments made up about 13300 m 3 , the waste from the operation of nuclear power plants about 10700 m 3 and the waste from reprocessing of spent fuel elements about 6700 m 3 . In addition the future amount of conditioned radioactive wastes with negligible heat generation was prognosticated. According to this forecast, the waste package volume will be approximately in the order of 218200 m 3 up to the year 2000. In 1986 a capacity of about 97500 m 3 for the interim storage of radioactive wastes was available in the Federal Republic of Germany. On December 31, 1986, this capacity was utilized by unconditioned and conditioned radioactive wastes at an average of about 38%. It may be concluded from the data on the expected amount of radioactive wastes with negligible heat generation and on the utilization factor of the interim storage facilities that no bottlenecks are to be assumed up to the planned operation of the Konrad repository. (orig./RB) [de

Technical support for GEIS: radioactive waste isolation in geologic formations. Volume 16. Repository preconceptual design studies: BPNL waste forms in salt

International Nuclear Information System (INIS)

1978-04-01

This volume, Volume 16, ''Repository Preconceptual Design Studies: BPNL Waste Forms in Salt,'' is one of a 23 volume series, ''Technical Support for GEIS: Radioactive Waste Isolation in Geologic Formations,'' Y/OWI/TM-36, which supplements the ''Contribution to Draft Generic Environmental Impact Statement on Commercial Waste Management: Radioactive Waste Isolation in Geologic Formations,'' Y/OWI/TM-44. The series provide a more complete technical basis for the preconceptual designs, resource requirements, and environmental source terms associated with isolating commercial LWR wastes in underground repositories in salt, granite, shale and basalt. Wastes are considered from three fuel cycles: uranium and plutonium recycling, no recycling of spent fuel and uranium-only recycling. This document describes a preconceptual design for a nuclear waste storage facility in salt. The waste forms assumed to arrive at the repository were supplied by Battelle Pacific Northwest Laboratories (BPNL). The facility design consists of several chambers excavated deep within a geologic formation together with access shafts and supportive surface structures. The facility design provides for: receiving and unloading waste containers; lowering them down shafts to the mine level; transporting them to the proper storage area and emplacing them in mined storage rooms. Drawings of the facility design are contained in TM-36/17, ''Drawings for Repository Preconceptual Design Studies: BPNL Waste Forms in Salt.''

Ceramic transactions: Environmental and waste management issues in the ceramic industry. Volume 39

International Nuclear Information System (INIS)

Mellinger, G.B.

1994-01-01

A symposium on environmental and waste management issues in the ceramic industry took place in Cincinnati, Ohio, April 19-22, 1993. The symposium was held in conjunction with the 95th Annual Meeting of the American Ceramic Society and was sponsored by the Ceramic Manufacturing Council, Legislative and Regulatory Affairs Committee with the Glass and Optical Materials, Basic Science, Cements, Nuclear, Refractory Ceramics, Structural Clay Products, Whitewares, Design, Electronics, Engineering Ceramics, and Materials and Equipment Divisions. This volume documents several of the papers that were presented at the symposium. Papers presented in this volume are categorized under the following headings: vitrification of hazardous and mixed wastes; waste glass properties and microstructure; processing of nuclear waste disposal glasses; waste form qualification; glass dissolution: modeling and mechanisms; systems and field testing of waste forms

Technical support for GEIS: radioactive waste isolation in geologic formations. Volume 2. Commercial waste forms, packaging and projections for preconceptual repository design studies

International Nuclear Information System (INIS)

1978-04-01

This volume, Y/OWI/TM-36/2, ''Commercial Waste Forms, Packaging and Projections for Preconceptual Repository Design Studies,'' is one of a 23-volume series, ''Technical Support for GEIS: Radioactive Waste Isolation in Geologic Formations,'' Y/OWI/TM-36, which supplements the ''Contribution to Draft Generic Environmental Impact Statement on Commercial Waste Management: Radioactive Waste Isolation in Geologic Formations,'' Y/OWI/TM-44. The series provides a more complete technical basis for the preconceptual designs, resource requirements, and environmental source terms associated with isolating commercial LWR wastes in underground repositories in salt, granite, shale and basalt. Wastes are considered from three fuel cycles: uranium and plutonium recycling, no recycling of spent fuel and uranium-only recycling. This volume contains the data base for waste forms, packages, and projections from the commercial waste defined by the Office of Waste Isolation in ''Nuclear Waste Projections and Source Term Data for FY 1977,'' Y/OWI/TM-34. Also, as an alternative data base for repository design and analysis, waste forms, packages, and projections for commercial waste defined by Battelle Pacific Northwest Laboratory (BPNL) have been included. This data base consists of a reference case for use in the alternative design study and a definition of combustible wastes for use in mine fire and hydrogen generation analyses

Waste regular management: experience and progress prospects

International Nuclear Information System (INIS)

Lallement, R.

1997-01-01

Since 1990, the CEA has devoted important financial means for the radioactive civilian waste cleaning of its centers: radioactive waste processing (and especially large stocks of ancient wastes), useless-fuel management for fuels produced by experimental reactors and laboratories, and wastes produced by ancient nuclear facilities dismantlement. A policy towards waste volume reduction had already led to a 20 pc volume reduction of its low-level wastes since 1993

Current trends of tropical fruit waste utilization.

Science.gov (United States)

Cheok, Choon Yoong; Mohd Adzahan, Noranizan; Abdul Rahman, Russly; Zainal Abedin, Nur Hanani; Hussain, Norhayati; Sulaiman, Rabiha; Chong, Gun Hean

2018-02-11

Recent rapid growth of the world's population has increased food demands. This phenomenon poses a great challenge for food manufacturers in maximizing the existing food or plant resources. Nowadays, the recovery of health benefit bioactive compounds from fruit wastes is a research trend not only to help minimize the waste burden, but also to meet the intensive demand from the public for phenolic compounds which are believed to have protective effects against chronic diseases. This review is focused on polyphenolic compounds recovery from tropical fruit wastes and its current trend of utilization. The tropical fruit wastes include in discussion are durian (Durio zibethinus), mangosteen (Garcinia mangostana L.), rambutan (Nephelium lappaceum), mango (Mangifera indica L.), jackfruit (Artocarpus heterophyllus), papaya (Carica papaya), passion fruit (Passiflora edulis), dragon fruit (Hylocereus spp), and pineapple (Ananas comosus). Highlights of bioactive compounds in different parts of a tropical fruit are targeted primarily for food industries as pragmatic references to create novel innovative health enhancement food products. This information is intended to inspire further research ideas in areas that are still under-explored and for food processing manufacturers who would like to minimize wastes as the norm of present day industry (design) objective.

Method for utilizing decay heat from radioactive nuclear wastes

International Nuclear Information System (INIS)

Busey, H.M.

1974-01-01

Management of radioactive heat-producing waste material while safely utilizing the heat thereof is accomplished by encapsulating the wastes after a cooling period, transporting the capsules to a facility including a plurality of vertically disposed storage tubes, lowering the capsules as they arrive at the facility into the storage tubes, cooling the storage tubes by circulating a gas thereover, employing the so heated gas to obtain an economically beneficial result, and continually adding waste capsules to the facility as they arrive thereat over a substantial period of time

Tank Farm Contractor Waste Remediation System and Utilization Plan

International Nuclear Information System (INIS)

KIRKBRIDE, R.A.

1999-01-01

The Tank Waste Remediation System Operation and Utilization Plan updates the operating scenario and plans for the delivery of feed to BNFL Inc., retrieval of waste from single-shell tanks, and the overall process flowsheets for Phases I and II of the privatization of the Tank Waste Remediation System. The plans and flowsheets are updated with the most recent tank-by-tank inventory and sludge washing data. Sensitivity cases were run to evaluate the impact or benefits of proposed changes to the BNFL Inc. contract and to evaluate a risk-based SST retrieval strategy

Russian low-level waste disposal program

Energy Technology Data Exchange (ETDEWEB)

Lehman, L. [L. Lehman and Associates, Inc., Burnsville, MN (United States)

1993-03-01

The strategy for disposal of low-level radioactive waste in Russia differs from that employed in the US. In Russia, there are separate authorities and facilities for wastes generated by nuclear power plants, defense wastes, and hospital/small generator/research wastes. The reactor wastes and the defense wastes are generally processed onsite and disposed of either onsite, or nearby. Treating these waste streams utilizes such volume reduction techniques as compaction and incineration. The Russians also employ methods such as bitumenization, cementation, and vitrification for waste treatment before burial. Shallow land trench burial is the most commonly used technique. Hospital and research waste is centrally regulated by the Moscow Council of Deputies. Plans are made in cooperation with the Ministry of Atomic Energy. Currently the former Soviet Union has a network of low-level disposal sites located near large cities. Fifteen disposal sites are located in the Federal Republic of Russia, six are in the Ukraine, and one is located in each of the remaining 13 republics. Like the US, each republic is in charge of management of the facilities within their borders. The sites are all similarly designed, being modeled after the RADON site near Moscow.

Acceptance issues for large items and difficult waste

International Nuclear Information System (INIS)

Palmer, J.; Lock, Peter

2002-01-01

Peter Lock described some particular cases which had given rise to difficult acceptance issues at NIREX, ranging from large size items to the impacts of chemicals used during decontamination on the mobility of radionuclides in a disposal facility: The UK strategy for intermediate level and certain low level radioactive waste disposal is based on production of cementitious waste-forms packaged in a standard range of containers as follows: 500 litre Drum - the normal container for most operational ILW (0.8 m diameter x 1.2 m high); 3 m"3 Box - a larger container for solid wastes (1.72 m x 1.72 m plan x 1.2 m high); 3 m"3 Drum - a larger container for in-drum mixing and immobilisation of sludge waste-forms (1.72 m diameter x 1.2 m high); 4 m Box - for large items of waste, especially from decommissioning (4.0 m x 2.4 m plan x 2.2 m high); 2 m LLW Box - for higher-density wastes (2.0 m x 2.4 m plan x 2.2 m high). In addition the majority of LLW is packaged by supercompaction followed by grouting in modified ISO freight containers (6 m x 2.5 m x 2.5 m). Some wastes do not fit easily into this strategy. These wastes include: very large items, (too big for the 4 m box) which, if dealt with whole, pose transport and disposal problems. These items are discussed further in Section 2; waste whose characteristics make packaging difficult. Such wastes are described in more detail in Section 3

Consolidated PCBs [polychlorinated biphenyls] improves waste control

International Nuclear Information System (INIS)

Smith, E.

1991-01-01

Consolidation of polychlorinated biphenyl (PCB) wastes is recommended for improving ownership control of wastes, eliminating PCB storage sites, and increasing cost-effectiveness of waste management. In Ontario, sites receiving the waste must be owned by the waste generator and registered as a PCB site. All PCBs must be removed from a site with no contaminated materials or wastes left behind, which requires a thorough site assessment to identify wastes prior to removal, a sampling and analytical scheme if necessary, and an approved plan for site cleanup. If large volumes of PCB-contaminated oil are involved, it may be cost-effective to put oil from several sites into bulk tanks and thus avoid the need to handle and decontaminate a large number of drums. With low volumes of oil, it may be possible to move the waste to another site where mobile PCB destruction is taking place. It also may be possible to get approval to blend high-level PCB liquids with mineral oil to reduce the PCB concentration to a level where chemical decontamination is allowed. For large volumes of high-level PCB wastes, consolidation will be necessary simply because of the high costs of mobilizing an incinerator and the requirement for public hearings for each incineration project. To make such a project cost-effective, PCB wastes will have to be concentrated from a large geographic area. 1 fig

Volume independence in large Nc QCD-like gauge theories

International Nuclear Information System (INIS)

Kovtun, Pavel; Uensal, Mithat; Yaffe, Laurence G.

2007-01-01

Volume independence in large N c gauge theories may be viewed as a generalized orbifold equivalence. The reduction to zero volume (or Eguchi-Kawai reduction) is a special case of this equivalence. So is temperature independence in confining phases. A natural generalization concerns volume independence in 'theory space' of quiver gauge theories. In pure Yang-Mills theory, the failure of volume independence for sufficiently small volumes (at weak coupling) due to spontaneous breaking of center symmetry, together with its validity above a critical size, nicely illustrate the symmetry realization conditions which are both necessary and sufficient for large N c orbifold equivalence. The existence of a minimal size below which volume independence fails also applies to Yang-Mills theory with antisymmetric representation fermions [QCD(AS)]. However, in Yang-Mills theory with adjoint representation fermions [QCD(Adj)], endowed with periodic boundary conditions, volume independence remains valid down to arbitrarily small size. In sufficiently large volumes, QCD(Adj) and QCD(AS) have a large N c ''orientifold'' equivalence, provided charge conjugation symmetry is unbroken in the latter theory. Therefore, via a combined orbifold-orientifold mapping, a well-defined large N c equivalence exists between QCD(AS) in large, or infinite, volume and QCD(Adj) in arbitrarily small volume. Since asymptotically free gauge theories, such as QCD(Adj), are much easier to study (analytically or numerically) in small volume, this equivalence should allow greater understanding of large N c QCD in infinite volume

Aerojet Energy Conversion Company mobile volume reduction system

International Nuclear Information System (INIS)

Smith, K.R.

1984-01-01

Over the past few years, rapidly increasing costs for the disposal of low level radioactive waste (LLW) have generated the need for utilities to volume-reduce their LLW prior to shipment and burial. Incineration systems have been selected by several utilities to fulfill this need for maximum volume reduction. Until recently, all of the incineration systems selected by utilities were designed to be housed and operated in a facility erected by the utility. Now, however, lack of capital and rising design/erection costs are causing utilities to reevaluate their plans for purchasing incineration systems to process their LLW. The result is a growing demand for incineration services. Once again, Commonwealth Edison Company (Com-Ed) is leading the industry with an ongoing program to utilize incineration services provided by Aerojet Energy Conversion Company (AECC) for the Dresden Quad Cities, LaSalle, and Zion Nuclear Stations. At the stations, combustible dry active waste and contaminated oil will be processed in a Mobile Volume Reduction System (MVRS) designed and fabricated by AECC. The MVRS is a totally self-contained system consisting of a controlled-air incinerator and a liquid offgas cleanup system. No buildings are required to house the system, and the MVRS achieves volume reduction factors similar to systems currently available for permanent in-plant installation. The result is an option for the utility having the benefits of volume reduction without the capital commitment normally required by the utility

Large volume syringe pump extruder for desktop 3D printers

Directory of Open Access Journals (Sweden)

Kira Pusch

2018-04-01

Full Text Available Syringe pump extruders are required for a wide range of 3D printing applications, including bioprinting, embedded printing, and food printing. However, the mass of the syringe becomes a major challenge for most printing platforms, requiring compromises in speed, resolution and/or volume. To address these issues, we have designed a syringe pump large volume extruder (LVE that is compatible with low-cost, open source 3D printers, and herein demonstrate its performance on a PrintrBot Simple Metal. Key aspects of the LVE include: (1 it is open source and compatible with open source hardware and software, making it inexpensive and widely accessible to the 3D printing community, (2 it utilizes a standard 60 mL syringe as its ink reservoir, effectively increasing print volume of the average bioprinter, (3 it is capable of retraction and high speed movements, and (4 it can print fluids using nozzle diameters as small as 100 μm, enabling the printing of complex shapes/objects when used in conjunction with the freeform reversible embedding of suspended hydrogels (FRESH 3D printing method. Printing performance of the LVE is demonstrated by utilizing alginate as a model biomaterial ink to fabricate parametric CAD models and standard calibration objects. Keywords: Additive manufacturing, 3D bioprinting, Embedded printing, FRESH, Soft materials extrusion

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

Energy Technology Data Exchange (ETDEWEB)

Templeton, K.J.

1996-05-23

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

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

International Nuclear Information System (INIS)

Templeton, K.J.

1996-01-01

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

Technical support for GEIS: radioactive waste isolation in geologic formations. Volume 2. Commercial waste forms, packaging and projections for preconceptual repository design studies

Energy Technology Data Exchange (ETDEWEB)

1978-04-01

This volume, Y/OWI/TM-36/2, ''Commercial Waste Forms, Packaging and Projections for Preconceptual Repository Design Studies,'' is one of a 23-volume series, ''Technical Support for GEIS: Radioactive Waste Isolation in Geologic Formations,'' Y/OWI/TM-36, which supplements the ''Contribution to Draft Generic Environmental Impact Statement on Commercial Waste Management: Radioactive Waste Isolation in Geologic Formations,'' Y/OWI/TM-44. The series provides a more complete technical basis for the preconceptual designs, resource requirements, and environmental source terms associated with isolating commercial LWR wastes in underground repositories in salt, granite, shale and basalt. Wastes are considered from three fuel cycles: uranium and plutonium recycling, no recycling of spent fuel and uranium-only recycling. This volume contains the data base for waste forms, packages, and projections from the commercial waste defined by the Office of Waste Isolation in ''Nuclear Waste Projections and Source Term Data for FY 1977,'' Y/OWI/TM-34. Also, as an alternative data base for repository design and analysis, waste forms, packages, and projections for commercial waste defined by Battelle Pacific Northwest Laboratory (BPNL) have been included. This data base consists of a reference case for use in the alternative design study and a definition of combustible wastes for use in mine fire and hydrogen generation analyses.

Scope for utilizing gamma radiation for microbiological control of sewage waste-water in India

International Nuclear Information System (INIS)

Lewis, N.F.

1975-01-01

Conventional methods, including the activated sludge process, the trickling filter process and oxidation pond process, of treating sewage waste in India, do not adequately ensure safe utilization of the secondary effluent for land irrigation purposes. Preliminary findings indicate that gamma radiation in the range of 0.1-0.3 Mrad effectively destroys pathogens in the secondary effluent, thereby making available very large quantities of water for land irrigation and industrial purposes. (author)

Clearance, a powerful tool in optimizing the volume of radioactive wastes

International Nuclear Information System (INIS)

Blommaert, W.; Teunckens, L.

1997-01-01

In the framework its activities in decommissioning nuclear installations, Belgoprocess applies the clearance practice in optimizing the volume of radioactive wastes. The applied clearance methodology is discussed with special emphasis to different types of materials and to the associated measurements. Four practical cases are elaborated, dealing with the decommissioning and decontamination of two small buildings up to green field conditions, the unconditional release of large quantities of slightly contaminated active carbon, the melting and clearance of stainless steel fuel racks and of aluminium heat exchangers. The attention is drawn on practical problems associated with sampling and measurement strategies, in relation to the proposed low limits for unconditional release. (author)

Waste management at KKP

International Nuclear Information System (INIS)

Blaser, W.; Grundke, E.; Majunke, J.

1997-01-01

The smooth management of radioactive plant waste is an integral, essential part of safe and economic operation of a nuclear power plant. The Philippsburg Nuclear Power Station (KKP) addressed these problems early on. The stationary facilities installed, with an organization established in the lights of the objectives to be met, allow problems to be solved largely independent of external factors and make for operational flexibility and optimum utilization of plant and personnel capacities. The good performance achieved in volume reduction and product quality of the conditioned radioactive waste justifies the capital investments made. In this way, KKP has met the ecological and economic requirements of orderly waste management. At KKP, waste management is considered an interdisciplinary duty. Existing resources in KKP's organization were used to achieve synergy effects. The Central Monitoring Unit is responsible for the cooperation of all groups involved with the objective of generating a product fit for final storage. The necessary coordination and monitoring efforts are made by a small team of specialists with extensive know-how in waste management. Four persons are responsible for coordination and monitoring, and another ten or twelve persons for direct execution of the work. (orig.) [de

DC graphite arc furnace, a simple system to reduce mixed waste volume

Energy Technology Data Exchange (ETDEWEB)

Wittle, J.K.; Hamilton, R.A.; Trescot, J. [and others

1995-12-31

The volume of low-level radioactive waste can be reduced by the high temperature in a DC Graphite Arc Furnace. This volume reduction can take place with the additional benefit of having the solid residue being stabilized by the vitrified product produced in the process. A DC Graphite Arc Furnace is a simple system in which electricity is used to generate heat to vitrify the material and thermally decompose any organic matter in the waste stream. Examples of this type of waste are protective clothing, resins, and grit blast materials produced in the nuclear industry. The various Department of Energy (DOE) complexes produce similar low-level waste streams. Electro-Pyrolysis, Inc. and Svedala/Kennedy Van Saun are engineering and building small 50-kg batch and up to 3,000 kg/hr continuous feed DC furnaces for the remediation, pollution prevention, and decontamination and decommissioning segments of the treatment community. This process has been demonstrated under DOE sponsorship at several facilities and has been shown to produce stable waste forms from surrogate waste materials.

DC graphite arc furnace, a simple system to reduce mixed waste volume

International Nuclear Information System (INIS)

Wittle, J.K.; Hamilton, R.A.; Trescot, J.

1995-01-01

The volume of low-level radioactive waste can be reduced by the high temperature in a DC Graphite Arc Furnace. This volume reduction can take place with the additional benefit of having the solid residue being stabilized by the vitrified product produced in the process. A DC Graphite Arc Furnace is a simple system in which electricity is used to generate heat to vitrify the material and thermally decompose any organic matter in the waste stream. Examples of this type of waste are protective clothing, resins, and grit blast materials produced in the nuclear industry. The various Department of Energy (DOE) complexes produce similar low-level waste streams. Electro-Pyrolysis, Inc. and Svedala/Kennedy Van Saun are engineering and building small 50-kg batch and up to 3,000 kg/hr continuous feed DC furnaces for the remediation, pollution prevention, and decontamination and decommissioning segments of the treatment community. This process has been demonstrated under DOE sponsorship at several facilities and has been shown to produce stable waste forms from surrogate waste materials

Characterization of Class A low-level radioactive waste 1986--1990. Volume 7: Appendices K--P

Energy Technology Data Exchange (ETDEWEB)

Dehmel, J.C.; Loomis, D.; Mauro, J. [S. Cohen & Associates, Inc., McLean, VA (United States); Kaplan, M. [Eastern Research Group, Inc., Lexington, MA (United States)

1994-01-01

Under contract to the US Nuclear Regulatory Commission, Office of Nuclear Regulatory Research, the firms of S. Cohen & Associates, Inc. (SC&A) and Eastern Research Group (ERG) have compiled a report that describes the physical, chemical, and radiological properties of Class-A low-level radioactive waste. The report also presents information characterizing various methods and facilities used to treat and dispose non-radioactive waste. A database management program was developed for use in accessing, sorting, analyzing, and displaying the electronic data provided by EG&G. The program was used to present and aggregate data characterizing the radiological, physical, and chemical properties of the waste from descriptions contained in shipping manifests. The data thus retrieved are summarized in tables, histograms, and cumulative distribution curves presenting radionuclide concentration distributions in Class-A waste as a function of waste streams, by category of waste generators, and regions of the United States. The report also provides information characterizing methods and facilities used to treat and dispose non-radioactive waste, including industrial, municipal, and hazardous waste regulated under Subparts C and D of the Resource Conservation and Recovery Act (RCRA). The information includes a list of disposal options, the geographical locations of the processing and disposal facilities, and a description of the characteristics of such processing and disposal facilities. Volume 1 contains the Executive Summary, Volume 2 presents the Class-A waste database, Volume 3 presents the information characterizing non-radioactive waste management practices and facilities, and Volumes 4 through 7 contain Appendices A through P with supporting information.

Technical support for GEIS: radioactive waste isolation in geologic formations. Volume 23. Environmental effluent analyses

International Nuclear Information System (INIS)

1978-04-01

This volume, Y/OWI/TM-36/23, ''Environmental Effluent Analysis,'' is one of a 23-volume series, ''Technical Support for GEIS: Radioactive Waste Isolation in Geologic Formations,'' Y/OWI/TM-36, which supplements the ''Contribution to Drat Generic Environmental Impact Statement on Commercial Waste Management: Radioactive Waste Isolation in Geologic Formations,'' Y/OWI/TM-44. The series provides a more complete technical basis for the preconceptual designs, resource requirements, and environmental source terms associated with isolating commercial LWR wastes in underground repositories in salt, granite, shale and basalt. Wastes are considered from three fuel cycles: uranium and plutonium recycling, no recycling of spent fuel and uranium-only recycling. This volume discusses the releases to the environment of radioactive and non-radioactive materials that arise during facility construction and waste handling operations, as well as releases that could occur in the event of an operational accident. The results of the analyses are presented along with a detailed description of the analytical methodologies employed

Low and intermediate radioactive waste management at OPG's western waste management facility

International Nuclear Information System (INIS)

Ellsworth, M.

2006-01-01

'Full text:' This paper will discuss low and intermediate level radioactive waste operations at Ontario Power Generation's Western Waste Management Facility. The facility has been in operation since 1974 and receives about 5000 - 7000 m 3 of low and intermediate level radioactive waste per year from Ontario's nuclear power plants. Low-level radioactive waste is received at the Waste Volume Reduction Building for possible volume reduction before it is placed into storage. Waste may be volume reduced by one of two methods at the WWMF, through either compaction or incineration. The Compactor is capable of reducing the volume of waste by a factor up to 5:1 for most waste. The Radioactive Incinerator is capable of volume reducing incinerable material by a factor up to 70:1. After processing, low-level waste is stored in above ground concrete warehouse-like structures called Low Level Storage Buildings. Low-level waste that cannot be volume reduced is placed into steel containers and stored in the Low Level Storage Buildings. Intermediate level waste is stored mainly in steel lined concrete storage structures. WWMF has both above ground and in-ground storage structures for intermediate level waste. Intermediate level waste consists primarily of resin and filters used to keep reactor water systems clean, and some used reactor core components. All low and intermediate level waste storage at the WWMF is considered interim storage and the material can be retrieved for future disposal or permanent storage. Current improvement initiatives include the installation of a new radioactive incinerator and a shredder/bagger. The new incinerator is a continuous feed system that is expected to achieve volume reduction rates up to 70:1, while incinerating higher volumes of waste than its predecessor. The shredder will break down large/bulky items into a form, which can be processed for further volume reduction. A Refurbishment Waste Storage Project is underway in anticipation of the

A logical approach to determine a waste segregation/volume reduction program

International Nuclear Information System (INIS)

Shriner, G.D.; Carmel, P.G.; Shimmura, H.

1986-01-01

This paper discusses advantages and disadvantages of hand sorting versus use of automated radioactive waste segregation monitors and makes an analysis of costs/versus benefits based on volume with time. Many programs to be employed to prevent unnecessary waste generation with little or no additional cost to the power plant. Parameters needed to perform a cost analysis and methods used to obtain them are discussed. Recommendations on use of vendor-supplied services for segregation, volume reduction, and decontamination are given. The data provided will enable the selection of a program(s) to benefit the individual user's requirements

Method of volume-reducing processing for radioactive wastes

International Nuclear Information System (INIS)

Sato, Koei; Yamauchi, Noriyuki; Hirayama, Toshihiko.

1985-01-01

Purpose: To process the processing products of radioactive liquid wastes and burnable solid wastes produced from nuclear facilities into stable solidification products by heat melting. Method: At first, glass fiber wastes of contaminated air filters are charged in a melting furnace. Then, waste products obtained through drying, sintering, incineration, etc. are mixed with a proper amount of glass fibers and charged into the melting furnace. Both of the charged components are heated to a temperature at which the glass fibers are melted. The burnable materials are burnt out to provide a highly volume-reduced products. When the products are further heated to a temperature at which metals or metal oxides of a higher melting point than the glass fiber, the glass fibers and the metals or metal oxides are fused to each other to be combined in a molecular structure into more stabilized products. The products are excellent in strength, stability, durability and leaching resistance at ambient temperature. (Kamimura, M.)

Other-than-high-level waste

International Nuclear Information System (INIS)

Bray, G.R.

1976-01-01

The main emphasis of the work in the area of partitioning transuranic elements from waste has been in the area of high-level liquid waste. But there are ''other-than-high-level wastes'' generated by the back end of the nuclear fuel cycle that are both large in volume and contaminated with significant quantities of transuranic elements. The combined volume of these other wastes is approximately 50 times that of the solidified high-level waste. These other wastes also contain up to 75% of the transuranic elements associated with waste generated by the back end of the fuel cycle. Therefore, any detailed evaluation of partitioning as a viable waste management option must address both high-level wastes and ''other-than-high-level wastes.''

Establishment the code for prediction of waste volume on NPP decommissioning

International Nuclear Information System (INIS)

Cho, W. H.; Park, S. K.; Choi, Y. D.; Kim, I. S.; Moon, J. K.

2013-01-01

In practice, decommissioning waste volume can be estimated appropriately by finding the differences between prediction and actual operation and considering the operational problem or supplementary matters. So in the nuclear developed countries such as U.S. or Japan, the decommissioning waste volume is predicted on the basis of the experience in their own decommissioning projects. Because of the contamination caused by radioactive material, decontamination activity and management of radio-active waste should be considered in decommissioning of nuclear facility unlike the usual plant or facility. As the decommissioning activity is performed repeatedly, data for similar activities are accumulated, and optimal strategy can be achieved by comparison with the predicted strategy. Therefore, a variety of decommissioning experiences are the most important. In Korea, there is no data on the decommissioning of commercial nuclear power plants yet. However, KAERI has accumulated the basis decommissioning data of nuclear facility through decommissioning of research reactor (KRR-2) and uranium conversion plant (UCP). And DECOMMIS(DECOMMissioning Information Management System) was developed to provide and manage the whole data of decommissioning project. Two codes, FAC code and WBS code, were established in this process. FAC code is the one which is classified by decommissioning target of nuclear facility, and WBS code is classified by each decommissioning activity. The reason why two codes where created is that the codes used in DEFACS (Decommissioning Facility Characterization management System) and DEWOCS (Decommissioning Work-unit productivity Calculation System) are different from each other, and they were classified each purpose. DEFACS which manages the facility needs the code that categorizes facility characteristics, and DEWOCS which calculates unit productivity needs the code that categorizes decommissioning waste volume. KAERI has accumulated decommissioning data of KRR

National Public Information Symposium on Peaceful Uses of Nuclear Energy, NUC Info'2000. Radioactive Waste Management and Site Restoration in Uranium Industry. Proceedings. Volume 1

International Nuclear Information System (INIS)

Dobos, Ion; Comsa, Olivia

2000-01-01

These proceedings published in two volumes contain materials presented at the National Public Information Symposium on Peaceful Uses of Nuclear Energy, NUC Info'2000, Radioactive Waste Management and Site Restoration in Uranium Industry, held on 5. September to 8. September 2000 at Baita Bihor, Romania. As the name of Symposium indicates, this manifestation is addressed not only to specialists but rather to the public at large. The proceedings are structured in 4 sections: 1. Management of radioactive waste arising from uranium mining, milling and decommissioning; 2. Uranium mine close-down; 3. Environmental restoration of uranium mining and milling sites; 4. Management of radioactive waste arising from nuclear applications. The first volume also contains an inaugural session dedicated to nuclear power, nuclear fuel cycle and development of uranium industry in Romania. The contributions in the first volume deal with the management of radioactive waste arising from uranium mining, milling and decommissioning and uranium mine close-out

State of the art review of radioactive waste volume reduction techniques for commercial nuclear power plants

International Nuclear Information System (INIS)

1980-04-01

A review is made of the state of the art of volume reduction techniques for low level liquid and solid radioactive wastes produced as a result of: (1) operation of commercial nuclear power plants, (2) storage of spent fuel in away-from-reactor facilities, and (3) decontamination/decommissioning of commercial nuclear power plants. The types of wastes and their chemical, physical, and radiological characteristics are identified. Methods used by industry for processing radioactive wastes are reviewed and compared to the new techniques for processing and reducing the volume of radioactive wastes. A detailed system description and report on operating experiences follow for each of the new volume reduction techniques. In addition, descriptions of volume reduction methods presently under development are provided. The Appendix records data collected during site surveys of vendor facilities and operating power plants. A Bibliography is provided for each of the various volume reduction techniques discussed in the report

Food waste-to-energy conversion technologies: current status and future directions.

Science.gov (United States)

Pham, Thi Phuong Thuy; Kaushik, Rajni; Parshetti, Ganesh K; Mahmood, Russell; Balasubramanian, Rajasekhar

2015-04-01

Food waste represents a significantly fraction of municipal solid waste. Proper management and recycling of huge volumes of food waste are required to reduce its environmental burdens and to minimize risks to human health. Food waste is indeed an untapped resource with great potential for energy production. Utilization of food waste for energy conversion currently represents a challenge due to various reasons. These include its inherent heterogeneously variable compositions, high moisture contents and low calorific value, which constitute an impediment for the development of robust, large scale, and efficient industrial processes. Although a considerable amount of research has been carried out on the conversion of food waste to renewable energy, there is a lack of comprehensive and systematic reviews of the published literature. The present review synthesizes the current knowledge available in the use of technologies for food-waste-to-energy conversion involving biological (e.g. anaerobic digestion and fermentation), thermal and thermochemical technologies (e.g. incineration, pyrolysis, gasification and hydrothermal oxidation). The competitive advantages of these technologies as well as the challenges associated with them are discussed. In addition, the future directions for more effective utilization of food waste for renewable energy generation are suggested from an interdisciplinary perspective. Copyright © 2014 Elsevier Ltd. All rights reserved.

INEL waste reduction: summary paper

International Nuclear Information System (INIS)

Rhoades, W.A.

1987-01-01

The Idaho National Engineering Laboratory (INEL) is a Department of Energy (DOE) facility located in southeastern Idaho. Located at the INEL are a Waste Experimental Reduction Facility (WERF) which processes low level radioactive waste (LLW) materials and a Radioactive Waste Management Complex (RWMC) which provides for disposal of radioactive waste materials. There are currently 9 active facilities (waste generators) at the INEL which produce an average total volume of about 5000 cubic meters of solid LLW annually. This boxed or bulk waste is ultimately disposed of at the RWMC Subsurface Disposal Area (SDA). The SDA is currently the only active LLW disposal site at the INEL, and the prospects for opening another shallow land burial disposal facility are uncertain. Therefore, it has become imperative that EG and G Idaho Waste Management Department make every reasonable effort to extend the disposal life of the SDA. Among Waste Management Department's principal efforts to extend the SDA disposal life are operation of the Waste Experimental Reduction Facility (WERF) and administration of the INEL Waste Reduction Program. The INEL Waste Reduction Program is charged with providing assistance to all INEL facilities in reducing LLW generation rates to the lowest practical levels while at the same time encouraging optimum utilization of the volume reduction capabilities of WERF. Both waste volume and waste generation reductions are discussed

Aerodynamics of the Large-Volume, Flow-Through Detector System. Final report

International Nuclear Information System (INIS)

Reed, H.; Saric, W.; Laananen, D.; Martinez, C.; Carrillo, R.; Myers, J.; Clevenger, D.

1996-03-01

The Large-Volume Flow-Through Detector System (LVFTDS) was designed to monitor alpha radiation from Pu, U, and Am in mixed-waste incinerator offgases; however, it can be adapted to other important monitoring uses that span a number of potential markets, including site remediation, indoor air quality, radon testing, and mine shaft monitoring. Goal of this effort was to provide mechanical design information for installation of LVFTDS in an incinerator, with emphasis on ability to withstand the high temperatures and high flow rates expected. The work was successfully carried out in three stages: calculation of pressure drop through the system, materials testing to determine surrogate materials for wind-tunnel testing, and wind-tunnel testing of an actual configuration

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

International Nuclear Information System (INIS)

BARCOT, R.A.

2003-01-01

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

Achievement report in fiscal 1999 on commissioned research project. 'Model project for facilities to effectively utilize wastes from industrial complexes in Thailand' Project for 1999 Volume 1; 1999 nendo seika hokokusho. Tai ni okeru kogyo danchi sangyo haikibutsu yuko riyo setsubi moderu jigyo - 1

Energy Technology Data Exchange (ETDEWEB)

NONE

2001-03-01

With an objective to reuse industrial wastes and effectively utilize them as a petroleum replacing energy resource, and attempt to reduce consumption of fossil fuel in Thailand where increase in discharge of industrial wastes is estimated, a model project for facilities to effectively utilize wastes from industrial complexes has been carried out. This paper reports the achievements in fiscal 1999. Specifically, the project calls for incineration in fluidized bed incinerators of industrial wastes discharged from factories in industrial complexes possessed by the Industrial Estate Authority of Thailand (IEAT), recovery of waste heat from waste heat recovering boilers to generate process steam, which is supplied to the factories in the complexes. The current fiscal year, which is the first current year of the project, has put into order the operations shared by Japan and Thailand, compiled the various procedures and schedules into the form of appendices to the agreement, and executed signing of the agreement. Thereafter, the Japanese side has carried out decision on the specifications of the facilities, the basic designs, the detailed designs of facilities to be arranged by Japan, and the fabrication of some of the devices according to the descriptions of the agreement appendices. The volume 1 summarizes the agreement appendices, and the specifications of the main devices. (NEDO)

Achievement report in fiscal 1999 on commissioned research project. 'Model project for facilities to effectively utilize wastes from industrial complexes in Thailand' Project for 1999 Volume 2; 1999 nendo seika hokokusho. Tai ni okeru kogyo danchi sangyo haikibutsu yuko riyo setsubi moderu jigyo - 2

Energy Technology Data Exchange (ETDEWEB)

NONE

2001-03-01

With an objective to reuse industrial wastes and effectively utilize them as a petroleum replacing energy resource, and attempt to reduce consumption of fossil fuel in Thailand where increase in discharge of industrial wastes is estimated, a model project for facilities to effectively utilize wastes from industrial complexes has been carried out. This paper reports the achievements in fiscal 1999. Specifically, the project calls for incineration in fluidized bed incinerators of industrial wastes discharged from factories in industrial complexes possessed by the Industrial Estate Authority of Thailand (IEAT), recovery of waste heat from waste heat recovering boilers to generate process steam, which is supplied to the factories in the complexes. The current fiscal year, which is the first current year of the project, has put into order the operations shared by Japan and Thailand, compiled the various procedures and schedules into the form of appendices to the agreement, and executed signing of the agreement. Thereafter, the Japanese side has carried out decision on the specifications of the facilities, the basic designs, the detailed designs of facilities to be arranged by Japan, and the fabrication of some of the devices according to the descriptions of the agreement appendices. The volume 2 summarizes the inspection reports in the referential materials. (NEDO)

Tank waste source term inventory validation. Volume II. Letter report

Energy Technology Data Exchange (ETDEWEB)

NONE

1995-04-01

This document comprises Volume II of the Letter Report entitled Tank Waste Source Term Inventory Validation. This volume contains Appendix C, Radionuclide Tables, and Appendix D, Chemical Analyte Tables. The sample data for selection of 11 radionuclides and 24 chemical analytes were extracted from six separate sample data sets, were arranged in a tabular format and were plotted on scatter plots for all of the 149 single-shell tanks, the 24 double-shell tanks and the four aging waste tanks. The solid and liquid sample data was placed in separate tables and plots. The sample data and plots were compiled from the following data sets: characterization raw sample data, recent core samples, D. Braun data base, Wastren (Van Vleet) data base, TRAC and HTCE inventories.

Tank waste source term inventory validation. Volume II. Letter report

International Nuclear Information System (INIS)

1995-04-01

This document comprises Volume II of the Letter Report entitled Tank Waste Source Term Inventory Validation. This volume contains Appendix C, Radionuclide Tables, and Appendix D, Chemical Analyte Tables. The sample data for selection of 11 radionuclides and 24 chemical analytes were extracted from six separate sample data sets, were arranged in a tabular format and were plotted on scatter plots for all of the 149 single-shell tanks, the 24 double-shell tanks and the four aging waste tanks. The solid and liquid sample data was placed in separate tables and plots. The sample data and plots were compiled from the following data sets: characterization raw sample data, recent core samples, D. Braun data base, Wastren (Van Vleet) data base, TRAC and HTCE inventories

Pretreatment and utilization of waste incineration bottom ashes

DEFF Research Database (Denmark)

Astrup, Thomas

2007-01-01

Within recent years, researchers and authorities have had increasing focus on leaching properties from waste incineration bottom ashes. Researchers have investigated processes such as those related to carbonation, weathering, metal complexation, and leaching control. Most of these investigations......, however, have had a strong emphasis on lab experiments with little focus on full scale bottom ash upgrading methods. The introduction of regulatory limit values restricting leaching from utilized bottom ashes, has created a need for a better understanding of how lab scale experiences can be utilized...

Utilization of waste heat from nuclear power plants in agriculture

International Nuclear Information System (INIS)

Horacek, P.

1981-01-01

The development of nuclear power will result in the relative and absolute increase in the amount of waste heat which can be used in agriculture for heating greenhouses, open spaces, for fish breeding in heated water, for growing edible mushrooms, growing algae, for frost protection of orchards, air conditioning of buildings for breeding livestock and poultry, and for other purposes. In addition of the positive effect of waste heat, the danger increases of disease, weeds and pests. Pilot plant installations should be build in Czechoslovakia for testing the development of waste heat utilization. (Ha)

High-level waste borosilicate glass: A compendium of corrosion characteristics. Volume 3

International Nuclear Information System (INIS)

Cunnane, J.C.

1994-03-01

The objective of this document is to summarize scientific information pertinent to evaluating the extent to which high-level waste borosilicate glass corrosion and the associated radionuclide release processes are understood for the range of environmental conditions to which waste glass may be exposed in service. Alteration processes occurring within the bulk of the glass (e.g., devitrification and radiation-induced changes) are discussed insofar as they affect glass corrosion. Volume III contains a bibliography of glass corrosion studies, including studies that are not cited in Volumes I and II

High-level waste borosilicate glass: A compendium of corrosion characteristics. Volume 3

Energy Technology Data Exchange (ETDEWEB)

Cunnane, J.C. [comp.; Bates, J.K.; Bradley, C.R. [Argonne National Lab., IL (United States)] [and others

1994-03-01

The objective of this document is to summarize scientific information pertinent to evaluating the extent to which high-level waste borosilicate glass corrosion and the associated radionuclide release processes are understood for the range of environmental conditions to which waste glass may be exposed in service. Alteration processes occurring within the bulk of the glass (e.g., devitrification and radiation-induced changes) are discussed insofar as they affect glass corrosion. Volume III contains a bibliography of glass corrosion studies, including studies that are not cited in Volumes I and II.

Storage process of large solid radioactive wastes

International Nuclear Information System (INIS)

Morin, Bruno; Thiery, Daniel.

1976-01-01

Process for the storage of large size solid radioactive waste, consisting of contaminated objects such as cartridge filters, metal swarf, tools, etc, whereby such waste is incorporated in a thermohardening resin at room temperature, after prior addition of at least one inert charge to the resin. Cross-linking of the resin is then brought about [fr

A catalytic wet oxidation process for mixed waste volume reduction/recycling

International Nuclear Information System (INIS)

Dhooge, Patrick M.

1992-01-01

Mixed wastes have presented a challenge to treatment and destruction technologies. A recently developed catalytic wet oxidation method has promising characteristics for volume reduction and recycling of mixed wastes. The process utilizes iron (III) as an oxidant in the presence of homogeneous cocatalysts which increase organics' oxidation rates and the rate of oxidation of iron (II) by oxygen. The reaction is conducted in an aqueous mineral acid solution at temperatures of 373 - 573 deg K. The mineral acid should solvate a number of heavy metals, including U and Pu. Studies of reaction rates show that the process can oxidize a wide range of organic compounds including aromatics and chlorinated hydrocarbons. Rate constants in the range of 10 -7 to 10 -4 sec -1 , depending on the cocatalyst, acidity, type of anions, type of organic, temperature, and time. Activation energies ranged from 25. to 32. KJ/mole. Preliminary measurements of the extent of oxidation which could be obtained ranged from 80% for trichloroethylene to 99.8% for 1,2,4-trimethylbenzene; evidence was obtained that absorption by the fluorocarbon liners of the reaction bombs allowed some of the organics to escape exposure to the catalyst solution. The results indicate that complete oxidation of the organics used here, and presumably many others, can be achieved. (author)

UTILIZATION OF WASTE PLASTIC BOTTLES IN ASPHALT MIXTURE

Directory of Open Access Journals (Sweden)

TAHER BAGHAEE MOGHADDAM

2013-06-01

Full Text Available Nowadays, large amounts of waste materials are being produced in the world. One of the waste materials is plastic bottle. Generating disposable plastic bottles is becoming a major problem in many countries. Using waste plastic as a secondary material in construction projects would be a solution to overcome the crisis of producing large amount of waste plastics in one hand and improving the structure’s characteristics such as resistance against cracking on the other hand. This study aimed to investigate the effects of adding plastic bottles in road pavement. Marshall properties as well as specific gravity of asphalt mixture containing different percentages of plastic bottles were evaluated. Besides, Optimum Asphalt Content (OAC was calculated for each percentages of plastic bottles used in the mix. The stiffness and fatigue characteristics of mixture were assessed at OAC value. Results showed that the stability and flow values of asphalt mixture increased by adding waste crushed plastic bottle into the asphalt mixture. Further, it was shown that the bulk specific gravity and stiffness of mixtures increased by adding lower amount of plastic bottles; however, adding higher amounts of plastic resulted in lower specific gravity and mix stiffness. In addition, it was concluded that the mixtures containing waste plastic bottles have lower OAC values compared to the conventional mixture, and this may reduce the amount of asphalt binder can be used in road construction projects. Besides, the mixtures containing waste plastic showed significantly greater fatigue resistance than the conventional mixture.

Large-scale production of bioenergy by the side of fuel-peat; Bioenergian suurtuotanto polttoturpeen rinnalla

Energy Technology Data Exchange (ETDEWEB)

Heikkilae, K. [Vapo Oy, Jyvaeskylae (Finland)

1996-12-31

The objective of the project was to clarify the large-scale production possibilities and the construction of the costs for bioenergy, and to develop the operational manners so that smaller volumes of biomasses are integrated to prevailing peat production and delivered so that peat ensures the quality of the fuel supply, as well as the prices and the reliability of deliveries. Hence it is possible to utilize the same organisation, machinery and volumes. The operation will be designed to be all-year-round so that the profitability can be improved. Another aim is to get the non-utilizeable wood-wastes into use, which would serve also the silvicultural purposes. The utilizeable municipal and other wastes and sludges could be used within biomass, and to make, using proper mixing ratios, biofuels precisely suitable for the purposes of the customer. At the grain growing areas it is possible to utilize the straw and at the seaside the reed grass

Second interim assessment of the Canadian concept for nuclear fuel waste disposal. Volume 1

International Nuclear Information System (INIS)

Wuschke, D.M.; Gillespie, P.A.; Main, D.E.

1985-07-01

The nuclear fuel waste disposal concept chosen for development and assessment in Canada involves the isolation of corrosion-resistant containers of waste in a vault located deep in plutonic rock. As the concept and the assessment tools are developed, periodic assessments are performed to permit evaluation of the methodology and provide feedback to those developing the concept. The ultimate goal of these assessments is to predict what impact the disposal system would have on man and the environment if the concept were implemented. The second assessment was performed in 1984 and is documented in the Second Interim assessment of the Canadian Concept for Nuclear Fuel Waste Disposal Volumes 1 to 4. This volume, entitled Summary, is a condensation of Volumes 2, 3 and 4. It briefly describes the Canadian nuclear fuel waste disposal concept, and the methods and results of the second interim pre-closure and post-closure assessments of that concept. 46 refs

Reduction of waste solution volume generated on electrokinetic remediation

Energy Technology Data Exchange (ETDEWEB)

Kim, Gye-Nam; Koo, Dae-Seo; Kim, Seung-Soo; Jeong, Jung-Whan; Han, Gyu-Seong; Moon, Jei-Kwon [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

2015-05-15

In this study, for the reduction of volume of metal oxides generated in cathode chamber, the optimum pH of waste electrolyte in cathode chamber were drawn out through several experiments with the manufactured electrokinetic decontamination equipment. Also, the required time to reach to below the clearance concentration level for self- disposal was estimated through experiments using the manufactured electrokinetic decontamination equipment. A diagram of soil decontamination process for the removal of uranium from contaminated soil was drawn out. The optimum pH of waste electrolyte in cathode chamber for the reduction of volume of metal oxides was below 2.35. Also, when the initial uranium concentration of the soils were 7-20 Bq/g, the required times to reach to below the clearance concentration level for self- disposal were 25-40 days. A diagram of soil decontamination process for the removal of uranium from contaminated soil was drawn out.

Estimation of restaurant solid waste generation rates

International Nuclear Information System (INIS)

Heck, H.H.; Major, I.

2002-01-01

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

76 FR 58543 - Draft Policy Statement on Volume Reduction and Low-Level Radioactive Waste Management

Science.gov (United States)

2011-09-21

...-Level Radioactive Waste Management AGENCY: Nuclear Regulatory Commission. ACTION: Reopening of comment... for public comment a draft Policy Statement on Volume Reduction and Low-Level Radioactive Waste...-based approaches to managing waste are also needed to safely manage Low-Level Radioactive Waste. The...

Waste management research abstracts volume 27. Information on radioactive waste management research in progress or planned

International Nuclear Information System (INIS)

2002-10-01

This issue of the Waste Management Research Abstracts (WMRA) contains 148 abstracts that describe research in progress in the field of radioactive waste management. The research abstracts contained in Volume 27 (WMRA 27) were collected between July 1, 2001 and September 30, 2002. The abstracts present ongoing work in various countries and international organizations. Although the abstracts are indexed by country, many programmes are actually the result of co-operation among several countries. Indeed, a primary reason for providing this compilation of programmes, institutions and scientists engaged in research into radioactive waste management is to increase international co-operation and facilitate communications

Characterization of Class A low-level radioactive waste 1986--1990. Volume 3: Main report -- Part B

Energy Technology Data Exchange (ETDEWEB)

Dehmel, J.C.; Loomis, D.; Mauro, J. [S. Cohen & Associates, Inc., McLean, VA (United States); Kaplan, M. [Eastern Research Group, Inc., Lexington, MA (United States)

1994-01-01

Under contract to the US Nuclear Regulatory Commission, Office of Nuclear Regulatory Research, the firms of S. Cohen & Associates, Inc. (SC&A) and Eastern Research Group (ERG) have compiled a report that describes the physical, chemical, and radiological properties of Class-A low-level radioactive waste. The report also presents information characterizing various methods and facilities used to treat and dispose non-radioactive waste. A database management program was developed for use in accessing, sorting, analyzing, and displaying the electronic data provided by EG&G. The program was used to present and aggregate data characterizing the radiological, physical, and chemical properties of the waste from descriptions contained in shipping manifests. The data thus retrieved are summarized in tables, histograms, and cumulative distribution curves presenting radionuclide concentration distributions in Class-A waste as a function of waste streams, by category of waste generators, and regions of the United States. The report also provides information characterizing methods and facilities used to treat and dispose non-radioactive waste, including industrial, municipal, and hazardous waste regulated under Subparts C and D of the Resource Conservation and Recovery Act (RCRA). The information includes a list of disposal options, the geographical locations of the processing and disposal facilities, and a description of the characteristics of such processing and disposal facilities. Volume 1 contains the Executive Summary, Volume 2 presents the Class-A waste database, Volume 3 presents the information characterizing non-radioactive waste management practices and facilities, and Volumes 4 to 7 contain Appendices A to P with supporting information.

Management of low-level radioactive waste in the Southeast Compact Region: Volume 2, Management plan: Final report

International Nuclear Information System (INIS)

1985-07-01

The Southeast Compact Commission for Low-Level Radioactive Waste Management has begun the development of a regional low-level radioactive waste management plan. They have reviewed and analyzed existing data on current low-level radioactive waste volumes shipped for disposal by generators in the Southeast region and have supplemented existing data by direct contact with State regulatory personnel, disposal site operators, and individual generators. The Commission has also projected the amounts and types of waste expected to require offsite disposal. This characterized data base and the projections of waste volumes and types through 1996 are included in this volume. Alternative disposal and treatment technologies were evaluated for management of the waste in the region. This evaluation consisted of a review of the literature concerning the several technologies in low level radioactive waste management. This information is summarized in Appendix A. 72 refs., 28 figs., 30 tabs

A comparison of costs associated with utility management options for dry active waste

Energy Technology Data Exchange (ETDEWEB)

Hornibrook, C. [EPRI, Palo Alto, CA (United States)

1995-12-31

The economics of low level waste management is receiving more attention today than ever before. This is due to four factors: (1) the increases in the cost of processing of these wastes; (2) increases in the cost of disposal; (3) the addition of storage costs for those without access to disposal; and (4) the increasing competitive nature of the electric generation industry. These pressures are forcing the industry to update it`s evaluation of the mix of processing that will afford it the best long term economics and minimize it`s risks for unforeseen costs. Whether disposal is available or not, all utilities face the same challenge of minimizing the costs associated with the management of these wastes. There are a number of variables that will impact how a utility manages their wastes but the problem is the uncertainty of what will actually happen, i.e., will disposal be available, when and at what cost. Using the EPRI-developed WASTECOST: DAW code, this paper explores a variety of LLW management options available to utilities. Along with providing the costs and benefits, other technical considerations which play an important part in the management of these wastes are also addressed.

Large-volume paracentesis with indwelling peritoneal catheter and albumin infusion: a community hospital study

Directory of Open Access Journals (Sweden)

Daniel K. Martin

2016-10-01

Full Text Available Background: The management of ascites can be problematic. This is especially true in patients with diuretic refractory ascites who develop a tense abdomen. This often results in hypotension and decreased venous return with resulting renal failure. In this paper, we further examine the risks and benefits of utilizing an indwelling peritoneal catheter to remove large-volume ascites over a 72-h period while maintaining intravascular volume and preventing renal failure. Methods: We retrospectively reviewed charts and identified 36 consecutive patients undergoing continuous large-volume paracentesis with an indwelling peritoneal catheter. At the time of drain placement, no patients had signs or laboratory parameters suggestive of spontaneous bacterial peritonitis. The patients underwent ascitic fluid removal through an indwelling peritoneal catheter and were supported with scheduled albumin throughout the duration. The catheter was used to remove up to 3 L every 8 h for a maximum of 72 h. Regular laboratory and ascitic fluid testing was performed. All patients had a clinical follow-up within 3 months after the drain placement. Results: An average of 16.5 L was removed over the 72-h time frame of indwelling peritoneal catheter maintenance. The albumin infusion utilized correlated to 12 mg/L removed. The average creatinine trend improved in a statistically significant manner from 1.37 on the day of admission to 1.21 on the day of drain removal. No patients developed renal failure during the hospital course. There were no documented episodes of neutrocytic ascites or bacterial peritonitis throughout the study review. Conclusion: Large-volume peritoneal drainage with an indwelling peritoneal catheter is safe and effective for patients with tense ascites. Concomitant albumin infusion allows for maintenance of renal function, and no increase in infectious complications was noted.

A plasma melting technology for volume reduction of noncombustible radioactive waste in Korea

International Nuclear Information System (INIS)

Song, Myung Jae; Moon, Young Pyo

1998-01-01

In Korea, there is a strong need for the development of radioactive waste volume reduction technology. Korea Electric Power Research Institute (KEPRI) has been searching for ways to reduce the radioactive volume significantly and to produce stable waste forms. In particular, plasma treatment technology has caught KEPR's attention for treating noncombustible radwaste because this technology may far surpass conventional methods. The potential for greater control of temperature, faster reaction times, better control of processing, lower capital costs, greater throughput and more efficient use of energy is there. For the plasma melting study of noncombustible waste, KEPRI has leased a lab scale multipurpose plasma furnace system and performed preliminary tests. Using simulated noncombustible waste based on field survey data from nuclear power plants, lab scale melting experiments have been carried out. The properties of molten slag vary with additives and noncombustible waste materials. KEPRI's current study is focused on finding an optimum composition ratio of various noncombustible wastes for melting, investigating physical properties of molten slag, and obtaining operating parameters for continuous operation. (author)

Technical support for GEIS: radioactive waste isolation in geologic formations. Volume 6. Baseline rock properties-shale

International Nuclear Information System (INIS)

1978-04-01

This volume, Y/OWI/TM36/6 Baseline Rock Properties--Shale, is one of a 23-volume series, ''Technical Support for GEIS: Radioactive Waste Isolation in Geologic Formations, Y/OWI/TM-36'' which supplements a ''Contribution to Draft Generic Environmental Impact Statement on Commercial Waste Management: Radioactive Waste Isolation in Geologic Formations, Y/OWI/TM-44.'' The series provides a more complete technical basis for the preconceptual designs, resource requirements, and environmental source terms associated with isolating commercial LWR wastes in underground repositories in salt, granite, shale and basalt. Wastes are considered from three fuel cycles: uranium and plutonium recycling, no recycling of spent fuel and uranium-only recycling. The report is a result of a literature survey of the rock properties of shales occurring in the United States. Firstly, data were collected from a wide variety of sources in order to obtain a feel for the range of properties encountered. Secondly, some typical shales were selected for detailed review and these are written up as separate chapters in this report. Owing to the wide variability in lithology and properties of shales occurring in the United States, it became necessary to focus the study on consolidated illite shales. Using the specific information already generated, a consistent set of intact properties for a typical, consolidated illite shale was obtained. Correction factors, largely based on geological considerations, were then applied to the intact data in order to yield typical rock mass properties for this type of shale. Lastly, excavation problems in shale formations were reviewed and three tunnel jobs were written up as case histories

A new large-volume metal reference standard for radioactive waste management.

Science.gov (United States)

Tzika, F; Hult, M; Stroh, H; Marissens, G; Arnold, D; Burda, O; Kovář, P; Suran, J; Listkowska, A; Tyminski, Z

2016-03-01

A new large-volume metal reference standard has been developed. The intended use is for calibration of free-release radioactivity measurement systems and is made up of cast iron tubes placed inside a box of the size of a Euro-pallet (80 × 120 cm). The tubes contain certified activity concentrations of (60)Co (0.290 ± 0.006 Bq g(-1)) and (110m)Ag (3.05 ± 0.09 Bq g(-1)) (reference date: 30 September 2013). They were produced using centrifugal casting from a smelt into which (60)Co was first added and then one piece of neutron irradiated silver wire was progressively diluted. The iron castings were machined to the desirable dimensions. The final material consists of 12 iron tubes of 20 cm outer diameter, 17.6 cm inner diameter, 40 cm length/height and 245.9 kg total mass. This paper describes the reference standard and the process of determining the reference activity values. © The Author 2015. Published by Oxford University Press.

Volume reduction of reactor wastes by spray drying

International Nuclear Information System (INIS)

Gay, R.L.; Grantham, L.F.; McKenzie, D.E.

1983-01-01

Three simulated low-level reactor wastes were dried using a spray dryer-baghouse system. The three aqueous feedstocks were sodium sulfate waste characteristic of a BWR, boric acid waste characteristic of a PWR, and a waste mixture of ion exchange resins and filter aid. These slurries were spiked with nonradioactive iron, cobalt, and manganese (representing corrosion products) and nonradioactive cesium and iodine (representing fission products). The throughput for the 2.1-m-diameter spray dryer and baghouse system was 160-180 kg/h, which is comparable to the requirements for a full-scale commercial installation. A free-flowing, dry product was produced in all of the tests. The volume reduction factor ranged from 2.5 to 5.8; the baghouse decontamination factor was typically in the range of 10 3 to 10 4 . Using an overall system decontamination factor of 10 6 , the activity of the off-gas was calculated to be one to two orders of magnitude less than the nuclide release limit of the major active species, Cs-137

Analysis of economic and energy utilization aspects for waste heat aquaculture

Energy Technology Data Exchange (ETDEWEB)

Olszewski, M.; Wilson, J. V.

1978-01-01

A waste heat aquaculture system using extensive culture techniques to produce fin and shellfish is currently under investigation at the Oak Ridge National Laboratory. The system uses nutrients in waste water streams to grow algae and zooplankton which are fed to fish and clams. A tilapia polyculture association and the freshwater clam Corbicula are the animals cultured in the system. The investigations were performed to determine the economic feasibility of the system and examine energy utilization in the system. A net energy analysis was performed to identify the energy saving potential for the system. This analysis includes all energy costs (both direct and indirect) associated with building and operating the system. The results of the economic study indicated that fish production costs of $0.55/kg ($0.25/lb) were possible. This cost, however, depends upon the fish production rate and food conversion efficiency and could rise to as much as $1.65/kg ($0.75/lb). Clam production costs were found to be in the neighborhood of $0.37/kg of clam meat ($1.24/bushel). The energy utilization study results indicated that, when all energy costs are included, fish from the aquaculture system may require only 35% of the net energy now required for fish products from the ocean. However, the energy requirements also depend on system parameters and could be as large as the energy required for ocean caught products. Clams can be produced in the aquaculture system using only about 25% of the net energy required by traditional means. The results of the analysis indicate that the system appears to be economically feasible. They also indicate that significant energy savings are possible if waste heat aquaculture products replace ocean caught products.

The transformation of waste Bakelite to replace natural fine aggregate in cement mortar

Directory of Open Access Journals (Sweden)

Nopagon Usahanunth

2017-06-01

Full Text Available Bakelite material has been used to produce the various components for cars and consumer goods industry in Thailand. The growth of Bakelite consumption increases Bakelite waste. Bakelite waste is prohibited from disposing of direct landfilling and open burning because of the improper disposal and emission reasons. A large amount of this waste needs the large safe space of warehouse area for keeping which becomes a waste management problem. Size reduction by milling machine is helpful for waste handling and storing, however, the post-milling waste Bakelite plastic utilization shall be studied to maintain the waste storing capacity. There are some studies of the milling machine used for waste plastic size reduction. However, the particular study of milling machine application for waste size reduction and its milling waste utilization is still insufficient in Thailand. The purpose of this research is the use of waste Bakelite aggregate milling machine for Bakelite waste size reduction and use of the post-milling waste Bakelite as a fine aggregate to replace natural sand material in cement mortar. The waste Bakelite fine aggregate (WBFA was mixed in cement mortar mixture with the proportion 0% 20% 40% 60% 80% and 100% by volume for cement mortar sample preparation. The mortar sample was tested for compressive strength follow ASTM standard. The compressive test result of mortar samples will be compared between conventional mortar (0% WBFA and waste Bakelite mortar (WBM as well as comparing with the mortar standard. From an analysis of the sample test data found that the WBFA content in cement mortar mixture can predict the strength of WBM. The compressive strength of WBM at 28 days age with the fraction of WBFA is not exceeded 11.03%, and 23.08% respectively can be met the mortar standard according to the equation. The utilization of WBM to develop mortar non-structural mortar product can be usable from a technical point of view.

Commissioning of a continuous melt densification system for plastic waste. Contributed Paper PE-05

International Nuclear Information System (INIS)

Anji Reddy, D.; Chennakeshavalu, G.; Ramesh Babu, B.; Subba Rao, V.; Coelho, G.J.M.; Rao, S.V.S.; Paul, Biplob

2014-01-01

Volume reduction of radioactive solid wastes is carried out with an aim to maximize the utilization of disposal space. Cellulosic combustible solid wastes like cotton, paper etc. are treated by incineration and the plastic wastes are volume reduced by baling. Compaction of plastic wastes gives volume reduction factors in the range of 3 to 5. With a view to achieve higher volume reduction factors, a melt-densification process was developed indigenously at CWMF for reducing the volume of plastic wastes before disposal. Based on laboratory results, a pilot plant scale batch Melt Densification Unit was designed and operated. 120 M 3 of Category-I polythene waste was melted and the Volume Reduction Factors (VRF) obtained were up to 20. To meet the future needs and increasing the throughput, a continues-feed, PLC controlled, advanced Melt Densification System was commissioned recently. (author)

A successful waste stream analysis on a large construction project in a radiologically controlled area

International Nuclear Information System (INIS)

Kennicott, M.; Richardson, D.; Starke, T.P.

1997-01-01

The Los Alamos National Laboratory (the Laboratory) Chemistry and Metallurgy Research (CMR) Facility, constructed in 1952, is currently under going a major, multi-year demolition and construction project. Many of the operations required under this project (i.e., design, demolition, decontamination, construction, and waste management) mimic the processes required of a large scale decontamination and decommissioning (D and D) job and are identical to the requirements of any of several upgrades projects anticipated for the laboratory and other Department of Energy (DOE) sites. For these reasons the CMR upgrades Project is seen as an ideal model facility--to test the application and measure the success of waste minimization techniques which could be implemented for any similar projects. The purpose of this paper will be to discuss the successful completion of a waste stream analysis. The analyses performed was to measure the potential impact of waste generation, in terms of volume and costs, for a reconfiguration option being considered to change the approach and execution of the original project

Large batch recycling of waste Nd–Fe–B magnets to manufacture sintered magnets with improved magnetic properties

International Nuclear Information System (INIS)

Li, X.T.; Yue, M.; Liu, W.Q.; Li, X.L.; Yi, X.F.; Huang, X.L.; Zhang, D.T.; Chen, J.W.

2015-01-01

The waste Nd–Fe–B sintered magnets up to 500 kg per batch were recycled to manufacture anisotropic sintered magnets by combination of hydrogen decrepitation (HD) and alloying technique. Magnetic properties and thermal stability of both the waste magnets and recycled magnets were investigated. The recycled magnet exhibits magnetic properties with remanence (B r ) of 12.38 kGs, coercivity (H ci ) of 24.89 kOe, and maximum energy product [(BH) max ] of 36.51 MGOe, respectively, which restores 99.20% of B r , 105.65% of H ci , and 98.65% of (BH) max of the waste magnets, respectively. The volume fraction of Nd-rich phase in the recycled magnets is about 10.1 vol.%, which is bigger than that of the waste magnets due to the additive of Nd 3 PrFe 14 B alloy containing more rare earth. The remanence temperature coefficient (α) and coercivity temperature coefficient (β) of the recycled magnets are −0.1155%/K and −0.5099%/K in the range of 288–423 K, respectively, which are comparative to those of the waste magnets. - Highlights: • Large batch recycling of waste Nd–Fe–B sintered magnets were performed. • The recycled magnet restores 99.20% of B r , 105.65% of H ci and 98.65% of (BH) max of the magnet. • The recycled magnets bears bigger volume fraction and better distribution of Nd-rich phase. • The recycled magnets exhibit similar temperature coefficients and maximum working temperature

Minimization of the volume and Pu content of the waste generated at a plutonium fuel fabrication plant

International Nuclear Information System (INIS)

Pauwels, H.

1992-01-01

The amounts of waste generated during 1987, 1989 and a past reference period have been reported in great detail. The main conclusions which can be drawn from these figures are: (i) for all kinds of waste, the waste-to-product ratio has decreased very substantially during the past few years. This reduction results partly from a scale effect, i.e. the better load factor of the plant, and partly from Belgonucleare's continuous effort to minimize the radioactive waste arisings; (ii) the ratio of the Pu content of the waste to the total Pu throughput of the plant has also decreased substantially; (iii) the mean Pu content of the solid Pu contaminated waste equals 1.39 g Pu per unit volume of 25 l. Only for a small fraction of this waste (<5% by volume) does the Pu content exceed 5 g per unit volume of 25 l; (iv) even after the implementation of waste reducing measures, some 45% of the solid Pu contaminated waste is generated by operations which involve the handling and transfer of powders. Finally, some 63% of the total amount of Pu in the waste can be imputed to these operations

Large volume cryogenic silicon detectors

International Nuclear Information System (INIS)

Braggio, C.; Boscardin, M.; Bressi, G.; Carugno, G.; Corti, D.; Galeazzi, G.; Zorzi, N.

2009-01-01

We present preliminary measurements for the development of a large volume silicon detector to detect low energy and low rate energy depositions. The tested detector is a one cm-thick silicon PIN diode with an active volume of 31 cm 3 , cooled to the liquid helium temperature to obtain depletion from thermally-generated free carriers. A thorough study has been done to show that effects of charge trapping during drift disappears at a bias field value of the order of 100V/cm.

Influence of Utilization of High-Volumes of Class F Fly Ash on the Abrasion Resistance of Concrete

Directory of Open Access Journals (Sweden)

William PRINCE

2007-01-01

Full Text Available Utilization of large volumes of fly ash in various concrete applications is a becoming a more general practice in an efforts towards using large quantities of fly ash. Around the world, Class C or Class F or both as available have been used in high volumes in cement-based materials. In India, majority of fly generated is of Class F type as per ASTM C 618. Yearly fly ash generation in India is approximately 95 million tonnes. Out of which around 15-20% is utilized in cement production and cement/concrete related activities. In order to increase its percentage utilization, an investigation was carried out to use it in concrete.In this paper, abrasion resistance of high volume fly ash (HVFA concretes made with 35, 45, 55, and 65% of cement replacement was evaluated in terms of its relation with compressive strength. Comparison was made between ordinary Portland cement and fly ash concrete. Test results indicated that abrasion resistance of concrete having cement replacement up to 35 percent was comparable to the normal concrete mix with out fly ash. Beyond 35% cement replacement, fly ash concretes exhibited slightly lower resistance to abrasion relative to non-fly ash concretes. Test results further indicated that abrasion resistance of concrete is closely related with compressive strength, and had a very good correlation between abrasion resistance and compressive strength (R2 value between 0.9018 and 0.9859 depending upon age.

Waste incineration and waste prevention: not a contradiction in terms; Abfallverbrennung ist kein Gegner der Abfallvermeidung

Energy Technology Data Exchange (ETDEWEB)

NONE

2008-07-15

The paper provides a detailed analysis of the current situation on waste management in Germany and identifies 10 arguments on the issue that waste incineration and waste prevention are not contradiction in terms. The following topics are discussed within this frame: waste prevention in production and consumption; resource-efficient products; offsetting of efficiency gains by growth of volume; consumer behavior, need of waste management; influence of long-term waste management contracts; product responsibility; highest recovery rates despite incineration of residual waste; precise sorting as a prerequisite for recovery. It is concluded that waste incineration with energy generation and utilization of slag is an environmentally sound option.

Optimal utilization of waste-to-energy in an LCA perspective.

Science.gov (United States)

Fruergaard, T; Astrup, T

2011-03-01

Energy production from two types of municipal solid waste was evaluated using life cycle assessment (LCA): (1) mixed high calorific waste suitable for production of solid recovered fuels (SRF) and (2) source separated organic waste. For SRF, co-combustion was compared with mass burn incineration. For organic waste, anaerobic digestion (AD) was compared with mass burn incineration. In the case of mass burn incineration, incineration with and without energy recovery was modelled. Biogas produced from anaerobic digestion was evaluated for use both as transportation fuel and for heat and power production. All relevant consequences for energy and resource consumptions, emissions to air, water and soil, upstream processes and downstream processes were included in the LCA. Energy substitutions were considered with respect to two different energy systems: a present-day Danish system based on fossil fuels and a potential future system based on 100% renewable energy. It was found that mass burn incineration of SRF with energy recovery provided savings in all impact categories, but co-combustion was better with respect to Global Warming (GW). If all heat from incineration could be utilized, however, the two alternatives were comparable for SRF. For organic waste, mass burn incineration with energy recovery was preferable over anaerobic digestion in most impact categories. Waste composition and flue gas cleaning at co-combustion plants were critical for the environmental performance of SRF treatment, while the impacts related to utilization of the digestate were significant for the outcome of organic waste treatment. The conclusions were robust in a present-day as well as in a future energy system. This indicated that mass burn incineration with efficient energy recovery is a very environmentally competitive solution overall. Copyright © 2010 Elsevier Ltd. All rights reserved.

Glassy slag: A complementary waste form to homogeneous glass for the implementation of MAWS in treating DOE low level/mixed wastes

International Nuclear Information System (INIS)

Feng, X.; Ordaz, G.; Krumrine, P.

1994-01-01

Glassy slag waste forms are being developed to complement glass waste forms in implementing the Minimum Additive Waste Stabilization (MAWS) Program for supporting DOE's environmental restoration efforts. These glassy slags are composed of various metal oxide crystalline phases embedded in an alumino-silicate glass phase. The slags are appropriate final waste forms for waste streams that contain large amounts of scrap metals and elements with low solubilities in glass, and that have low-flux contents. Homogeneous glass waste forms are appropriate for wastes with sufficient fluxes and low metal contents. Therefore, utilization of both glass and glassy slag waste forms will make vitrification technology applicable to the treatment of a much larger range of radioactive and mixed wastes. The MAWS approach was a plied to glassy slags by blending multiple waste streams to produce the final waste form, minimizing overall waste form volume and reducing costs. The crystalline oxide phases formed in the glassy slags can be specially formulated so that they are very durable and contain hazardous and radioactive elements in their lattice structures. The Structural Bond Strength (SBS) Model was used to predict the chemical durability of the product from the slag composition so that optimized slag compositions could be obtain with a limited number of crucible melts and testing

A utility's perspective on the Nuclear Waste Policy Act

International Nuclear Information System (INIS)

Berry, W.W.

1985-01-01

The Nuclear Waste Policy Act is especially important to utilities because their customers pay for the disposal program, and the program is vital to nuclear operations and reconsideration of the nuclear option. DOE's accomplishments in implementing the Act are noteworthy, but we are concerned that some of them have been achieved later than specified by the schedule in the Act. We make recommendations regarding disposal fees, defense wastes, and shipping casks. Virginia Power has adopted a three-part strategy relying mainly on developing dry cask storage to solve the company's interim storage problems

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

International Nuclear Information System (INIS)

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

1999-01-01

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

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

Energy Technology Data Exchange (ETDEWEB)

J. P. Adams; M. L. Carboneau

1999-03-01

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

Generation of electricity and combustible gas by utilization of agricultural waste in Nara canal area water board

International Nuclear Information System (INIS)

Joyo, P.; Memon, F.; Sohag, M.A.

2005-01-01

Biomass in an important source of energy, however, it is not fully utilized in Sindh. The various types of biomass normally used for the generation of energy are extensively available in the province. These are forest debris and thinning; residue from wood products industry; agricultural waste; fast-growing trees and crops; wood and wood waste; animal manures and non-hazardous organic portion of municipal solid waste. Since agriculture is pre-dominant in Sindh, it has a large amount of agricultural waste available in most of the areas. Agriculture wastes like rice husk, wheat straw, cotton stalks, and sugarcane bagasse can be utilized to produce gas and afterwards electricity. Pakistan Agricultural Research Council (PARC) has found that at most of the locations of Sindh, agricultural waste is available more than the energy requirements of that particular area. Biomass can also generate electricity (or heat) in one of the several processes, can be used in a piston driven engine, high efficiency gas turbine generator or a fuel cell to produce electricity. Biomass gasifies have gained attention for their efficiency, economy and environment-friendly. The Nara Canal Area Water Board is facing acute problem of electricity in the O and M of its drainage network and running of tube wells. The frequent breakdown and irregular supply of power is badly affecting in the management of drainage system and control of rising water-table, however, it is anticipated that the generation of electricity through biomass can address this acute problem and greatly help in controlling water logging and salinity in Sindh. (author)

Site study plan for utilities and solid waste, Deaf Smith County Site, Texas: Environmental Field Program: Preliminary draft

International Nuclear Information System (INIS)

1987-06-01

This site plan describes utilities and solid waste studies to be conducted during the characterization of the Deaf Smith County, Texas, site for the US Department of Energy's Salt Repository Project. After utilities and solid waste information needs derived from Federal, State, and local statutes and regulations and the project specifications are briefly described, the site study plan describes the study design and rationale, the field data collection procedures and equipment, and data analysis methods and application of results, the data management strategy, the schedule of field activities, the management of the study, and the study's quality assurance program. The field data collection activities are organized into programs to characterize electrical power, natural gas, communication, water, wastewater sludge, nonradiological solid waste, nonradiological hazardous waste, and low-level radiological waste. These programs include details for the collection of project needs, identification of utilities and solid waste disposal contractor capabilities, and verification of the obtained data. Utilities and solid waste field activities will begin approximately at the time of site access. Utilities and solid waste characterization will be completed within the first year of activity. 29 refs., 6 figs., 2 tabs

A low-temperature process for the denitration of Hanford single-shell tank, nitrate-based waste utilizing the nitrate to ammonia and ceramic (NAC) process

International Nuclear Information System (INIS)

Mattus, A.J.; Lee, D.D.; Dillow, T.A.; Farr, L.L.; Loghry, S.L.; Pitt, W.W.; Gibson, M.R.

1994-12-01

Bench-top feasibility studies with Hanford single-shell tank (SST) simulants, using a new, low-temperature (50 to 60C) process for converting nitrate to ammonia and ceramic (NAC), have conclusively shown that between 85 to 99% of the nitrate can be readily converted. In this process, aluminum powders or shot can be used to convert alkaline, nitrate-based supernate to ammonia and an aluminum oxide-sodium aluminate-based solid which might function as its own waste form. The process may actually be able to utilize already contaminated aluminum scrap metal from various DOE sites to effect the conversion. The final, nearly nitrate-free ceramic-like product can be pressed and sintered like other ceramics. Based upon the starting volumes of 6.2 and 3.1 M sodium nitrate solution, volume reductions of 50 to 55% were obtained for the waste form produced, compared to an expected 35 to 50% volume increase if the Hanford supernate were grouted. Engineering data extracted from bench-top studies indicate that the process will be very economical to operate, and data were used to cost a batch, 1,200-kg NO 3 /h plant for working off Hanford SST waste over 20 years. Their total process cost analysis presented in the appendix, indicates that between $2.01 to 2.66 per kilogram of nitrate converted will be required. Additionally, data on the fate of select radioelements present in solution are presented in this report as well as kinetic, operational, and control data for a number of experiments. Additionally, if the ceramic product functions as its own waste form, it too will offer other cost savings associated with having a smaller volume of waste form as well as eliminating other process steps such as grouting

Treatment of solid radioactive waste: Volume reduction of non-combustible waste

International Nuclear Information System (INIS)

Boehme, G.

1982-01-01

Press compaction is very common as for volume reduction of low level radioactive solid waste. In most cases a sorting step and if necessary a fragmenting step are desirable prior to the compaction process. Besides contamination-free loading and unloading techniques are important. Typical technical solutions for mixed solid waste handling and compacting equipment are shown and discussed by means of the lay-out drawings for a medium size radwaste compaction facility. A special technique can be applied if one has to compact active exhaust air filters in a hot cell. KfK has developed a remotely operated mobile equipment for this purpose. As for the nuclear fuel cycle considerable interest is existing in compacting spent fuel halls after fuel dissolution. In various European countries mechanical compaction and high temperature processes are therefore under development. These processes are described and the related equipment is discussed. (orig./RW)

Status of waste form testing

International Nuclear Information System (INIS)

Lawroski, H.

1984-01-01

The promulgation of the amendment of 10 CFR Part 61 by the Nuclear Regulatory Commission of December 27, 1982 by Federal Register Notice with an effective date of December 27, 1983 established the criteria for licensing requirements, paragraph 60.56, contained the description to provide adequate stability of the site through the use of suitable waste forms. In May, 1983, the NRC published a final Branch Technical Position (BTP) paper on waste form. The position taken by the BTP was considerably more severe than indicated in 10 CFR Part 61. An extensive and expensive testing program was started in 1983. As an interim measure, the presently utilized solidification processes such as cement, Dow binder, Envirostone and bitumen, and the presently qualified High Integrity containers (HICs) were considered acceptable with the caveat that acceptable process control programs were being utilized. The NRC requested that topical reports for licenses be submitted. The topical reports were to contain test results to substantiate the acceptability of the waste forms. The test results to date show that the volume of wastes will have to increase to meet the position taken by the NRC in the BTP. This position will cause more waste to be generated which is contrary to the emphasis by states and others to reduce the volume of waste. The details of testing will be discussed in the paper to be presented

Large volume cryogenic silicon detectors

Energy Technology Data Exchange (ETDEWEB)

Braggio, C. [Dipartimento di Fisica, Universita di Padova, via Marzolo 8, 35131 Padova (Italy); Boscardin, M. [Fondazione Bruno Kessler (FBK), via Sommarive 18, I-38100 Povo (Italy); Bressi, G. [INFN sez. di Pavia, via Bassi 6, 27100 Pavia (Italy); Carugno, G.; Corti, D. [INFN sez. di Padova, via Marzolo 8, 35131 Padova (Italy); Galeazzi, G. [INFN lab. naz. Legnaro, viale dell' Universita 2, 35020 Legnaro (Italy); Zorzi, N. [Fondazione Bruno Kessler (FBK), via Sommarive 18, I-38100 Povo (Italy)

2009-12-15

We present preliminary measurements for the development of a large volume silicon detector to detect low energy and low rate energy depositions. The tested detector is a one cm-thick silicon PIN diode with an active volume of 31 cm{sup 3}, cooled to the liquid helium temperature to obtain depletion from thermally-generated free carriers. A thorough study has been done to show that effects of charge trapping during drift disappears at a bias field value of the order of 100V/cm.

Coupling model of aerobic waste degradation considering temperature, initial moisture content and air injection volume.

Science.gov (United States)

Ma, Jun; Liu, Lei; Ge, Sai; Xue, Qiang; Li, Jiangshan; Wan, Yong; Hui, Xinminnan

2018-03-01

A quantitative description of aerobic waste degradation is important in evaluating landfill waste stability and economic management. This research aimed to develop a coupling model to predict the degree of aerobic waste degradation. On the basis of the first-order kinetic equation and the law of conservation of mass, we first developed the coupling model of aerobic waste degradation that considered temperature, initial moisture content and air injection volume to simulate and predict the chemical oxygen demand in the leachate. Three different laboratory experiments on aerobic waste degradation were simulated to test the model applicability. Parameter sensitivity analyses were conducted to evaluate the reliability of parameters. The coupling model can simulate aerobic waste degradation, and the obtained simulation agreed with the corresponding results of the experiment. Comparison of the experiment and simulation demonstrated that the coupling model is a new approach to predict aerobic waste degradation and can be considered as the basis for selecting the economic air injection volume and appropriate management in the future.

Mixed waste focus area integrated technical baseline report. Phase I, Volume 2: Revision 0

International Nuclear Information System (INIS)

1996-01-01

This document (Volume 2) contains the Appendices A through J for the Mixed Waste Focus Area Integrated Technical Baseline Report Phase I for the Idaho National Engineering Laboratory. Included are: Waste Type Managers' Resumes, detailed information on wastewater, combustible organics, debris, unique waste, and inorganic homogeneous solids and soils, and waste data information. A detailed list of technology deficiencies and site needs identification is also provided

Analysis of some nuclear waste management options. Volume II. Appendices

International Nuclear Information System (INIS)

Berman, L.E.; Ensminger, D.A.; Giuffre, M.S.; Koplik, C.M.; Oston, S.G.; Pollak, G.D.; Ross, B.I.

1978-01-01

This report describes risk analyses performed on that portion of a nuclear fuel cycle which begins following solidification of high-level waste. Risks associated with handling, interim storage and transportation of the waste are assessed, as well as the long term implications of disposal in deep mined cavities. The risk is expressed in terms of expected dose to the general population and peak dose to individuals in the population. This volume consists of appendices which provide technical details of the work performed

Analysis of some nuclear waste management options. Volume II. Appendices

Energy Technology Data Exchange (ETDEWEB)

Berman, L.E.; Ensminger, D.A.; Giuffre, M.S.; Koplik, C.M.; Oston, S.G.; Pollak, G.D.; Ross, B.I.

1978-10-10

This report describes risk analyses performed on that portion of a nuclear fuel cycle which begins following solidification of high-level waste. Risks associated with handling, interim storage and transportation of the waste are assessed, as well as the long term implications of disposal in deep mined cavities. The risk is expressed in terms of expected dose to the general population and peak dose to individuals in the population. This volume consists of appendices which provide technical details of the work performed.

Effect of natural ageing on volume stability of MSW and wood waste incineration residues

International Nuclear Information System (INIS)

Gori, Manuela; Bergfeldt, Britta; Reichelt, Jürgen; Sirini, Piero

2013-01-01

Highlights: ► Natural weathering on BA from MSW and wood waste incineration was evaluated. ► Type of mineral phases, pH and volume stability were considered. ► Weathering reactions effect in improved stability of the materials. - Abstract: This paper presents the results of a study on the effect of natural weathering on volume stability of bottom ash (BA) from municipal solid waste (MSW) and wood waste incineration. BA samples were taken at different steps of treatment (fresh, 4 weeks and 12 weeks aged) and then characterised for their chemical and mineralogical composition and for volume stability by means of the mineralogical test method (M HMVA-StB), which is part of the German quality control system for using aggregates in road construction (TL Gestein-StB 04). Changes of mineralogical composition with the proceeding of the weathering treatment were also monitored by leaching tests. At the end of the 12 weeks of treatment, almost all the considered samples resulted to be usable without restrictions in road construction with reference to the test parameter volume stability

Dilute scintillators for large-volume tracking detectors

Energy Technology Data Exchange (ETDEWEB)

Reeder, R.A. (University of New Mexico, Albuquerque, NM (United States)); Dieterle, B.D. (University of New Mexico, Albuquerque, NM (United States)); Gregory, C. (University of New Mexico, Albuquerque, NM (United States)); Schaefer, F. (University of New Mexico, Albuquerque, NM (United States)); Schum, K. (University of New Mexico, Albuquerque, NM (United States)); Strossman, W. (University of California, Riverside, CA (United States)); Smith, D. (Embry-Riddle Aeronautical Univ., Prescott, AZ (United States)); Christofek, L. (Los Alamos National Lab., NM (United States)); Johnston, K. (Los Alamos National Lab., NM (United States)); Louis, W.C. (Los Alamos National Lab., NM (United States)); Schillaci, M. (Los Alamos National Lab., NM (United States)); Volta, M. (Los Alamos National Lab., NM (United States)); White, D.H. (Los Alamos National Lab., NM (United States)); Whitehouse, D. (Los Alamos National Lab., NM (United States)); Albert, M. (University of Pennsylvania, Phi

1993-10-01

Dilute scintillation mixtures emit isotropic light for both fast and slow particles, but retain the Cherenkov light cone from fast particles. Large volume detectors using photomultipliers to reconstruct relativistic tracks will also be sensitive to slow particles if they are filled with these mixtures. Our data show that 0.03 g/l of b-PBD in mineral oil has a 2.4:1 ratio (in the first 12 ns) of isotropic light to Cherenkov light for positron tracks. The light attenuation length is greater than 15 m for wavelength above 400 nm, and the scintillation decay time is about 2 ns for the fast component. There is also a slow isotropic light component that is larger (relative to the fast component) for protons than for electrons. This effect allows particle identification by a technique similar to pulse shape discrimination. These features will be utilized in LSND, a neutrino detector at LAMPF. (orig.)

A risk management approach to double-shell tank waste volume versus storage capacity

Energy Technology Data Exchange (ETDEWEB)

Coles, G.A. [Westinghouse Hanford Co., Richland, WA (United States); Thurkow, T.J.; Fritz, R.L.; Nuhlestein, L.O.; Allen, M.R.; Stuart, R.J. [ARES Corp. (United States)

1996-01-01

A risk-based assessment of the overall waste volume versus double-shell tank storage capacity was conducted to develop fallback positions for projections where the waste volume was at a high risk of exceeding capacity. This study was initiated to provide that assessment. A working simulation model was the primary deliverable of this study. The model validates the approach and demonstrates that simulation analysis can provide a method of tracking uncertainties in available data, assessing probabilities, and serves as a tool to be used by management to determine the consequences of various off-normal occurrences.

A risk management approach to double-shell tank waste volume versus storage capacity

International Nuclear Information System (INIS)

Coles, G.A.; Thurkow, T.J.; Fritz, R.L.; Nuhlestein, L.O.; Allen, M.R.; Stuart, R.J.

1996-01-01

A risk-based assessment of the overall waste volume versus double-shell tank storage capacity was conducted to develop fallback positions for projections where the waste volume was at a high risk of exceeding capacity. This study was initiated to provide that assessment. A working simulation model was the primary deliverable of this study. The model validates the approach and demonstrates that simulation analysis can provide a method of tracking uncertainties in available data, assessing probabilities, and serves as a tool to be used by management to determine the consequences of various off-normal occurrences

Incineration of Low Level Radioactive Vegetation for Waste Volume Reduction

International Nuclear Information System (INIS)

Malik, N.P.S.; Rucker, G.G.; Looper, M.G.

1995-01-01

The DOE changing mission at Savannah River Site (SRS) are to increase activities for Waste Management and Environmental Restoration. There are a number of Comprehensive Environmental Response, Compensation and Liability Act (CERCLA) locations that are contaminated with radioactivity and support dense vegetation, and are targeted for remediation. Two such locations have been studied for non-time critical removal actions under the National Contingency Plan (NCP). Both of these sites support about 23 plant species. Surveys of the vegetation show that radiation emanates mainly from vines, shrubs, and trees and range from 20,000 to 200,000 d/m beta gamma. Planning for removal and disposal of low-level radioactive vegetation was done with two principal goals: to process contaminated vegetation for optimum volume reduction and waste minimization, and for the protection of human health and environment. Four alternatives were identified as candidates for vegetation removal and disposal: chipping the vegetation and packing in carbon steel boxes (lined with synthetic commercial liners) and disposal at the Solid Waste Disposal Facility at SRS; composting the vegetation; burning the vegetation in the field; and incinerating the vegetation. One alternative 'incineration' was considered viable choice for waste minimization, safe handling, and the protection of the environment and human health. Advantages and disadvantages of all four alternatives considered have been evaluated. For waste minimization and ultimate disposal of radioactive vegetation incineration is the preferred option. Advantages of incineration are that volume reduction is achieved and low-level radioactive waste are stabilized. For incineration and final disposal vegetation will be chipped and packed in card board boxes and discharged to the rotary kiln of the incinerator. The slow rotation and longer resident time in the kiln will ensure complete combustion of the vegetative material

Information base for waste repository design. Volume 5. Decommissioning of underground facilities. Technical report

International Nuclear Information System (INIS)

Giuffre, M.S.; Plum, R.L.; Koplik, C.M.; Talbot, R.

1979-03-01

This report is Volume 5 of a seven volume document on nuclear waste repository design issues. This report discusses the requirements for decommissioning a deep underground facility for the disposal of radioactive waste. The techniques for sealing the mined excavations are presented and an information base on potential backfill materials is provided. Possible requirements for monitoring the site are discussed. The performance requirements for backfill materials are outlined. The advantages and disadvantages of each sealing method are stated

Supercompactor force effectiveness as related to dry active waste volume reduction

International Nuclear Information System (INIS)

Williams, P.C.; Phillips, W.S.

1986-01-01

The first U.S. permanently installed supercompactor is now in operation at the Babcock and Wilcox volume reduction center, Parks Township, Pennsylvania. Tests with various DAW (dry active waste) material have been conducted, recording press force versus drum height as one means of estimating volume reduction capability of this machine at various compaction forces. The results of these tests, as well as other factors, are presented herein

Effects of uncertainty in model predictions of individual tree volume on large area volume estimates

Science.gov (United States)

Ronald E. McRoberts; James A. Westfall

2014-01-01

Forest inventory estimates of tree volume for large areas are typically calculated by adding model predictions of volumes for individual trees. However, the uncertainty in the model predictions is generally ignored with the result that the precision of the large area volume estimates is overestimated. The primary study objective was to estimate the effects of model...

Community Energy Systems and the Law of Public Utilities. Volume Nine. Connecticut

Energy Technology Data Exchange (ETDEWEB)

Feurer, D A; Weaver, C L

1981-01-01

A detailed description of the laws and programs of the State of Connecticut governing the regulation of public energy utilities, the siting of energy generating and transmission facilities, the municipal franchising of public energy utilities, and the prescription of rates to be charged by utilities including attendant problems of cost allocations, rate base and operating expense determinations, and rate of return allowances. These laws and programs are analyzed to identify impediments which they may present to the implementation of Integrated Community Energy Systems (ICES). This report is one of fifty-one separate volumes which describe such regulatory programs at the Federal level and in each state as background to the report entitled Community Energy Systems and the Law of Public Utilities - Volume One: An Overview. This report also contains a summary of a strategy described in Volume One - An Overview for overcoming these impediments by working within the existing regulatory framework and by making changes in the regulatory programs to enhance the likelihood of ICES implementation.

Community Energy Systems and the Law of Public Utilities. Volume Twelve. Georgia

Energy Technology Data Exchange (ETDEWEB)

Feurer, D A; Weaver, C L

1981-01-01

A detailed description of the laws and programs of the State of Georgia governing the regulation of public energy utilities, the siting of energy generating and transmission facilities, the municipal franchising of public energy utilities, and the prescription of rates to be charged by utilities including attendant problems of cost allocations, rate base and operating expense determinations, and rate of return allowances. These laws and programs are analyzed to identify impediments which they may present to the implementation of Integrated Community Energy Systems (ICES). This report is one of fifty-one separate volumes which describe such regulatory programs at the Federal level and in each state as background to the report entitled Community Energy Systems and the Law of Public Utilities - Volume One: An Overview. This report also contains a summary of a strategy described in Volume One - An Overview for overcoming these impediments by working within the existing regulatory framework and by making changes in the regulatory programs to enhance the likelihood of ICES implementation.

A utility perspective on the proposed Northeast interstate compact

International Nuclear Information System (INIS)

Keating, W.R.

1984-01-01

The proposed Northeast Compact on Low-Level Radioactive Waste appears to be stalled in its present form. The Low-Level Waste Policy Act of 1980 encourages states to enter into regional waste compacts where practicable. The Northeast Region, which includes eleven states made up of the six New England states plus New York, New Jersey, Pennsylvania, Delaware, and Maryland, is the largest proposed compact region from the standpoint of low-level radioactive waste volumes. There is also wide variation in volumes among the states. Four states in the region have ratified the Northeast Compact, but the remaining seven states, including the three largest generating states, have not ratified to date. The large states are pivotal in determining whether the compact will move forward. The prime concerns of these large volume generating states appear to be host state selection and responsibility issues, as well as some of the proposed powers and authority of the Regional Commission

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

International Nuclear Information System (INIS)

Adams, J.P.

1995-09-01

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

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

International Nuclear Information System (INIS)

Li Ruixiang; Liu Xinhua; Gan Lin

1994-09-01

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

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

Directory of Open Access Journals (Sweden)

Hamza Ali

2017-01-01

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

System of large transport containers for waste from dismantling light water and gas-cooled nuclear reactors. Volume 2

International Nuclear Information System (INIS)

Price, M.S.T.

1986-09-01

This report deals with the operational, radiological and economic aspects of transport as well as conceptual designs of large containers for the transport of radioactive decommissioning wastes from nuclear power plants within the member states of the European Economic Community. The means of transport, the costs and radiological detriment are considered, and conceptual designs of containers are described. Recommendations are made for further studies. (U.K.)

Development of recycling techniques for nuclear power plant decommissioning waste

International Nuclear Information System (INIS)

Ishikura, Takeshi; Oguri, Daiichiro; Abe, Seiji; Ohnishi, Kazuhiko

2003-01-01

Recycling of concrete and metal waste will provide solution to reduce waste volume, contributing to save the natural resources and to protect the environment. Nuclear Power Engineering Corporation has developed techniques of concrete and metal recycling for decommissioning waste of commercial nuclear power plants. A process of radioactive concrete usage for mortar solidification was seen to reduce concrete waste volume by 2/3. A concrete reclamation process for high quality aggregate was confirmed that the reclaimed aggregate concrete is equivalent to ordinary concrete. Its byproduct powder was seen to be utilized various usage. A process of waste metal casting to use radioactive metal as filler could substantially decrease the waste metal volume when thinner containers are applied. A pyro-metallurgical separation process was seen to decrease cobalt concentration by 1/100. Some of these techniques are finished of demonstration tests for future decommissioning activity. (author)

MERCURY CONTROL IN MUNICIPAL WASTE COMBUSTORS AND COAL-FIRED UTILITIES

Science.gov (United States)

Control of mercury (Hg) emissions from municipal waste combustors (MWCs) and coal-fired utilities has attracted attention due to current and potential regulations. Among several techniques evaluated for Hg control, dry sorbent injection (primarily injection of activated carbon) h...

Significant volume reduction of tank waste by selective crystallization: 1994 Annual report

International Nuclear Information System (INIS)

Herting, D.L.; Lunsford, T.R.

1994-01-01

The objective of this technology task plan is to develop and demonstrate a scaleable process of reclaim sodium nitrate (NaNO 3 ) from Hanford waste tanks as a clean nonradioactive salt. The purpose of the so-called Clean Salt Process is to reduce the volume of low level waste glass by as much as 70%. During the reporting period of October 1, 1993, through May 31, 1994, progress was made on four fronts -- laboratory studies, surrogate waste compositions, contracting for university research, and flowsheet development and modeling. In the laboratory, experiments with simulated waste were done to explore the effects of crystallization parameters on the size and crystal habit of product NaNO 3 crystals. Data were obtained to allows prediction of decontamination factor as a function of solid/liquid separation parameters. Experiments with actual waste from tank 101-SY were done to determine the extent of contaminant occlusions in NaNO 3 crystals. In preparation for defining surrogate waste compositions, single shell tanks were categorized according to the weight percent NaNO 3 in each tank. A detailed process flowsheet and computer model were created using the ASPENPlus steady state process simulator. This is the same program being used by the Tank Waste Remediation System (TWRS) program for their waste pretreatment and disposal projections. Therefore, evaluations can be made of the effect of the Clean Salt Process on the low level waste volume and composition resulting from the TWRS baseline flowsheet. Calculations, using the same assumptions as used for the TWRS baseline where applicable indicate that the number of low level glass vaults would be reduced from 44 to 16 if the Clean Salt Process were incorporated into the baseline flowsheet

Some problems in utilization system of FP nuclides and actinides in the high level liquid wastes

International Nuclear Information System (INIS)

Ichiyanagi, Katsuaki; Emura, Satoru

1974-01-01

There are three nuclides of sup(134/137)Cs for irradiation sources, 90 Sr for radioisotope thermoelectric generators, and 238 Pu for cardiac pacemakers, as the nuclides for which considerable demand is expected in near future among those contained in reprocessed high level liquid wastes. Technical problems are first described from the viewpoint of utilization system. Then the control system of reprocessed high level wastes is expained. Finally, economic possibility and problems in their utilization are discussed. Being in competition with 60 Co, the price of sup(134/137)Cs will be lower than that of 60 Co after a decade. The annual demand in 1985 may be 6.1 x 10 6 Ci. The conclusive factor of 90 Sr market price is hard to get because it finds no strong competitive nuclides. It may be about 20 yen/Ci after ten years. Demand is expected to be approximately 1.2 x 10 7 Ci/year. However it is pretty hard to pay the cost of group separation and solidification, storage and conversion to products with such gain. It is estimated that the balance of income and outgo would be almost profitable, if the utilization of FP nuclides would progress and the demand three times as large as this assumption would be developed. (Wakatsuki, Y.)

High level waste storage tank farms/242-A evaporator Standards/Requirements Identification Document (S/RID), Volume 6

Energy Technology Data Exchange (ETDEWEB)

1994-04-01

The High-Level Waste Storage Tank Farms/242-A Evaporator Standards/Requirements Identification Document (S/RID) is contained in multiple volumes. This document (Volume 6) outlines the standards and requirements for the sections on: Environmental Restoration and Waste Management, Research and Development and Experimental Activities, and Nuclear Safety.

High level waste storage tank farms/242-A evaporator Standards/Requirements Identification Document (S/RID), Volume 6

International Nuclear Information System (INIS)

1994-04-01

The High-Level Waste Storage Tank Farms/242-A Evaporator Standards/Requirements Identification Document (S/RID) is contained in multiple volumes. This document (Volume 6) outlines the standards and requirements for the sections on: Environmental Restoration and Waste Management, Research and Development and Experimental Activities, and Nuclear Safety

New volume reduction conditioning options for solid alpha-bearing waste

International Nuclear Information System (INIS)

Jouan, A.; Jacquet-Francillon, N.; Kertesz, C.; Frotscher, H.; Ganser, B.; Klein, M.

1990-01-01

The current and future development of nuclear energy requires increasing allowance for nuclear waste treatment: α-bearing wastes destined for geological storage are already conditioned, generally in a cement matrix. Other containment processes producing higher quality matrices and allowing volume reduction have been investigated over the last five years by the General Directorate for Science Research and Development of the Commission of the European Communities. This paper discusses the work on conditioning α-bearing ashes produced by incineration of contaminated combustible materials, and on fuel cladding hulls resulting from spent fuel reprocessing

Combined energy production and waste management in manned spacecraft utilizing on-demand hydrogen production and fuel cells

Science.gov (United States)

Elitzur, Shani; Rosenband, Valery; Gany, Alon

2016-11-01

Energy supply and waste management are among the most significant challenges in human spacecraft. Great efforts are invested in managing solid waste, recycling grey water and urine, cleaning the atmosphere, removing CO2, generating and saving energy, and making further use of components and products. This paper describes and investigates a concept for managing waste water and urine to simultaneously produce electric and heat energies as well as fresh water. It utilizes an original technique for aluminum activation to react spontaneously with water at room temperature to produce hydrogen on-site and on-demand. This reaction has further been proven to be effective also when using waste water and urine. Applying the hydrogen produced in a fuel cell, one obtains electric energy as well as fresh (drinking) water. The method was compared to the traditional energy production technology of the Space Shuttle, which is based on storing the fuel cell reactants, hydrogen and oxygen, in cryogenic tanks. It is shown that the alternative concept presented here may provide improved safety, compactness (reduction of more than one half of the volume of the hydrogen storage system), and management of waste liquids for energy generation and drinking water production. Nevertheless, it adds mass compared to the cryogenic hydrogen technology. It is concluded that the proposed method may be used as an emergency and backup power system as well as an additional hydrogen source for extended missions in human spacecraft.

Amount of radioactive wastes in the Federal Republic of Germany. Waste inventory for the year 1984

International Nuclear Information System (INIS)

Brennecke, P.; Schuhmacher, J.

1986-03-01

On December 31, 1984, about 53 200 waste packages were stored in intermediate storage facilities. The unconditioned radioactive wastes amounted to about 7 000 m 3 . The volume of the conditioned radioactive wastes amounted to about 25 100 m 3 . Thereof the waste from nuclear research establishments made up about 10 000 m 3 , the waste from the operation of nuclear power plants about 7 400 m 3 and the waste from spent fuel reprocessing about 5 100 m 3 . In addition the future amount of conditioned radioactive wastes with negligible heat generation was prognosticated. Due to this forecast an amount of about 238 000 m 3 of these wastes is expected in the year 2000. In 1984 a capacity of about 87 800 m 3 for the intermediate storage of radioactive wastes was available. On December 31, 1984, this capacity was utilized by unconditioned and conditioned radioactive wastes to about 37%. It may be concluded from the data on the expected amount of radioactive wastes with negligible heat generation and on the utilization factor of the intermediate storage facilities that no bottlenecks are to be assumed up to the planned operation of the Konrad repository. (orig./HP) [de

Technical support for GEIS: radioactive waste isolation in geologic formations. Volume 10. Repository preconceptual design studies: granite

International Nuclear Information System (INIS)

1978-04-01

This volume, Volume 10 ''Repository Preconceptual Design Studies: Granite,'' is one of a 23-volume series, ''Technical Support for GEIS: Radioactive Waste Isolation in Geologic Formations,'' Y/OWI/TM-36, which supplements the ''Contribution to Draft Generic Environmental Impact Statement on Commercial Waste Management: Radioactive Waste Isolation in Geologic Formations,'' Y/OWI/TM-44. The series provides a more complete technical basis for the preconceptual designs, resource requirements, and environmental source terms associated with isolating commercial LWR wastes in underground repositories in salt, granite, shale and basalt. Wastes are considered from three fuel cycles: uranium and plutonium recycling, no recycling of spent fuel and uranium-only recycling. This document describes a preconceptual design for a nuclear waste storage facility in granite. The facility design consists of several chambers excavated deep within a geologic formation together with access shafts and supportive surface structures. The facility design provides for: receiving and unloading waste containers; lowering them down shafts to the mine level; transporting them to the proper storage area, and emplacing them in mined storage rooms. Drawings of the facility design are contained in TM-36/11, ''Drawings for Repository Preconceptual Design Studies: Granite.''

Technical support for GEIS: radioactive waste isolation in geologic formations. Volume 8. Repository preconceptual design studies: salt

International Nuclear Information System (INIS)

1978-04-01

This volume, Volume 8 ''Repository Preconceptual Design Studies: Salt,'' is one of a 23-volume series, ''Technical Support for GEIS: Radioactive Waste Isolation in Geologic Formations,'' Y/OWI/TM-36, which supplements the ''Contribution to Draft Generic Environmental Impact Statement on Commercial Waste Management: Radioactive Waste Isolation in Geologic Formations,'' Y/OWI/TM-44. The series provides a more complete technical basis for the preconceptual designs, resource requirements, and environmental source terms associated with isolating commercial LWR wastes in underground repositories in salt, granite, shale and basalt. Wastes are considered from three fuel cycles: uranium and plutonium recycling, no recycling of spent fuel and uranium-only recycling. This document describes a preconceptual design for a nuclear waste storage facility in salt. The facility design consists of several chambers excavated deep within a geologic formation together with access shafts and supportive surface structures. The facility design provides for: receiving and unloading waste containers; lowering them down shafts to the mine level; transporting them to the proper storage area, and emplacing them in mined storage rooms. Drawings of the facility design are contained in TM-36/9, ''Drawings for Repository Preconceptual Design Studies: Salt.''

Volume reduction of low-level radioactive waste with a hammermill

International Nuclear Information System (INIS)

Gregory, W.D.

1979-01-01

A Jacobson Model J-3 Hammermill was recently installed at the University of Rochester to process low-level radioactive wastes from hospital and research laboratories. The hammermill will handle both glass and plastic vials of all types. The waste is poured into a hopper located on the top of the seven foot high assembly. The material is gravity fed into the hammermill which is driven by a 15-horsepower motor at 3600 rpm. The waste is pounded by the rotating hammers into a metal screen perforated with one inch holes. The gound-up product is discharged from the bottom of the unit into a 55-gallon shipping drum. A volume reduction of 4:1 has been acheived on an equal mixture of glass and plastic vials

Waste Retrieval Sluicing System Campaign Number 3 Solids Volume Transferred Calculation

International Nuclear Information System (INIS)

CAROTHERS, K.G.

1999-01-01

Waste Retrieval Sluicing System (WRSS) operations at tank 241-C-106 began on Wednesday, November 18, 1998. The purpose of this system is to retrieve and transfer the high-heat sludge from the tank for storage in double-shell tank 241-AY-102, thereby resolving the high-heat safety issue for the tank, and to demonstrate modernized past-practice retrieval technology for single-shell tank waste. Performance Agreement (PA) TWR 1.2.2, C-106 Sluicing, was established by the Department of Energy, Office of River Protection (ORP) for achieving completion of sluicing retrieval of waste from tank 241-C-106 by September 30, 1999. This level of sludge removal is defined in the PA as either removal of approximately 72 inches of sludge or removal of 172,000 gallons of sludge (approximately 62 inches) and less than 6,000 gallons (approximately 2 inches) of sludge removal per 12 hour sluice batch for three consecutive batches. Preliminary calculations of the volume of tank 241-C-106 sludge removed as of September 29, 1999 were provided to ORP documenting completion of PA TWR 1.2.2 (Allen 1999a). The purpose of this calculation is to document the final sludge volume removed from tank 241-C-106 up through September 30, 1999. Additionally, the results of an extra batch completed October 6, 1999 is included to show the total volume of sludge removed through the end of WRSS operations. The calculation of the sludge volume transferred from the tank is guided by engineering procedure HNF-SD-WM-PROC-021, Section 15.0,Rev. 3, sub-section 4.4, ''Calculation of Sludge Transferred.''

Waste Retrieval Sluicing System Campaign Number 3 Solids Volume Transferred Calculation

International Nuclear Information System (INIS)

CAROTHERS, K.G.

1999-01-01

Waste Retrieval Sluicing System (WRSS) operations at tank 241-C-106 began on Wednesday, November 18,1998. The purpose of this system is to retrieve and transfer the high-heat sludge from the tank for storage in double-shell tank 241-AY-102, thereby resolving the high-heat safety issue for the tank, and to demonstrate modernized past-practice retrieval technology for single-shell tank waste. Performance Agreement (PA) TWR 1.2.2, C-106 Sluicing, was established by the Department of Energy, Office of River Protection (ORP) for achieving completion of sluicing retrieval of waste from tank 241-C-106 by September 30,1999. This level of sludge removal is defined in the PA as either removal of approximately 72 inches of sludge or removal of 172,000 gallons of sludge (approximately 62 inches) and less than 6,000 gallons (approximately 2 inches) of sludge removal per 12 hour sluice batch for three consecutive batches. Preliminary calculations of the volume of tank 241-C-106 sludge removed as of September 29, 1999 were provided to ORP documenting completion of PA TWR 1.2.2 (Allen 1999a). The purpose of this calculation is to document the final sludge volume removed from tank 241-C-106 up through September 30, 1999. Additionally, the results of an extra batch completed October 6, 1999 is included to show the total volume of sludge removed through the end of WRSS operations. The calculation of the sludge volume transferred from the tank is guided by engineering procedure HNF-SD-WM-PROC-021, Section 15.0,Rev. 3, sub-section 4.4, ''Calculation of Sludge Transferred.''

Final waste management programmatic environmental impact statement for managing treatment, storage, and disposl of radioactive and hazardous waste. Volume II

International Nuclear Information System (INIS)

1997-01-01

The Final Waste Management Programmatic Environmental Impact Statement (WM PEIS) examines the potential environmental and cost impacts of strategic management alternatives for managing five types of radioactive and hazardous wastes that have resulted and will continue to result from nuclear defense and research activities at a variety of sites around the United States. The five waste types are low-level mixed waste, low-level waste, transuranic waste, high-level waste, and hazardous waste. The WM PEIS provides information on the impacts of various siting alternatives which the Department of Energy (DOE) will use to decide at which sites to locate additional treatment, storage, and disposal capacity for each waste type.Volume II is an integral part of the Office of Environmental Management''s (EM''s) Waste Management Programmatic Environmental Impact Statement (WM PEIS), which portrays the impacts of EM''s waste management activities at each of the 17 major DOE sites evaluated in the WM PEIS

The methods of conversion of radioactive waste: a look at the past

International Nuclear Information System (INIS)

Rezchikov, D.

2000-01-01

In 1948, the Government of the USSR made provisions to establish an industrial complex to produce Pu-239 in the Chelyabinsk region. PA 'MAYAK' was part of this complex. It is now addressing radioactive waste disposition in peacetime. Making Pu-239 in metal form led to the formation of large quantities of liquid radioactive waste. Since it was impossible to clean the water at that time, radioactive waste was put in the Techa River until 1951. The liquid waste contained a mixture of radioactive Sr, Cs, Nb, Ru and other elements. Sr-90 and Cs-137 accounted for about a quarte of the radioactivity. Many people lived near the Techa and received large doses of radiation. About 2.7 million Curies was put into the river before this practice stopped arid waste was then put into Lake Karachay. High-activity waste was placed in concrete and steel for protection. The volume was cooled with water. When cooling was stopped, the dry mixture heated to 300-350 degrees and exploded. According to official information, the reason for the incident was because the system's control temperature and level of the waste were exceeded. Repair was impossible because radiation fields were high. Contents of the volume were released in the plume and spread into the atmosphere. Around 90 percent of the radioactivity fell near the place of the burst. The rest of the 2 million curies was spread by wind and appeared as the West Ural Trace. It was very important to utilize solid waste (SW). Around 200 special places were made for storage of SW. High-activity SW was kept in reinforced-concrete containers. Middle-activity waste was put in a trench. The total activity of SW is approximately 2 million Curies. (authors)

Description of solid waste expected from a large commercial reprocessing plant

International Nuclear Information System (INIS)

Keely, R.B.

1979-01-01

Both low-level and high-level solid wastes generated during reprocessing of spent nuclear fuel are characterized in this paper with respect to source, quantity, content, radioactivity, potential volume reduction, and transuranic content

Iron Phosphate Glasses: An Alternative for Vitrifying Certain Nuclear Wastes

Energy Technology Data Exchange (ETDEWEB)

Delbert E. Day; Chandra S. Ray; Cheol-Woon Kim

2004-12-28

Vitrification of nuclear waste in a glass is currently the preferred process for waste disposal. DOE currently approves only borosilicate (BS) type glasses for such purposes. However, many nuclear wastes, presently awaiting disposal, have complex and diverse chemical compositions, and often contain components that are poorly soluble or chemically incompatible in BS glasses. Such problematic wastes can be pre-processed and/or diluted to compensate for their incompatibility with a BS glass matrix, but both of these solutions increases the wasteform volume and the overall cost for vitrification. Direct vitrification using alternative glasses that utilize the major components already present in the waste is preferable, since it avoids pre-treating or diluting the waste, and, thus, minimizes the wasteform volume and overall cost.

Iron Phosphate Glasses: An Alternative for Vitrifying Certain Nuclear Wastes

International Nuclear Information System (INIS)

Day, Delbert E.; Ray, Chandra S.; Cheol-Woon Kim

2004-01-01

Vitrification of nuclear waste in a glass is currently the preferred process for waste disposal. DOE currently approves only borosilicate (BS) type glasses for such purposes. However, many nuclear wastes, presently awaiting disposal, have complex and diverse chemical compositions, and often contain components that are poorly soluble or chemically incompatible in BS glasses. Such problematic wastes can be pre-processed and/or diluted to compensate for their incompatibility with a BS glass matrix, but both of these solutions increases the wasteform volume and the overall cost for vitrification. Direct vitrification using alternative glasses that utilize the major components already present in the waste is preferable, since it avoids pre-treating or diluting the waste, and, thus, minimizes the wasteform volume and overall cost

Characterizing food waste substrates for co-digestion through biochemical methane potential (BMP) experiments.

Science.gov (United States)

Lisboa, Maria Sol; Lansing, Stephanie

2013-12-01

Co-digestion of food waste with dairy manure is increasingly utilized to increase energy production and make anaerobic digestion more affordable; however, there is a lack of information on appropriate co-digestion substrates. In this study, biochemical methane potential (BMP) tests were conducted to determine the suitability of four food waste substrates (meatball, chicken, cranberry and ice cream processing wastes) for co-digestion with flushed dairy manure at a ratio of 3.2% food waste and 96.8% manure (by volume), which equated to 14.7% (ice-cream) to 80.7% (chicken) of the VS being attributed to the food waste. All treatments led to increases in methane production, ranging from a 67.0% increase (ice cream waste) to a 2940% increase (chicken processing waste) compared to digesting manure alone, demonstrating the large potential methane production of food waste additions compared to relatively low methane production potential of the flushed dairy manure, even if the overall quantity of food waste added was minimal. Copyright © 2013 Elsevier Ltd. All rights reserved.

Savannah River Site mixed waste Proposed Site Treatment Plan (PSTP). Volumes 1 and 2 and reference document: Revision 2

International Nuclear Information System (INIS)

Helmich, E.; Noller, D.K.; Wierzbicki, K.S.; Bailey, L.L.

1995-01-01

The DOE is required by the Resource Conservation and Recovery Act to prepare site treatment plans describing the development of treatment capacities and technologies for treating mixed waste. This proposed plan contains Savannah River Site's preferred options and schedules for constructing new facilities, and otherwise obtaining treatment for mixed wastes. The proposed plan consists of 2 volumes. Volume 1, Compliance Plan, identifies the capacity to be developed and the schedules as required. Volume 2, Background, provides a detailed discussion of the preferred options with technical basis, plus a description of the specific waste streams. Chapters are: Introduction; Methodology; Mixed low level waste streams; Mixed transuranic waste; High level waste; Future generation of mixed waste streams; Storage; Process for evaluation of disposal issues in support of the site treatment plans discussions; Treatment facilities and treatment technologies; Offsite waste streams for which SRS treatment is the Preferred Option (Naval reactor wastes); Summary information; and Acronyms and glossary. This revision does not contain the complete revised report, but only those pages that have been revised

Waste Controls at Base Metal Mines

Science.gov (United States)

Bell, Alan V.

1976-01-01

Mining and milling of copper, lead, zinc and nickel in Canada involves an accumulation of a half-million tons of waste material each day and requires 250 million gallons of process water daily. Waste management considerations for handling large volumes of wastes in an economically and environmentally safe manner are discussed. (BT)

Practical utilization of modeling and simulation in laboratory process waste assessments

International Nuclear Information System (INIS)

Lyttle, T.W.; Smith, D.M.; Weinrach, J.B.; Burns, M.L.

1993-01-01

At Los Alamos National Laboratory (LANL), facility waste streams tend to be small but highly diverse. Initial characterization of such waste streams is difficult in part due to a lack of tools to assist the waste generators in completing such assessments. A methodology has been developed at LANL to allow process knowledgeable field personnel to develop baseline waste generation assessments and to evaluate potential waste minimization technology. This process waste assessment (PWA) system is an application constructed within the process modeling system. The Process Modeling System (PMS) is an object-oriented, mass balance-based, discrete-event simulation using the common LISP object system (CLOS). Analytical capabilities supported within the PWA system include: complete mass balance specifications, historical characterization of selected waste streams and generation of facility profiles for materials consumption, resource utilization and worker exposure. Anticipated development activities include provisions for a best available technologies (BAT) database and integration with the LANL facilities management Geographic Information System (GIS). The environments used to develop these assessment tools will be discussed in addition to a review of initial implementation results

Food waste volume and origin: Case studies in the Finnish food service sector.

Science.gov (United States)

Silvennoinen, Kirsi; Heikkilä, Lotta; Katajajuuri, Juha-Matti; Reinikainen, Anu

2015-12-01

We carried out a project to map the volume and composition of food waste in the Finnish food service sector. The amount, type and origin of avoidable food waste were investigated in 51 food service outlets, including schools, day-care centres, workplace canteens, petrol stations, restaurants and diners. Food service outlet personnel kept diaries and weighed the food produced and wasted during a one-week or one-day period. For weighing and sorting, the food waste was divided into two categories: originally edible (OE) food waste was separated from originally inedible (OIE) waste, such as vegetable peelings, bones and coffee grounds. In addition, food waste (OE) was divided into three categories in accordance with its origins: kitchen waste, service waste and customer leftovers. According to the results, about 20% of all food handled and prepared in the sector was wasted. The findings also suggest that the main drivers of wasted food are buffet services and overproduction. Copyright © 2015 Elsevier Ltd. All rights reserved.

Trial operation of the advanced volume reduction facilities for LLW at JAEA

International Nuclear Information System (INIS)

Nakashio, Nobuyuki; Higuchi, Hidekazu; Momma, Toshiyuki; Kozawa, Kazushige; Touhei, Toshio; Sudou, Tomoyuki; Mitsuda, Motoyuki; Kurosawa, Shigenobu; Hemmi, Kou; Ishikawa, Joji; Kato, Mitsugu; Sato, Motoaki

2007-01-01

The Japan Atomic Energy Agency (JAEA) constructed the Advanced Volume Reduction Facilities (AVRF), in which volume reduction techniques are applied and achieved high volume reduction ratio, homogenization and stabilization by means of melting or super compaction processes for low level radioactive solid wastes. It will be able to produce waste packages for final disposal and to reduce the volume of stored wastes by operating the AVRF. The AVRF consist of the Waste Size Reduction and Storage Facilities (WSRSF) and the Waste Volume Reduction Facilities (WVRF); the former has cutting installations for large size wastes and the latter has melting units and a super compactor. Cutting installations in the WSRSF have been operating since July 1999. Radioactive wastes treated so far amount to 750 m 3 and the volume reduction ratio is from 1.7 to 3.7. The WVRF has been operating with non-radioactive wastes since February 2003 for the training and the homogeneity investigation in the melting processes. The operation of the pretreatment system in the WVRF with radioactive wastes has partly started in FY2005. (author)

Second interim assessment of the Canadian concept for nuclear fuel waste disposal. Volume 2

International Nuclear Information System (INIS)

Gillespie, P.A.; Wuschke, D.M.; Guvanasen, V.M.; Mehta, K.K.; McConnell, D.B.; Tamm, J.A.; Lyon, R.B.

1985-12-01

The nuclear fuel waste disposal concept chosen for development and assessment in Canada involves the burial of corrosion-resistant containers of waste in a vault located deep in plutonic rock in the Canadian Shield. As the concept and the assessment tools are developed, periodic assessments are performed to permit evaluatin of the methodology and provide feedback to those developing the concept. The ultimate goal of these assessments is to predict what impact the disposal system would have if the concept were implemented. The second assessment was performed in 1984 and is documented in Second Interim Assessment of the Canadian Concept for Nuclear Fuel Waste Disposal - Volumes 1 to 4. This volume, entitled Background, discusses Canadian nuclear fuel wastes and the desirable features of a waste disposal method. It outlines several disposal options being considered by a number of countries, including the option chosen for development and assessment in Canada. The reference disposal systems assumed for the second assessment are described, and the approach used for concept assessment is discussed briefly. 79 refs

Community Energy Systems and the Law of Public Utilities. Volume Eighteen. Kansas

Energy Technology Data Exchange (ETDEWEB)

Feurer, D A; Weaver, C L

1981-01-01

A detailed description is given of the laws and programs of the State of Kansas governing the regulation of public energy utilities, the siting of energy generating and transmission facilities, the municipal franchising of public energy utilities, and the prescription of rates to be charged by utilities including attendant problems of cost allocations, rate base and operating expense determinations, and rate of return allowances. These laws and programs are analyzed to identify impediments which they may present to the implementation of Integrated Community Energy Systems (ICES). This report is one of fifty-one separate volumes which describe such regulatory programs at the Federal level and in each state as background to the report entitled Community Energy Systems and the Law of Public Utilities - Volume One: An Overview. This report also contains a summary of a strategy described in Volume One - An Overview for overcoming these impediments by working within the existing regulatory framework and by making changes in the regulatory programs to enhance the likelihood of ICES implementation.

Community Energy Systems and the Law of Public Utilities. Volume Eleven. Florida

Energy Technology Data Exchange (ETDEWEB)

Feurer, D A; Weaver, C L

1981-01-01

A detailed description is given of the laws and programs of the State of Florida governing the regulation of public energy utilities, the siting of energy generating and transmission facilities, the municipal franchising of public energy utilities, and the prescription of rates to be charged by utilities including attendant problems of cost allocations, rate base and operating expense determinations, and rate of return allowances. These laws and programs are analyzed to identify impediments which they may present to the implementation of Integrated Community Energy Systems (ICES). This report is one of fifty-one separate volumes which describe such regulatory programs at the Federal level and in each state as background to the report entitled Community Energy Systems and the Law of Public Utilities - Volume One: An Overview. This report also contains a summary of a strategy described in Volume One - An Overview for overcoming these impediments by working within the existing regulatory framework and by making changes in the regulatory programs to enhance the likelihood of ICES implementation.

Community Energy Systems and the Law of Public Utilities. Volume Eight. Colorado

Energy Technology Data Exchange (ETDEWEB)

Feurer, D A; Weaver, C L

1981-01-01

A detailed description is given of the laws and programs of the State of Colorado governing the regulation of public energy utilities, the siting of energy generating and transmission facilities, the municipal franchising of public energy utilities, and the prescription of rates to be charged by utilities including attendant problems of cost allocations, rate base and operating expense determinations, and rate of return allowances. These laws and programs are analyzed to identify impediments which they may present to the implementation of Integrated Community Energy Systems (ICES). This report is one of fifty-one separate volumes which describe such regulatory programs at the Federal level and in each state as background to the report entitled Community Energy Systems and the Law of Public Utilities - Volume One: An Overview. This report also contains a summary of a strategy described in Volume One - An Overview for overcoming these impediments by working within the existing regulatory framework and by making changes in the regulatory programs to enhance the likelihood of ICES implementation.

Community Energy Systems and the Law of Public Utilities. Volume Seventeen. Iowa

Energy Technology Data Exchange (ETDEWEB)

Feurer, D A; Weaver, C L

1981-01-01

A detailed description is given of the laws and programs of the State of Iowa governing the regulation of public energy utilities, the siting of energy generating and transmission facilities, the municipal franchising of public energy utilities, and the prescription of rates to be charged by utilities including attendant problems of cost allocations, rate base and operating expense determinations, and rate of return allowances. These laws and programs are analyzed to identify impediments which they may present to the implementation of Integrated Community Energy Systems (ICES). This report is one of fifty-one separate volumes which describe such regulatory programs at the Federal level and in each state as background to the report entitled Community Energy Systems and the Law of Public Utilities - Volume One: An Overview. This report also contains a summary of a strategy described in Volume One - An Overview for overcoming these impediments by working within the existing regulatory framework and by making changes in the regulatory programs to enhance the likelihood of ICES implementation.

Community Energy Systems and the Law of Public Utilities. Volume Nineteen. Kentucky

Energy Technology Data Exchange (ETDEWEB)

Feurer, D A; Weaver, C L

1981-01-01

A detailed description is given of the laws and programs of the State of Kentucky governing the regulation of public energy utilities, the siting of energy generating and transmission facilities, the municipal franchising of public energy utilities, and the prescription of rates to be charged by utilities including attendant problems of cost allocations, rate base and operating expense determinations, and rate of return allowances. These laws and programs are analyzed to identify impediments which they may present to the implementation of Integrated Community Energy Systems (ICES). This report is one of fifty-one separate volumes which describe such regulatory programs at the Federal level and in each state as background to the report entitled Community Energy Systems and the Law of Public Utilities - Volume One: An Overview. This report also contains a summary of a strategy described in Volume One - An Overview for overcoming these impediments by working within the existing regulatory framework and by making changes in the regulatory programs to enhance the likelihood of ICES implementation.

Community Energy Systems and the Law of Public Utilities. Volume Six. Arkansas

Energy Technology Data Exchange (ETDEWEB)

Feurer, D A; Weaver, C L

1981-01-01

A detailed description is given of the laws and programs of the State of Arkansas governing the regulation of public energy utilities, the siting of energy generating and transmission facilities, the municipal franchising of public energy utilities, and the prescription of rates to be charged by utilities including attendant problems of cost allocations, rate base and operating expense determinations, and rate of return allowances. These laws and programs are analyzed to identify impediments which they may present to the implementation of Integrated Community Energy Systems (ICES). This report is one of fifty-one separate volumes which describe such regulatory programs at the Federal level and in each state as background to the report entitled Community Energy Systems and the Law of Public Utilities - Volume One: An Overview. This report also contains a summary of a strategy described in Volume One - An Overview for overcoming these impediments by working within the existing regulatory framework and by making changes in the regulatory programs to enhance the likelihood of ICES implementation.

Community Energy Systems and the Law of Public Utilities. Volume Five. Arizona

Energy Technology Data Exchange (ETDEWEB)

Feurer, D A; Weaver, C L

1981-01-01

A detailed description is given of the laws and programs of the State of Arizona governing the regulation of public energy utilities, the siting of energy generating and transmission facilities, the municipal franchising of public energy utilities, and the prescription of rates to be charged by utilities including attendant problems of cost allocations, rate base and operating expense determinations, and rate of return allowances. These laws and programs are analyzed to identify impediments which they may present to the implementation of Integrated Community Energy Systems (ICES). This report is one of fifty-one separate volumes which describe such regulatory programs at the Federal level and in each state as background to the report entitled Community Energy Systems and the Law of Public Utilities - Volume One: An Overview. This report also contains a summary of a strategy described in Volume One - An Overview for overcoming these impediments by working within the existing regulatory framework and by making changes in the regulatory programs to enhance the likelihood of ICES implementation.

Community Energy Systems and the Law of Public Utilities. Volume Three. Alabama

Energy Technology Data Exchange (ETDEWEB)

Feurer, D A; Weaver, C L

1981-01-01

A detailed description is given of the laws and programs of the State of Alabama governing the regulation of public energy utilities, the siting of energy generating and transmission facilities, the municipal franchising of public energy utilities, and the prescription of rates to be charged by utilities including attendant problems of cost allocations, rate base and operating expense determinations, and rate of return allowances. These laws and programs are analyzed to identify impediments which they may present to the implementation of Integrated Community Energy Systems (ICES). This report is one of fifty-one separate volumes which describe such regulatory programs at the Federal level and in each state as background to the report entitled Community Energy Systems and the Law of Public Utilities - Volume One: An Overview. This report also contains a summary of a strategy described in Volume One - An Overview for overcoming these impediments by working within the existing regulatory framework and by making changes in the regulatory programs to enhance the likelihood of ICES implementation.

Community Energy Systems and the Law of Public Utilities. Volume Sixteen. Indiana

Energy Technology Data Exchange (ETDEWEB)

Feurer, D A; Weaver, C L

1981-01-01

A detailed description is given of the laws and programs of the State of Indiana governing the regulation of public energy utilities, the siting of energy generating and transmission facilities, the municipal franchising of public energy utilities, and the prescription of rates to be charged by utilities including attendant problems of cost allocations, rate base and operating expense determinations, and rate of return allowances. These laws and programs are analyzed to identify impediments which they may present to the implementation of Integrated Community Energy Systems (ICES). This report is one of fifty-one separate volumes which describe such regulatory programs at the Federal level and in each state as background to the report entitled Community Energy Systems and the Law of Public Utilities - Volume One: An Overview. This report also contains a summary of a strategy described in Volume One - An Overview for overcoming these impediments by working within the existing regulatory framework and by making changes in the regulatory programs to enhance the likelihood of ICES implementation.

Community Energy Systems and the Law of Public Utilities. Volume Thirty. Nevada

Energy Technology Data Exchange (ETDEWEB)

Feurer, D.A.; Weaver, C.L.

1981-01-01

A detailed description is given of the laws and programs of the State of Nevada governing the regulation of public energy utilities, the siting of energy generating and transmission facilities, the municipal franchising of public energy utilities, and the prescription of rates to be charged by utilities including attendant problems of cost allocations, rate base and operating expense determinations, and rate of return allowances. These laws and programs are analyzed to identify impediments which they may present to the implementation of Integrated Community Energy Systems (ICES). This report is one of fifty-one separate volumes which describe such regulatory programs at the Federal level and in each state as background to the report entitled Community Energy Systems and the Law of Public Utilities - Volume One: An Overview. This report also contains a summary of a strategy described in Volume One - An Overview for overcoming these impediments by working within the existing regulatory framework and by making changes in the regulatory programs to enhance the likelihood of ICES implementation.

Community Energy Systems and the Law of Public Utilities. Volume Thirteen. Hawaii

Energy Technology Data Exchange (ETDEWEB)

Feurer, D A; Weaver, C L

1981-01-01

A detailed description is given of the laws and programs of the State of Hawaii governing the regulation of public energy utilities, the siting of energy generating and transmission facilities, the municipal franchising of public energy utilities, and the prescription of rates to be charged by utilities including attendant problems of cost allocations, rate base and operating expense determinations, and rate of return allowances. These laws and programs are analyzed to identify impediments which they may present to the implementation of Integrated Community Energy Systems (ICES). This report is one of fifty-one separate volumes which describe such regulatory programs at the Federal level and in each state as background to the report entitled Community Energy Systems and the Law of Public Utilities - Volume One: An Overview. This report also contains a summary of a strategy described in Volume One - An Overview for overcoming these impediments by working within the existing regulatory framework and by making changes in the regulatory programs to enhance the likelihood of ICES implementation.

Community Energy Systems and the Law of Public Utilities. Volume Seven. California

Energy Technology Data Exchange (ETDEWEB)

Feurer, D A; Weaver, C L

1981-01-01

A detailed description is given of the laws and programs of the State of California governing the regulation of public energy utilities, the siting of energy generating and transmission facilities, the municipal franchising of public energy utilities, and the prescription of rates to be charged by utilities including attendant problems of cost allocations, rate base and operating expense determinations, and rate of return allowances. These laws and programs are analyzed to identify impediments which they may present to the implementation of Integrated Community Energy Systems (ICES). This report is one of fifty-one separate volumes which describe such regulatory programs at the Federal level and in each state as background to the report entitled Community Energy Systems and the Law of Public Utilities - Volume One: An Overview. This report also contains a summary of a strategy described in Volume One - An Overview for overcoming these impediments by working within the existing regulatory framework and by making changes in the regulatory programs to enhance the likelihood of ICES implementation.

Community Energy Systems and the Law of Public Utilities. Volume Ten. Delaware

Energy Technology Data Exchange (ETDEWEB)

Feurer, D A; Weaver, C L

1981-01-01

A detailed description is given of the laws and programs of the State of Delaware governing the regulation of public energy utilities, the siting of energy generating and transmission facilities, the municipal franchising of public energy utilities, and the prescription of rates to be charged by utilities including attendant problems of cost allocations, rate base and operating expense determinations, and rate of return allowances. These laws and programs are analyzed to identify impediments which they may present to the implementation of Integrated Community Energy Systems (ICES). This report is one of fifty-one separate volumes which describe such regulatory programs at the Federal level and in each state as background to the report entitled Community Energy Systems and the Law of Public Utilities - Volume One: An Overview. This report also contains a summary of a strategy described in Volume One - An Overview for overcoming these impediments by working within the existing regulatory framework and by making changes in the regulatory programs to enhance the likelihood of ICES implementation.

Community Energy Systems and the Law of Public Utilities. Volume Fifteen. Illinois

Energy Technology Data Exchange (ETDEWEB)

Feurer, D A; Weaver, C L

1981-01-01

A detailed description is given of the laws and programs of the State of Illinois governing the regulation of public energy utilities, the siting of energy generating and transmission facilities, the municipal franchising of public energy utilities, and the prescription of rates to be charged by utilities including attendant problems of cost allocations, rate base and operating expense determinations, and rate of return allowances. These laws and programs are analyzed to identify impediments which they may present to the implementation of Integrated Community Energy Systems (ICES). This report is one of fifty-one separate volumes which describe such regulatory programs at the Federal level and in each state as background to the report entitled Community Energy Systems and the Law of Public Utilities - Volume One: An Overview. This report also contains a summary of a strategy described in Volume One - An Overview for overcoming these impediments by working within the existing regulatory framework and by making changes in the regulatory programs to enhance the likelihood of ICES implementation.

Volume reduction techniques for solid radioactive wastes

International Nuclear Information System (INIS)

Clarke, J.H.

1980-01-01

This report gives an account of some of the techniques in current use in the UK for the treatment of solid radioactive wastes to reduce their volume prior to storage or disposal. Reference is also made to current research and development projects. It is based on a report presented at a recent International Atomic Energy Agency Technical Committee when this subject was the main theme. An IAEA Technical Series report covering techniques in use in all parts of the world should be published within the next two years. (author)

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

International Nuclear Information System (INIS)

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

1995-09-01

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

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

International Nuclear Information System (INIS)

Adams, J.P.

1995-08-01

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

Defense waste solidification studies. Volume 2. Drawing supplement. Savannah River Plant, Project S-1780

International Nuclear Information System (INIS)

1977-01-01

Volume 2 contains the drawings prepared and used in scoping and estimating the Glass-Form Waste Solidification facilities and the alternative studies cited in the report, the Off-Site Shipping Case, the Decontaminated Salt Storage Case, and a revised Reference Plant (Concrete-Form Waste) Case

Inventory and management of radioactive waste in Thailand

International Nuclear Information System (INIS)

Vonglertmongkol, S.

1994-01-01

The objectives of the study are to conceive the data based on the utilization of radiation and radioisotopes in Thailand and the inventory of radioactive waste arising from such utilization. The suggestions of the future radioactive waste management are also given as well. Data collection was done by mean of questionnaire and interviewing 245 radioisotope users in Thailand. The outcome can be summarized as follows:. Increase in the quantity of radioisotope in all sectors of the utilization was found, especially on the applications in nuclear medicine and industry. The amount of radioactive waste is increasing accordingly. The waste from unsealed radioisotopes increase 10.68 percent per year for liquid wastes and about 6.39 percent per year for solid waste. Most of these wastes are subjected to transfer for treatment by the Office of Atomic Energy for Peace (OAEP). The wastes from sealed radiation sources were packed in shielded containers. Most of these wastes would be shipped to the country of supply, but, some will be handled by OAEP. The accumulated wastes volume after treatment and conditioning, in the next 30 year will be around 220 cubic meter, excluding the wastes from the operation of nuclear research reactor, nuclear power plant, decommissioning, used sealed sources and the wastes from mining and milling of radioactive ores

System of the advanced volume reduction facilities for LLW at JAERI

International Nuclear Information System (INIS)

Higuchi, Hidekazu; Monma, Toshiyuki; Nakashio, Nobuyuki; Kozawa, Kazushige; Touhei, Toshio; Sudou, Tomoyuki; Mitsuda, Motoyuki; Kurosawa, Shigenobu; Henmi, Kou; Ishikawa, Joji; Kato, Mitsugu; Sato, Motoaki

2005-01-01

The Japan Atomic Energy Research Institute (JAERI) constructed the Advanced Volume Reduction Facilities (AVRF), in which volume reduction techniques are applied and achieved high volume reduction ratio, homogenization and stabilization by means of melting or super compaction processes for low level solid wastes. It will be able to produce waste packages for final disposal and to reduce the amount of the wastes by operating the AVRF. The AVRF consist of the Waste Size Reduction and Storage Facilities (WSRSF) and the Waste Volume Reduction Facilities (WVRF); the former have cutting installations for large size wastes and the latter have melting units and a super compactor. Cutting installations in the WSRSF have been operating since June 1999. Radioactive wastes treated so far amount to 600 m 3 and the volume reduction ratio is from 1/2 to 1/3. The WVRF have been operating with non-radioactive wastes since February 2003 for the training and the homogeneity investigation in the melting processes. The operation with radioactive wastes will start in FY2005. (author)

How utilities respond to radwaste needs

International Nuclear Information System (INIS)

Strauss, S.D.

1987-01-01

Slow progress is being made toward regionalization of waste disposal, some states working toward regional compacts while others choose to go it alone. More promising is the reduction of radwaste volumes discharged from nuclear stations. More and more utilities are contracting with private companies for LLW processing. While such services are provided predominantly by mobile units at plant sites, one fixed installation already offers processing of dry waste and two others await final regulatory approval. Both developments are detailed. This article also includes an analysis of the design, performances comparison between slagging combustors (SC) and the FBC boiler. Comparisons are also made for SC technology to FBC for 250-MW unit and of utility-unit conversion costs

Selective enrichment of a methanol-utilizing consortium using pulp & paper mill waste streams

Energy Technology Data Exchange (ETDEWEB)

Gregory R. Mockos; William A. Smith; Frank J. Loge; David N. Thompson

2007-04-01

Efficient utilization of carbon inputs is critical to the economic viability of the current forest products sector. Input carbon losses occur in various locations within a pulp mill, including losses as volatile organics and wastewater . Opportunities exist to capture this carbon in the form of value-added products such as biodegradable polymers. Waste activated sludge from a pulp mill wastewater facility was enriched for 80 days for a methanol-utilizing consortium with the goal of using this consortium to produce biopolymers from methanol-rich pulp mill waste streams. Five enrichment conditions were utilized: three high-methanol streams from the kraft mill foul condensate system, one methanol-amended stream from the mill wastewater plant, and one methanol-only enrichment. Enrichment reactors were operated aerobically in sequencing batch mode at neutral pH and 25°C with a hydraulic residence time and a solids retention time of four days. Non-enriched waste activated sludge did not consume methanol or reduce chemical oxygen demand. With enrichment, however, the chemical oxygen demand reduction over 24 hour feed/decant cycles ranged from 79 to 89 %, and methanol concentrations dropped below method detection limits. Neither the non-enriched waste activated sludge nor any of the enrichment cultures accumulated polyhydroxyalkanoates (PHAs) under conditions of nitrogen sufficiency. Similarly, the non-enriched waste activated sludge did not accumulate PHAs under nitrogen limited conditions. By contrast, enriched cultures accumulated PHAs to nearly 14% on a dry weight basis under nitrogen limited conditions. This indicates that selectively-enriched pulp mill waste activated sludge can serve as an inoculum for PHA production from methanol-rich pulp mill effluents.

Feasibility Assessment of Using Power Plant Waste Heat in Large Scale Horticulture Facility Energy Supply Systems

Directory of Open Access Journals (Sweden)

Min Gyung Yu

2016-02-01

Full Text Available Recently, the Korean government has been carrying out projects to construct several large scale horticulture facilities. However, it is difficult for an energy supply to operate stably and economically with only a conventional fossil fuel boiler system. For this reason, several unused energy sources have become attractive and it was found that power plant waste heat has the greatest potential for application in this scenario. In this study, we performed a feasibility assessment of power plant waste heat as an energy source for horticulture facilities. As a result, it was confirmed that there was a sufficient amount of energy potential for the use of waste heat to supply energy to the assumed area. In Dangjin, an horticultural area of 500 ha could be constructed by utilizing 20% of the energy reserves. In Hadong, a horticulture facility can be set up to be 260 ha with 7.4% of the energy reserves. In Youngdong, an assumed area of 65 ha could be built utilizing about 19% of the energy reserves. Furthermore, the payback period was calculated in order to evaluate the economic feasibility compared with a conventional system. The initial investment costs can be recovered by the approximately 83% reduction in the annual operating costs.

Radioactive solid waste management at Trombay

International Nuclear Information System (INIS)

Jayaraman, A.P.; Balu, K.

1977-01-01

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

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

Energy Technology Data Exchange (ETDEWEB)

Adams, J.P.

1995-08-01

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

Reduction volume of radioactive wastes using natural zeolite

International Nuclear Information System (INIS)

Endro Kismolo; Nurimaniwathy; Vemi Ridantami

2013-01-01

The aim of this experience was to know of the characteristics of zeolite as the sorbent for reduction volume of liquid waste with the Pb contaminant contain. The experiment was done by sorption method a batch performed by using zeolite from Gedangsari Gunung Kidul with the grain size (-60+80) mesh, (-80+100) mesh dan (-100+120) mesh which was activated by (NH 4 ) CI and NH 4 N0 3 1.0 M. Weight of sorbent was added was variated from 5.0 to 40.0 %, and variation of silica sand to added from 0.5 to 2.5 % of weight sorbent. Stirring speed was varied from 30 to 180 rpm and the stirring time of 10 to 120 minutes, and filtrates from filtering process to analyzed by Absorption Analysis Spectrophotometry utilities. From the experience can be achieved of data that the best sorption to obtained at the condition of zeolite on (-80+100) mesh, sorbent added of 25 %, stirring speed of 120 rpm, time of stirring of 90 minutes, and the setting time of 120 minutes. At this condition to obtained sorption efficiency are 64.162 % for natural zeolite, 7.034 % for zeolite be activated with NH 4 N0 3 and 77.414 % for zeolite be activated with NH 4 Cl 1.0 M. (author)

Technical procedures for utilities and solid waste: Environmental Field Program, Deaf Smith County site, Texas: Final draft

International Nuclear Information System (INIS)

1987-08-01

The evaluation of environmental issues and concerns and the addressing of statutory requirements are fundamental parts in the characterization of the site in Deaf Smith County, Texas for the US Department of Energy's Salt Repository Project (SRP). To ensure that the environmental field program comprehensively addresses the issues and requirements of the project, a site study plan (SSP) has been prepared for Utilities and Solid Waste considerations. This technical procedure (TP) has been developed to implement the field program described in the Utilities and Solid Waste Site Study Plan. The purpose and scope of the Utilities and Solid Waste Technical Procedure is to develop and implement a data collection procedure to fulfill the data base needs of the Utilities and Solid Waste SSP. The procedure describes a method of obtaining, assessing and verifying the capabilities of the regional service utilities and disposal contractors. This data base can be used to identify a preferred service source for the engineering contractor. The technical procedure was produced under the guidelines established in Technical Administrative Procedure No. 1.0, Preparation, Review and Approval of Technical Procedures

Performance and availability of seawater distiller with heat pipe utilizing low grade waste heat

Energy Technology Data Exchange (ETDEWEB)

Park, Chang Dae; Chung, Kyung Yul [Korea Institute of Machinery and Materials, Daejeon (Korea, Republic of); Tanaka, Hiroshi [Department of Mechanical Engineering, Ulsan (Korea, Republic of)

2013-01-15

Exhaust gas from a small portable electric generator is simply exhausted to the surroundings because the capacity and quality of the waste heat of this gas is generally not sufficient to recover and utilize. We have proposed a seawater distiller utilizing the thermal energy of waste gas from an electric generator. The distiller recovers heat from the waste gas by means of a heat pipe and uses it effectively through a multiple effect diffusion type structure. We constructed an experimental apparatus with a vertical single effect still having a 4 stroke 50cc generator engine and found that the experimental results for distillate productivity show good agreement with the theoretical predictions. The results show that the distiller can recover 52W of waste heat from the gas at 171.deg.C, and {approx}85%, of the recovered heat can be utilized for distillation to produce 70g/h of fresh water. This is equivalent to a productivity of 500g/h in the case of a 10 effect still. Therefore, the proposed distiller should be useful in remote areas where electricity and water grids are inadequate.

The relationship among CPU utilization, temperature, and thermal power for waste heat utilization

International Nuclear Information System (INIS)

Haywood, Anna M.; Sherbeck, Jon; Phelan, Patrick; Varsamopoulos, Georgios; Gupta, Sandeep K.S.

2015-01-01

Highlights: • This work graphs a triad relationship among CPU utilization, temperature and power. • Using a custom-built cold plate, we were able capture CPU-generated high quality heat. • The work undertakes a radical approach using mineral oil to directly cool CPUs. • We found that it is possible to use CPU waste energy to power an absorption chiller. - Abstract: This work addresses significant datacenter issues of growth in numbers of computer servers and subsequent electricity expenditure by proposing, analyzing and testing a unique idea of recycling the highest quality waste heat generated by datacenter servers. The aim was to provide a renewable and sustainable energy source for use in cooling the datacenter. The work incorporates novel approaches in waste heat usage, graphing CPU temperature, power and utilization simultaneously, and a mineral oil experimental design and implementation. The work presented investigates and illustrates the quantity and quality of heat that can be captured from a variably tasked liquid-cooled microprocessor on a datacenter server blade. It undertakes a radical approach using mineral oil. The trials examine the feasibility of using the thermal energy from a CPU to drive a cooling process. Results indicate that 123 servers encapsulated in mineral oil can power a 10-ton chiller with a design point of 50.2 kW th . Compared with water-cooling experiments, the mineral oil experiment mitigated the temperature drop between the heat source and discharge line by up to 81%. In addition, due to this reduction in temperature drop, the heat quality in the oil discharge line was up to 12.3 °C higher on average than for water-cooled experiments. Furthermore, mineral oil cooling holds the potential to eliminate the 50% cooling expenditure which initially motivated this project

Tank Waste Remediation System, Hanford Site, Richland, Washington. Final Environmental Impact Statement. Volume IV

International Nuclear Information System (INIS)

1996-08-01

This document, Volume 4, describes the current safety concerns associated with the tank waste and analyzes the potential accidents and associated potential health effects that could occur under the alternatives included in this Tank Waste Remediation System (TWRS) Final Environmental Impact Statement (EIS) for the Hanford Site, Richland, Washington

Technical support for GEIS: radioactive waste isolation in geologic formations. Volume 22. Nuclear considerations for repository design

International Nuclear Information System (INIS)

1978-04-01

This volume, Y/OWI/TM-36/22, ''Nuclear Considerations for Repository Design,'' is one of a 23-volume series, ''Technical Support for GEIS: Radioactive Waste Isolation in Geologic Formations,'' Y/OWI/TM-36, which supplements the ''Contribution to Draft Generic Environmental Impact Statement on Commercial Waste Management: Radioactive Waste Isolation in Geologic Formations,'' Y/OWI/TM-44. The series provides a more complete technical basis for the preconceptual designs, resource requirements, and environmental source terms associated with isolating commercial LWR wastes in underground repositories in salt, granite, shale and basalt. Wastes are considered from three fuel cycles: uranium and plutonium recycling, no recycling of spent fuel and uranium-only recycling. Included in this volume are baseline design considerations such as characteristics of canisters, drums, casks, overpacks, and shipping containers; maximum allowable and actual decay-heat levels; and canister radiation levels. Other topics include safeguard and protection considerations; occupational radiation exposure including ALARA programs; shielding of canisters, transporters and forklift trucks; monitoring considerations; mine water treatment; canister integrity; and criticality calculations

High-Energy X-Ray Imaging Applied to Nondestructive Characterization of Large Nuclear Waste Drums

Science.gov (United States)

Estre, Nicolas; Eck, Daniel; Pettier, Jean-Luc; Payan, Emmanuel; Roure, Christophe; Simon, Eric

2015-12-01

As part of its R&D programs on non-destructive testing of nuclear waste drums, CEA is commissioning an irradiation cell named CINPHONIE, at Cadarache. This cell allows high-energy imaging (radiography and tomography) on large volumes (up to 5 m3) and heavy weights (up to 5 tons). A demonstrator has been finalized, based on existing components. The X-ray source is a 9 MeV LINAC which produces Bremsstrahlung X-rays (up to 23 Gy/min at 1 meter in the beam axis). The mechanical bench is digitally controlled on three axes (translation, rotation, elevation) and can handle objects up to 2 t. This bench performs trajectories necessary for acquisition of projections (sinograms) according to different geometries: Translation-Rotation, Fan-Beam and Cone-Beam. Two detection systems both developed by CEA-Leti are available. The first one is a large GADOX scintillating screen ( 800 ×600 mm2) coupled to a low-noise pixelated camera. The second one is a multi-CdTe semiconductor detector, offering measurements up to 5 decades of attenuation (equivalent to 25 cm of lead or 180 cm of standard concrete). At the end of the acquisition, a Filtered Back Projection-based algorithm is performed. Then, a density slice (fan-beam tomography) or a density volume (cone-beam tomography or helical tomography) is produced and used to examine the waste. Characterization of LINAC, associated detectors as well as the full acquisition chain, are presented. Experimental performances on phantoms and real drum are discussed and expected limits on defect detectability are evaluated by simulation. The final system, designed to handle objects up to 5 tons is then presented.

Utility unbundling : large consumer's perspective

International Nuclear Information System (INIS)

Block, C.

1997-01-01

The perspectives of Sunoco as a large user of electric power on utility unbundling were presented. Sunoco's Sarnia refinery runs up an energy bill of over $60 million per year for electricity, natural gas (used both as a feedstock as well as a fuel), natural gas liquids and steam. As a large customer Sunoco advocates unbundling of all services, leaving only the 'pipes and wires' as true monopolies. In their view, regulation distorts the market place and prevents the lower prices that would result from competition as has been seen in the airline and telephone industries. Sunoco's expectation is that in the post-deregulated environment large and small consumers will have a choice of energy supplier, and large consumers will increasingly turn to co-generation as the most desirable way of meeting their power needs

Community energy systems and the law of public utilities. Volume 20. Louisiana

Energy Technology Data Exchange (ETDEWEB)

Feurer, D A; Weaver, C L

1981-01-01

A detailed description is given of the laws and programs of the State of Louisiana governing the regulation of public energy utilities, the siting of energy generating and transmission facilities, the municipal franchising of public energy utilities including attendant problems of cost allocations, rate base and operating expense determinations, and rate of return allowances. These laws and programs are analyzed to identify impediments which they may present to the implementation of Integrated Community Energy Systems (ICES). This report is one of fifty-one separate volumes which describe such regulatory programs at the Federal level and in each state as background to the report entitled Community Energy Systems and the Law of Public Utilities--Volume One: An overview. This report also contains a summary of a strategy described in Volume One--An Overview for overcoming these impediments by working within the existing regulatory framework and by making changes in the regulatory programs to enchance the likelihood of ICES implementation.

Radioactive waste package assay facility. Volume 1. Application of assay technology

International Nuclear Information System (INIS)

Findlay, D.J.S.; Green, T.H.; Molesworth, T.V.; Staniforth, D.; Strachan, N.R.; Rogers, J.D.; Wise, M.O.; Forrest, K.R.

1992-01-01

This report, in three volumes, covers the work carried out by Taylor Woodrow Construction Ltd., and two major sub-contractors: Harwell Laboratory (AEA Technology) and Siemens Plessey Controls Ltd., on the development of a radioactive waste package assay facility, for cemented 500 litre intermediate level waste drums. In volume 1, the reasons for assay are considered together with the various techniques that can be used, and the information that can be obtained. The practical problems associated with the use of the various techniques in an integrated assay facility are identified, and the key parameters defined. Engineering and operational features are examined and provisional designs proposed for facilities at three throughput levels: 15,000, 750 and 30 drums per year respectively. The capital and operating costs for such facilities have been estimated. A number of recommendations are made for further work. 16 refs., 14 figs., 13 tabs

Alternatives for managing wastes from reactors and post-fission operations in the LWR fuel cycle. Volume 4. Alternatives for waste isolation and disposal

International Nuclear Information System (INIS)

1976-05-01

Volume IV of the five-volume report contains information on alternatives for final storage and disposal of radioactive wastes. Section titles include: basic concepts for geologic isolation; geologic storage alternatives; geologic disposal alternatives; extraterrestrial disposal; and, transmutation

Amount of radioactive wastes in the Federal Republic of Germany - waste inquiry for the year 1985

International Nuclear Information System (INIS)

Brennecke, P.; Schumacher, J.

1986-09-01

On December 31, 1985, about 61 400 waste packages were stored in intermediate storage facilities. The unconditioned radioactive wastes amounted to about 6 300 m 3 . The volume of the conditioned radioactive wastes amounted to about 29 600 m 3 . Thereof the waste from nuclear research establishments made up about 11 200 m 3 , the waste from the operation of nuclear power plants about 9 900 m 3 and the waste from reprocessing of spent fuel elements about 5 800 m 3 . In addition the future amount of conditioned radioactive wastes with negligible heat generation was prognosticated. Due to this forecast an amount of about 227 600 m 3 of these wastes is expected in the year 2000. In 1985 a capacity of about 88 700 m 3 for the intermediate storage of radioactive wastes was available in the Federal Republic of Germany. On December 31, 1985, this capacity was utilized by unconditioned and conditioned radioactive wastes at an average of about 40%. It may be concluded from the data on the expected amount of radioactive wastes with negligible heat generation and on the utilization factor of the intermediate storage facilities that no bottlenecks are to be assumed up to the planned operation of the Konrad repository. (orig./HP) [de

Incineration method for volume reduction and disposal of transuranic waste

International Nuclear Information System (INIS)

Borham, B.M.

1985-01-01

The Process Experimental Pilot Plant (PREPP) at Idaho National Engineering Laboratory (INEL) is designed to process 7 TPD of transuranic (TRU) waste producing 8.5 TPD of cemented waste and 4100 ACFM of combustion gases with a volume reduction of up to 17:1. The waste and its container are shredded then fed to a rotary kiln heated to 1700 0 F, then cooled and classified by a trommel screen. The fine portion is mixed with a cement grout which is placed with the coarse portion in steel drums for disposal at the Waste Isolation Pilot Plant (WIPP). The kiln off-gas is reheated to 2000 0 F to destroy any remaining hydrocarbons and toxic volatiles. The gases are cooled and passed in a venturi scrubber to remove particulates and corrosive gases. The venturi off-gas is passed through a mist eliminator and is reheated to 50 0 F above the dew point prior to passing through a High Efficiency Particulate Air (HEPA) filter. The scrub solution is concentrated to 25% solids by an inertial filter. The sludge containing the combustion chemical contaminants is encapsulated with the residue of the incinerated waste

1982 State-by-state assessment of low-level radioactive wastes shipped to commercial disposal sites

International Nuclear Information System (INIS)

1983-12-01

This report uses the volume of low-level waste reported as received at each commercial disposal site as the national baseline figure. A volume of 75,891 cubic meters of radioactive waste containing 413,898 curies of activity was reported disposed at the commercial sites in 1982. The distribution of these waste volumes by disposal site is presented in Table 1. Table 2 summarizes estimated volumes by generator categories. The total volume and curie values tabulated for each state were obtained directly from the commercial disposal site operators. The total is the sum of the volume and radioactivity by disposal site for each state. Summary information on commercial nuclear power plant wastes was obtained from semiannual waste reports submitted to the NRC in accordance with the NRC Regulatory Guide 1.21. Data reported for the calendar year 1982 were used for this report where available. When report data were not available, reactor information was obtained directly from the utility

Waste Isolation Pilot Plant disposal phase final supplemental environmental impact statement. Volume 2: Appendices

International Nuclear Information System (INIS)

1997-09-01

The purpose of the Waste Isolation Pilot Plant Disposal Final Supplemental Environmental Impact Statement (SEIS-II) is to provide information on environmental impacts regarding the Department of Energy's (DOE) proposed disposal operations at WIPP. The Proposed Action describes the treatment and disposal of the Basic inventory of TRU waste over a 35-year period. The Action Alternatives proposed the treatment of the Basic Inventory and an Additional Inventory as well as the transportation of the treated waste to WIPP for disposal over a 150- to 190-year period. The three Action Alternatives include the treatment of TRU waste at consolidation sites to meet WIPP planning-basic Waste Acceptance Criteria, the thermal treatment of TRU waste to meet Land Disposal Restrictions, and the treatment of TRU waste by a shred and grout process. SEIS-II evaluates environmental impacts resulting from the various treatment options; the transportation of TRU waste to WIPP using truck, a combination of truck and regular rail service, and a combination of truck and dedicated rail service; and the disposal of this waste in the repository. Evaluated impacts include those to the general environment and to human health. Additional issues associated with the implementation of the alternatives are discussed to provide further understanding of the decisions to be reached and to provide the opportunity for public input on improving DOE's Environmental Management Program. This volume contains the following appendices: Waste inventory; Summary of the waste management programmatic environmental impact statement and its use in determining human health impacts at treatment sites; Air quality; Life-cycle costs and economic impacts; Transportation; Human health; Facility accidents; Long-term consequence analysis for proposed action and action alternatives; Long-term consequence analysis for no action alternative 2; and Updated estimates of the DOE's transuranic waste volumes

Technical and economic feasibility of a solar-bio-powered waste utilization and treatment system in Central America.

Science.gov (United States)

Aguilar Alvarez, Ronald Esteban; Bustamante Roman, Mauricio; Kirk, Dana; Miranda Chavarria, Jose Alberto; Baudrit, Daniel; Aguilar Pereira, Jose Francisco; Rodriguez Montero, Werner; Reinhold, Dawn; Liao, Wei

2016-12-15

The purpose of this study was to implement and evaluate a pilot-scale and closed-loop system that synergistically combines solar thermal collector, anaerobic digester, and constructed treatment wetland to simultaneously treat and utilize organic wastes. The system utilizes 863 kg of mixed animal and food wastes to generate 263 MJ renewable energy, produced 28 kg nitrogen and phosphorus fertilizer, and reclaimed 550 kg water per day. The net revenue considering electricity and fertilizer was $2436 annually. The payback period for the system is estimated to be 17.8 years for a relatively dilute waste stream (i.e., 2% total solids). The implemented system has successfully demonstrated a self-efficient and flexible waste utilization and treatment system. It creates a win-win solution to satisfy the energy needs of the community and address environmental concerns of organic wastes disposal in the region. Copyright © 2016 Elsevier Ltd. All rights reserved.

Disposal of Rocky Flats residues as waste

International Nuclear Information System (INIS)

Dustin, D.F.; Sendelweck, V.S.

1993-01-01

Work is underway at the Rocky Flats Plant to evaluate alternatives for the removal of a large inventory of plutonium-contaminated residues from the plant. One alternative under consideration is to package the residues as transuranic wastes for ultimate shipment to the Waste Isolation Pilot Plant. Current waste acceptance criteria and transportation regulations require that approximately 1000 cubic yards of residues be repackaged to produce over 20,000 cubic yards of WIPP certified waste. The major regulatory drivers leading to this increase in waste volume are the fissile gram equivalent, surface radiation dose rate, and thermal power limits. In the interest of waste minimization, analyses have been conducted to determine, for each residue type, the controlling criterion leading to the volume increase, the impact of relaxing that criterion on subsequent waste volume, and the means by which rules changes may be implemented. The results of this study have identified the most appropriate changes to be proposed in regulatory requirements in order to minimize the costs of disposing of Rocky Flats residues as transuranic wastes

Economic analysis of waste management alternatives for reprocessing wastes

International Nuclear Information System (INIS)

McKee, R.W.; Clark, L.L.; Daling, P.M.; Nesbitt, J.F.; Swanson, J.L.

1984-02-01

This study describes the results of a cost analysis of a broad range of alternatives for management of reprocessing wastes that would require geologic repository disposal. The intent was to identify cost-effective alternatives and the costs of potential repository performance requirements. Four integrated treatment facility alternatives for transuranic (TRU) wastes are described and compared. These include no treatment, compaction, incineration, and hulls melting. The advantages of reducing high-level wastes (HLW) volume are also evaluated as are waste transportation alternatives and several performance-related alternatives for emplacing waste in a basalt repository. Results show (1) that system costs for disposal of reprocessing waste are likely to be higher than those for disposal of spent fuel; (2) that volume reduction is cost-effective for both remote-handled (RH) TRU wastes and HLW, and that rail transport for HLW is more cost-effective than truck transport; (3) that coemplacement of RH-TRU wastes with HLW does not have a large cost advantage in a basalt repository; and (4) that, relative to performance requirements, the cost impact for elimination of combustibles is about 5%, long-lived containers for RH-TRU wastes can increase repository costs 10% to 20%, and immediate backfill compared to delayed backfill (bentonite/basalt) around the HLW canisters would increase repository costs up to 10% or overall system costs up to about 5%. 13 references, 4 figures, 12 tables

Alternatives for managing wastes from reactors and post-fission operations in the LWR fuel cycle. Volume 4. Alternatives for waste isolation and disposal

Energy Technology Data Exchange (ETDEWEB)

1976-05-01

Volume IV of the five-volume report contains information on alternatives for final storage and disposal of radioactive wastes. Section titles include: basic concepts for geologic isolation; geologic storage alternatives; geologic disposal alternatives; extraterrestrial disposal; and, transmutation. (JGB)

Reengineering of waste management at the Oak Ridge National Laboratory. Volume 2

Energy Technology Data Exchange (ETDEWEB)

Myrick, T.E.

1997-08-01

A reengineering evaluation of the waste management program at the Oak Ridge National Laboratory (ORNL) was conducted during the months of February through July 1997. The goal of the reengineering was to identify ways in which the waste management process could be streamlined and improved to reduce costs while maintaining full compliance and customer satisfaction. A Core Team conducted preliminary evaluations and determined that eight particular aspects of the ORNL waste management program warranted focused investigations during the reengineering. The eight areas included Pollution Prevention, Waste Characterization, Waste Certification/Verification, Hazardous/Mixed Waste Stream, Generator/WM Teaming, Reporting/Records, Disposal End Points, and On-Site Treatment/Storage. The Core Team commissioned and assembled Process Teams to conduct in-depth evaluations of each of these eight areas. The Core Team then evaluated the Process Team results and consolidated the 80 process-specific recommendations into 15 overall recommendations. Volume 2 consists of nine appendices which contain the Process Team reports and Benchmarking reports.

Reengineering of waste management at the Oak Ridge National Laboratory. Volume 2