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Sample records for disposal alternatives analysis

  1. Economic analysis of alternative LLW disposal methods

    International Nuclear Information System (INIS)

    Foutes, C.E.

    1987-01-01

    The Environmental Protection Agency (EPA) has evaluated the costs and benefits of alternative disposal technologies as part of its program to develop generally applicable environmental standards for the land disposal of low-level radioactive waste (LLW). Costs, population health effects and Critical Population Group (CPG) exposures resulting from alternative waste treatment and disposal methods were developed and input into the analysis. The cost-effectiveness analysis took into account a number of waste streams, hydrogeologic and climatic region settings, and waste treatment and disposal methods. Total costs of each level of a standard included costs for packaging, processing, transportation, and burial of waste. Benefits are defined in terms of reductions in the general population health risk (expected fatal cancers and genetic effects) evaluated over 10,000 years. A cost-effectiveness ratio, was calculated for each alternative standard. This paper describes the alternatives considered and preliminary results of the cost-effectiveness analysis

  2. Economic analysis of alternative LLW disposal methods

    International Nuclear Information System (INIS)

    Foutes, C.E.; Queenan, C.J. III

    1987-01-01

    The Environmental Protection Agency (EPA) has evaluated the costs and benefits of alternative disposal technologies as part of its program to develop generally applicable environmental standards for the land disposal of low-level radioactive waste (LLW). Costs, population health effects and Critical Population Group (CPG) exposures resulting from alternative waste treatment and disposal methods were evaluated both in absolute terms and also relative to a base case (current practice). Incremental costs of the standard included costs for packaging, processing, transportation, and burial of waste. Benefits are defined in terms of reductions in the general population health risk (expected fatal cancers and genetic effects) evaluated over 10,000 years. A cost-effectiveness ratio, defined as the incremental cost per avoided health effect, was calculated for each alternative standard. The cost-effectiveness analysis took into account a number of waste streams, hydrogeologic and climatic region settings, and waste treatment and disposal methods. This paper describes the alternatives considered and preliminary results of the cost-effectiveness analysis. 15 references, 7 figures, 3 tables

  3. Pathway analysis for alternate low-level waste disposal methods

    International Nuclear Information System (INIS)

    Rao, R.R.; Kozak, M.W.; McCord, J.T.; Olague, N.E.

    1992-01-01

    The purpose of this paper is to evaluate a complete set of environmental pathways for disposal options and conditions that the Nuclear Regulatory Commission (NRC) may analyze for a low-level radioactive waste (LLW) license application. The regulations pertaining In the past, shallow-land burial has been used for the disposal of low-level radioactive waste. However, with the advent of the State Compact system of LLW disposal, many alternative technologies may be used. The alternative LLW disposal facilities include below- ground vault, tumulus, above-ground vault, shaft, and mine disposal This paper will form the foundation of an update of the previously developed Sandia National Laboratories (SNL)/NRC LLW performance assessment methodology. Based on the pathway assessment for alternative disposal methods, a determination will be made about whether the current methodology can satisfactorily analyze the pathways and phenomena likely to be important for the full range of potential disposal options. We have attempted to be conservative in keeping pathways in the lists that may usually be of marginal importance. In this way we can build confidence that we have spanned the range of cases likely to be encountered at a real site. Results of the pathway assessment indicate that disposal methods can be categorized in groupings based on their depth of disposal. For the deep disposal options of shaft and mine disposal, the key pathways are identical. The shallow disposal options, such as tumulus, shallow-land, and below-ground vault disposal also may be grouped together from a pathway analysis perspective. Above-ground vault disposal cannot be grouped with any of the other disposal options. The pathway analysis shows a definite trend concerning depth of disposal. The above-ground option has the largest number of significant pathways. As the waste becomes more isolated, the number of significant pathways is reduced. Similar to shallow-land burial, it was found that for all

  4. Analysis of alternatives for immobilized low activity waste disposal

    Energy Technology Data Exchange (ETDEWEB)

    Burbank, D.A.

    1997-10-28

    This report presents a study of alternative disposal system architectures and implementation strategies to provide onsite near-surface disposal capacity to receive the immobilized low-activity waste produced by the private vendors. The analysis shows that a flexible unit strategy that provides a suite of design solutions tailored to the characteristics of the immobilized low-activity waste will provide a disposal system that best meets the program goals of reducing the environmental, health, and safety impacts; meeting the schedule milestones; and minimizing the life-cycle cost of the program.

  5. Analysis of alternatives for immobilized low-activity waste disposal

    International Nuclear Information System (INIS)

    Burbank, D.A.

    1997-01-01

    This report presents a study of alternative disposal system architectures and implementation strategies to provide onsite near-surface disposal capacity to receive the immobilized low-activity waste produced by the private vendors. The analysis shows that a flexible unit strategy that provides a suite of design solutions tailored to the characteristics of the immobilized low-activity waste will provide a disposal system that best meets the program goals of reducing the environmental, health, and safety impacts; meeting the schedule milestones; and minimizing the life-cycle cost of the program

  6. Benefit-cost-risk analysis of alternatives for greater-confinement disposal of radioactive waste

    International Nuclear Information System (INIS)

    Gilbert, T.L.; Luner, C.; Peterson, J.M.

    1983-01-01

    Seven alternatives are included in the analysis: near-surface disposal; improved waste form; below-ground engineered structure; augered shaft; shale fracturing; shallow geologic repository; and high-level waste repository. These alternatives are representative generic facilities that span the range from low-level waste disposal practice to high-level waste disposal practice, tentatively ordered according to an expected increasing cost and/or effectiveness of confinement. They have been chosen to enable an assessment of the degree of confinement that represents an appropriate balance between public health and safety requirements and costs rather than identification of a specific preferred facility design. The objective of the analysis is to provide a comparative ranking of the alternatives on the basis of benefit-cost-risk considerations

  7. Remote-Handled Low-Level Waste Disposal Project Alternatives Analysis

    Energy Technology Data Exchange (ETDEWEB)

    David Duncan

    2011-04-01

    This report identifies, evaluates, and compares alternatives for meeting the U.S. Department of Energy’s mission need for management of remote-handled low-level waste generated by the Idaho National Laboratory and its tenants. Each alternative identified in the Mission Need Statement for the Remote-Handled Low-Level Waste Treatment Project is described and evaluated for capability to fulfill the mission need. Alternatives that could meet the mission need are further evaluated and compared using criteria of cost, risk, complexity, stakeholder values, and regulatory compliance. The alternative for disposal of remote-handled low-level waste that has the highest confidence of meeting the mission need and represents best value to the government is to build a new disposal facility at the Idaho National Laboratory Site.

  8. Remote-Handled Low Level Waste Disposal Project Alternatives Analysis

    Energy Technology Data Exchange (ETDEWEB)

    David Duncan

    2010-10-01

    This report identifies, evaluates, and compares alternatives for meeting the U.S. Department of Energy’s mission need for management of remote-handled low-level waste generated by the Idaho National Laboratory and its tenants. Each alternative identified in the Mission Need Statement for the Remote-Handled Low-Level Waste Treatment Project is described and evaluated for capability to fulfill the mission need. Alternatives that could meet the mission need are further evaluated and compared using criteria of cost, risk, complexity, stakeholder values, and regulatory compliance. The alternative for disposal of remote-handled low-level waste that has the highest confidence of meeting the mission need and represents best value to the government is to build a new disposal facility at the Idaho National Laboratory Site.

  9. Remote-Handled Low-Level Waste Disposal Project Alternatives Analysis

    Energy Technology Data Exchange (ETDEWEB)

    David Duncan

    2011-03-01

    This report identifies, evaluates, and compares alternatives for meeting the U.S. Department of Energy’s mission need for management of remote-handled low-level waste generated by the Idaho National Laboratory and its tenants. Each alternative identified in the Mission Need Statement for the Remote-Handled Low-Level Waste Treatment Project is described and evaluated for capability to fulfill the mission need. Alternatives that could meet the mission need are further evaluated and compared using criteria of cost, risk, complexity, stakeholder values, and regulatory compliance. The alternative for disposal of remote-handled low-level waste that has the highest confidence of meeting the mission need and represents best value to the government is to build a new disposal facility at the Idaho National Laboratory Site.

  10. Remote-Handled Low-Level Waste Disposal Project Alternatives Analysis

    Energy Technology Data Exchange (ETDEWEB)

    David Duncan

    2010-06-01

    This report identifies, evaluates, and compares alternatives for meeting the U.S. Department of Energy’s mission need for management of remote-handled low-level waste generated by the Idaho National Laboratory and its tenants. Each alternative identified in the Mission Need Statement for the Remote-Handled Low-Level Waste Treatment Project is described and evaluated for capability to fulfill the mission need. Alternatives that could meet the mission need are further evaluated and compared using criteria of cost, risk, complexity, stakeholder values, and regulatory compliance. The alternative for disposal of remote-handled low-level waste that has the highest confidence of meeting the mission need and represents best value to the government is to build a new disposal facility at the Idaho National Laboratory Site.

  11. Deep Borehole Disposal as an Alternative Concept to Deep Geological Disposal

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Jongyoul; Lee, Minsoo; Choi, Heuijoo; Kim, Kyungsu [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2016-10-15

    In this paper, the general concept and key technologies for deep borehole disposal of spent fuels or HLW, as an alternative method to the mined geological disposal method, were reviewed. After then an analysis on the distance between boreholes for the disposal of HLW was carried out. Based on the results, a disposal area were calculated approximately and compared with that of mined geological disposal. These results will be used as an input for the analyses of applicability for DBD in Korea. The disposal safety of this system has been demonstrated with underground research laboratory and some advanced countries such as Finland and Sweden are implementing their disposal project on commercial stage. However, if the spent fuels or the high-level radioactive wastes can be disposed of in the depth of 3-5 km and more stable rock formation, it has several advantages. Therefore, as an alternative disposal concept to the mined deep geological disposal concept (DGD), very deep borehole disposal (DBD) technology is under consideration in number of countries in terms of its outstanding safety and cost effectiveness. In this paper, the general concept of deep borehole disposal for spent fuels or high level radioactive wastes was reviewed. And the key technologies, such as drilling technology of large diameter borehole, packaging and emplacement technology, sealing technology and performance/safety analyses technologies, and their challenges in development of deep borehole disposal system were analyzed. Also, very preliminary deep borehole disposal concept including disposal canister concept was developed according to the nuclear environment in Korea.

  12. Deep Borehole Disposal as an Alternative Concept to Deep Geological Disposal

    International Nuclear Information System (INIS)

    Lee, Jongyoul; Lee, Minsoo; Choi, Heuijoo; Kim, Kyungsu

    2016-01-01

    In this paper, the general concept and key technologies for deep borehole disposal of spent fuels or HLW, as an alternative method to the mined geological disposal method, were reviewed. After then an analysis on the distance between boreholes for the disposal of HLW was carried out. Based on the results, a disposal area were calculated approximately and compared with that of mined geological disposal. These results will be used as an input for the analyses of applicability for DBD in Korea. The disposal safety of this system has been demonstrated with underground research laboratory and some advanced countries such as Finland and Sweden are implementing their disposal project on commercial stage. However, if the spent fuels or the high-level radioactive wastes can be disposed of in the depth of 3-5 km and more stable rock formation, it has several advantages. Therefore, as an alternative disposal concept to the mined deep geological disposal concept (DGD), very deep borehole disposal (DBD) technology is under consideration in number of countries in terms of its outstanding safety and cost effectiveness. In this paper, the general concept of deep borehole disposal for spent fuels or high level radioactive wastes was reviewed. And the key technologies, such as drilling technology of large diameter borehole, packaging and emplacement technology, sealing technology and performance/safety analyses technologies, and their challenges in development of deep borehole disposal system were analyzed. Also, very preliminary deep borehole disposal concept including disposal canister concept was developed according to the nuclear environment in Korea

  13. Summary of EPA's risk assessment results from the analysis of alternative methods of low-level waste disposal

    International Nuclear Information System (INIS)

    Bandrowski, M.S.; Hung, C.Y.; Meyer, G.L.; Rogers, V.C.

    1987-01-01

    Evaluation of the potential health risk and individual exposure from a broad number of disposal alternatives is an important part of EPA's program to develop generally applicable environmental standards for the land disposal of low-level radioactive wastes (LLW). The Agency has completed an analysis of the potential population health risks and maximum individual exposures from ten disposal methods under three different hydrogeological and climatic settings. This paper briefly describes the general input and analysis procedures used in the risk assessment for LLW disposal and presents their preliminary results. Some important lessons learned from simulating LLW disposal under a large variety of methods and conditions are identified

  14. Evaluation of alternative methods for the disposal of low-level radioactive wastes

    International Nuclear Information System (INIS)

    Macbeth, P.; Wehmann, G.; Thamer, B.J.; Card, D.H.

    1979-07-01

    A comparative analysis of the most viable alternatives for disposal of solid low-level radioactive wastes is presented to aid in evaluating national waste management options. Four basic alternative methods are analyzed and compared to the present practice of shallow land burial. These include deeper burial, disposal in mined cavities, disposal in engineered structures, and disposal in the oceans. Some variations in the basic methods are also presented. Technical, socio-political, and economic factors are assigened relative importances (weights) and evaluated for the various alternatives. Based on disposal of a constant volume of waste with given nuclear characteristics, the most desirable alternatives to shallow land burial in descending order of desirability appear to be: improving present practices, deeper burial, use of acceptable abandoned mines, new mines, ocean dumping, and structural disposal concepts. It must be emphasized that the evaluations reported here are generic, and use of other weights or different values for specific sites could change the conclusions and ordering of alternatives determined in this study. Impacts and costs associated with transportation over long distances predominate over differences among alternatives, indicating the desireability of establishing regional waste disposal locations. The impacts presented are for generic comparisons among alternatives, and are not intended to be predictive of the performance of any actual waste disposal facility

  15. Discriminating performance of disposal alternatives - can it be done

    International Nuclear Information System (INIS)

    Rogers, V.C.; Baird, R.D.; Murphy, E.S.

    1987-01-01

    A basic principle of radioactive waste disposal is that the degree of isolation of the waste from human exposure should increase with the increase in the hazard of the waste. Most disposal concepts, including low-level waste disposal concepts, rely on isolation, limits on release rates, environmental retention, or environmental dilution to provide the necessary margin of safety. The answer to the question posed by the title of this paper is a qualified yes, depending on the measure of performance. Three methodologies for discriminating performance of low-level waste disposal alternatives are described. The disposal technology classification system distinguishes technologies on the basis of three qualitative performance functional features. These are relationship to natural grade, extent of cover, and presence and type of structure. Multi-attribute utility estimation is a semiquantitative decision analysis methodology used to rank disposal alternatives by taking into account both the technical merit of a particular alternative and the relative importance of issues and factors used to make the technical judgment. Use of this decision methodology by several states and compacts to rank proposed near surface disposal alternatives is described. Multipathway performance assessment is a quantitative methodology that uses models to evaluate the abilities of different disposal technologies to limit the release of radioactivity to man and the environment. Unfortunately, the degree of sophistication of present models is such that discrimination between technologies is, generally, determined by differences in input parameters that are usually difficult to justify. Several examples of the use of pathway modeling are presented. 11 references, 2 figures, 5 tables

  16. Alternatives for definse waste-salt disposal

    International Nuclear Information System (INIS)

    Benjamin, R.W.; McDonell, W.R.

    1983-01-01

    Alternatives for disposal of decontaminated high-level waste salt at Savannah River were reviewed to estimate costs and potential environmental impact for several processes. In this review, the reference process utilizing intermediate-depth burial of salt-concrete (saltcrete) monoliths was compared with alternatives including land application of the decontaminated salt as fertilizer for SRP pine stands, ocean disposal with and without containment, and terminal storage as saltcake in existing SRP waste tanks. Discounted total costs for the reference process and its modifications were in the same range as those for most of the alternative processes; uncontained ocean disposal with truck transport to Savannah River barges and storage as saltcake in SRP tanks had lower costs, but presented other difficulties. Environmental impacts could generally be maintained within acceptable limits for all processes except retention of saltcake in waste tanks, which could result in chemical contamination of surrounding areas on tank collapse. Land application would require additional salt decontamination to meet radioactive waste disposal standards, and ocean disposal without containment is not permitted in existing US practice. The reference process was judged to be the only salt disposal option studied which would meet all current requirements at an acceptable cost

  17. Alternative disposal technologies for new low-level radioactive waste disposal/storage facilities at the Savannah River Plant

    International Nuclear Information System (INIS)

    Cook, J.R.

    1987-01-01

    A Draft Environmental Impact Statement for Waste Management Activities for groundwater protection has been prepared for the Savannah River Plant. Support documentation for the DEIS included an Environmental Information Document on new radioactive waste disposal and storage facilities in which possible alternative disposal technologies were examined in depth. Six technologies that would meet the needs of the Savannah River Plant that selected for description and analysis include near surface disposal, near surface disposal with exceptions, engineered storage, engineered disposal, vault disposal of untreated waste, and a combination of near surface disposal, engineered disposal, and engineered storage. 2 refs

  18. NRC perspective on alternative disposal methods

    International Nuclear Information System (INIS)

    Pittiglio, C.L.; Tokar, M.

    1987-01-01

    In this paper is discussed an NRC staff strategy for the development of technical criteria and procedures for the licensing of various alternatives for disposal of low-level radioactive waste. Steps taken by the staff to identify viable alternative disposal methods and to comply with the requirements of the Low-Level Radioactive Waste Policy Amendments Act (LLRWPAA) of 1985 are also discussed. The strategy proposed by the NRC staff is to focus efforts in FY 87 on alternative concepts that incorporate concrete materials with soil or rock cover (e.g., below ground vaults and earth-mounded concrete bunkers), which several State and State Compacts have identified as preferred disposal options. While the NRC staff believes that other options, such as above ground vaults and mined cavities, are workable and licensable, the staff also believes, for reasons addressed in the paper, that it is in the best interest of the industry and the public to encourage standardization and to focus limited resources on a manageable number of alternative options. Therefore, guidance on above ground vaults, which are susceptible to long-term materials degradation due to climatological effects, and mined cavities, which represent a significant departure from the current experience base for low-level radioactive waste disposal, will receive minimal attention. 6 references

  19. Screening of alternative methods for the disposal of low-level radioactive wastes

    International Nuclear Information System (INIS)

    Macbeth, P.J.; Thamer, B.J.; Christensen, D.E.; Wehmann, G.

    1978-10-01

    A systematic method for categorizing these disposal alternatives which provides assurance that no viable alternatives are overlooked is reported. Alternatives are categorized by (1) the general media in which disposal occurs, (2) by whether the disposal method can be considered as dispersal, containment or elimination of the wastes, and (3) by the applicability of the disposal method to the possible physical waste forms. A literature survey was performed and pertinent references listed for the various alternatives discussed. A bibliography is given which provides coverage of published information on low-level radioactive waste management options. The extensive list of disposal alternatives identified was screened and the most viable choices were selected for further evaluation. A Technical Advisory Panel met and reviewed the results. Suggestions from that meeting and other comments are discussed. The most viable options selected for further evaluation are: (1) improving present shallow land burial practices; (2) deeper depth burial; (3) disposal in cavities; (4) disposal in exposed or buried structures; and (5) ocean disposal. 42 references

  20. Review and evaluation of alternative chemical disposal technologies

    National Research Council Canada - National Science Library

    National Research Council Staff; Commission on Engineering and Technical Systems; Division on Engineering and Physical Sciences; National Research Council; National Academy of Sciences

    .... In light of the fact that alternative technologies have evolved since the 1994 study, this new volume evaluates five Army-chosen alternatives to the baseline incineration system for the disposal...

  1. A preliminary evaluation of alternatives for disposal of INEL low-level waste and low-level mixed waste

    International Nuclear Information System (INIS)

    Smith, T.H.; Roesener, W.S.; Jorgenson-Waters, M.J.

    1993-07-01

    The Mixed and Low-Level Waste Disposal Facility (MLLWDF) project was established in 1992 by the US Department of Energy Idaho Operations Office to provide enhanced disposal capabilities for Idaho National Engineering Laboratory (INEL) low-level mixed waste and low-level waste. This Preliminary Evaluation of Alternatives for Disposal of INEL Low-Level Waste and Low-Level Mixed Waste identifies and evaluates-on a preliminary, overview basis-the alternatives for disposal of that waste. Five disposal alternatives, ranging from of no-action'' to constructing and operating the MLLWDF, are identified and evaluated. Several subalternatives are formulated within the MLLWDF alternative. The subalternatives involve various disposal technologies as well as various scenarios related to the waste volumes and waste forms to be received for disposal. The evaluations include qualitative comparisons of the projected isolation performance for each alternative, and facility, health and safety, environmental, institutional, schedule, and rough order-of-magnitude life-cycle cost comparisons. The performance of each alternative is evaluated against lists of ''musts'' and ''wants.'' Also included is a discussion of other key considerations for decisionmaking. The analysis of results indicated further study is necessary to obtain the best estimate of long-term future waste volume and characteristics from the INEL Environmental Restoration activities and the expanded INEL Decontamination and Decommissioning Program

  2. Alternatives for the disposal of NORM [naturally occurring radioactive materials] wastes in Texas

    International Nuclear Information System (INIS)

    Nielson, K.K.; Rogers, V.C.; Pollard, C.G.

    1989-01-01

    Some of the Texas wastes containing naturally occurring radioactive materials (NORM) have been disposed of in a uranium mill tailings impoundment. There is currently no operating disposal facility in Texas to accept these wastes. As a result, some wastes containing extremely small amounts of radioactivity are sent to elaborate disposal sites at extremely high costs. The Texas Low-Level Radioactive Waste Disposal Authority has sponsored a study to investigate lower cost, alternative disposal methods for certain wastes containing small quantities of NORM. This paper presents the results of a multipathway safety analysis of various scenarios for disposing of wastes containing limited quantities of NORM in Texas. The wastes include pipe scales and sludges from oil and gas production, residues from rare-earth mineral processing, and water treatment resins, but exclude large-volume, diffuse wastes (coal fly ash, phosphogypsum). The purpose of the safety analysis is to define concentration and quantity limits for the key nuclides of NORM that will avoid dangerous radiation exposures under different waste disposal scenarios

  3. Alternatives for future land disposal of radioactive waste

    International Nuclear Information System (INIS)

    Mallory, C.W.

    1982-01-01

    Shallow land burial incorporating improvements to facilitate stabilization and decommissioning will continue to be the primary method of disposing of low level waste in areas where conditions are suitable for this type of disposal. The existing disposal sites should be closely monitored to assure that continued acceptance of this method of disposal. Plans for the decommissioning of the existing sites should be closely reviewed to assure that the planning is adequate and that adequate resources will be available to implement the decommissioning plan. For these areas where geological conditions are not suitable for shallow land burial and in situations where a higher degree of containment is desired, alternative disposal methods should be considered. Technology exists or is readily attainable to provide engineered disposal facilities which provide a higher degree of containment and can be readily decommissioned. The cost of disposal using these methods can be competitive with shallow land burial when the cost of environmental and hydrogeologic investigations and decommissioning are included. Disposal of radioactive waste having low activity in secure sanitary landfills could significantly reduce the transportation and disposal requirements for low level waste

  4. 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

  5. Economic analysis of radioactive waste storage and disposal projects

    International Nuclear Information System (INIS)

    Kleinen, P.J.; Starnes, R.B.

    1995-01-01

    Radioactive waste storage and disposal efforts present challenging issues for cost and economic analyses. In particular, legal requirements for states and compact areas to develop radioactive waste disposal sites, combined with closure of some sites, have placed urgency on planning, locating, and constructing storage and disposal sites. Cost analyses of potential projects are important to the decision processes. Principal objectives for cost analyses for projects are to identify all activities, covering the entire project life cycle, and to develop costs for those activities using methods that allow direct comparisons between competing project alternatives. For radioactive waste projects, long project lives ranging from tens of years to 100 or more years must be considered. Alternative, and competing, technologies, designs, and operating plans must be evaluated. Thorough base cost estimates must be made for all project phases: planning, development, licensing/permitting, construction, operations, and maintenance, closure, and post-closure/institutional care. Economic analysis procedures need to accommodate the specific features of each project alternative and facilitate cost comparisons between differing alternatives. Economic analysis assumptions must be developed to address the unusually long project lives involved in radioactive waste projects

  6. 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)

  7. Seabed disposal of high-level nuclear wastes: an alternative viewpoint

    International Nuclear Information System (INIS)

    Glasby, G.P.

    1985-01-01

    Various comments on a published article on subseabed disposal of nuclear wastes are presented. These include the scale of the proposed operation, the technical problems of canister retrievability, the feasibility of the free-fall penetrometer disposal method, canister lifetime, the possible contravention of the 1972 London Dumping Convention and land-based geological repositories as an alternative method of disposal. (author)

  8. Alternative disposal options for alpha-mixed low-level waste

    International Nuclear Information System (INIS)

    Loomis, G.G.; Sherick, M.J.

    1995-01-01

    This paper presents several disposal options for the Department of Energy alpha-mixed low-level waste. The mixed nature of the waste favors thermally treating the waste to either an iron-enriched basalt or glass waste form, at which point a multitude of reasonable disposal options, including in-state disposal, are a possibility. Most notably, these waste forms will meet the land-ban restrictions. However, the thermal treatment of this waste involves considerable waste handling and complicated/expensive offgas systems with secondary waste management problems. In the United States, public perception of offgas systems in the radioactive incinerator area is unfavorable. The alternatives presented here are nonthermal in nature and involve homogenizing the waste with cryogenic techniques followed by complete encapsulation with a variety of chemical/grouting agents into retrievable waste forms. Once encapsulated, the waste forms are suitable for transport out of the state or for actual in-state disposal. This paper investigates variances that would have to be obtained and contrasts the alternative encapsulation idea with the thermal treatment option

  9. Alternative disposal options for alpha-mixed low-level waste

    Energy Technology Data Exchange (ETDEWEB)

    Loomis, G.G.; Sherick, M.J. [Idaho National Engineering Lab., Idaho Falls, ID (United States)

    1995-12-31

    This paper presents several disposal options for the Department of Energy alpha-mixed low-level waste. The mixed nature of the waste favors thermally treating the waste to either an iron-enriched basalt or glass waste form, at which point a multitude of reasonable disposal options, including in-state disposal, are a possibility. Most notably, these waste forms will meet the land-ban restrictions. However, the thermal treatment of this waste involves considerable waste handling and complicated/expensive offgas, systems with secondary waste management problems. In the United States, public perception of off gas systems in the radioactive incinerator area is unfavorable. The alternatives presented here are nonthermal in nature and involve homogenizing the waste with cryogenic techniques followed by complete encapsulation with a variety of chemical/grouting agents into retrievable waste forms. Once encapsulated, the waste forms are suitable for transport out of the state or for actual in-state disposal. This paper investigates variances that would have to be obtained and contrasts the alternative encapsulation idea with the thermal treatment option.

  10. An evaluation on the disposal alternatives for low- and intermediate- level radwaste (II)

    International Nuclear Information System (INIS)

    Park, Hun Hwee; Han, Kyung Won; Hahn, Pil Soo; Lee, Han Soo; Cho, Won Jin; Lee, Jae Dwan; Park, Chung Kyun; Lee, Myung Joo; Choi, Heui Joo; Lee, Youn Myoung

    1988-02-01

    An evaluation on the radioactive waste disposal alternatives for the low-and intermediate level wastes being produced from nuclear power generation and radioisotope application was carried out in view of the radiological safety, socio-political aspects and repository construction economics. Three types of possible alternatives-sample shallow land disposal method, engineered shallow land disposal method and engineered rock cavern disposal method are investigated. The safety assessment consists of radiological dose calculation and nonradiological impacts which is expressed as total number of injuries and fatalities during construction, operation and transportation. The sociopolitical assessment is done in terms of site conditions including easiness for land acquisition, technical feasibility and public acceptance. The economic assessment is performed by cost comparison regarding land acquisition, construction, operation and closure for each alternatives. The evaluation shows that engineered rock cavern disposal method has remarkable favour in safety than others. And also an integrated evaluation using AHP results the engineered rock cavern disposal method as the most favorable option

  11. Alternatives to disposal of Hanford Site liquid effluents to the soil column

    International Nuclear Information System (INIS)

    Meinhardt, C.C.; Flyckt, D.L.; Wirsing, R.M.; Winterhalder, J.A.

    1987-04-01

    Alternative systems were selected for 28 effluent streams, based on the use of available technology and ability to eliminate the contaminated effluent or reduce contaminant levels to meet specified effluent disposal criteria and standards derived from DOE Orders and environmental statutes. This study determined that technically feasible alternative waste disposal systems are available. 6 refs., 2 figs., 2 tabs

  12. Alternative methods of salt disposal at the seven salt sites for a nuclear waste repository

    International Nuclear Information System (INIS)

    1987-02-01

    This study discusses the various alternative salt management techniques for the disposal of excess mined salt at seven potentially acceptable nuclear waste repository sites: Deaf Smith and Swisher Counties, Texas; Richton and Cypress Creek Domes, Mississippi; Vacherie Dome, Louisiana; and Davis and Lavender Canyons, Utah. Because the repository development involves the underground excavation of corridors and waste emplacement rooms, in either bedded or domed salt formations, excess salt will be mined and must be disposed of offsite. The salt disposal alternatives examined for all the sites include commercial use, ocean disposal, deep well injection, landfill disposal, and underground mine disposal. These alternatives (and other site-specific disposal methods) are reviewed, using estimated amounts of excavated, backfilled, and excess salt. Methods of transporting the excess salt are discussed, along with possible impacts of each disposal method and potential regulatory requirements. A preferred method of disposal is recommended for each potentially acceptable repository site. 14 refs., 5 tabs

  13. State workshop on shallow land burial and alternative disposal concepts: proceedings

    International Nuclear Information System (INIS)

    1984-10-01

    Three of the major conclusions reached by state participants were the following: (1) Significant data gaps and information needs have to be addressed before timely state decisionmaking can be accomplished. State participants felt a generic cost/risk/benefit analysis for all viable alternatives would be useful and might best be performed by the federal government on behalf of the states. (2) Recognizing the imprecision in summarizing overall attitudes of the workshop participants, alternative disposal concepts that appear to be the most favorably perceived when rank ordered by critical factors are augered holes with liners, belowground vaults, earth mounded concrete bunkers, aboveground vaults and mined cavities. (3) The public appears to place greater confidence in disposal methods that incorporate man-made engineered barriers because of some past problems at closed shallow land burial facilities. Concern was expressed by workshop participants that the public may not consider the perceived risks associated with shallow land burial to be acceptable. In addition to the four 10 CFR Part 61, Subpart C performance objectives, public acceptance of risk was considered to be a critical factor by state officials in selecting a disposal technology. The states should take the lead in pursuing development-oriented analyses, such as detailed concept engineering and economic feasibility studies. It is not within the purview of NRC responsibility to undertake such studies

  14. Evaluation of alternatives for high-level and transuranic radioactive- waste disposal standards

    International Nuclear Information System (INIS)

    Klett, R.D.; Gruebel, M.M.

    1992-12-01

    The remand of the US Environmental Protection Agency's long-term performance standards for radioactive-waste disposal provides an opportunity to suggest modifications that would make the regulation more defensible and remove inconsistencies yet retain the basic structure of the original rule. Proposed modifications are in three specific areas: release and dose limits, probabilistic containment requirements, and transuranic-waste disposal criteria. Examination of the modifications includes discussion of the alternatives, demonstration of methods of development and implementation, comparison of the characteristics, attributes, and deficiencies of possible options within each area, and analysis of the implications for performance assessments. An additional consideration is the impact on the entire regulation when developing or modifying the individual components of the radiological standards

  15. Alternative solutions for the disposal of radioactive wastes

    International Nuclear Information System (INIS)

    Ramsey, R.W. Jr.

    1976-01-01

    Besides outlining the possibility of dispatching concentrated highly radioactive waste by rockets into space, or of transmuting long-lived isotopes by nuclear reactions into short-lived ones, the author discusses further alternatives for the disposal of radioactive wastes, especially the storage in geologic formations. (HR/LN) [de

  16. Alternatives for the treatment and disposal of healthcare wastes in developing countries

    International Nuclear Information System (INIS)

    Diaz, L.F.; Savage, G.M.; Eggerth, L.L.

    2005-01-01

    Waste production in healthcare facilities in developing countries has brought about a variety of concerns due to the use of inappropriate methods of managing the wastes. Inappropriate treatment and final disposal of the wastes can lead to adverse impacts to public health, to occupational health and safety, and to the environment. Unfortunately, most economically developing countries suffer a variety of constraints to adequately managing these wastes. Generally in developing countries, few individuals in the staff of the healthcare facility are familiar with the procedures required for a proper waste management program. Furthermore, the management of wastes usually is delegated to poorly educated laborers who perform most activities without proper guidance and insufficient protection. This paper presents some of the most common treatment and disposal methods utilized in the management of infectious healthcare wastes in developing countries. The methods discussed include: autoclave; microwave; chemical disinfection; combustion (low-, medium-, and high-technology); and disposal on the ground (dump site, controlled landfill, pits, and sanitary landfill). Each alternative for treatment and disposal is explained, including a description of the types of wastes that can and cannot be treated. Background information on the technologies also is included in order to provide information to those who may not be familiar with the details of each alternative. In addition, a brief presentation of some of the emissions from each of the treatment and disposal alternatives is presented

  17. Disposal alternatives and recommendations for waste salt management for repository excavation in the Palo Duro Basin, Texas

    International Nuclear Information System (INIS)

    1987-01-01

    This report documents an evaluation of five alternatives for the disposal of waste salt that would be generated by the construction of a repository for radioactive waste in underground salt deposits at either of two sites in the Palo Duro Basin, Texas. The alternatives include commercial disposal, offsite deep-well injection, disposal in abandoned mines, ocean disposal, and land surface disposal on or off the site. For each alternative a reference case was rated - positive, neutral, or negative - in terms of environmental and dependability factors developed specifically for Texas sites. The factors constituting the environmental checklist relate to water quality impact, water- and land-use conflicts, ecological compatibility, conformity with air quality standards, and aesthetic impact. Factors on the dependability check-list relate to public acceptance, the adequacy of site characterization, permit and licensing requirements, technological requirements, and operational availability. A comparison of the ratings yielded the following viable alternatives, in order of preference: (1) land surface disposal, specifically disposal on tailings piles associated with abandoned potash mines; (2) disposal in abandoned mines, specifically potash mines; and (3) commercial disposal. Approaches to the further study of these three salt management techniques are recommended

  18. Potential radiological impacts of upper-bound operational accidents during proposed waste disposal alternatives for Hanford defense waste

    Energy Technology Data Exchange (ETDEWEB)

    Mishima, J.; Sutter, S.L.; Hawley, K.A.; Jenkins, C.E.; Napier, B.A.

    1986-02-01

    The Geologic Disposal Alternative, the In-Place Stabilization and Disposal Alternative, and the Reference Disposal Alternative are being evaluated for disposal of Hanford defense high-level, transuranic, and tank wastes. Environmental impacts associated with disposal of these wastes according to the alternatives listed above include potential doses to the downwind population from operation during the application of the handling and processing techniques comprising each disposal alternative. Scenarios for operational accident and abnormal operational events are postulated, on the basis of the currently available information, for the application of the techniques employed for each waste class for each disposal alternative. From these scenarios, an upper-bound airborne release of radioactive material was postulated for each waste class and disposal alternative. Potential downwind radiologic impacts were calculated from these upper-bound events. In all three alternatives, the single postulated event with the largest calculated radiologic impact for any waste class is an explosion of a mixture of ferri/ferro cyanide precipitates during the mechanical retrieval or microwave drying of the salt cake in single shell waste tanks. The anticipated downwind dose (70-year dose commitment) to the maximally exposed individual is 3 rem with a total population dose of 7000 man-rem. The same individual would receive 7 rem from natural background radiation during the same time period, and the same population would receive 3,000,000 man-rem. Radiological impacts to the public from all other postulated accidents would be less than that from this accident; furthermore, the radiological impacts resulting from this accident would be less than one-half that from the natural background radiation dose.

  19. Potential radiological impacts of upper-bound operational accidents during proposed waste disposal alternatives for Hanford defense waste

    International Nuclear Information System (INIS)

    Mishima, J.; Sutter, S.L.; Hawley, K.A.; Jenkins, C.E.; Napier, B.A.

    1986-02-01

    The Geologic Disposal Alternative, the In-Place Stabilization and Disposal Alternative, and the Reference Disposal Alternative are being evaluated for disposal of Hanford defense high-level, transuranic, and tank wastes. Environmental impacts associated with disposal of these wastes according to the alternatives listed above include potential doses to the downwind population from operation during the application of the handling and processing techniques comprising each disposal alternative. Scenarios for operational accident and abnormal operational events are postulated, on the basis of the currently available information, for the application of the techniques employed for each waste class for each disposal alternative. From these scenarios, an upper-bound airborne release of radioactive material was postulated for each waste class and disposal alternative. Potential downwind radiologic impacts were calculated from these upper-bound events. In all three alternatives, the single postulated event with the largest calculated radiologic impact for any waste class is an explosion of a mixture of ferri/ferro cyanide precipitates during the mechanical retrieval or microwave drying of the salt cake in single shell waste tanks. The anticipated downwind dose (70-year dose commitment) to the maximally exposed individual is 3 rem with a total population dose of 7000 man-rem. The same individual would receive 7 rem from natural background radiation during the same time period, and the same population would receive 3,000,000 man-rem. Radiological impacts to the public from all other postulated accidents would be less than that from this accident; furthermore, the radiological impacts resulting from this accident would be less than one-half that from the natural background radiation dose

  20. Assessment of alternative disposal concepts

    Energy Technology Data Exchange (ETDEWEB)

    Autio, J.; Saanio, T.; Tolppanen, P. [Saanio and Riekkola Consulting Engineers, Helsinki (Finland); Raiko, H.; Vieno, T. [VTT Energy, Espoo (Finland); Salo, J.P. [Posiva Oy, Helsinki (Finland)

    1996-12-01

    Four alternative repository designs for the disposal of spent nuclear in the Finnish crystalline bedrock were assessed in the study. The alternatives were: (1) the basic KBS-3 design in which copper canisters are emplaced in vertical deposition holes bored in the floors of horizontal tunnels, (2) the KBS-3-2C design with two canisters in a deposition hole, (3) Short Horizontal Holes (SHH) in the side walls of the tunnels, and (4) the Medium Long Holes (MLH) concept in which approximately 25 canisters are emplaced in a horizontal deposition hole about 200 metres in length bored between central and side tunnels. In all the alternatives considered, the thickness of the layer of compacted bentonite between copper canister and bedrock is 35 cm. Two different copper canister designs were also assessed. Technical feasibility and flexibility, post-closure safety and repository cost were assessed for each of the alternative canister and repository designs. On the basis of this assessment it is recommended that further development and studies should focus on the vacuum- or inert gas-filled cast insert type copper canister and the basic KBS-3 type repository design with a single canister in a vertical deposition hole. The KBS-3 design is robust and flexible and provides excellent post-closure safety. The transfer, emplacement and sealing operations are technically uncomplicated. The alternative options assessed do not offer any significant benefits in safety or cost over the basic design, but they are technically more complex and also in some respects more vulnerable to malfunction during the emplacement of canisters and buffer, as well as common mode failures. (60 refs.).

  1. Assessment of alternative disposal concepts

    International Nuclear Information System (INIS)

    Autio, J.; Saanio, T.; Tolppanen, P.; Raiko, H.; Vieno, T.; Salo, J.P.

    1996-12-01

    Four alternative repository designs for the disposal of spent nuclear in the Finnish crystalline bedrock were assessed in the study. The alternatives were: (1) the basic KBS-3 design in which copper canisters are emplaced in vertical deposition holes bored in the floors of horizontal tunnels, (2) the KBS-3-2C design with two canisters in a deposition hole, (3) Short Horizontal Holes (SHH) in the side walls of the tunnels, and (4) the Medium Long Holes (MLH) concept in which approximately 25 canisters are emplaced in a horizontal deposition hole about 200 metres in length bored between central and side tunnels. In all the alternatives considered, the thickness of the layer of compacted bentonite between copper canister and bedrock is 35 cm. Two different copper canister designs were also assessed. Technical feasibility and flexibility, post-closure safety and repository cost were assessed for each of the alternative canister and repository designs. On the basis of this assessment it is recommended that further development and studies should focus on the vacuum- or inert gas-filled cast insert type copper canister and the basic KBS-3 type repository design with a single canister in a vertical deposition hole. The KBS-3 design is robust and flexible and provides excellent post-closure safety. The transfer, emplacement and sealing operations are technically uncomplicated. The alternative options assessed do not offer any significant benefits in safety or cost over the basic design, but they are technically more complex and also in some respects more vulnerable to malfunction during the emplacement of canisters and buffer, as well as common mode failures. (60 refs.)

  2. Alternative disposal options for transuranic waste

    International Nuclear Information System (INIS)

    Loomis, G.G.

    1994-01-01

    Three alternative concepts are proposed for the final disposal of stored and retrieved buried transuranic waste. These proposed options answer criticisms of the existing U.S. Department of Energy strategy of directly disposing of stored transuranic waste in deep, geological salt formations at the Waste Isolation Pilot Plant (WIPP) in Carlsbad, New Mexico. The first option involves enhanced stabilization of stored waste by thermal treatment followed by convoy transportation and internment in the existing WIPP facility. This concept could also be extended to retrieved buried waste with proper permitting. The second option involves in-state, in situ internment using an encapsulating lens around the waste. This concept applies only to previously buried transuranic waste. The third option involves sending stored and retrieved waste to the Nevada Test Site and configuring the waste around a thermonuclear device from the U.S. or Russian arsenal in a specially designed underground chamber. The thermonuclear explosion would transmute plutonium and disassociate hazardous materials while entombing the waste in a national sacrifice area

  3. Assessment of recycling or disposal alternatives for radioactive scrap metal

    International Nuclear Information System (INIS)

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

    1993-01-01

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

  4. Multiattribute utility analysis of alternative sites for the disposal of nuclear waste

    International Nuclear Information System (INIS)

    Merkhofer, M.W.; Keeney, R.L.

    1987-01-01

    Five potential sites nominated for the Nation's first geologic repository for disposing of nuclear waste are evaluated using multiattribute utility analysis. The analysis was designed to aid the Department of Energy in its selection of 3 sites for characterization, a detailed data-gathering process that will involve the construction of exploratory shafts for underground testing and that may cost as much as $1 billion per site. The analysis produced insights into the relative advantages and disadvantages of the nominated sites and clarified current uncertainties regarding repository performance

  5. Assessment of recycling or disposal alternatives for radioactive scrap metal

    International Nuclear Information System (INIS)

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

    1993-01-01

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

  6. Alternative methods for disposal of low-level radioactive wastes. Task 2c: technical requirements for earth mounded concrete bunker disposal of low-level radioactive waste. Volume 4

    International Nuclear Information System (INIS)

    Miller, W.O.; Bennett, R.D.

    1985-10-01

    The study reported herein contains the results of Task 2c (Technical Requirements for Earth Mounded Concrete Bunker Disposal of Low-Level Radioactive Waste) of a four-task study entitled ''Criteria for Evaluating Engineered Facilities''. The overall objective of this study is to ensure that the criteria needed to evaluate five alternative low-level radioactive waste (LLW) disposal methods are available to potential license applicants. The earth mounded concrete bunker disposal alternative is one of several methods that may be proposed for disposal of low-level radioactive waste. The name of this alternative is descriptive of the disposal method used in France at the Centre de la Manche. Experience gained with this method at the Centre is described, including unit operations and features and components. Some improvements to the French system are recommended herein, including the use of previous backfill around monoliths and extending the limits of a low permeability surface layer. The applicability of existing criteria developed for near-surface disposal (10 CFR Part 61 Subpart D) to the earth mounded concrete bunker disposal method, as assessed in Task 1, are reassessed herein. With minor qualifications, these criteria were found to be applicable in the reassessment. These conclusions differ slightly from the Task 1 findings

  7. Disposing of nuclear waste: an economic analysis of two alternative concepts

    International Nuclear Information System (INIS)

    Dippold, D.G.; Tzemos, S.

    1987-01-01

    WADCOM II is a nuclear waste disposal cost model intended to provide its users with relatively quick, although macro, insight into the economics of hypothetical nuclear waste disposal scenarios. The nuclear waste management system represented by the model, the philosophy underlying the model's design, and the logic of the model itself are described. The model is used to analyze the economics of two nuclear waste disposal concepts, the borehold package concept and the generic package concept. Results indicate the generic package concept leads to the higher costs under all the assumed conditions

  8. Subseabed disposal safety analysis

    International Nuclear Information System (INIS)

    Koplick, C.M.; Kabele, T.J.

    1982-01-01

    This report summarizes the status of work performed by Analytic Sciences Corporation (TASC) in FY'81 on subseabed disposal safety analysis. Safety analysis for subseabed disposal is divided into two phases: pre-emplacement which includes all transportation, handling, and emplacement activities; and long-term (post-emplacement), which is concerned with the potential hazard after waste is safely emplaced. Details of TASC work in these two areas are provided in two technical reports. The work to date, while preliminary, supports the technical and environmental feasibility of subseabed disposal of HLW

  9. Some considerations in the evaluation of concrete as a structural material for alternative LLW disposal technologies

    International Nuclear Information System (INIS)

    MacKenzie, D.R.; Siskind, B.; Bowerman, B.S.; Piciulo, P.L.

    1987-01-01

    The objective of this study was to develop information needed to evaluate the long-term performance of concrete and reinforced concrete as a structural material for alternative LLW disposal methods. The capability to carry out such an evaluation is required for licensing a site which employs one of these alternative methods. The basis for achieving the study objective was the review and analysis of the literature on concrete and its properties, particularly its durability. In carrying out this program characteristics of concrete useful in evaluating its performance and factors that can affect its performance were identified. The factors are both intrinsic, i.e., associated with composition of the concrete (and thus controllable), and extrinsic, i.e., due to external environmental forces such as climatic conditions and aggressive chemicals in the soil. The testing of concrete, using both accelerated tests and long-term non-accelerated tests, is discussed with special reference to its application to modeling of long-term performance prediction. On the basis of the study's results, conditions for acceptance are recommended as an aid in the licensing of disposal sites which make use of alternative methods

  10. 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

  11. Considerations for alternative low-level radioactive disposal sites

    International Nuclear Information System (INIS)

    Beck, J.M.

    1986-01-01

    In the immediate future, there is a need for low-level radioactive disposal sites to accommodate wastes that would otherwise be placed at a later date in permanent, government sanctioned ''compact'' sites. Until these ''compact'' sites become operational, a potential, relatively low-cost alternative exists in the numerous inactive uranium processing sites that are likewise proposed for remedial action removal or stabilization operations. This paper addressed disposal from the aspects of engineering design, economics and liability of participating parties. Many uranium (and by-product) processing facilities in the western states now stand idle due to current economic conditions within the industry. Many more were previously deactivated for various reasons. All must be dealt with under the UMTRA Program Guidelines with regard to removal, reclamation or other remedial action activities. With cooperative efforts, some of these sites would appear to be suitable for disposal of small volume, low-level radioactive wastes that presently render urban properties valueless in terms of real estate and aesthetic values. Likely sites would appear to be those slated for in-place stabilization and reclamation, particularly where the urban property material has a lower level of radioactivity than the disposal site material. The resultant impacts for site stabilization and reclamation would be solely in the areas of increased material volumes (generally requiring a minimal increase in engineering design complexity) and liability. Clearly, liability will be the overriding factor in such an approach. With the complex hierarchy of regulatory agencies involved and the private sector, what appears to be a relative simple and economic approach may have extreme difficulty in achieving reality

  12. Alternate Methods of Effluent Disposal for On-Lot Home Sewage Systems. Special Circular 214.

    Science.gov (United States)

    Wooding, N. Henry

    This circular provides current information for homeowners who must repair or replace existing on-lot sewage disposal systems. Several alternatives such as elevated sand mounds, sand-lined beds and trenches and oversized absorption areas are discussed. Site characteristics and preparation are outlined. Each alternative is accompanied by a diagram…

  13. The disposal of Canada's nuclear fuel waste: engineered barriers alternatives

    International Nuclear Information System (INIS)

    Johnson, L.H.; Tait, J.C.; Shoesmith, D.W.; Crosthwaite, J.L.; Gray, M.N.

    1994-01-01

    The concept for disposal of Canada's nuclear fuel waste involves emplacing the waste in a vault excavated at a depth of 500 to 1000 m in plutonic rock of the Canadian Shield. The solid waste would be isolated from the biosphere by a multibarrier system consisting of engineered barriers, including long-lived containers and clay and cement-based sealing materials, and the natural barrier provided by the massive geological formation. The technical feasibility of this concept and its impact on the environment and human health are being documented in an Environmental Impact Statement (EIS), which will be submitted for review under the federal Environmental Assessment and Review Process. This report, one of nine EIS primary references, describes the various alternative designs and materials for engineered barriers that have been considered during the development of the Canadian disposal concept and summarizes engineered barrier concepts being evaluated in other countries. The basis for the selection of a reference engineered barrier system for the EIS is presented. This reference system involves placing used CANDU (Canada Deuterium Uranium) fuel bundles in titanium containers, which would then be emplaced in boreholes drilled in the floor of disposal rooms. Clay-based sealing materials would be used to fill both the space between the containers and the rock and the remaining excavations. In the section on waste forms, the properties of both used-fuel bundles and solidified high-level wastes, which would be produced by treating wastes resulting from the reprocessing of used fuel, are discussed. Methods of solidifying the wastes and the chemical durability of the solidified waste under disposal conditions are reviewed. Various alternative container designs are reviewed, ranging from preliminary conceptual designs to designs that have received extensive prototype testing. Results of structural performance, welding and inspection studies are also summarized. The corrosion of

  14. Guidance: Demonstrating Compliance with the Land Disposal Restrictions (LDR) Alternative Soil Treatment Standards

    Science.gov (United States)

    This guidance provides suggestions and perspectives on how members of the regulated community, states, and the public can demonstrate compliance with the alternative treatment standards for certain contaminated soils that will be land disposed.

  15. Land disposal alternatives for low-level waste

    International Nuclear Information System (INIS)

    Alexander, P.; Lindeman, R.; Saulnier, G.; Adam, J.; Sutherland, A.; Gruhlke, J.; Hung, C.

    1982-01-01

    The objective of this project is to develop data regarding the effectiveness and costs of the following options for disposing of specific low-level nuclear waste streams; sanitary landfill; improved shallow land burial; intermediate depth disposal; deep well injection; conventional shallow land burial; engineered surface storage; deep geological disposal; and hydrofracturing. This will be accomplished through the following steps: (1) characterize the properties of the commercial low-level wastes requiring disposal; (2) evaluate the various options for disposing of this waste, characterize selected representative waste disposal sites and design storage facilities suitable for use at those sites; (3) calculate the effects of various waste disposal options on population health risks; (4) estimate the costs of various waste disposal options for specific sites; and (5) perform trade-off analyses of the benefits of various waste disposal options against the costs of implementing these options. These steps are described. 2 figures, 2 tables

  16. Commercial processing and disposal alternatives for very low levels of radioactive waste in the United States

    International Nuclear Information System (INIS)

    Benda, G.A.

    2005-01-01

    The United States has several options available in the commercial processing and disposal of very low levels of radioactive waste. These range from NRC licensed low level radioactive sites for Class A, B and C waste to conditional disposal or free release of very low concentrations of material. Throughout the development of disposal alternatives, the US promoted a graded disposal approach based on risk of the material hazards. The US still promotes this approach and is renewing the emphasis on risk based disposal for very low levels of radioactive waste. One state in the US, Tennessee, has had a long and successful history of disposal of very low levels of radioactive material. This paper describes that approach and the continuing commercial options for safe, long term processing and disposal. (author)

  17. Alternative Concept to Enhance the Disposal Efficiency for CANDU Spent Fuel Disposal System

    International Nuclear Information System (INIS)

    Lee, Jong Youl; Cho, Dong Geun; Kook, Dong Hak; Lee, Min Soo; Choi, Heui Joo

    2011-01-01

    There are two types of nuclear reactors in Korea and they are PWR type and CANDU type. The safe management of the spent fuels from these reactors is very important factor to maintain the sustainable energy supply with nuclear power plant. In Korea, a reference disposal system for the spent fuels has been developed through a study on the direct disposal of the PWR and CANDU spent fuel. Recently, the research on the demonstration and the efficiency analyses of the disposal system has been performed to make the disposal system safer and more economic. PWR spent fuels which include a lot of reusable material can be considered being recycled and a study on the disposal of HLW from this recycling process is being performed. CANDU spent fuels are considered being disposed of directly in deep geological formation, since they have little reusable material. In this study, based on the Korean Reference spent fuel disposal System (KRS) which was to dispose of both PWR type and CANDU type, the more effective CANDU spent fuel disposal systems were developed. To do this, the disposal canister for CANDU spent fuels was modified to hold the storage basket for 60 bundles which is used in nuclear power plant. With these modified disposal canister concepts, the disposal concepts to meet the thermal requirement that the temperature of the buffer materials should not be over 100 .deg. C were developed. These disposal concepts were reviewed and analyzed in terms of disposal effective factors which were thermal effectiveness, U-density, disposal area, excavation volume, material volume etc. and the most effective concept was proposed. The results of this study will be used in the development of various wastes disposal system together with the HLW wastes from the PWR spent fuel recycling process.

  18. HEU to LEU conversion and blending facility: UNH blending alternative to produce LEU oxide for disposal

    International Nuclear Information System (INIS)

    1995-09-01

    The United States Department of Energy (DOE) is examining options for the disposition of surplus weapons-usable fissile materials and storage of all weapons-usable fissile materials. Disposition is a process of use or disposal of material that results in the material being converted to a form that is substantially and inherently more proliferation-resistant than is the original form. Examining options for increasing the proliferation resistance of highly enriched uranium (HEU) is part of this effort. This report provides data to be used in the environmental impact analysis for the uranyl nitrate hexahydrate blending option to produce oxide for disposal. This the Conversion and Blending Facility (CBF) alternative will have two missions (1) convert HEU materials into HEU uranyl nitrate (UNH) and (2) blend the HEU uranyl nitrate with depleted and natural assay uranyl nitrate to produce an oxide that can be stored until an acceptable disposal approach is available. The primary emphasis of this blending operation will be to destroy the weapons capability of large, surplus stockpiles of HEU. The blended LEU product can only be made weapons capable again by the uranium enrichment process. The blended LEU will be produced as a waste suitable for storage or disposal

  19. HEU to LEU conversion and blending facility: UNH blending alternative to produce LEU oxide for disposal

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1995-09-01

    The United States Department of Energy (DOE) is examining options for the disposition of surplus weapons-usable fissile materials and storage of all weapons-usable fissile materials. Disposition is a process of use or disposal of material that results in the material being converted to a form that is substantially and inherently more proliferation-resistant than is the original form. Examining options for increasing the proliferation resistance of highly enriched uranium (HEU) is part of this effort. This report provides data to be used in the environmental impact analysis for the uranyl nitrate hexahydrate blending option to produce oxide for disposal. This the Conversion and Blending Facility (CBF) alternative will have two missions (1) convert HEU materials into HEU uranyl nitrate (UNH) and (2) blend the HEU uranyl nitrate with depleted and natural assay uranyl nitrate to produce an oxide that can be stored until an acceptable disposal approach is available. The primary emphasis of this blending operation will be to destroy the weapons capability of large, surplus stockpiles of HEU. The blended LEU product can only be made weapons capable again by the uranium enrichment process. The blended LEU will be produced as a waste suitable for storage or disposal.

  20. Spent Nuclear Fuel Alternative Technology Decision Analysis

    International Nuclear Information System (INIS)

    Shedrow, C.B.

    1999-01-01

    The Westinghouse Savannah River Company (WSRC) made a FY98 commitment to the Department of Energy (DOE) to recommend a technology for the disposal of aluminum-based spent nuclear fuel (SNF) at the Savannah River Site (SRS). The two technologies being considered, direct co-disposal and melt and dilute, had been previously selected from a group of eleven potential SNF management technologies by the Research Reactor Spent Nuclear Fuel Task Team chartered by the DOE''s Office of Spent Fuel Management. To meet this commitment, WSRC organized the SNF Alternative Technology Program to further develop the direct co-disposal and melt and dilute technologies and ultimately provide a WSRC recommendation to DOE on a preferred SNF alternative management technology

  1. Materials and degradation modes in an alternative LLW [low-level waste] disposal facility

    International Nuclear Information System (INIS)

    Cowgill, M.G.; MacKenzie, D.R.

    1989-01-01

    The materials used in the construction of alternative low-level waste disposal facilities will be subject to interaction with both the internal and the external environments associated with the facilities and unless precautions are taken, may degrade, leading to structural failure. This paper reviews the characteristics of both environments with respect to three alternative disposal concepts, then assesses how reaction with them might affect the properties of the materials, which include concrete, steel-reinforced concrete, structural steel, and various protective coatings and membranes. It identifies and evaluates the probability of reactions occurring which might lead to degradation of the materials and so compromise the structure. The probability of failure (interpreted relative to the ability of the structure to restrict ingress and egress of water) is assessed for each material and precautionary measures, intended to maximize the durability of the facility, are reviewed. 19 refs., 2 tabs

  2. Spent Nuclear Fuel Alternative Technology Decision Analysis

    Energy Technology Data Exchange (ETDEWEB)

    Shedrow, C.B.

    1999-11-29

    The Westinghouse Savannah River Company (WSRC) made a FY98 commitment to the Department of Energy (DOE) to recommend a technology for the disposal of aluminum-based spent nuclear fuel (SNF) at the Savannah River Site (SRS). The two technologies being considered, direct co-disposal and melt and dilute, had been previously selected from a group of eleven potential SNF management technologies by the Research Reactor Spent Nuclear Fuel Task Team chartered by the DOE''s Office of Spent Fuel Management. To meet this commitment, WSRC organized the SNF Alternative Technology Program to further develop the direct co-disposal and melt and dilute technologies and ultimately provide a WSRC recommendation to DOE on a preferred SNF alternative management technology.

  3. Outfall as a Suitable Alternative for Disposal of Municipal Wastewater in Coastal Areas

    Directory of Open Access Journals (Sweden)

    Afshin Takdastan

    2005-11-01

    Full Text Available Disposal of raw municipal wastewater or effluent of preliminary treatment into the sea and ocean is economically more accepted and technically more efficient than secondary treatment. In this method, the wastewater disposed at the bottom of the sea in some points from diffuser. Nowadays, lots of researchers select outfall as a suitable alternative treatment method for coastal cities. The goal of this paper was to introduce the outfall as a wastewater treatment method and its design criteria considering different characteristics of the sea such as salinity, density, temperature, stratification etc. In addition, stagnant sea and thermal stratification is reviewed. In this paper the latest information were reviewed. In this alternative the wastewater treated under dilution, mixing and natural conditions. Moreover, sensitive coastal point are preserved from different wastewater pollutants. Usually, there is no limitation regarding discharge of coliform, DO, BOD, and nutrient concentrations in initial mixing zoom. The parameters such as thermal stratification, salinity stratification, density stratification, marine flows influence design of outfall.

  4. A benefit-cost methodology for developing environmental standards for uranium mill tailings disposal

    International Nuclear Information System (INIS)

    Leiter, A.J.

    1982-01-01

    This paper describes a method for using benefit-cost analysis in developing generally applicable environmental standards for uranium mill tailings disposal. Several disposal alternatives were selected which consist of different combinations of control measures. The resulting cost and benefit estimations allow the calculation of the incremental cost of obtaining incremental benefits of radiation protection. The overall benefit of a disposal alternative is expressed in terms of an index which is based on weighting factors assigned to individual benefits. The results show that some disposal alternatives have higher costs while providing no additional benefit than other alternatives. These alternatives should be eliminated from consideration in developing standards

  5. Licensing of alternative methods of disposal of low-level radioactive waste: Branch technical position, Low-Level Waste Licensing Branch

    International Nuclear Information System (INIS)

    Higginbotham, L.B.; Dragonette, K.S.; Pittiglio, C.L. Jr.

    1986-12-01

    This branch technical position statement identifies and describes specific methods of disposal currently being considered as alternatives to shallow land burial, provides general guidance on these methods of disposal, and recommends procedures that will improve and simplify the licensing process. The statement provides answers to certain questions that have arisen regarding the applicability of 10 CFR 61 to near-surface disposal of waste, using methods that incorporate engineered barriers or structures, and other alternatives to conventional shallow land burial disposal practices. This position also identifies a recently published NRC contractor report that addresses the applicability of 10 CFR 61 to a range of generic disposal concepts and which provides technical guidance that the staff intends to use for these concepts. This position statement combined with the above-mentioned NRC contractor report fulfills the requirements of Section 8(a) of Public Law 99-240, the Low-Level Radioactive Waste Policy Amendments Act of 1985

  6. Salt formations offer disposal alternative

    International Nuclear Information System (INIS)

    Funderburk, R.

    1990-01-01

    This paper discusses how three U.S. firms are spending millions to permit and build underground disposal sites in salt formations. These companies claim salt is the ideal geological medium for holding hazardous wastes. Two Texas locations and one in Michigan have been targeted as future sites for hazardous waste disposal. The Michigan site, outside Detroit, is a former salt mine 2,000 feet beneath the Ford Motor Co. (Detroit) assembly works in Dearborn. Both Texas sites are atop salt domes---one east and one west of Houston

  7. Overview of nuclear waste disposal in space

    International Nuclear Information System (INIS)

    Rice, E.E.; Priest, C.C.

    1981-01-01

    One option receiving consideration by the Department of Energy (DOE) is the space disposal of certain high-level nuclear wastes. The National Aeronautics and Space Administration is assessing the space disposal option in support of DOE studies on alternatives for nuclear waste management. The space disposal option is viewed as a complement, since total disposal of fuel rods from commercial power plants is not considered to be economically practical with Space Shuttle technology. The space disposal of certain high-level wastes may, however, provide reduced calculated and perceived risks. The space disposal option in conjunction with terrestrial disposal may offer a more flexible and lower risk overall waste management system. For the space disposal option to be viable, it must be demonstrated that the overall long-term risks associated with this activity, as a complement to the mined geologic repository, would be significantly less than the long-term risk associated with disposing of all the high-level waste. The long-term risk benefit must be achieved within an acceptable short-term and overall program cost. This paper briefly describes space disposal alternatives, the space disposal destination, possible waste mixes and forms, systems and typical operations, and the energy and cost analysis

  8. FUNDING ALTERNATIVES FOR LOW-LEVEL WASTE DISPOSAL

    International Nuclear Information System (INIS)

    Becker, Bruce D.; Carilli, Jhon

    2003-01-01

    For 13 years, low-level waste (LLW) generator fees and disposal volumes for the U.S. Department of Energy (DOE) National Nuclear Security Administration Nevada Operations Office (NNSA/NV) Radioactive Waste Management Sites (RWMSs) had been on a veritable roller coaster ride. As forecast volumes and disposal volumes fluctuated wildly, generator fees were difficult to determine and implement. Fiscal Year (FY) 2000 forecast projections were so low, the very existence of disposal operations at the Nevada Test Site (NTS) were threatened. Providing the DOE Complex with a viable, cost-effective disposal option, while assuring the disposal site a stable source of funding, became the driving force behind the development of the Waste Generator Access Fee at the NTS. On September 26, 2000, NNSA/NV (after seeking input from DOE/Headquarters [HQ]), granted permission to Bechtel Nevada (BN) to implement the Access Fee for FY 2001 as a two-year Pilot Program. In FY 2001 (the first year the Access Fee was implemented), the NTS Disposal Operations experienced a 90 percent increase in waste receipts from the previous year and a 33 percent reduction in disposal fee charged to the waste generators. Waste receipts for FY 2002 were projected to be 63 percent higher than FY 2001 and 15 percent lower in cost. Forecast data for the outyears are just as promising. This paper describes the development, implementation, and ultimate success of this fee strategy

  9. Preliminary assessment of the performance of concrete as a structural material for alternative low-level radioactive waste disposal technologies

    International Nuclear Information System (INIS)

    MacKenzie, D.R.; Siskind, B.; Bowerman, B.S.; Piciulo, P.L.

    1986-12-01

    The objective of this study was to develop information needed to evaluate the long-term performance of concrete and reinforced concrete as a structural material for alternative LLW disposal methods. The capability to carry out such an evaluation is required for licensing a site which employs one of these alternative methods. The basis for achieving the study objective was the review and analysis of the literature on concrete and its properties, particularly its durability. In carrying out this program, criteria for evaluating performance of concrete and factors that can effect its performance were identified. The factors are both intrinsic, i.e., associated with composition of the concrete (and thus controllable), and extrinsic, i.e., due to external environmental forces such as climatic conditions and aggressive chemicals in the soil. A section of the report is devoted to the properties of coatings and their possible use in protecting concrete from chemical attack and enhancing its useful properties. The testing of concrete, using both accelerated tests and long-term non-accelerated tests, is discussed with special reference to its application to modeling of long-term performance prediction. On the basis of the study's results, minimum acceptance criteria are recommended as an aid in the licensing of disposal sites which make sure use of alternative methods

  10. Waste association in mass for coating formulations: a viable alternative to dispose

    International Nuclear Information System (INIS)

    Ferreira, E.A.C.; Soares Filho, J.E.; Souza, F.J.P.; Almeida, V.S. de; Oliveira, T.M. de

    2016-01-01

    The ceramic coatings industries are able to use in their formulations whose waste Eco disposal make the costly disposal, being able to reduce production costs by replacing traditional inputs for mining and industrial waste. Their raw materials are classified as plasticizers, fluxes and structural according to their physicochemical characteristics. Since waste falls within these classifications, their use in formulations becomes a viable and attractive alternative from an ecological point of view and marketing. Several studies have attested to waste incorporating viability porcelains formulations, however, is not common to find studies evaluating the addition of more than one simultaneously in formulations. It is the objective of the study, to examine whether fine waste rock and kaolin together with traditional raw materials are able to produce porcelain wet as technological properties defined by the NBR-13818. (author)

  11. Hanford grout disposal program - an environmentally sound alternative

    International Nuclear Information System (INIS)

    Bergman, T.B.; Allison, J.M.

    1987-01-01

    The Hanford Grout Disposal Program (HGDP) is a comprehensive, integrated program to develop technology and facilities for the disposal of ∼ 3.0 x 10 5 m 3 (80 million gal) of the low-level fraction of liquid radioactive tank wastes at the Hanford site in southeastern Washington state. Environmentally sound disposal via long-term protection of the public and the environment is the principal goal of the HGDP. To accomplish this goal, several criteria have been established that guide technology and facility development activities. The key criteria are discussed. To meet the challenges posed by disposal of these wastes, the HGDP is developing a waste form using grout-forming materials, such as blast furnace slag, fly ash, clays, and Portland cement for solidification and immobilization of both the radioactive and hazardous chemical constituents. In addition to development of a final waste form, the HGDP is also developing a unique disposal system to assure long-term protection of the public and the environment. Disposal of a low-level nonhazardous waste will be initiated, as a demonstration of the disposal system concept, in June 1988. Disposal of higher activity hazardous wastes is scheduled to begin in October 1989

  12. Economics of a small-volume low-level radioactive waste disposal facility

    International Nuclear Information System (INIS)

    1993-04-01

    This report was prepared by the US Department of Energy National Low-Level Waste Management Program to present the results of a life-cycle cost analysis of a low-level radioactive waste disposal facility, including all support facilities, beginning in the preoperational phase and continuing through post-closure care. The disposal technology selected for this report is earth-covered concrete vaults, which use reinforced concrete vaults constructed above grade and an earth cover constructed at the end of the operational period for permanent closure. The report develops a design, cost estimate, and schedule for the base case and eight alternative scenarios involving changes in total disposal capacity, operating life, annual disposal rate, source of financing and long-term interest rates. The purpose of this analysis of alternatives is to determine the sensitivity of cost to changes in key analytical or technical parameters, thereby evaluating the influence of a broad range of conditions. The total estimated cost of each alternative is estimated and a unit disposal charge is developed

  13. De minimis applications for alternative disposal of very low level radioactive waste at Duke Power Company

    International Nuclear Information System (INIS)

    Lan, C.

    1986-01-01

    Existing NRC regulations provide no minimum level of radioactivity in waste from a licensee's facility that may be disposed of in a manner other than as radioactive waste. With one exception, in 10CFRsection20.306, licensees may dispose of certain levels of tritium and carbon-14 in liquid-scintillation and animal-carcass waste without regard to its radioactivity. In the interim, before specific or generic provisions for disposing of very low level radioactive wastes are adopted through rule making, licensees have another alternative for obtaining approval to dispose of large volumes of materials contaminated with very low levels of radioactivity under provision 10CFRsection20.302(a) ''Method for obtaining approval of proposed disposal procedures.'' This paper provides the experiences of obtaining both NRC and states (North Carolina and South Carolina) approval for disposing of very low-level radioactive wastes from Duke Power Company's nuclear stations. The approved disposal procedures include landfarming of water treatment residues, on-site disposal (burial) of sand and feedwater heaters, and include offsite release for treatment and disposal of sanitary sewage sludge. In summary, users of radioactive materials should not exclude this approach in their quest to reduce the volume of radioactive waste. It is expected that such submittals could provide a data base for further development of generic limits for radioactive wastes

  14. Waste-Mixes Study for space disposal

    International Nuclear Information System (INIS)

    McCallum, R.F.; Blair, H.T.; McKee, R.W.; Silviera, D.J.; Swanson, J.L.

    1983-01-01

    The Wastes Mixes Study is a component of Cy-1981 and 1982 research activities to determine if space disposal could be a feasible complement to geologic disposal for certain high-level (HLW) and transuranic wastes (TRU). The objectives of the study are: to determine if removal of radionuclides from HLW and TRU significantly reduces the long-term radiological risks of geologic disposal; to determine if chemical partitioning of the waste for space disposal is technically feasible; to identify acceptable waste forms for space disposal; and to compare improvements in geologic disposal system performance to impacts of additional treatment, storage, and transportation necessary for space disposal. To compare radiological effects, five system alternatives are defined: Reference case - All HLW and TRU to a repository. Alternative A - Iodine to space, the balance to a repository. Alternative B - Technetium to space, the balance to a repository. Alternative C - 95% of cesium and strontium to a repository; the balance of HLW aged first, then to space; plutonium separated from TRU for recycle; the balance of the TRU to a repository. Alternative D - HLW aged first, then to space, plutonium separated from TRU for recycle; the balance of the TRU to a repository. The conclusions of this study are: the incentive for space disposal is that it offers a perception of reduced risks rather than significant reduction. Suitable waste forms for space disposal are cermet for HLW, metallic technetium, and lead iodide. Space disposal of HLW appears to offer insignificant safety enhancements when compared to geologic disposal; the disposal of iodine and technetium wastes in space does not offer risk advantages. Increases in short-term doses for the alternatives are minimal; however, incremental costs of treating, storing and transporting wastes for space disposal are substantial

  15. A preliminary analysis of the reactor-based plutonium disposition alternative deployment schedules

    International Nuclear Information System (INIS)

    Zurn, R.M.

    1997-09-01

    This paper discusses the preliminary analysis of the implementation schedules of the reactor-based plutonium disposition alternatives. These schedule analyses are a part of a larger process to examine the nine decision criteria used to determine the most appropriate method of disposing of U.S. surplus weapons plutonium. The preliminary analysis indicates that the mission durations for the reactor-based alternatives range from eleven years to eighteen years and the initial mission fuel assemblies containing surplus weapons-usable plutonium could be loaded into the reactors between nine and fourteen years after the Record of Decision

  16. Key Factors to Determine the Borehole Spacing in a Deep Borehole Disposal for HLW

    International Nuclear Information System (INIS)

    Lee, Jongyoul; Choi, Heuijoo; Lee, Minsoo; Kim, Geonyoung; Kim, Kyeongsoo

    2015-01-01

    Deep fluids also resist vertical movement because they are density stratified and reducing conditions will sharply limit solubility of most dose critical radionuclides at the depth. Finally, high ionic strengths of deep fluids will prevent colloidal transport. Therefore, as an alternative disposal concept, i.e., deep borehole disposal technology is under consideration in number of countries in terms of its outstanding safety and cost effectiveness. In this paper, the general concept for deep borehole disposal of spent fuels or high level radioactive wastes which has been developed by some countries according to the rapid advance in the development of drilling technology, as an alternative method to the deep geological disposal method, was reviewed. After then an analysis on key factors for the distance between boreholes for the disposal of HLW was carried out. In this paper, the general concept for deep borehole disposal of spent fuels or HLW wastes, as an alternative method to the deep geological disposal method, were reviewed. After then an analysis on key factors for the determining the distance between boreholes for the disposal of HLW was carried out. These results can be used for the development of the HLW deep borehole disposal system

  17. Key Factors to Determine the Borehole Spacing in a Deep Borehole Disposal for HLW

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Jongyoul; Choi, Heuijoo; Lee, Minsoo; Kim, Geonyoung; Kim, Kyeongsoo [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2015-05-15

    Deep fluids also resist vertical movement because they are density stratified and reducing conditions will sharply limit solubility of most dose critical radionuclides at the depth. Finally, high ionic strengths of deep fluids will prevent colloidal transport. Therefore, as an alternative disposal concept, i.e., deep borehole disposal technology is under consideration in number of countries in terms of its outstanding safety and cost effectiveness. In this paper, the general concept for deep borehole disposal of spent fuels or high level radioactive wastes which has been developed by some countries according to the rapid advance in the development of drilling technology, as an alternative method to the deep geological disposal method, was reviewed. After then an analysis on key factors for the distance between boreholes for the disposal of HLW was carried out. In this paper, the general concept for deep borehole disposal of spent fuels or HLW wastes, as an alternative method to the deep geological disposal method, were reviewed. After then an analysis on key factors for the determining the distance between boreholes for the disposal of HLW was carried out. These results can be used for the development of the HLW deep borehole disposal system.

  18. DESIGN ANALYSIS FOR THE DEFENSE HIGH-LEVEL WASTE DISPOSAL CONTAINER

    International Nuclear Information System (INIS)

    Radulesscu, G.; Tang, J.S.

    2000-01-01

    The purpose of ''Design Analysis for the Defense High-Level Waste Disposal Container'' analysis is to technically define the defense high-level waste (DHLW) disposal container/waste package using the Waste Package Department's (WPD) design methods, as documented in ''Waste Package Design Methodology Report'' (CRWMS M andO [Civilian Radioactive Waste Management System Management and Operating Contractor] 2000a). The DHLW disposal container is intended for disposal of commercial high-level waste (HLW) and DHLW (including immobilized plutonium waste forms), placed within disposable canisters. The U.S. Department of Energy (DOE)-managed spent nuclear fuel (SNF) in disposable canisters may also be placed in a DHLW disposal container along with HLW forms. The objective of this analysis is to demonstrate that the DHLW disposal container/waste package satisfies the project requirements, as embodied in Defense High Level Waste Disposal Container System Description Document (SDD) (CRWMS M andO 1999a), and additional criteria, as identified in Waste Package Design Sensitivity Report (CRWMS M andQ 2000b, Table 4). The analysis briefly describes the analytical methods appropriate for the design of the DHLW disposal contained waste package, and summarizes the results of the calculations that illustrate the analytical methods. However, the analysis is limited to the calculations selected for the DHLW disposal container in support of the Site Recommendation (SR) (CRWMS M andO 2000b, Section 7). The scope of this analysis is restricted to the design of the codisposal waste package of the Savannah River Site (SRS) DHLW glass canisters and the Training, Research, Isotopes General Atomics (TRIGA) SNF loaded in a short 18-in.-outer diameter (OD) DOE standardized SNF canister. This waste package is representative of the waste packages that consist of the DHLW disposal container, the DHLW/HLW glass canisters, and the DOE-managed SNF in disposable canisters. The intended use of this

  19. DESIGN ANALYSIS FOR THE DEFENSE HIGH-LEVEL WASTE DISPOSAL CONTAINER

    Energy Technology Data Exchange (ETDEWEB)

    G. Radulesscu; J.S. Tang

    2000-06-07

    The purpose of ''Design Analysis for the Defense High-Level Waste Disposal Container'' analysis is to technically define the defense high-level waste (DHLW) disposal container/waste package using the Waste Package Department's (WPD) design methods, as documented in ''Waste Package Design Methodology Report'' (CRWMS M&O [Civilian Radioactive Waste Management System Management and Operating Contractor] 2000a). The DHLW disposal container is intended for disposal of commercial high-level waste (HLW) and DHLW (including immobilized plutonium waste forms), placed within disposable canisters. The U.S. Department of Energy (DOE)-managed spent nuclear fuel (SNF) in disposable canisters may also be placed in a DHLW disposal container along with HLW forms. The objective of this analysis is to demonstrate that the DHLW disposal container/waste package satisfies the project requirements, as embodied in Defense High Level Waste Disposal Container System Description Document (SDD) (CRWMS M&O 1999a), and additional criteria, as identified in Waste Package Design Sensitivity Report (CRWMS M&Q 2000b, Table 4). The analysis briefly describes the analytical methods appropriate for the design of the DHLW disposal contained waste package, and summarizes the results of the calculations that illustrate the analytical methods. However, the analysis is limited to the calculations selected for the DHLW disposal container in support of the Site Recommendation (SR) (CRWMS M&O 2000b, Section 7). The scope of this analysis is restricted to the design of the codisposal waste package of the Savannah River Site (SRS) DHLW glass canisters and the Training, Research, Isotopes General Atomics (TRIGA) SNF loaded in a short 18-in.-outer diameter (OD) DOE standardized SNF canister. This waste package is representative of the waste packages that consist of the DHLW disposal container, the DHLW/HLW glass canisters, and the DOE-managed SNF in disposable

  20. A multi-attribute utility decision analysis for treatment alternatives for the DOE/SR aluminum-based spent nuclear fuel

    International Nuclear Information System (INIS)

    Davis, Freddie J.; Weiner, Ruth Fleischman; Wheeler, Timothy A.; Sorenson, Ken B.; Kuzio, Kenneth A.

    2000-01-01

    A multi-attribute utility analysis is applied to a decision process to select a treatment method for the management of aluminum-based spent nuclear fuel (Al-SNF) owned by the US Department of Energy (DOE). DOE will receive, treat, and temporarily store Al-SNF, most of which is composed of highly enriched uranium, at its Savannah River Site in South Carolina. DOE intends ultimately to send the treated Al-SNF to a geologic repository for permanent disposal. DOE initially considered ten treatment alternatives for the management of Al-SNF, and has narrowed the choice to two of these: the direct disposal and melt and dilute alternatives. The decision analysis presented in this document focuses on a formal decision process used to evaluate these two remaining alternatives

  1. Siting Study for the Remote-Handled Low-Level Waste Disposal Project

    Energy Technology Data Exchange (ETDEWEB)

    Lisa Harvego; Joan Connolly; Lance Peterson; Brennon Orr; Bob Starr

    2010-10-01

    The U.S. Department of Energy has identified a mission need for continued disposal capacity for remote-handled low-level waste (LLW) generated at the Idaho National Laboratory (INL). An alternatives analysis that was conducted to evaluate strategies to achieve this mission need identified two broad options for disposal of INL generated remote-handled LLW: (1) offsite disposal and (2) onsite disposal. The purpose of this study is to identify candidate sites or locations within INL boundaries for the alternative of an onsite remote handled LLW disposal facility and recommend the highest-ranked locations for consideration in the National Environmental Policy Act process. The study implements an evaluation based on consideration of five key elements: (1) regulations, (2) key assumptions, (3) conceptual design, (4) facility performance, and (5) previous INL siting study criteria, and uses a five-step process to identify, screen, evaluate, score, and rank 34 separate sites located across INL. The result of the evaluation is identification of two recommended alternative locations for siting an onsite remote-handled LLW disposal facility. The two alternative locations that best meet the evaluation criteria are (1) near the Advanced Test Reactor Complex and (2) west of the Idaho Comprehensive Environmental Response, Compensation, and Liability Act Disposal Facility.

  2. Analysis of the technical capabilities of DOE sites for disposal of residuals from the treatment of mixed low-level waste

    International Nuclear Information System (INIS)

    Waters, R.D.; Gruebel, M.M.; Langkopf, B.S.; Kuehne, P.B.

    1997-04-01

    The US Department of Energy (DOE) has stored or expects to generate over the next five years more than 130,000 m 3 of mixed low-level waste (MLLW). Before disposal, MLLW is usually treated to comply with the land disposal restrictions of the Resource Conservation and Recovery Act. Depending on the type of treatment, the original volume of MLLW and the radionuclide concentrations in the waste streams may change. These changes must be taken into account in determining the necessary disposal capacity at a site. Treatment may remove the characteristic in some waste that caused it to be classified as mixed. Treatment of some waste may, by reduction of the mass, increase the concentrations of some transuranic radionuclides sufficiently so that it becomes transuranic waste. In this report, the DOE MLLW streams were analyzed to determine after-treatment volumes and radionuclide concentrations. The waste streams were reclassified as residual MLLW or low-level or transuranic waste resulting from treatment. The volume analysis indicated that about 89,000 m 3 of waste will require disposal as residual MLLW. Fifteen DOE sites were then evaluated to determine their capabilities for hosting disposal facilities for some or all of the residual MLLW. Waste streams associated with about 90% of the total residual MLLW volume are likely to present no significant issues for disposal and require little additional analysis. Future studies should focus on the remaining waste streams that are potentially problematic by examining site-specific waste acceptance criteria, alternative treatment processes, alternative waste forms for disposal, and pending changes in regulatory requirements

  3. The disposal of Canada's nuclear fuel waste: engineering for a disposal facility

    International Nuclear Information System (INIS)

    Simmons, G.R.; Baumgartner, P.

    1994-01-01

    This report presents some general considerations for engineering a nuclear fuel waste disposal facility, alternative disposal-vault concepts and arrangements, and a conceptual design of a used-fuel disposal centre that was used to assess the technical feasibility, costs and potential effects of disposal. The general considerations and alternative disposal-vault arrangements are presented to show that options are available to allow the design to be adapted to actual site conditions. The conceptual design for a used-fuel disposal centre includes descriptions of the two major components of the disposal facility, the Used-Fuel Packaging Plant and the disposal vault; the ancillary facilities and services needed to carry out the operations are also identified. The development of the disposal facility, its operation, its decommissioning, and the reclamation of the site are discussed. The costs, labour requirements and schedules used to assess socioeconomic effects and that may be used to assess the cost burden of waste disposal to the consumer of nuclear energy are estimated. The Canadian Nuclear Fuel Waste Management Program is funded jointly by AECL and Ontario Hydro under the auspices of the CANDU Owners Group. (author)

  4. Life-cycle cost analysis for Foreign Research Reactor, Spent Nuclear Fuel disposal

    International Nuclear Information System (INIS)

    Parks, P.B.; Geddes, R.L.; Jackson, W.N.; McDonell, W.R.; Dupont, M.E.; McWhorter, D.L.; Liutkus, A.S.

    1994-01-01

    DOE-EM-37 requested a life-cycle cost analysis for disposal of the Foreign Research Reactor-Spent Nuclear Fuel (FRR-SNF). The analysis was to address life-cycle and unit costs for a range of FRR-SNF elements from those currently available (6,000 elements) to the (then) bounding case (15,000 elements). Five alternative disposition strategies were devised for the FRR-SNF elements. Life-cycle costs were computed for each strategy. In addition, the five strategies were evaluated in terms of six societal and technical goals. This report summarizes the study that was originally documented to DOE-EM

  5. Selection of infectious medical waste disposal firms by using the analytic hierarchy process and sensitivity analysis

    International Nuclear Information System (INIS)

    Hsu, P.-F.; Wu, C.-R.; Li, Y.-T.

    2008-01-01

    While Taiwanese hospitals dispose of large amounts of medical waste to ensure sanitation and personal hygiene, doing so inefficiently creates potential environmental hazards and increases operational expenses. However, hospitals lack objective criteria to select the most appropriate waste disposal firm and evaluate its performance, instead relying on their own subjective judgment and previous experiences. Therefore, this work presents an analytic hierarchy process (AHP) method to objectively select medical waste disposal firms based on the results of interviews with experts in the field, thus reducing overhead costs and enhancing medical waste management. An appropriate weight criterion based on AHP is derived to assess the effectiveness of medical waste disposal firms. The proposed AHP-based method offers a more efficient and precise means of selecting medical waste firms than subjective assessment methods do, thus reducing the potential risks for hospitals. Analysis results indicate that the medical sector selects the most appropriate infectious medical waste disposal firm based on the following rank: matching degree, contractor's qualifications, contractor's service capability, contractor's equipment and economic factors. By providing hospitals with an effective means of evaluating medical waste disposal firms, the proposed AHP method can reduce overhead costs and enable medical waste management to understand the market demand in the health sector. Moreover, performed through use of Expert Choice software, sensitivity analysis can survey the criterion weight of the degree of influence with an alternative hierarchy

  6. Waste disposal: preliminary studies

    International Nuclear Information System (INIS)

    Carvalho, J.F. de.

    1983-01-01

    The problem of high level radioactive waste disposal is analyzed, suggesting an alternative for the final waste disposal from irradiated fuel elements. A methodology for determining the temperature field around an underground disposal facility is presented. (E.G.) [pt

  7. Composite analysis E-area vaults and saltstone disposal facilities

    Energy Technology Data Exchange (ETDEWEB)

    Cook, J.R.

    1997-09-01

    This report documents the Composite Analysis (CA) performed on the two active Savannah River Site (SRS) low-level radioactive waste (LLW) disposal facilities. The facilities are the Z-Area Saltstone Disposal Facility and the E-Area Vaults (EAV) Disposal Facility. The analysis calculated potential releases to the environment from all sources of residual radioactive material expected to remain in the General Separations Area (GSA). The GSA is the central part of SRS and contains all of the waste disposal facilities, chemical separations facilities and associated high-level waste storage facilities as well as numerous other sources of radioactive material. The analysis considered 114 potential sources of radioactive material containing 115 radionuclides. The results of the CA clearly indicate that continued disposal of low-level waste in the saltstone and EAV facilities, consistent with their respective radiological performance assessments, will have no adverse impact on future members of the public.

  8. Composite analysis E-area vaults and saltstone disposal facilities

    International Nuclear Information System (INIS)

    Cook, J.R.

    1997-09-01

    This report documents the Composite Analysis (CA) performed on the two active Savannah River Site (SRS) low-level radioactive waste (LLW) disposal facilities. The facilities are the Z-Area Saltstone Disposal Facility and the E-Area Vaults (EAV) Disposal Facility. The analysis calculated potential releases to the environment from all sources of residual radioactive material expected to remain in the General Separations Area (GSA). The GSA is the central part of SRS and contains all of the waste disposal facilities, chemical separations facilities and associated high-level waste storage facilities as well as numerous other sources of radioactive material. The analysis considered 114 potential sources of radioactive material containing 115 radionuclides. The results of the CA clearly indicate that continued disposal of low-level waste in the saltstone and EAV facilities, consistent with their respective radiological performance assessments, will have no adverse impact on future members of the public

  9. Results of the German alternative fuel cycle evaluation and further efforts geared toward demonstration of direct disposal

    International Nuclear Information System (INIS)

    Papp, R.; Closs, K.D.

    1986-01-01

    In a comparative study initiated by the German Federal Ministry for Research and Technology which was carried out by Karlsruhe Nuclear Research Center in the period from 1981 to 1985, direct disposal of spent fuel was contrasted to the traditional fuel cycle with reprocessing and recycle. The results of the study did not exhibit decisive advantages of direct disposal over fuel reprocessing. Due to this face and legal requirements of the German Atomic Energy Act, the cabinet concluded to continue to adhere to fuel reprocessing as the preferred version of ''Entsorgung''. But the door was left ajar for the direct disposal alternative that, under present atomic law, is permissible for fuel for which reprocessing is neither technically feasible nor economically justified. An ambitious program has been launched in the Federal Republic of Germany (FRG), geared to bring direct disposal to a point of technical maturity

  10. Efficiency analyses of the CANDU spent fuel repository using modified disposal canisters for a deep geological disposal system design

    International Nuclear Information System (INIS)

    Lee, J.Y.; Cho, D.K.; Lee, M.S.; Kook, D.H.; Choi, H.J.; Choi, J.W.; Wang, L.M.

    2012-01-01

    Highlights: ► A reference disposal concept for spent nuclear fuels in Korea has been reviewed. ► To enhance the disposal efficiency, alternative disposal concepts were developed. ► Thermal analyses for alternative disposal concepts were performed. ► From the result of the analyses, the disposal efficiency of the concepts was reviewed. ► The most effective concept was suggested. - Abstract: Deep geological disposal concept is considered to be the most preferable for isolating high-level radioactive waste (HLW), including nuclear spent fuels, from the biosphere in a safe manner. The purpose of deep geological disposal of HLW is to isolate radioactive waste and to inhibit its release of for a long time, so that its toxicity does not affect the human beings and the biosphere. One of the most important requirements of HLW repository design for a deep geological disposal system is to keep the buffer temperature below 100 °C in order to maintain the integrity of the engineered barrier system. In this study, a reference disposal concept for spent nuclear fuels in Korea has been reviewed, and based on this concept, efficient alternative concepts that consider modified CANDU spent fuels disposal canister, were developed. To meet the thermal requirement of the disposal system, the spacing of the disposal tunnels and that of the disposal pits for each alternative concept, were drawn following heat transfer analyses. From the result of the thermal analyses, the disposal efficiency of the alternative concepts was reviewed and the most effective concept suggested. The results of these analyses can be used for a deep geological repository design and detailed analyses, based on exact site characteristics data, will reduce the uncertainty of the results.

  11. Biomass of tomorrow: Banknotes. Two new disposal methods as an alternative to combustion. Die Biomasse von morgen: Banknoten. Zwei neue Verwertungsverfahren als Alternative zur Verbrennung

    Energy Technology Data Exchange (ETDEWEB)

    Franken, M.

    1999-06-01

    Old banknotes may be tomorrow's biomass. Experts on biowaste are investigating two new processes for disposal of the 1000 tonnes of old bills sorted out every year which may be an alternative to combustion. The author presents details.

  12. Engineering Evaluation/Cost Analysis for Power Burst Facility (PER-620) Final End State and PBF Vessel Disposal

    Energy Technology Data Exchange (ETDEWEB)

    B. C. Culp

    2007-05-01

    Preparation of this engineering evaluation/cost analysis is consistent with the joint U.S. Department of Energy and U.S. Environmental Protection Agency Policy on Decommissioning of Department of Energy Facilities Under the Comprehensive Environmental Response, Compensation, and Liability Act, (DOE and EPA 1995) which establishes the Comprehensive Environmental, Response, Compensation, and Liability Act non-time critical removal action process as an approach for decommissioning. The scope of this engineering evaluation/cost analysis is to evaluate alternatives and recommend a preferred alternative for the final end state of the PBF and the final disposal location for the PBF vessel.

  13. Safety analysis of disposal of spent nuclear fuel

    International Nuclear Information System (INIS)

    Vieno, T.

    1994-04-01

    The spent fuel from the Olkiluoto NPP (TVO I and II) is planned to be disposed of in a repository to be constructed at a depth of about 500 meters in the crystalline bedrock. The thesis is dealing with the safety analysis of the disposal. The main topics presented in the thesis are: (1) The amount of radioactive properties of the spent fuel, (2) The canister design and the planned disposal concept, (3) The results of the preliminary site investigations, (4) Discussion of the multi-barrier principle, (5) The general principles and methodology of the TVO-92 safety analysis, (6) Groundwater flow analysis, (7) Durability and behaviour of the canister, (8) Biosphere analysis and reference scenario, and (9) The sensitivity and uncertainty analyses. (246 refs., 75 figs., 44 tabs.)

  14. Preliminary study of radioactive waste disposal in granitic underground caves

    International Nuclear Information System (INIS)

    Carvalho, J.F. de; Carajilescov, P.

    1984-01-01

    To date, the disposal of radioactive wastes is one of the major problems faced by the nuclear industry. The utilization of granitic underground caves surrounded by a clay envelope is suggested as a safe alternative for such disposal. A preliminary analysis of the dimensions of those deposits is done. (Author) [pt

  15. Modeling of a sedimentary rock alternative for the siting of the radioactive waste disposal system

    International Nuclear Information System (INIS)

    Fuentes, Nestor O.

    2007-01-01

    Here are described the main concepts, the approximations, and all those simulation aspects that characterize the modeling performed using the unsaturated saturated approach for porous media. The objective of this work is to obtain a generic description of a sedimentary rock soil as an alternative site for the low and intermediate level radioactive waste disposal system. (author) [es

  16. 2005 dossier: granite. Tome: safety analysis of the geologic disposal

    International Nuclear Information System (INIS)

    2005-01-01

    This document makes a status of the researches carried out by the French national agency of radioactive wastes (ANDRA) about the safety aspects of the geologic disposal of high-level and long-lived (HLLL) radioactive wastes in granite formations. Content: 1 - safety approach: context and general goal, references, design approach by safety functions, safety approach during the construction-exploitation-observation-closure phase, safety analysis during the post-closure phase; 2 - general description: HLLL wastes, granitic environment, general structure of the architecture of a disposal facility; 3 - safety functions and disposal design: general context, safety functions of the long-term disposal, design dispositions retained to answer the functions; 4 - operational safety: people's protection, radiological risks during exploitation, risk analysis in accident situation; 5 - qualitative safety analysis: methodology, main results of the analysis of the features, events and processes (FEP) database; 6 - disposal efficiency evaluation during post-closure phase: calculation models, calculation tools used for the modeling of radionuclides transport, calculation results and main lessons. (J.S.)

  17. Radwaste Disposal Safety Analysis

    International Nuclear Information System (INIS)

    Hwang, Yong Soo; Kang, C. H.; Lee, Y. M.; Lee, S. H.; Jeong, J. T.; Choi, J. W.; Park, S. W.; Lee, H. S.; Kim, J. H.; Jeong, M. S.

    2010-02-01

    For the purpose of evaluating annual individual doses from a potential repository disposing of radioactive wastes from the operation of the prospective advanced nuclear fuel cycle facilities in Korea, the new safety assessment approaches are developed such as PID methods. The existing KAERI FEP list was reviewed. Based on these new reference and alternative scenarios are developed along with a new code based on the Goldsim. The code based on the compartment theory can be applied to assess both normal and what if scenarios. In addition detailed studies on THRC coupling is studied. The oriental biosphere study ends with great success over the completion of code V and V with JAEA. The further development of quality assurance, in the form of the CYPRUS+ enables handy use of it for information management

  18. Eco-efficiency analysis of techniques for disposal of urban solid waste

    International Nuclear Information System (INIS)

    Dmitrijevas, Cibele

    2010-01-01

    Municipal solid waste is one of the major problems of modern society. In this sense it is necessary to discuss solutions to the fate of waste generated daily, increasingly in larger amounts, being imperative to advance the search for alternatives, not only in search of new technologies and solutions, as well as the improvement of methodologies currently employed to solve this relevant issue, especially in large urban centers. This paper presents the results of a comparative economic-environmental assessment performed by a method developed by BASF, two potential technologies: landfill and incineration with energy recovery. To facilitate the work, the information used were both real data - landfill and incinerator - Essencis Solucoes Ambientais S.A., (assuming some assumptions) and the use of secondary data, using the study of Arena et al., 2003. This ecoefficiency analysis tool covers the methodology of Life Cycle Assessment (LCA), which is a technique to evaluate the inputs and outputs of matter and energy and the potential environmental impacts associated with all stages of resource extraction and their transformations , and the use and final disposal of the product. The data in the environmental assessment are presented according to major categories, using a weighting method developed by BASF and understand the consumption of natural resources, consumption of energy resources, air emissions, water and soil, potential for human toxicity, accidents work, occupational diseases and land use. Economic evaluation in this work took into account the costs involved in operation and maintenance of disposal techniques or treatment of waste. The comparative study found the treatment or disposal of 7.324109 billion kilograms of waste. As a result, the array of eco-efficiency indicates that the incinerator is the alternative that stands out, considering the environmental and economic profile, within the assumptions made in this study and taking into account which is a

  19. Special waste disposal in Austria - cost benefit analysis

    International Nuclear Information System (INIS)

    Kuntscher, H.

    1983-01-01

    The present situation of special waste disposal in Austria is summarized for radioactive and nonradioactive wastes. A cost benefit analysis for regulary collection, transport and disposal of industrial wastes, especially chemical wastes is given and the cost burden for the industry is calculated. (A.N.)

  20. The disposal of orphan wastes using the greater confinement disposal concept

    International Nuclear Information System (INIS)

    Bonano, E.J.; Chu, M.S.Y.; Price, L.L.; Conrad, S.H.; Dickman, P.T.

    1991-01-01

    In the United States, radioactive wastes are conventionally classified as high-level wastes, transuranic wastes, or low-level wastes. Each of these types of wastes, by law, has a ''home'' for their final disposal; i.e., high-level wastes are destined for disposal at the proposed repository at Yucca Mountain, transuranic waste for the proposed Waste Isolation Pilot Plant, and low-level waste for shallow-land disposal sites. However, there are some radioactive wastes within the United States Department of Energy (DOE) complex that do not meet the criteria established for disposal of either high-level waste, transuranic waste, or low-level waste. The former are called ''special-case'' or ''orphan'' wastes. This paper describes an ongoing project sponsored by the DOE's Nevada Operations Office for the disposal of orphan wastes at the Radioactive Waste Management Site at Area 5 of the Nevada Test Site using the greater confinement disposal (GCD) concept. The objectives of the GCD project are to evaluate the safety of the site for disposal of orphan wastes by assessing compliance with pertinent regulations through performance assessment, and to examine the feasibility of this disposal concept as a cost-effective, safe alternative for management of orphan wastes within the DOE complex. Decisions on the use of GCD or other alternate disposal concepts for orphan wastes be expected to be addressed in a Programmatic Environmental Impact Statement being prepared by DOE. The ultimate decision to use GCD will require a Record of Decision through the National Environmental Policy Act (NEPA) process. 20 refs., 3 figs., 2 tabs

  1. Detailed analysis of a RCRA landfill for the United Nuclear Corporation Disposal Site at the Oak Ridge Y-12 Plant, Oak Ridge, Tennessee

    International Nuclear Information System (INIS)

    1991-04-01

    The purpose of this detailed analysis is to provide a preliminary compilation of data, information, and estimated costs associated with a RCRA landfill alternative for UNC Disposal Site. This is in response to Environmental Protection Agency (EPA) comment No. 6 from their review of a open-quotes Feasibility Study for the United Nuclear Corporation Disposal Site at the Oak Ridge Y-12 Plant, Oak Ridge, Tennessee.close quotes

  2. TVO-92 safety analysis of spent fuel disposal

    International Nuclear Information System (INIS)

    Vieno, T.; Hautojaervi, A.; Koskinen, L.; Nordman, H.

    1993-08-01

    The spent fuel from the TVO I and TVO II reactors at the Olkiluoto nuclear power plant is planned to be disposed in a repository constructed at a depth of about 500 meters in crystalline bedrock. Teollisuuden Voima Oy (TVO) has carried out preliminary site investigations for spent fuel disposal between 1987 and 1992 at five areas in Finland (Olkiluoto, Kivetty, Romuvaara, Syyry and Veitsivaara). The Safety analysis of the disposal system is presented in the report. Spent fuel will be encapsulated in composite copper-steel canisters. The canister design (ACP canister) consists of an inner container of steel as a load-bearing element and an outer container of oxygen-free copper to provide a shield against corrosion. In the repository the canisters will be emplaced in vertical holes drilled in the floors of horizontal deposition tunnels. The annulus between the canister and the rock is filled with compacted bentonite. The results of the safety analysis attest that the planned disposal system fulfils the safety requirements. Suitable places for the repository can be found at each of the five investigation sites

  3. Weak Disposability in Nonparametric Production Analysis with Undesirable Outputs

    NARCIS (Netherlands)

    Kuosmanen, T.K.

    2005-01-01

    Environmental Economics and Natural Resources Group at Wageningen University in The Netherlands Weak disposability of outputs means that firms can abate harmful emissions by decreasing the activity level. Modeling weak disposability in nonparametric production analysis has caused some confusion.

  4. Environmental control aspects for fabrication, reprocessing and waste disposal of alternative LWR and LMFBR fuels

    International Nuclear Information System (INIS)

    Nolan, A.M.; Lewallen, M.A.; McNair, G.W.

    1979-11-01

    Environmental control aspects of alternative fuel cycles have been analyzed by evaluating fabrication, reprocessing, and waste disposal operations. Various indices have been used to assess potential environmental control requirements. For the fabrication and reprocessing operations, 50-year dose commitments were used. Waste disposal was evaluated by comparing projected nuclide concentrations in ground water at various time periods with maximum permissible concentrations (MPCs). Three different fabrication plants were analyzed: a fuel fabrication plant (FFP) to produce low-activity uranium and uranium-thorium fuel rods; a plutonium fuel refabrication plant (PFRFP) to produce plutonium-uranium and plutonium-thorium fuel rods; and a uranium fuel refabrication plant (UFRFP) to produce fuel rods containing the high-activity isotopes 232 U and 233 U. Each plant's dose commitments are discussed separately. Source terms for the analysis of effluents from the fuel reprocessing plant (FRP) were calculated using the fuel burnup codes LEOPARD, CINDER and ORIGEN. Effluent quantities are estimated for each fuel type. Bedded salt was chosen for the waste repository analysis. The repository site is modeled on the Waste Isolation Pilot Program site in New Mexico. Wastes assumed to be stored in the repository include high-level vitrified waste from the FRP, packaged fuel residue from the FRP, and transuranic (TRU) contaminated wastes from the FFP, PFRFP, and UFRFP. The potential environmental significance was determined by estimating the ground-water concentrations of the various nuclides over a time span of a million years. The MPC for each nuclide was used along with the estimated ground-water concentration to generate a biohazard index for the comparison among fuel compositions

  5. 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

  6. Regional LLRW processing alternatives applying the DOE REGINALT systems analysis model

    International Nuclear Information System (INIS)

    Beers, G.H.

    1987-01-01

    The DOE Low-Level Waste Management Program has developed a computer-based decision support system of models that may be used by nonprogrammers to evaluate a comprehensive approach to commercial low-level radioactive waste (LLRW) management. REGINALT (Regional Waste Management Alternatives Analysis Model) implementation will be described as the model is applied to hypothetical regional compact for the purpose of examining the technical and economic potential of two waste processing alternatives. Using waste from a typical regional compact, two specific regional waste processing centers are compared for feasibility. Example 1 assumes that a regional supercompaction facility is being developed for the region. Example 2 assumes that a regional facility with both supercompaction and incineration is specified. Both examples include identical disposal facilities, except that capacity may differ due to variation in volume reduction achieved. The two examples are compared with regard to volume reduction achieved, estimated occupational exposure for the processing facilities, and life cycle costs per generated unit waste. A base case also illustrates current disposal practices. The results of the comparisons evaluated, and other steps, if necessary, for additional decision support are identified

  7. Disposal configuration options for future uses of greater confinement disposal at the Nevada Test Site

    International Nuclear Information System (INIS)

    Price, L.

    1994-09-01

    The US Department of Energy (DOE) is responsible for disposing of a variety of radioactive and mixed wastes, some of which are considered special-case waste because they do not currently have a clear disposal option. The DOE's Nevada Field Office contracted with Sandia National Laboratories to investigate the possibility of disposing of some of this special-case waste at the Nevada Test Site (NTS). As part of this investigation, a review of a near-surface and subsurface disposal options that was performed to develop alternative disposal configurations for special-case waste disposal at the NTS. The criteria for the review included (1) configurations appropriate for disposal at the NTS; (2) configurations for disposal of waste at least 100 ft below the ground surface; (3) configurations for which equipment and technology currently exist; and (4) configurations that meet the special requirements imposed by the nature of special-case waste. Four options for subsurface disposal of special-case waste are proposed: mined consolidated rock, mined alluvium, deep pits or trenches, and deep boreholes. Six different methods for near-surface disposal are also presented: earth-covered tumuli, above-grade concrete structures, trenches, below-grade concrete structures, shallow boreholes, and hydrofracture. Greater confinement disposal (GCD) in boreholes at least 100 ft deep, similar to that currently practiced at the GCD facility at the Area 5 Radioactive Waste Management Site at the NTS, was retained as the option that met the criteria for the review. Four borehole disposal configurations are proposed with engineered barriers that range from the native alluvium to a combination of gravel and concrete. The configurations identified will be used for system analysis that will be performed to determine the disposal configurations and wastes that may be suitable candidates for disposal of special-case wastes at the NTS

  8. Financing of radioactive waste disposal

    International Nuclear Information System (INIS)

    Reich, J.

    1989-01-01

    Waste disposal is modelled as a financial calculus. In this connection the particularity is not primarily the dimension to be expected of financial requirement but above all the uncertainty of financial requirement as well as the ecological, socio-economic and especially also the temporal dimension of the Nuclear Waste Disposal project (disposal of spent fuel elements from light-water reactors with and without reprocessing, decommissioning = safe containment and disposal of nuclear power plants, permanent isolation of radioactive waste from the biosphere, intermediate storage). Based on the above mentioned factors the author analyses alternative approaches of financing or financial planning. He points out the decisive significance of the perception of risks or the evaluation of risks by involved or affected persons - i.e. the social acceptance of planned and designed waste disposal concepts - for the achievement and assessment of alternative solutions. With the help of an acceptance-specific risk measure developed on the basis of a mathematical chaos theory he illustrates, in a model, the social influence on the financing of nuclear waste disposal. (orig./HP) [de

  9. A multi-criteria decision analysis of management alternatives for anaerobically digested kraft pulp mill sludge.

    Directory of Open Access Journals (Sweden)

    Martijn Eikelboom

    Full Text Available The Multi-Criteria Decision Analysis (MCDA procedure was used to compare waste management options for kraft pulp mill sludge following its anaerobic digestion. Anaerobic digestion of sludge is advantageous because it produces biogas that may be used to generate electricity, heat and biofuels. However, adequate management of the digested sludge is essential. Landfill disposal is a non-sustainable waste management alternative. Kraft pulp mill digested sludge applied to land may pose risks to the environment and public health if the sludge has not been properly treated. This study is aimed to compare several recycling alternatives for anaerobically digested sludge from kraft pulp mills: land application, landfill disposal, composting, incineration, pyrolysis/gasification, and biofuel production by algae. The MCDA procedure considered nine criteria into three domains to compare digested sludge recycling alternatives in a kraft pulp mill: environmental (CO2 emission, exposure to pathogens, risk of pollution, material and energy recovery, economic (overall costs, value of products and technical (maintenance and operation, feasibility of implementation. The most suitable management options for digested sludge from kraft pulp mills were found to be composting and incineration (when the latter was coupled with recycling ash to the cement industry. Landfill disposal was the worst option, presenting low performance in feasibility of implementation, risk of pollution, material and energy recovery.

  10. A multi-criteria decision analysis of management alternatives for anaerobically digested kraft pulp mill sludge

    Science.gov (United States)

    Eikelboom, Martijn; Lopes, Alice do Carmo Precci; Silva, Claudio Mudadu; Rodrigues, Fábio de Ávila; Zanuncio, José Cola

    2018-01-01

    The Multi-Criteria Decision Analysis (MCDA) procedure was used to compare waste management options for kraft pulp mill sludge following its anaerobic digestion. Anaerobic digestion of sludge is advantageous because it produces biogas that may be used to generate electricity, heat and biofuels. However, adequate management of the digested sludge is essential. Landfill disposal is a non-sustainable waste management alternative. Kraft pulp mill digested sludge applied to land may pose risks to the environment and public health if the sludge has not been properly treated. This study is aimed to compare several recycling alternatives for anaerobically digested sludge from kraft pulp mills: land application, landfill disposal, composting, incineration, pyrolysis/gasification, and biofuel production by algae. The MCDA procedure considered nine criteria into three domains to compare digested sludge recycling alternatives in a kraft pulp mill: environmental (CO2 emission, exposure to pathogens, risk of pollution, material and energy recovery), economic (overall costs, value of products) and technical (maintenance and operation, feasibility of implementation). The most suitable management options for digested sludge from kraft pulp mills were found to be composting and incineration (when the latter was coupled with recycling ash to the cement industry). Landfill disposal was the worst option, presenting low performance in feasibility of implementation, risk of pollution, material and energy recovery. PMID:29298296

  11. Risk analysis of geological disposal of radioactive waste

    International Nuclear Information System (INIS)

    Girardi, F.; de Marsily, G.; Weber, J.

    1980-01-01

    The problems of risk analysis of geological disposal of radioactive waste are briefly summarized. Several characteristics, such as the very long time span considered, make it rather unique among the problems of modern society. The safety of nuclear waste disposal in geological formations is based on several barriers, natural and man-made, which prevent disposed radionuclides from reaching the biosphere. They include a) the physico-chemical form of conditioned waste, b) the waste container, c) the geological isolation, d) buffering and backfilling materials, radionuclide retention in the geosphere and e) environmental dilution and isolation processes. The knowledge available on each barrier and its modelling is reviewed. Specific disposal strategies in clay, granite and salt formations are considered, outlining the performance of the barriers in each particular strategy, and results obtained in preliminary evaluations

  12. Incineration as a low-level radioactive waste disposal alternative for the very low level (approx. 200 mCi/yr) institutional waste generator

    International Nuclear Information System (INIS)

    Miller, S.D.

    1982-01-01

    As a result of increased shipping costs and decreased land availability, serious questions have arisen regarding the continued use of shallow land burial for disposal of institutional radioactive wastes. These factors are of special significance to very low-level waste generators such as Arizona State University whose most recent waste shipment averaged approximately 2 mCi per shipped barrel at an effective cost of over $100 per mCi disposed - a total cost of over $14,000. Recent studies have shown incineration to be an attractive waste disposal alternative both in terms of volume reduction of waste, and in its expected insignificant radiological and environmental impact. Arizona State University has purchased an incinerator and has initiated a program to incinerate radioactive wastes. Licensing restrictions involving stack monitoring for a variety of possibly hazardous effluents and 10CFR20 restrictions affecting incineration of certain isotopes could render the change to incineration completely inefficient unless accompanied by a rigorous program of waste segregation designed to ease licensing restrictions. This paper reviews incinerator technology as it applies to radioactive waste management and presents the analysis performed during the licensing phase, along with some of the difficulties inherent in the development process

  13. Alternative concepts for Low-Level Radioactive Waste Disposal: Conceptual design report

    International Nuclear Information System (INIS)

    1987-06-01

    This conceptual design report is provided by the Department of Energy's Nuclear Energy Low-Level Waste Management Program to assist states and compact regions in developing new low-level radioactive waste (LLW) disposal facilities in accordance with the Low-Level Radioactive Waste Policy Amendment Act of 1985. The report provides conceptual designs and evaluations of six widely considered concepts for LLW disposal. These are shallow land disposal (SLD), intermediate depth disposal (IDD), below-ground vaults (BGV), above-ground vaults (AGV), modular concrete canister disposal (MCCD), earth-mounded concrete bunker (EMCB). 40 refs., 45 figs., 77 tabs

  14. Alternative approaches to assessing the performance and suitability of Yucca Mountain for spent fuel disposal. Final report

    International Nuclear Information System (INIS)

    McGuire, R.; Smith, G.; Klos, R.

    1998-11-01

    Significant resources and effort have been expended by EPRI over the past few years in modeling and understanding issues related to high-level radioactive waste disposal. Previous reports have documented the general model used in the EPRI work and specific inputs to that model for examination of the potential repository at Yucca Mountain, Nevada. Modeling of the potential Yucca Mountain site is an on-going process, and new data are being collected with which to evaluate and modify models of physical processes. This report is divided into two parts. The first part presents results from specific calculational cases of repository performance, updated for the most recent data and conceptual models. The second part discusses possible alternatives for the components of the assessment context for a repository at Yucca Mountain. Part 2 also presents additional information on time frames and a interaction matrix method of documenting TSPA model interactions. The main purposes of Part of this report is to describe the subsystem and total system performance models and present results and analysis of the results. Part 1 includes presentation of new models of waste container failure that accounts for new container material, a new model of the effect of hydrothermal activity and heterogeneous groundwater flow in the unsaturated zone on temperatures and the distribution of groundwater capable of dripping into the repository drifts. Part 1 also: identifies the key technical components of the candidate spent fuel and HLW disposal facility at Yucca Mountain using IMARC Phase 4; makes recommendations regarding the prioritization of the technical development work remaining; and provides an assessment of the overall technical suitability of the candidate HLW disposal facility at Yucca Mountain

  15. Evaluation of the long-term performance of six alternative disposal methods for LLRW

    Energy Technology Data Exchange (ETDEWEB)

    Kossik, R.; Sharp, G. [Golder Associates, Inc., Redmond, WA (United States); Chau, T. [Rogers & Associates Engineering Corp., Salt Lake City, UT (United States)

    1995-12-31

    The State of New York has carried out a comparison of six alternative disposal methods for low-level radioactive waste (LLRW). An important part of these evaluations involved quantitatively analyzing the long-term (10,000 yr) performance of the methods with respect to dose to humans, radionuclide concentrations in the environment, and cumulative release from the facility. Four near-surface methods (covered above-grade vault, uncovered above-grade vault, below-grade vault, augered holes) and two mine methods (vertical shaft mine and drift mine) were evaluated. Each method was analyzed for several generic site conditions applicable for the state. The evaluations were carried out using RIP (Repository Integration Program), an integrated, total system performance assessment computer code which has been applied to radioactive waste disposal facilities both in the U.S. (Yucca Mountain, WIPP) and worldwide. The evaluations indicate that mines in intact low-permeability rock and near-surface facilities with engineered covers generally have a high potential to perform well (within regulatory limits). Uncovered above-grade vaults and mines in highly fractured crystalline rock, however, have a high potential to perform poorly, exceeding regulatory limits.

  16. A sensitivity study of an evaluation of alternatives for disposal of INEL low-level waste and low-level mixed waste

    International Nuclear Information System (INIS)

    Roesener, W.S.; Smith, T.H.; Jorgenson-Waters, M.J.; Sherick, M.J.

    1995-01-01

    This paper presents insights gained from an informal sensitivity study of an evaluation of disposal alternatives for Idaho National Engineering Laboratory low-level waste and low-level mixed waste. The insights relate to the sensitivity of the alternative rankings to changes in assumptions identified as open-quotes key uncertaintiesclose quotes. The result of the sensitivity study is that significant changes occur in the rankings when selected open-quotes key uncertaintiesclose quotes are varied over reasonable ranges. Three alternatives involving the use of (a) shallow land burial and boreholes or (b) greater-depth burial and boreholes rank high for all cases investigated. The other alternatives rank low in some or all cases

  17. Uncertainty analysis for geologic disposal of radioactive waste

    International Nuclear Information System (INIS)

    Cranwell, R.M.; Helton, J.C.

    1981-01-01

    The incorporation and representation of uncertainty in the analysis of the consequences and risks associated with the geologic disposal of high-level radioactive waste are discussed. Such uncertainty has three primary components: process modeling uncertainty, model input data uncertainty, and scenario uncertainty. The following topics are considered in connection with the preceding components: propagation of uncertainty in the modeling of a disposal site, sampling of input data for models, and uncertainty associated with model output

  18. Disposal criticality analysis methodology for fissile waste forms

    International Nuclear Information System (INIS)

    Davis, J.W.; Gottlieb, P.

    1998-03-01

    A general methodology has been developed to evaluate the criticality potential of the wide range of waste forms planned for geologic disposal. The range of waste forms include commercial spent fuel, high level waste, DOE spent fuel (including highly enriched), MOX using weapons grade plutonium, and immobilized plutonium. The disposal of these waste forms will be in a container with sufficiently thick corrosion resistant barriers to prevent water penetration for up to 10,000 years. The criticality control for DOE spent fuel is primarily provided by neutron absorber material incorporated into the basket holding the individual assemblies. For the immobilized plutonium, the neutron absorber material is incorporated into the waste form itself. The disposal criticality analysis methodology includes the analysis of geochemical and physical processes that can breach the waste package and affect the waste forms within. The basic purpose of the methodology is to guide the criticality control features of the waste package design, and to demonstrate that the final design meets the criticality control licensing requirements. The methodology can also be extended to the analysis of criticality consequences (primarily increased radionuclide inventory), which will support the total performance assessment for the respository

  19. Long-term-consequence analysis of no action alternative 2

    International Nuclear Information System (INIS)

    Buck, J.W.; Bagaasen, L.M.; Staven, L.H.; Serne, R.J.

    1996-07-01

    This report is a supplement to the Waste Isolation Pilot Plant (WIPP) Disposal-Phase Supplemental Environmental Impact Statement. Data and information is described which pertains to estimated impacts from postulated long-term release of radionuclides and hazardous constituents from alpha-bearing wastes stored at major generator/storage sites after loss of institutional control (no action alternative 2). Under this alternative, wastes would remain at the generator sites and not be emplaced at WIPP

  20. Low-level waste inventory, characteristics, generation, and facility assessment for treatment, storage, and disposal alternatives considered in the US Department of Energy waste management programmatic environmental impact statement

    Energy Technology Data Exchange (ETDEWEB)

    Goyette, M.L.; Dolak, D.A.

    1996-12-01

    This report provides technical support information for use in analyzing environmental impacts associated with U.S. Department of Energy (DOE) low-level radioactive waste (LLW) management alternatives in the Waste-Management (WM) Programmatic Environmental Impact Statement (PEIS). Waste loads treated and disposed of for each of the LLW alternatives considered in the DOE WM PEIS are presented. Waste loads are presented for DOE Waste Management (WM) wastes, which are generated from routine operations. Radioactivity concentrations and waste quantities for treatment and disposal under the different LLW alternatives are described for WM waste. 76 refs., 14 figs., 42 tabs.

  1. Recycling/Disposal Alternatives for Depleted Uranium Wastes

    Science.gov (United States)

    1981-01-01

    AFB, FL 32542 77 14. MONITORING AGENCY NAME & ADORESS(If dtiereent Irom Contoltlifni Ofteie) IS. SECURITY CLASS. (of thee report) ’UNCLASSIFIED ISO ...Plant Florida Phosphate Council Golden, CO Florida (303) 497-2181 (813) 646- 8583 Merwyn Sanders Commercial Disposal Site Union Carbide Corporation Fred

  2. Subseabed-disposal program: systems-analysis program plan

    International Nuclear Information System (INIS)

    Klett, R.D.

    1981-03-01

    This report contains an overview of the Subseabed Nuclear Waste Disposal Program systems analysis program plan, and includes sensitivity, safety, optimization, and cost/benefit analyses. Details of the primary barrier sensitivity analysis and the data acquisition and modeling cost/benefit studies are given, as well as the schedule through the technical, environmental, and engineering feasibility phases of the program

  3. Alternatives Analysis For Selecting ET 3 Site

    International Nuclear Information System (INIS)

    Collard, L.; Hamm, L.

    2012-01-01

    Engineered trenches (ETs) are considered to be a cost-effective method for disposing Low Level Waste (LLW). Based on waste forecasts from waste generators, the last engineered trench in operation (ET No.2) is anticipated to close in FY14, requiring development of a new ET. Solid Waste requested that SRNL develop an assessment report that reviews four disposal options for this new ET (ET No.3) and determine which option would provide the 'best' Performance Assessment (PA) disposal limits for LLW (Appendix A). Those four options (see option footprint locations in Figure 1-1) are: (1) Disposal at grade on TRU Pads 7-13 where soil would be mounded over waste packages; (2) Excavation at a slightly modified SLIT No.13 location - near the Used Equipment Storage Area; (3) Excavation at a modified SLIT No.12 location - near the 643-26E Naval Reactor Component Disposal Area; and (4) Excavation east of TRU Pad No.26 that replaces northeast portions of four slit trench (ST) disposal units in the eastern set of STs. The assessment consisted of both quantitative and qualitative analyses. The quantitative analysis captured key aspects that were readily quantifiable and had predictable impacts on limits and doses. A simplified modeling strategy stemming from current Special Analysis (SA) practices was employed. Both inventory capacity for a specific nuclide (a quasi-inventory limit) and overall performance for specified inventory mixtures (doses resulting from historical inventories) were considered. The qualitative analysis evaluated other key aspects based on engineering judgment in the form of pros and cons.

  4. Preliminary Disposal Analysis for Selected Accelerator Production of Tritium Waste Streams

    International Nuclear Information System (INIS)

    Ades, M.J.; England, J.L.

    1998-06-01

    A preliminary analysis was performed for two selected Accelerator Production of Tritium (APT) generated mixed and low-level waste streams to determine if one mixed low-level waste (MLLW) stream that includes the Mixed Waste Lead (MWL) can be disposed of at the Nevada Test Site (NTS) and at the Hanford Site and if one low-level radioactive waste (LLW) stream, that includes the Tungsten waste stream (TWS) generated by the Tungsten Neutron Source modules and used in the Target/Blanket cavity vessel, can be disposed of in the LLW Vaults at the Savannah River Plant (SRP). The preliminary disposal analysis that the radionuclide concentrations of the two selected APT waste streams are not in full compliance with the Waste Acceptance Criteria (WAC) and the Performance Assessment (PA) radionuclide limits of the disposal sites considered

  5. The residuals analysis project: Evaluating disposal options for treated mixed low-level waste

    International Nuclear Information System (INIS)

    Waters, R.D.; Gruebel, M.M.; Case, J.T.; Letourneau, M.J.

    1997-01-01

    For almost four years, the U.S. Department of Energy (DOE) through its Federal Facility Compliance Act Disposal Workgroup has been working with state regulators and governors' offices to develop an acceptable configuration for disposal of its mixed low-level waste (MLLW). These interactions have resulted in screening the universe of potential disposal sites from 49 to 15 and conducting ''performance evaluations'' for those fifteen sites to estimate their technical capabilities for disposal of MLLW. In the residuals analysis project, we estimated the volume of DOE's MLLW that will require disposal after treatment and the concentrations of radionuclides in the treated waste. We then compared the radionuclide concentrations with the disposal limits determined in the performance evaluation project for each of the fifteen sites. The results are a scoping-level estimate of the required volumetric capacity for MLLW disposal and the identification of waste streams that may pose problems for disposal based on current treatment plans. The analysis provides technical information for continued discussions between the DOE and affected States about disposal of MLLW and systematic input to waste treatment developers on disposal issues

  6. Atmospheric Pathway Screening Analysis for Saltstone Disposal Facility Vault 4

    International Nuclear Information System (INIS)

    COOK, JAMES

    2004-01-01

    A sequential screening process using a methodology developed by the National Council on Radiation Protection and Measurements, professional judgment and process knowledge has been used to produce a list of radionuclides requiring detailed analysis to derive disposal limits for the Saltstone Disposal Facility based on the atmospheric pathway

  7. Preliminary Safety Design Report for Remote Handled Low-Level Waste Disposal Facility

    Energy Technology Data Exchange (ETDEWEB)

    Timothy Solack; Carol Mason

    2012-03-01

    A new onsite, remote-handled low-level waste disposal facility has been identified as the highest ranked alternative for providing continued, uninterrupted remote-handled low-level waste disposal for remote-handled low-level waste from the Idaho National Laboratory and for nuclear fuel processing activities at the Naval Reactors Facility. Historically, this type of waste has been disposed of at the Radioactive Waste Management Complex. Disposal of remote-handled low-level waste in concrete disposal vaults at the Radioactive Waste Management Complex will continue until the facility is full or until it must be closed in preparation for final remediation of the Subsurface Disposal Area (approximately at the end of Fiscal Year 2017). This preliminary safety design report supports the design of a proposed onsite remote-handled low-level waste disposal facility by providing an initial nuclear facility hazard categorization, by discussing site characteristics that impact accident analysis, by providing the facility and process information necessary to support the hazard analysis, by identifying and evaluating potential hazards for processes associated with onsite handling and disposal of remote-handled low-level waste, and by discussing the need for safety features that will become part of the facility design.

  8. Radionuclide inventory and heat generation analysis in disposal of radioactive waste

    International Nuclear Information System (INIS)

    Suryanto

    1997-01-01

    Radionuclide inventory and heat generation analysis on spent nuclear fuel were done in order to study the potential radionuclides contributing radiological impact to human being caused by spent fuel disposal. The study was carried out using the Bateman equation of radionuclide decay chains for fission products and actinides. the results showed that Cs-137, Sr-90 and Pu-239 dominated inventory of spent fuel, in which Pu-238 and Pu-240 dominated heat generation during disposal. Accordingly, the above radionuclides could be considered as the reference radionuclides for safety analysis of spent nuclear fuel disposal (author)

  9. Preliminary performance assessment strategy for single-shell tank waste disposal

    International Nuclear Information System (INIS)

    Sonnichsen, J.C. Jr.

    1991-10-01

    The disposal of the waste stored in single-shell tanks at the Hanford Site is recognized as a major environmental concern. A comprehensive program has been initiated to evaluate the various alternatives available for disposal of these wastes. Theses wastes will be disposed of in a manner consistent with applicable laws and regulations. Long-term waste isolation is one measure of performance that will be used for purposes of selection. The performance of each disposal alternative will be simulated using numerical models. Contained herein is a discussion of the strategy that has and continues to evolve to establish a general analytical framework to evaluate this performance. This general framework will be used to construct individual models of each waste disposal alternative selected for purposes of evaluation. 30 refs., 3 figs

  10. Nuclear waste disposal: alternatives to solidification in glass proposed

    International Nuclear Information System (INIS)

    Kerr, R.A.

    1979-01-01

    More than a quarter-million cubic meters of liquid radioactive wastes are now being held at government installations awaiting final disposal. During the past 20 years, the disposal plan of choice has been to incorporate the 40 to 50 radioactive elements dissolved in liquid wastes into blocks of glass, seal the glass in metal canisters, and insert the canisters into deep, geologically stable salt beds. Over the last few years, some geologists and materials scientists have become concerned that perhaps not enough is known yet about the interaction of waste, container, and salt (or any rock) to have a reasonable assurance that the hazardous wastes will be contained successfully. The biggest advantage of glass at present is the demonstrated practicality of producing large, highly radioactive blocks of it. The frontrunner as a successor to glass is ceramics, which are nonmetallic crystalline materials formed at high temperature, such as chinaware or natural minerals. An apparent advantage of ceramics is that they already have an ordered atomic structure, whose properties can be tailored to a particular waste element and to conditions of a specific disposal site. A ceramic tailored for waste disposal called supercalcine-ceramic has been developed. It was emphasized that the best minerals for waste solidification may be those that have proved most stable under natural conditions over geologic time. Disadvantage to ceramics are radiation damage and transmutation. However, it is now obvious that some ceramics are more stable than glass under certain conditions. Metal-encapsulated ceramic, called cermet, is being developed as a waste form. Cermets are considerably more resistant at 100 0 C than a borosilicate waste glass. Researchers are now testing prospective waste forms under the most extreme conditions that might prevail in a waste disposal site

  11. Special Analysis: Disposal Plan for Pit 38 at Technical Area 54, Area G

    Energy Technology Data Exchange (ETDEWEB)

    French, Sean B. [Los Alamos National Laboratory; Shuman, Rob [URS Coporation

    2012-06-26

    Los Alamos National Laboratory (LANL) generates radioactive waste as a result of various activities. Operational waste is generated from a wide variety of research and development activities including nuclear weapons development, energy production, and medical research; environmental restoration (ER), and decontamination and decommissioning (D&D) waste is generated as contaminated sites and facilities at LANL undergo cleanup or remediation. The majority of this waste is low-level radioactive waste (LLW) and is disposed of at the Technical Area 54 (TA-54), Area G disposal facility. U.S. Department of Energy (DOE) Order 435.1 (DOE, 2001) requires that radioactive waste be managed in a manner that protects public health and safety, and the environment. To comply with this order, DOE field sites must prepare site-specific radiological performance assessments for LLW disposal facilities that accept waste after September 26, 1988. Furthermore, sites are required to conduct composite analyses that account for the cumulative impacts of all waste that has been (or will be) disposed of at the facilities and other sources of radioactive material that may interact with the facilities. Revision 4 of the Area G performance assessment and composite analysis was issued in 2008 (LANL, 2008). These analyses estimate rates of radionuclide release from the waste disposed of at the facility, simulate the movement of radionuclides through the environment, and project potential radiation doses to humans for several on- and off-site exposure scenarios. The assessments are based on existing site and disposal facility data, and on assumptions about future rates and methods of waste disposal. The Area G disposal facility consists of Material Disposal Area (MDA) G and the Zone 4 expansion area. To date, disposal operations have been confined to MDA G and are scheduled to continue in that region until MDA G undergoes final closure at the end of 2013. Given its impending closure, efforts have

  12. Special Analysis: Disposal Plan for Pit 38 at Technical Area 54, Area G

    International Nuclear Information System (INIS)

    French, Sean B.; Shuman, Rob

    2012-01-01

    Los Alamos National Laboratory (LANL) generates radioactive waste as a result of various activities. Operational waste is generated from a wide variety of research and development activities including nuclear weapons development, energy production, and medical research; environmental restoration (ER), and decontamination and decommissioning (D and D) waste is generated as contaminated sites and facilities at LANL undergo cleanup or remediation. The majority of this waste is low-level radioactive waste (LLW) and is disposed of at the Technical Area 54 (TA-54), Area G disposal facility. U.S. Department of Energy (DOE) Order 435.1 (DOE, 2001) requires that radioactive waste be managed in a manner that protects public health and safety, and the environment. To comply with this order, DOE field sites must prepare site-specific radiological performance assessments for LLW disposal facilities that accept waste after September 26, 1988. Furthermore, sites are required to conduct composite analyses that account for the cumulative impacts of all waste that has been (or will be) disposed of at the facilities and other sources of radioactive material that may interact with the facilities. Revision 4 of the Area G performance assessment and composite analysis was issued in 2008 (LANL, 2008). These analyses estimate rates of radionuclide release from the waste disposed of at the facility, simulate the movement of radionuclides through the environment, and project potential radiation doses to humans for several on- and off-site exposure scenarios. The assessments are based on existing site and disposal facility data, and on assumptions about future rates and methods of waste disposal. The Area G disposal facility consists of Material Disposal Area (MDA) G and the Zone 4 expansion area. To date, disposal operations have been confined to MDA G and are scheduled to continue in that region until MDA G undergoes final closure at the end of 2013. Given its impending closure, efforts

  13. Demonstration of risk-based decision analysis in remedial alternative selection and design

    International Nuclear Information System (INIS)

    Evans, E.K.; Duffield, G.M.; Massmann, J.W.; Freeze, R.A.; Stephenson, D.E.

    1993-01-01

    This study demonstrates the use of risk-based decision analysis (Massmann and Freeze 1987a, 1987b) in the selection and design of an engineering alternative for groundwater remediation at a waste site at the Savannah River Site, a US Department of Energy facility in South Carolina. The investigation focuses on the remediation and closure of the H-Area Seepage Basins, an inactive disposal site that formerly received effluent water from a nearby production facility. A previous study by Duffield et al. (1992), which used risk-based decision analysis to screen a number of ground-water remediation alternatives under consideration for this site, indicated that the most attractive remedial option is ground-water extraction by wells coupled with surface water discharge of treated effluent. The aim of the present study is to demonstrate the iterative use of risk-based decision analysis throughout the design of a particular remedial alternative. In this study, we consider the interaction between two episodes of aquifer testing over a 6-year period and the refinement of a remedial extraction well system design. Using a three-dimensional ground-water flow model, this study employs (1) geostatistics and Monte Carlo techniques to simulate hydraulic conductivity as a stochastic process and (2) Bayesian updating and conditional simulation to investigate multiple phases of aquifer testing. In our evaluation of a remedial alternative, we compute probabilistic costs associated with the failure of an alternative to completely capture a simulated contaminant plume. The results of this study demonstrate the utility of risk-based decision analysis as a tool for improving the design of a remedial alternative through the course of phased data collection at a remedial site

  14. Disposal of by-products in olive oil industry: waste-to-energy solutions

    International Nuclear Information System (INIS)

    Caputo, Antonio C.; Scacchia, Federica; Pelagagge, Pacifico M.

    2003-01-01

    Olive oil production industry is characterized by relevant amounts of liquid and solid by-products [olive mill wastewater (OMW) and olive husk (OH)], and by economical, technical and organizational constraints that make difficult the adoption of environmentally sustainable waste disposal approaches. In this context, waste treatment technologies aimed at energy recovery represent an interesting alternative. In the paper, a technical and economical analysis of thermal disposal plant solutions with energy recovery has been carried out. The considered plants enable the combined treatment of OMW and OH which, although penalizes the energy recovery, proves to be feasible and profitable in a future legislative scenario when stricter limitation on OMW disposal will force oil producers to bear high disposal costs. Results are compared by using economic performance measures, including revenues from produced energy and avoided disposal costs. A sensitivity and risk analysis is also performed in order to assess the economic profitability of the proposed solutions

  15. Survey of waste disposal methods in Awka metropolis | Bill | Journal ...

    African Journals Online (AJOL)

    Waste disposal methods commonly practiced in Awka metropolis, Anambra state were investigated from August to October, 2013. Data was analyzed with both descriptive statistics of frequency and percentages, and alternate hypotheses were tested using Analysis of Variance (ANOVA) at a significance level of 0.05.

  16. Nuclear fuel waste disposal

    International Nuclear Information System (INIS)

    Allan, C.J.

    1993-01-01

    The Canadian concept for nuclear fuel waste disposal is based on disposing of the waste in a vault excavated 500-1000 m deep in intrusive igneous rock of the Canadian Shield. The author believes that, if the concept is accepted following review by a federal environmental assessment panel (probably in 1995), then it is important that implementation should begin without delay. His reasons are listed under the following headings: Environmental leadership and reducing the burden on future generations; Fostering public confidence in nuclear energy; Forestalling inaction by default; Preserving the knowledge base. Although disposal of reprocessing waste is a possible future alternative option, it will still almost certainly include a requirement for geologic disposal

  17. Nuclear waste management: storage and disposal aspects

    International Nuclear Information System (INIS)

    Patterson, B.D.; Dave, S.A.; O'Connell, W.J.

    1980-01-01

    Long-term disposal of nuclear wastes must resolve difficulties arising chiefly from the potential for contamination of the environment and the risk of misuse. Alternatives available for storage and disposal of wastes are examined in this overview paper. Guidelines and criteria which may govern in the development of methods of disposal are discussed

  18. Addendum to the Composite Analysis for the E-Area Vaults and Saltstone Disposal Facilities

    International Nuclear Information System (INIS)

    Cook, J.R.

    2002-01-01

    Revision 1 of the Composite Analysis (CA) Addendum has been prepared to respond to the U.S. Department of Energy (DOE) Low-Level Waste Disposal Facilities Federal Review Group review of the CA. This addendum to the composite analysis responds to the conditions of approval. The composite analysis was performed on the two active SRS low-level radioactive waste disposal facilities. The facilities are the Z-Area Saltstone Disposal Facility and the E-Area Vaults Disposal Facility. The analysis calculated potential releases to the environment from all sources of residual radioactive material expected to remain in the General Separations Area (GSA). The GSA is the central part of the Savannah River Site and contains all of the waste disposal facilities, the chemical separation facilities and associated high-level waste storage facilities, as well as numerous other sources of radioactive material

  19. Uncertainties about the safety of disposal leading to a wish to keep alternatives open. Discussion on the concepts 'storage' ('wait and see') vs. 'disposal' and 'retrievable disposal' vs. 'definitive disposal'

    International Nuclear Information System (INIS)

    Norrby, S.

    2000-01-01

    Uncertainties about the safety of final disposal may lead to unwillingness to take decisions about waste management issues that may seem to be non-reversible. This has lead to proposals that we should wait with decisions on final measures and instead store the waste for some period of time. Also the possibility of retrieval may lead to decisions not to go for permanent disposal but instead to retrievable disposal. These aspects and the pros and cons are discussed both from a more general perspective and also with some reflections from the Swedish programme for nuclear waste management and disposal. (author)

  20. Research and development for treatment and disposal technologies of TRU waste

    International Nuclear Information System (INIS)

    Kamei, Gento; Honda, Akira; Mihara, Morihiro; Oda, Chie; Murakami, Hiroshi; Masuda, Kenta; Yamaguchi, Kohei; Nakanishi, Hiroshi; Sasaki, Ryoichi; Ichige, Satoru; Takahashi, Kuniaki; Meguro, Yoshihiro; Yamaguchi, Hiromi; Aoyama, Yoshio

    2007-09-01

    After the publication of the 2nd progress report of geological disposal of TRU waste in Japan, policy and general scheme of future study for the waste disposal in Japan was published by ANRE and JAEA. This annual report summarized aim and progress of individual problem, which was assigned into JAEA in the published policy and general scheme. The problems are as follows; characteristics of TRU waste and its geologic disposal, treatment and waste production, quality control and inspection methodology for waste, mechanical analysis of near-field, data acquisition and preparation on radionuclides migration, cementitious material transition, bentonite and rock alteration in alkaline solution, nitrate effect, performance assessment of the disposal system and decomposition of nitrate as an alternative technology. (author)

  1. Estimates of relative areas for the disposal in bedded salt of LWR wastes from alternative fuel cycles

    International Nuclear Information System (INIS)

    Lincoln, R.C.; Larson, D.W.; Sisson, C.E.

    1978-01-01

    The relative mine-level areas (land use requirements) which would be required for the disposal of light-water reactor (LWR) radioactive wastes in a hypothetical bedded-salt formation have been estimated. Five waste types from alternative fuel cycles have been considered. The relative thermal response of each of five different site conditions to each waste type has been determined. The fuel cycles considered are the once-through (no recycle), the uranium-only recycle, and the uranium and plutonium recycle. The waste types which were considered include (1) unreprocessed spent reactor fuel, (2) solidified waste derived from reprocessing uranium oxide fuel, (3) plutonium recovered from reprocessing spent reactor fuel and doped with 1.5% of the accompanying waste from reprocessing uranium oxide fuel, (4) waste derived from reprocessing mixed uranium/plutonium oxide fuel in the third recycle, and (5) unreprocessed spent fuel after three recycles of mixed uranium/plutonium oxide fuels. The relative waste-disposal areas were determined from a calculated value of maximum thermal energy (MTE) content of the geologic formations. Results are presented for each geologic site condition in terms of area ratios. Disposal area requirements for each waste type are expressed as ratios relative to the smallest area requirement (for waste type No. 2 above). For the reference geologic site condition, the estimated mine-level disposal area ratios are 4.9 for waste type No. 1, 4.3 for No. 3, 2.6 for No. 4, and 11 for No. 5

  2. Performance analysis for disposal of mixed low-level waste. 1: Methodology

    International Nuclear Information System (INIS)

    Waters, R.D.; Gruebel, M.M.

    1999-01-01

    A simple methodology has been developed for evaluating the technical capabilities of potential sites for disposal of mixed low-level radioactive waste. The results of the evaluation are expressed as permissible radionuclide concentrations in disposed waste. The methodology includes an analysis of three separate pathways: (1) releases of radionuclides to groundwater; (2) releases of potentially volatile radionuclides to the atmosphere; and (3) the consequences of inadvertent intrusion into a disposal facility. For each radionuclide, its limiting permissible concentration in disposed waste is the lowest of the permissible concentrations determined from each of the three pathways. These permissible concentrations in waste at an evaluated site can be used to assess the capability of the site to dispose of waste streams containing multiple radionuclides

  3. Project Execution Plan for the Remote Handled Low-Level Waste Disposal Project

    Energy Technology Data Exchange (ETDEWEB)

    Danny Anderson

    2014-07-01

    As part of ongoing cleanup activities at the Idaho National Laboratory (INL), closure of the Radioactive Waste Management Complex (RWMC) is proceeding under the Comprehensive Environmental Response, Compensation, and Liability Act (42 USC 9601 et seq. 1980). INL-generated radioactive waste has been disposed of at RWMC since 1952. The Subsurface Disposal Area (SDA) at RWMC accepted the bulk of INL’s contact and remote-handled low-level waste (LLW) for disposal. Disposal of contact-handled LLW and remote-handled LLW ion-exchange resins from the Advanced Test Reactor in the open pit of the SDA ceased September 30, 2008. Disposal of remote-handled LLW in concrete disposal vaults at RWMC will continue until the facility is full or until it must be closed in preparation for final remediation of the SDA (approximately at the end of fiscal year FY 2017). The continuing nuclear mission of INL, associated ongoing and planned operations, and Naval spent fuel activities at the Naval Reactors Facility (NRF) require continued capability to appropriately dispose of contact and remote handled LLW. A programmatic analysis of disposal alternatives for contact and remote-handled LLW generated at INL was conducted by the INL contractor in Fiscal Year 2006; subsequent evaluations were completed in Fiscal Year 2007. The result of these analyses was a recommendation to the Department of Energy (DOE) that all contact-handled LLW generated after September 30, 2008, be disposed offsite, and that DOE proceed with a capital project to establish replacement remote-handled LLW disposal capability. An analysis of the alternatives for providing replacement remote-handled LLW disposal capability has been performed to support Critical Decision-1. The highest ranked alternative to provide this required capability has been determined to be the development of a new onsite remote-handled LLW disposal facility to replace the existing remote-handled LLW disposal vaults at the SDA. Several offsite DOE

  4. A quantitative analysis of municipal solid waste disposal charges in China.

    Science.gov (United States)

    Wu, Jian; Zhang, Weiqian; Xu, Jiaxuan; Che, Yue

    2015-03-01

    Rapid industrialization and economic development have caused a tremendous increase in municipal solid waste (MSW) generation in China. China began implementing a policy of MSW disposal fees for household waste management at the end of last century. Three charging methods were implemented throughout the country: a fixed disposal fee, a potable water-based disposal fee, and a plastic bag-based disposal fee. To date, there has been little qualitative or quantitative analysis on the effectiveness of this relatively new policy. This paper provides a general overview of MSW fee policy in China, attempts to verify whether the policy is successful in reducing general waste collected, and proposes an improved charging system to address current problems. The paper presents an empirical statistical analysis of policy effectiveness derived from an environmental Kuznets curve (EKC) test on panel data of China. EKC tests on different kinds of MSW charge systems were then examined for individual provinces or cities. A comparison of existing charging systems was conducted using environmental and economic criteria. The results indicate the following: (1) the MSW policies implemented over the study period were effective in the reduction of waste generation, (2) the household waste discharge fee policy did not act as a strong driver in terms of waste prevention and reduction, and (3) the plastic bag-based disposal fee appeared to be performing well according to qualitative and quantitative analysis. Based on current situation of waste discharging management in China, a three-stage transitional charging scheme is proposed and both advantages and drawbacks discussed. Evidence suggests that a transition from a fixed disposal fee to a plastic bag-based disposal fee involving various stakeholders should be the next objective of waste reduction efforts.

  5. Analysis of disposition alternatives for radioactively contaminated scrap metal

    International Nuclear Information System (INIS)

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

    1997-01-01

    Millions of tonnes of slightly radioactive, scrap iron and steel, stainless steel, and copper are likely to become available as nuclear and other facilities and equipment are withdrawn from service. Disposition of this material is an international policy issue under consideration currently. The major alternatives for managing this material are to either develop a regulatory process for decontamination and recycling that will safeguard human health or to dispose of the scrap and replace the metal stocks. To evaluate the alternatives, we estimate quantities of scrap arising from nuclear power plant decommissioning, evaluate potential price impacts of recycling on regional markets, and assess the health and environmental impacts of the management alternatives. We conclude that decontaminating and recycling the scrap is the superior alternative

  6. Disposal facility in Olkiluoto, description of above ground facilities in tunnel transport alternative

    International Nuclear Information System (INIS)

    Kukkola, T.

    2006-11-01

    The above ground facilities of the disposal plant on the Olkiluoto site are described in this report as they will be when the operation of the disposal facility starts in the year 2020. The disposal plant is visualised on the Olkiluoto site. Parallel construction of the deposition tunnels and disposal of the spent fuel canisters constitute the principal design basis of the disposal plant. The annual production of disposal canisters for spent fuel amounts to about 40. Production of 100 disposal canisters has been used as the capacity basis. Fuel from the Olkiluoto plant and from the Loviisa plant will be encapsulated in the same production line. The disposal plant will require an area of about 15 to 20 hectares above ground level. The total building volume of the above ground facilities is about 75000 m 3 . The purpose of the report is to provide the base for detailed design of the encapsulation plant and the repository spaces, as well as for coordination between the disposal plant and ONKALO. The dimensioning bases for the disposal plant are shown in the Tables at the end of the report. The report can also be used as a basis for comparison in deciding whether the fuel canisters are transported to the repository by a lift or a by vehicle along the access tunnel. (orig.)

  7. Disposal facility in olkiluoto, description of above ground facilities in lift transport alternative

    International Nuclear Information System (INIS)

    Kukkola, T.

    2006-11-01

    The above ground facilities of the disposal plant on the Olkiluoto site are described in this report as they will be when the operation of the disposal facility starts in the year 2020. The disposal plant is visualised on the Olkiluoto site. Parallel construction of the deposition tunnels and disposal of the spent fuel canisters constitute the principal design basis of the disposal plant. The annual production of disposal canisters for spent fuel amounts to about 40. Production of 100 disposal canisters has been used as the capacity basis. Fuel from the Olkiluoto plant and from the Loviisa plant will be encapsulated in the same production line. The disposal plant will require an area of about 15 to 20 hectares above ground level. The total building volume of the above ground facilities is about 75000 m 3 . The purpose of the report is to provide the base for detailed design of the encapsulation plant and the repository spaces, as well as for coordination between the disposal plant and ONKALO. The dimensioning bases for the disposal plant are shown in the Tables at the end of the report. The report can also be used as a basis for comparison in deciding whether the fuel canisters are transported to the repository by a lift or by a vehicle along the access tunnel. (orig.)

  8. Alternative biosphere modeling for safety assessment of HLW disposal taking account of geosphere-biosphere interface of marine environment

    International Nuclear Information System (INIS)

    Kato, Tomoko; Ishiguro, Katsuhiko; Naito, Morimasa; Ikeda, Takao; Little, Richard

    2001-03-01

    In the safety assessment of a high-level radioactive waste (HLW) disposal system, it is required to estimate radiological impacts on future human beings arising from potential radionuclide releases from a deep repository into the surface environment. In order to estimated the impacts, a biosphere model is developed by reasonably assuming radionuclide migration processes in the surface environment and relevant human lifestyles. It is important to modify the present biosphere models or to develop alternative biosphere models applying the biosphere models according to quality and quantify of the information acquired through the siting process for constructing the repository. In this study, alternative biosphere models were developed taking geosphere-biosphere interface of marine environment into account. Moreover, the flux to dose conversion factors calculated by these alternative biosphere models was compared with those by the present basic biosphere models. (author)

  9. Addendum to the composite analysis for the E-Area Vaults and Saltstone Disposal Facilities

    Energy Technology Data Exchange (ETDEWEB)

    Cook, J.R.

    2000-03-13

    This report documents the composite analysis performed on the two active SRS low-level radioactive waste disposal facilities. The facilities are the Z-Area Saltstone Disposal Facility and the E-Area Vaults Disposal Facility.

  10. Addendum to the composite analysis for the E-Area Vaults and Saltstone Disposal Facilities

    International Nuclear Information System (INIS)

    Cook, J.R.

    2000-01-01

    This report documents the composite analysis performed on the two active SRS low-level radioactive waste disposal facilities. The facilities are the Z-Area Saltstone Disposal Facility and the E-Area Vaults Disposal Facility

  11. Depleted uranium management alternatives

    Energy Technology Data Exchange (ETDEWEB)

    Hertzler, T.J.; Nishimoto, D.D.

    1994-08-01

    This report evaluates two management alternatives for Department of Energy depleted uranium: continued storage as uranium hexafluoride, and conversion to uranium metal and fabrication to shielding for spent nuclear fuel containers. The results will be used to compare the costs with other alternatives, such as disposal. Cost estimates for the continued storage alternative are based on a life-cycle of 27 years through the year 2020. Cost estimates for the recycle alternative are based on existing conversion process costs and Capital costs for fabricating the containers. Additionally, the recycle alternative accounts for costs associated with intermediate product resale and secondary waste disposal for materials generated during the conversion process.

  12. Depleted uranium management alternatives

    International Nuclear Information System (INIS)

    Hertzler, T.J.; Nishimoto, D.D.

    1994-08-01

    This report evaluates two management alternatives for Department of Energy depleted uranium: continued storage as uranium hexafluoride, and conversion to uranium metal and fabrication to shielding for spent nuclear fuel containers. The results will be used to compare the costs with other alternatives, such as disposal. Cost estimates for the continued storage alternative are based on a life-cycle of 27 years through the year 2020. Cost estimates for the recycle alternative are based on existing conversion process costs and Capital costs for fabricating the containers. Additionally, the recycle alternative accounts for costs associated with intermediate product resale and secondary waste disposal for materials generated during the conversion process

  13. Disposal of Iodine-129

    International Nuclear Information System (INIS)

    Morgan, M.T.; Moore, J.G.; Devaney, H.E.; Rogers, G.C.; Williams, C.; Newman, E.

    1978-01-01

    One of the problems to be solved in the nuclear waste management field is the disposal of radioactive iodine-129, which is one of the more volatile and long-lived fission products. Studies have shown that fission products can be fixed in concrete for permanent disposal. Current studies have demonstrated that practical cementitious grouts may contain up to 18% iodine as barium iodate. The waste disposal criterion is based on the fact that harmful effects to present or future generations can be avoided by isolation and/or dilution. Long-term isolation is effective in deep, dry repositories; however, since penetration by water is possible, although unlikely, release was calculated based on leach rates into water. Further considerations have indicated that sea disposal on or in the ocean floor may be a more acceptable alternative

  14. Radioactive waste (disposal)

    International Nuclear Information System (INIS)

    Jenkin, P.

    1985-01-01

    The disposal of low- and intermediate-level radioactive wastes was discussed. The following aspects were covered: public consultation on the principles for assessing disposal facilities; procedures for dealing with the possible sites which the Nuclear Industry Radioactive Waste Executive (NIREX) had originally identified; geological investigations to be carried out by NIREX to search for alternative sites; announcement that proposal for a site at Billingham is not to proceed further; NIREX membership; storage of radioactive wastes; public inquiries; social and environmental aspects; safety aspects; interest groups; public relations; government policies. (U.K.)

  15. Survey of university students' knowledge and views on nuclear waste disposal and the alternative dispute resolution process

    International Nuclear Information System (INIS)

    Sheng, G.; Deffner, L.; Fiorini, S.

    1996-01-01

    The management of the high level radioactive waste is an issue which generates multifaceted conflicts. These conflicts are multi-determined, but are nonetheless, based on a myriad of associated concerns including but not exclusive to: effects of radiation on public health and safety, uncertainty associated with long-term assessments and effects, confidence in technology and in government and industry to protect public health and safety, and concerns regarding concurrent and intergenerational equity. These concerns are likely to be deeply felt by the many potential actors and stakeholders who will be impacted during the process of site selection for a nuclear waste disposal facility. Because this site selection is sure to be a controversial undertaking, it is in the interests of those who wish to promote the use of the high-level radioactive waste disposal concept, to understand fully the potential for conflict and consider alternative means of proactively preventing and/or resolving conflicts

  16. Disposal criticality analysis methodology's principal isotope burnup credit

    International Nuclear Information System (INIS)

    Doering, T.W.; Thomas, D.A.

    2001-01-01

    This paper presents the burnup credit aspects of the United States Department of Energy Yucca Mountain Project's methodology for performing criticality analyses for commercial light-water-reactor fuel. The disposal burnup credit methodology uses a 'principal isotope' model, which takes credit for the reduced reactivity associated with the build-up of the primary principal actinides and fission products in irradiated fuel. Burnup credit is important to the disposal criticality analysis methodology and to the design of commercial fuel waste packages. The burnup credit methodology developed for disposal of irradiated commercial nuclear fuel can also be applied to storage and transportation of irradiated commercial nuclear fuel. For all applications a series of loading curves are developed using a best estimate methodology and depending on the application, an additional administrative safety margin may be applied. The burnup credit methodology better represents the 'true' reactivity of the irradiated fuel configuration, and hence the real safety margin, than do evaluations using the 'fresh fuel' assumption. (author)

  17. Consideration of disposal alternatives for tritium-contaminated wastewater streams at Hanford

    International Nuclear Information System (INIS)

    Waters, E.D.

    1988-03-01

    Small quantities of tritium are produced as an undesirable by-product of the operation of light-water reactors. At the US Department of Energy Hanford Site in Washington State, some tritium has been discharged to the environment in low-level liquid and gaseous wastes from the N Reactor plant, but more than 97% of the tritium stays typically within the irradiated fuel as it is delivered for reprocessing. During fuel reprocessing, the tritium is distributed in the process streams, and most of the tritium is presently released to the soil column with excess process condensates from the Plutonium-Uranium Extraction (PUREX) Plant. On an annual basis, approximately 1 g of tritium is discharged in more than 1 x 10 6 L of process condensate water. Principal tritium release points and quantities are presented in section 4.0. The present study is intended to identify and evaluate alternate methods of tritium control and disposal that might merit additional study or development for potential application to Hanford Site effluents. 30 refs., 15 figs., 5 tabs

  18. System for the hydrogeologic analysis of uranium mill waste disposal sites

    International Nuclear Information System (INIS)

    Osiensky, J.L.

    1983-01-01

    Most of the uranium mill wastes generated before 1977 are stored in unlined tailings ponds. Seepage from some of these ponds has been of sufficient severity that the US Nuclear Regulatory Commission (NRC) has required the installation of withdrawal wells to remove the contaminated groundwater. Uranium mill waste disposal facilities typically are located in complex hydrogeologic environments. This research was initiated in 1980 to analyze hydrogeologic data collected at seven disposal sites in the US that have experienced problems with groundwater contamination. The characteristics of seepage migration are site specific and are controlled by the hydrogeologic environment in the vicinity of each tailings pond. Careful monitoring of most seepage plumes was not initiated until approximately 1977. These efforts were accelerated as a consequence of the uranium Mill Tailings Act of 1979. Some of the data collected at uranium mill waste disposal sites in the past are incomplete and some were collected by methods that are outdated. Data frequently were collected in sequences which disrupted the continuity of the hydrogeologic analysis and decreased the effectiveness of the data collection programs. Evaluation of data collection programs for seven uranium mill waste disposal sites in the US has led to the development and presentation herein of a system for the hydrogeologic analysis of disposal sites

  19. Phenylbutyrate improves nitrogen disposal via alternative pathway without eliciting an increase in protein breakdown and catabolism in control and ornithine transcarbamylace-deficient patients

    Science.gov (United States)

    Phenylbutyrate (PB) is a drug used in urea cycle disorder patients to elicit alternative pathways for nitrogen disposal. However, PB decreases plasma branched chain amino acid (BCAA) concentrations and prior research suggests that PB may increase leucine oxidation, indicating increased protein degra...

  20. INEEL special case waste storage and disposal alternatives

    International Nuclear Information System (INIS)

    Larson, L.A.; Bishop, C.W.; Bhatt, R.N.

    1997-07-01

    Special case waste is historically defined as radioactive waste that does not have a path forward or fit into current Department of Energy management plans for final treatment or disposal. The objectives of this report, relative to special case waste at the Idaho National Engineering and Environmental Laboratory, are to (a) identify its current storage locations, conditions, and configuration; (b) review and verify the currently reported inventory; (c) segregate the inventory into manageable categories; (d) identify the portion that has a path forward or is managed under other major programs/projects; (e) identify options for reconfiguring and separating the disposable portions; (f) determine if the special case waste needs to be consolidated into a single storage location; and (g) identify a preferred facility for storage. This report also provides an inventory of stored sealed sources that are potentially greater than Class C or special case waste based on Nuclear Regulatory Commission and Site-Specific Waste Acceptance Criteria

  1. Alternatives to land disposal of solid radioactive mixed wastes on the Hanford Site

    International Nuclear Information System (INIS)

    Jacobsen, P.H.

    1992-03-01

    This report is a detailed description of the generation and management of land disposal restricted mixed waste generated, treated, and stored at the Hanford Site. This report discusses the land disposal restricted waste (mixed waste) managed at the Hanford Site by point of generation and current storage locations. The waste is separated into groups on the future treatment of the waste before disposal. This grouping resulted in the definition of 16 groups or streams of land disposal restricted waste

  2. Study on the background information for the geological disposal concept

    International Nuclear Information System (INIS)

    Matsui, Kazuaki; Murano, Tohru; Hirusawa, Shigenobu; Komoto, Harumi

    2000-03-01

    Japan Nuclear Cycle Development Institute (JNC) has published first R and D report in 1992, in which the fruits of the R and D work were compiled. Since then, JNC, has been promoting the second R and D progress report until before 2000, in which the background information on the geological disposal of high level radioactive waste (HLW) was to be presented as well as the technical basis. Recognizing the importance of the social consensus to the geological disposal, understanding and consensus by the society are essential to the development and realization of the geological disposal of HLW. In this fiscal year, studies were divided into 2 phases, considering the time schedule of the second R and D progress report. 1. Phase 1: Analysis of the background information on the geological disposal concept. Based on the recent informations and the research works of last 2 years, final version of the study was made to contribute to the background informations for the second R and D progress report. (This was published in Nov. 1999 as the intermediate report: JNC TJ 1420 2000-006). 2. Phase 2: Following 2 specific items were selected for the candidate issues which need to be studied, considering the present circumstances around the R and D of geological disposal. (1) Educational materials and strategies related to nuclear energy and nuclear waste. Specific strategies and approaches in the area of nuclear energy and nuclear waste educational outreach and curriculum activities by the nuclear industry, government and other entities in 6 countries were surveyed and summarized. (2) Alternatives to geological disposal of HLW: Past national/international consideration and current status. The alternatives for the disposal of HLW have been discussed in the past and the major waste-producing countries have almost all chosen deep geological disposal as preferred method. Here past histories and recent discussions on the variations to geological disposal were studied. (author)

  3. Safety assessment for deep underground disposal vault-pathways analysis

    International Nuclear Information System (INIS)

    Lyon, R.B.; Rosinger, E.L.J.

    1980-01-01

    The concept verification phase of the Canadian programme for the disposal of nuclear fuel waste encompasses a period of about three years before the start of site selection. During this time, the methodology for Environmental and Safety Assessment studies is being developed by focusing on a model site. Pathways analysis is an important component of these studies. It involves the prediction of the rate at which radionuclides might be released from a disposal vault and travel through the geosphere and biosphere to reach man. The pathways analysis studies cover three major topics: geosphere pathways analysis, biosphere pathways analysis and potentially-disruptive-phenomena analysis. Geosphere pathways analysis includes a total systems analysis, using the computer program GARD2, vault analysis, which considers container failure and waste leaching, hydrogeological modelling and geochemical modelling. Biosphere pathways analysis incorporates a compartmental modelling approach using the computer program RAMM, and a food chain analysis using the computer program FOOD II. Potentially-disruptive-phenomena analysis involves the estimation of the probability and consequences of events such as earthquakes which might reduce the effectiveness of the barriers preventing the release of radionuclides. The current stage of development of the required methodology and data is discussed in each of the three areas and preliminary results are presented. (author)

  4. Advances in poultry litter disposal technology--a review.

    Science.gov (United States)

    Kelleher, B P; Leahy, J J; Henihan, A M; O'Dwyer, T F; Sutton, D; Leahy, M J

    2002-05-01

    The land disposal of waste from the poultry industry and subsequent environmental implications has stimulated interest into cleaner and more useful disposal options. The review presented here details advances in the three main alternative disposal routes for poultry litter, specifically in the last decade. Results of experimental investigations into the optimisation of composting, anaerobic digestion and direct combustion are summarised. These technologies open up increased opportunities to market the energy and nutrients in poultry litter to agricultural and non-agricultural uses. Common problems experienced by the current technologies are the existence and fate of nitrogen as ammonia, pH and temperature levels, moisture content and the economics of alternative disposal methods. Further advancement of these technologies is currently receiving increased interest, both academically and commercially. However, significant financial incentives are required to attract the agricultural industry.

  5. Cost benefit analysis of remediation alternatives for controlling the flux of strontium-90 into the Columbia River

    International Nuclear Information System (INIS)

    Gustafson, F.W.; Todd, M.E.

    1993-09-01

    The release of large volumes of water to waste disposal cribs at the Hanford Site's 100-N Area caused contaminants, principally strontium-90, to be carried toward the Columbia River through the groundwater. Since shutdown of the N Reactor, these releases have been discontinued, although small water flows continue to be discharged to the 1325-N crib. Most of the contamination which is now transported to the river is occurring as a result of the natural groundwater movement. The contaminated groundwater at N Springs flows into the river through seeps and springs along the river's edge. An expedited response action (ERA) has been proposed to eliminate or restrict the flux of strontium-90 into the river. A cost benefit analysis of potential remedial alternatives was completed that recommends the alternative which best meets given selection criteria prescribed by the Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA). The methodology used for evaluation, cost analysis, and alternative recommendation is the engineering evaluation/cost analysis (EE/CA). Complete remediation of the contaminated groundwater beneath 100-N Area was not a principal objective of the analysis. The objective of the cost benefit analysis was to identify a remedial alternative that optimizes the degree of benefit produced for the costs incurred

  6. Preliminary disposal limits, plume interaction factors, and final disposal limits

    Energy Technology Data Exchange (ETDEWEB)

    Flach, G. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL)

    2018-01-11

    In the 2008 E-Area Performance Assessment (PA), each final disposal limit was constructed as the product of a preliminary disposal limit and a plume interaction factor. The following mathematical development demonstrates that performance objectives are generally expected to be satisfied with high confidence under practical PA scenarios using this method. However, radionuclides that experience significant decay between a disposal unit and the 100-meter boundary, such as H-3 and Sr-90, can challenge performance objectives, depending on the disposed-of waste composition, facility geometry, and the significance of the plume interaction factor. Pros and cons of analyzing single disposal units or multiple disposal units as a group in the preliminary disposal limits analysis are also identified.

  7. Study on the background information for the R and D of geological disposal

    International Nuclear Information System (INIS)

    Matsui, Kazuaki; Hirusawa, Shigenobu; Komoto, Harumi

    2001-02-01

    It is quite important for Japan Nuclear Cycle Development Institute (JNC) to analyze the R and D items after 'H12 report' and also provide their results of R and D activities to general public effectively. Recognizing the importance of the social consensus to the geological disposal, relating background informations were to be picked up. In this fiscal year, following two main topics were selected and studied. 1. Research and analysis on the options for the geological disposal concept. The major nuclear power-generating countries have almost all chosen deep geological disposal as preferred method for HLW disposal. Since 1990's, to make the geological disposal flexible, the alternative concepts for the disposal of HLW have been discussed promoting the social acceptance. In this context, recent optional discussions and international evaluations on the following topics were studied and summarized. (1) Reversibility of waste disposal/Retrievability of waste/Waste monitoring, (2) Long-term storage concept and its effectiveness, (3) Present position and role of international disposal. 2. Research and analysis on some educational materials collected from foreign countries. Although geological disposals is scheduled to start still in future, it is quite important to study the procedures to attract younger generation and get their proper perceptions on the nuclear energy and waste problems. As the supporting analysis to implement strategically the public relational activities for JNC's geological disposal R and D, particular attention was focused on the educational materials obtained in the last year's survey. Representative educational materials were selected and following items were studied and summarized. (1) Basic approach, positioning and characteristics of the educational materials, (2) Detailed analysis of the representatively selected educational materials, (3) Comparison of the analyzed characteristics and study on its feedback to Japanese materials. (author)

  8. Evaluation of waste disposal by shale fracturing

    International Nuclear Information System (INIS)

    Weeren, H.O.

    1976-02-01

    The shale fracturing process is evaluated as a means for permanent disposal of radioactive intermediate level liquid waste generated at the Oak Ridge National Laboratory. The estimated capital operating and development costs of a proposed disposal facility are compared with equivalent estimated costs for alternative methods of waste fixation

  9. Disposal of high-level waste from nuclear power plants in Denmark. Salt dome investigations. v.1

    International Nuclear Information System (INIS)

    1981-01-01

    A summary is presented of a report in five volumes on possible disposal of radioactive waste in Denmark. The investigation was made by the Danish electric utilities ELKRAFT and ELSAM at the request of the Danish Government. The investigation proved it possible to consider two alternative designs for a disposal facility, one based on the deposition of waste in individual, deep holes, the other on placing the waste in mine galleries. A safety analysis was completed with the Mors dome as example. The purpose of the analysis was to prove whether safe disposal of high-level waste in Denmark was feasible. The utilities concluded that the results of the analysis were satisfactory and the report is now being assessed by the authorities. (BP)

  10. Direct ultimate disposal of spent fuel DEAB. Systems analysis. Ultimate disposal concepts. Final report. Main volume

    International Nuclear Information System (INIS)

    Wahl, A.

    1995-10-01

    The results elaborated under the project, systems analysis of mixed radwaste disposal concepts and systems analysis of ultimate disposal concepts, provide a comprehensive description and assessment of a radwaste repository, for heat generating wastes and for wastes with negligible heat generation, and thus represent the knowledge basis for forthcoming planning work for a repository in an abandoned salt mine. A fact to be considered is that temperature field calculations have shown that there is room for further optimization with regard to the mine layout. The following aspects have been analysed: (1) safety of operation; (2) technical feasibility and realisation and licensability of the concepts; (3) operational aspects; (4) varieties of utilization of the salt dome for the intended purpose (boreholes for waste emplacement, emplacement in galleries, multi-horizon systems); (5) long-term structural stability of the mine; (6) economic efficiency; (7) nuclear materials safeguards. (orig./HP) [de

  11. Corrective Action Investigation Plan for Corrective Action Unit 137: Waste Disposal Sites, Nevada Test Site, Nevada

    International Nuclear Information System (INIS)

    Wickline, Alfred

    2005-01-01

    This Corrective Action Investigation Plan (CAIP) contains project-specific information including facility descriptions, environmental sample collection objectives, and criteria for conducting site investigation activities at Corrective Action Unit (CAU) 137: Waste Disposal Sites. This CAIP has been developed in accordance with the ''Federal Facility Agreement and Consent Order'' (FFACO) (1996) that was agreed to by the State of Nevada, the U.S. Department of Energy (DOE), and the U.S. Department of Defense. Corrective Action Unit 137 contains sites that are located in Areas 1, 3, 7, 9, and 12 of the Nevada Test Site (NTS), which is approximately 65 miles (mi) northwest of Las Vegas, Nevada (Figure 1-1). Corrective Action Unit 137 is comprised of the eight corrective action sites (CASs) shown on Figure 1-1 and listed below: (1) CAS 01-08-01, Waste Disposal Site; (2) CAS 03-23-01, Waste Disposal Site; (3) CAS 03-23-07, Radioactive Waste Disposal Site; (4) CAS 03-99-15, Waste Disposal Site; (5) CAS 07-23-02, Radioactive Waste Disposal Site; (6) CAS 09-23-07, Radioactive Waste Disposal Site; (7) CAS 12-08-01, Waste Disposal Site; and (8) CAS 12-23-07, Waste Disposal Site. The Corrective Action Investigation (CAI) will include field inspections, radiological surveys, geophysical surveys, sampling of environmental media, analysis of samples, and assessment of investigation results, where appropriate. Data will be obtained to support corrective action alternative evaluations and waste management decisions. The CASs in CAU 137 are being investigated because hazardous and/or radioactive constituents may be present in concentrations that could potentially pose a threat to human health and the environment. Existing information on the nature and extent of potential contamination is insufficient to evaluate and recommend corrective action alternatives for the CASs. Additional information will be generated by conducting a CAI before evaluating and selecting corrective action

  12. Historical perspective, economic analysis, and regulatory analysis of the impacts of waste partitioning-transmutation on the disposal of radioactive wastes

    International Nuclear Information System (INIS)

    Forsberg, C.W.; Croff, A.G.; Kocher, D.C.

    1990-10-01

    Partitioning-transmutation, sometimes called actinide burning, is an alternative approach to high-level radioactive waste management. It consists of removing long-lived radionuclides from wastes and destroying those radionuclides, thus reducing the long-term hazards of radioactive waste. It was studied in detail in the 1970's. New developments in technology and other factors are resulting in a reexamination of this waste management option. This report consists of three papers which summarize the historical work, update the analysis of the costs of waste disposal, and describe current regulatory requirements which might be impacted by P-T. The papers provide a starting point for future research on P-T. 152 refs., 2 figs., 19 tabs

  13. Nuclear waste disposal: achieving adequate financing - special study

    International Nuclear Information System (INIS)

    Quasebarth, M.V.

    1984-01-01

    An analysis by the Congressional Budget Office (CBO) evaluates whether the current one mill fee now charged to nuclear-electricity consumers will adequately finance the waste disposal program. The CBO found that, if the fee is adjusted annually for inflation, it should provide enough revenues to cover all program costs under all nuclear growth forecasts. If the fee is unchanged, however, the fees will be inadequate if inflation exceeds 3% annually. The report suggests two alternatives for fee revision, but makes no recommendations. The alternatives are to increase the fee only at specific intervals or to automatically adjust the fee through indexation. The report examines the effect of delaying the program, cost overruns, and alternative inflation rate and interest rate assumptions. 3 figures, 12 tables

  14. Practical evaluations of low-level waste disposal facilities

    International Nuclear Information System (INIS)

    Rogers, V.C.

    1989-01-01

    In general, there have been about four main tools that have been used to assist in selecting a disposal technology and in evaluating that technology: Legislative direction; Operator selection; Multiattribute utility estimation; and Risk assessment and cost benefit evaluation. The first technique, legislative direction, is an important factor in determining the range of disposal technologies that may be considered. Some host state entities have chosen not to participate in the disposal technology selection, but will let the facility operator propose and defend his preferred facility concept in the license application. Multiattribute utility estimation is a widely used tool for evaluating technologies, particularly in the preliminary stages of selecting a disposal technology when significant technical and institutional information is missing. Many factors, including a range of technical, safety, environmental, societal, political, and economic concerns must be considered in the selection process. Many of these are hard to quantify and not all are of equal importance. Multiattrubute utility estimation allows for these factors to be considered in selecting a technology with incomplete information. This chapter provides description of two analysis techniques: multiattribute utility estimation and cost benefit evaluation. Both can be used to help profile disposal alternatives in relation to specific factors or criteria

  15. A sensitivity analysis of the WIPP disposal room model: Phase 1

    Energy Technology Data Exchange (ETDEWEB)

    Labreche, D.A.; Beikmann, M.A. [RE/SPEC, Inc., Albuquerque, NM (United States); Osnes, J.D. [RE/SPEC, Inc., Rapid City, SD (United States); Butcher, B.M. [Sandia National Labs., Albuquerque, NM (United States)

    1995-07-01

    The WIPP Disposal Room Model (DRM) is a numerical model with three major components constitutive models of TRU waste, crushed salt backfill, and intact halite -- and several secondary components, including air gap elements, slidelines, and assumptions on symmetry and geometry. A sensitivity analysis of the Disposal Room Model was initiated on two of the three major components (waste and backfill models) and on several secondary components as a group. The immediate goal of this component sensitivity analysis (Phase I) was to sort (rank) model parameters in terms of their relative importance to model response so that a Monte Carlo analysis on a reduced set of DRM parameters could be performed under Phase II. The goal of the Phase II analysis will be to develop a probabilistic definition of a disposal room porosity surface (porosity, gas volume, time) that could be used in WIPP Performance Assessment analyses. This report documents a literature survey which quantifies the relative importance of the secondary room components to room closure, a differential analysis of the creep consolidation model and definition of a follow-up Monte Carlo analysis of the model, and an analysis and refitting of the waste component data on which a volumetric plasticity model of TRU drum waste is based. A summary, evaluation of progress, and recommendations for future work conclude the report.

  16. Environmental impact statement for initiation of transuranic waste disposal at the waste isolation pilot plant

    International Nuclear Information System (INIS)

    Johnson, H.E.; Whatley, M.E.

    1996-01-01

    WIPP's long-standing mission is to demonstrate the safe disposal of TRU waste from US defense activities. In 1980, to comply with NEPA, US DOE completed its first environmental impact statement (EIS) which compared impacts of alternatives for TRU waste disposal. Based on this 1980 analysis, DOE decided to construct WIPP in 1981. In a 1990 decision based on examination of alternatives in a 1990 Supplemental EIS, DOE decided to continue WIPP development by proceeding with a testing program to examine WIPP's suitability as a TRU waste repository. Now, as DOE's Carlsbad Area Office (CAO) attempts to complete its regulatory obligations to begin WIPP disposal operations, CAO is developing WIPP's second supplemental EIS (SEIS-II). To complete the SEIS-II, CAO will have to meet a number of challenges. This paper explores both the past and present EISs prepared to evaluate the suitability of WIPP. The challenges in completing an objective comparison of alternatives, while also finalizing other critical-path compliance documents, controlling costs, and keeping stakeholders involved during the decision-making process are addressed

  17. Usability study of a novel, self-lighted, disposable speculum: military applications.

    Science.gov (United States)

    Jones, Christina L; Gruber, Daniel D; Warner, William; Buller, Jerome L

    2013-04-01

    Data collected from a postutilization questionnaire were used to evaluate the usability of the OfficeSPEC disposable vaginal speculum, specifically the effectiveness, efficiency, and acceptability, in clinical, hospital, and austere environments. Usability data analysis showed the OfficeSPEC speculum had an effectiveness rating of 4.6/5, efficiency rating of 4.5/5, and acceptability rating of 4.6/5; overall usability in deployed environments was favorable. The overall rankings were 3.4 for plastic, 4.2 for metal (p disposable speculum as a reasonable alternative with yearly cost of $129,200, compared to traditional metal ($209,100) and plastic ($319,175). By evaluating the OfficeSPEC speculum within a usability framework, it proved to be practical, viable alternative in all environments, particularly in the forward deployed environment. Reprint & Copyright © 2013 Association of Military Surgeons of the U.S.

  18. Financing of radioactive waste disposal. Finanzierung der nuklearen Entsorgung

    Energy Technology Data Exchange (ETDEWEB)

    Reich, J

    1989-01-01

    Waste disposal is modelled as a financial calculus. In this connection the particularity is not primarily the dimension to be expected of financial requirement but above all the uncertainty of financial requirement as well as the ecological, socio-economic and especially also the temporal dimension of the Nuclear Waste Disposal project (disposal of spent fuel elements from light-water reactors with and without reprocessing, decommissioning = safe containment and disposal of nuclear power plants, permanent isolation of radioactive waste from the biosphere, intermediate storage). Based on the above mentioned factors the author analyses alternative approaches of financing or financial planning. He points out the decisive significance of the perception of risks or the evaluation of risks by involved or affected persons - i.e. the social acceptance of planned and designed waste disposal concepts - for the achievement and assessment of alternative solutions. With the help of an acceptance-specific risk measure developed on the basis of a mathematical chaos theory he illustrates, in a model, the social influence on the financing of nuclear waste disposal. (orig./HP).

  19. Deep geological disposal system development; mechanical structural stability analysis of spent nuclear fuel disposal canister under the internal/external pressure variation

    Energy Technology Data Exchange (ETDEWEB)

    Kwen, Y. J.; Kang, S. W.; Ha, Z. Y. [Hongik University, Seoul (Korea)

    2001-04-01

    This work constitutes a summary of the research and development work made for the design and dimensioning of the canister for nuclear fuel disposal. Since the spent nuclear fuel disposal emits high temperature heats and much radiation, its careful treatment is required. For that, a long term(usually 10,000 years) safe repository for spent fuel disposal should be securred. Usually this repository is expected to locate at a depth of 500m underground. The canister construction type introduced here is a solid structure with a cast iron insert and a corrosion resistant overpack, which is designed for spent nuclear fuel disposal in a deep repository in the crystalline bedrock, which entails an evenly distributed load of hydrostatic pressure from undergroundwater and high pressure from swelling of bentonite buffer. Hence, the canister must be designed to withstand these high pressure loads. Many design variables may affect the structural strength of the canister. In this study, among those variables array type of inner baskets and thicknesses of outer shell and lid and bottom are tried to be determined through the mechanical linear structural analysis, thicknesses of outer shell is determined through the nonlinear structural analysis, and the bentonite buffer analysis for the rock movement is conducted through the of nonlinear structural analysis Also the thermal stress effect is computed for the cast iron insert. The canister types studied here are one for PWR fuel and another for CANDU fuel. 23 refs., 60 figs., 23 tabs. (Author)

  20. Techno-economical Analysis of High Level Waste Storage and Disposal Options

    International Nuclear Information System (INIS)

    Bace, M.; Trontl, K.; Vrankic, K.

    2002-01-01

    Global warming and instability of gas and oil prices are redefining the role of nuclear energy in electrical energy production. A production of high-level radioactive waste (HLW), during the nuclear power plant operation and a danger of high level waste mitigation to the environment are considered by the public as a main obstacle of accepting the nuclear option. As economical and technical aspects of the back end of fuel cycle will affect the nuclear energy acceptance the techno-economical analysis of different methods for high level waste storage and disposal has to be performed. The aim of this paper is to present technical and economical characteristics of different HLW storage and disposal technologies. The final choice of a particular HLW management method is closely connected to the selection of a fuel cycle type: open or closed. Wet and dry temporary storage has been analyzed including different types of spent fuel pool capacity increase methods, different pool location (at reactor site and away from reactor site) as well as casks and vault system of dry storage. Since deep geological deposition is the only disposal method with a realistic potential, we focused our attention on that disposal technology. Special attention has been given to the new idea of international and regional disposal location. The analysis showed that a coexistence of different storage methods and deep geological deposition is expected in the future, regardless of the fuel cycle type. (author)

  1. Tank waste remediation system retrieval and disposal mission phase 1 financial analysis

    International Nuclear Information System (INIS)

    Wells, M.W.

    1998-01-01

    The purpose of the Tank Waste Remediation System (TWRS) Retrieval and Disposal Mission Phase 1 Financial Analysis is to provide a quantitative and qualitative cost and schedule risk analysis of HNF-1946, Tank Waste Remediation System Retrieval and Disposal Mission Initial Updated Baseline (Swita et al. 1998). The Updated Baseline (Section 3.0) is compared to the current TWRS Project Multi-Year Work Plan (MYWP) for fiscal year (FY) 1998 and target budgets for FY 1999 through FY 2011 (Section 4.1). The analysis then evaluates the executability of HNF-1946 (Sections 4.2 through 4.5) and recommends a path forward for risk mitigation (Sections 4.6, 4.7, and 5.0). A sound systems engineering approach was applied to understand and analyze the Phase 1B Retrieval and Disposal mission. Program and Level 1 Logics were decomposed to Level 8 of the Work Breakdown Structure (WBS) where logic was detailed, scope was defined, detail durations and estimates prepared, and resource loaded schedules developed. Technical Basis Review (TBR) packages were prepared which include this information and, in addition, defined the enabling assumptions for each task, and the risks associated with performance. This process is discussed in Section 2.1. Detailed reviews at the subactivity within the Level 1 Logic TBR levels were conducted to provide the recommended solution to the Phase 1B Retrieval and Disposal Mission. Independent cost analysis and risk assessments were performed by members of the Lockheed Martin Hanford Corporation (LMHC) Business Management and Chief Financial Officer organization along with specialists in risk analysis from TRW, Inc. and Lockheed Martin Energy Systems. The process evaluated technical, schedule, and cost risk by category (program specific fixed and variable, integrated program, and programmatic) based on risk certainly from high probability well defined to very low probability that is not bounded or priceable as discussed in Section 2.2. The results have been

  2. Scenario analysis for the postclosure assessment of the Canadian concept for nuclear fuel waste disposal

    Energy Technology Data Exchange (ETDEWEB)

    Goodwin, B W; Stephens, M E; Davison, C C; Johnson, L H; Zach, R

    1994-12-01

    AECL Research has developed and evaluated a concept for disposal of Canada`s nuclear fuel waste involving deep underground disposal of the waste in intrusive igneous rock of the Canadian Shield. The postclosure assessment of this concept focusses on the effects on human health and the environment due to potential contaminant releases into the biosphere after the disposal vault is closed. Both radiotoxic and chemically toxic contaminants are considered. One of the steps in the postclosure assessment process is scenario analysis. Scenario analysis identifies factors that could affect the performance of the disposal system and groups these factors into scenarios that require detailed quantitative evaluation. This report documents a systematic procedure for scenario analysis that was developed for the postclosure assessment and then applied to the study of a hypothetical disposal system. The application leads to a comprehensive list of factors and a set of scenarios that require further quantitative study. The application also identifies a number of other factors and potential scenarios that would not contribute significantly to environmental and safety impacts for the hypothetical disposal system. (author). 46 refs., 3 tabs., 3 figs., 2 appendices.

  3. Scenario analysis for the postclosure assessment of the Canadian concept for nuclear fuel waste disposal

    International Nuclear Information System (INIS)

    Goodwin, B.W.; Stephens, M.E.; Davison, C.C.; Johnson, L.H.; Zach, R.

    1994-12-01

    AECL Research has developed and evaluated a concept for disposal of Canada's nuclear fuel waste involving deep underground disposal of the waste in intrusive igneous rock of the Canadian Shield. The postclosure assessment of this concept focusses on the effects on human health and the environment due to potential contaminant releases into the biosphere after the disposal vault is closed. Both radiotoxic and chemically toxic contaminants are considered. One of the steps in the postclosure assessment process is scenario analysis. Scenario analysis identifies factors that could affect the performance of the disposal system and groups these factors into scenarios that require detailed quantitative evaluation. This report documents a systematic procedure for scenario analysis that was developed for the postclosure assessment and then applied to the study of a hypothetical disposal system. The application leads to a comprehensive list of factors and a set of scenarios that require further quantitative study. The application also identifies a number of other factors and potential scenarios that would not contribute significantly to environmental and safety impacts for the hypothetical disposal system. (author). 46 refs., 3 tabs., 3 figs., 2 appendices

  4. Life cycle assessment of alternative sewage sludge disposal methods; Oekobilanz von Klaerschlammentsorgungsalternativen

    Energy Technology Data Exchange (ETDEWEB)

    Fehrenbach, H. [Institut fuer Energie- und Umweltforschung (ifeu), Heidelberg (Germany)

    1994-10-01

    At present there are three principal options for sewage sludge disposal in use or under discussion: agricultural utilisation - landfilling - cold pretreatment prior to disposal or utilisation (e.g., composting or fermentation) - thermal pretreatment prior to disposal or utilisation (e.g., monocombustion, co-combustion, pyrolysis, gasification). 10% of sewage sludge is currently combusted, 60% is landfilled, and 30% is used for agriculture. The ifeu Institute has carried out several studies which examine and compare the environmental impact of sewage sludge disposal options. [Deutsch] Zur Entsorgung bzw. Verwertung von Klaerschlamm stehen derzeit drei grundsaetzliche Optionen in Anwendung oder werden diskutiert: - Landwirtschaftliche Verwertung - Deponierung - kalte Vorbehandlung vor Deponierung oder Verwertung (z.B. Kompostierung oder Vergaerung) - thermische Vorbehandlung vorn Deponierung oder Verwertung (z.B. Mono- oder Mitverbrennung, Pyrolyse, Vergasung). Verbrannt werden gegenwaertig etwa 10%, 60% deponiert und 30% landwirschaftlich verwertet. Das ifeu-Institut hat in verschiedenen Arbeiten die Umweltauswirkungen von Klaerschlammentsorgungsoptionen untersucht und gegenuebergestellt. (orig./SR)

  5. Behavior of cement paste as backfill in waste disposal boreholes

    International Nuclear Information System (INIS)

    Ferreira, Eduardo G.A.; Isiki, Vera L.K.; Miyamoto, Hissae; Marumo, Julio T.; Vicente, Roberto

    2011-01-01

    The Radioactive Waste Management Laboratory (GRR) at the Nuclear and Energy Research Institute (IPEN) in Sao Paulo, Brazil, is developing the concept a repository for disposition of disused sealed radioactive sources in a deep borehole, aiming at providing a feasible and inexpensive alternative for final disposal. A relevant fraction of the Brazilian inventory of sources has long half-life which prevents them to be disposed of in shallow ground disposal facilities. In the concept of repository under study, Portland cement paste is intended to be used as a backfill between the steel casing and the geological formation around the borehole. Cement paste will function as structural, an additional barrier against the migration of radionuclides outside the repository, and as a blockage against the transport of water between the different strata of the geological setting. The durability of cementitious materials under the conditions prevailing at the depth of disposal is as yet unknown. The objective of this research is to investigate the behavior of the cement paste and to estimate its service life. In this paper we present the results of mechanical strength measurements and chemical and mineralogical analysis of samples to detect the changes caused by radiation, temperature and aggressive chemicals present in ground water. Techniques of analysis included Inductively Coupled Plasma Atomic Emission Spectroscopy, Ion Chromatography, X-Ray Diffraction, and Thermo-Gravimetric Analysis. (author)

  6. Waste Isolation Pilot Plant disposal phase: Draft supplemental Environmental Impact Statement

    International Nuclear Information System (INIS)

    1996-11-01

    Purpose of this SEIS-II is to provide information on environmental impacts regarding DOE's proposed disposal operations at WIPP. To that end, SEIS-II was prepared to assess the potential impacts of continuing the phased development of WIPP as a geologic repository for the safe disposal of transuranic (TRU) waste. SEIS-II evaluates a Proposed Action, three Action Alternatives, and two No Action Alternatives. The Proposed Action describes the treatment and disposal of the Basic Inventory of TRU waste over a 35-year period. SEIS-II evaluates environmental impacts resulting from the various treatment options; 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 implementation of the alternatives are discussed

  7. Inadvertent Intruder Analysis For The Portsmouth On-Site Waste Disposal Facility (OSWDF)

    Energy Technology Data Exchange (ETDEWEB)

    Smith, Frank G. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL); Phifer, Mark A. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL)

    2014-01-22

    The inadvertent intruder analysis considers the radiological impacts to hypothetical persons who are assumed to inadvertently intrude on the Portsmouth OSWDF site after institutional control ceases 100 years after site closure. For the purposes of this analysis, we assume that the waste disposal in the OSWDF occurs at time zero, the site is under institutional control for the next 100 years, and inadvertent intrusion can occur over the following 1,000 year time period. Disposal of low-level radioactive waste in the OSWDF must meet a requirement to assess impacts on such individuals, and demonstrate that the effective dose equivalent to an intruder would not likely exceed 100 mrem per year for scenarios involving continuous exposure (i.e. chronic) or 500 mrem for scenarios involving a single acute exposure. The focus in development of exposure scenarios for inadvertent intruders was on selecting reasonable events that may occur, giving consideration to regional customs and construction practices. An important assumption in all scenarios is that an intruder has no prior knowledge of the existence of a waste disposal facility at the site. Results of the analysis show that a hypothetical inadvertent intruder at the OSWDF who, in the worst case scenario, resides on the site and consumes vegetables from a garden established on the site using contaminated soil (chronic agriculture scenario) would receive a maximum chronic dose of approximately 7.0 mrem/yr during the 1000 year period of assessment. This dose falls well below the DOE chronic dose limit of 100 mrem/yr. Results of the analysis also showed that a hypothetical inadvertent intruder at the OSWDF who, in the worst case scenario, excavates a basement in the soil that reaches the waste (acute basement construction scenario) would receive a maximum acute dose of approximately 0.25 mrem/yr during the 1000 year period of assessment. This dose falls well below the DOE acute dose limit of 500 mrem/yr. Disposal inventory

  8. Greening Reversed-Phase Liquid Chromatography Methods Using Alternative Solvents for Pharmaceutical Analysis

    Directory of Open Access Journals (Sweden)

    Moussa Yabré

    2018-05-01

    Full Text Available The greening of analytical methods has gained increasing interest in the field of pharmaceutical analysis to reduce environmental impacts and improve the health safety of analysts. Reversed-phase high-performance liquid chromatography (RP-HPLC is the most widely used analytical technique involved in pharmaceutical drug development and manufacturing, such as the quality control of bulk drugs and pharmaceutical formulations, as well as the analysis of drugs in biological samples. However, RP-HPLC methods commonly use large amounts of organic solvents and generate high quantities of waste to be disposed, leading to some issues in terms of ecological impact and operator safety. In this context, greening HPLC methods is becoming highly desirable. One strategy to reduce the impact of hazardous solvents is to replace classically used organic solvents (i.e., acetonitrile and methanol with greener ones. So far, ethanol has been the most often used alternative organic solvent. Others strategies have followed, such as the use of totally aqueous mobile phases, micellar liquid chromatography, and ionic liquids. These approaches have been well developed, as they do not require equipment investments and are rather economical. This review describes and critically discusses the recent advances in greening RP-HPLC methods dedicated to pharmaceutical analysis based on the use of alternative solvents.

  9. Safety in the Chemical Laboratory: Contracts to Dispose of Laboratory Waste.

    Science.gov (United States)

    Fischer, Kenneth E.

    1985-01-01

    Presents a sample contract for disposing of hazardous wastes in an environmentally sound, timely manner in accordance with all federal, state, and local requirements. Addresses situations where hazardous waste must be disposed of outside the laboratory and where alternate disposal methods are not feasible. (JN)

  10. Ocean disposal option for bulk wastes containing naturally occurring radionuclides: an assessment case history

    International Nuclear Information System (INIS)

    Stull, E.A.; Merry-Libby, P.

    1985-01-01

    There are 180,000 m 3 of slightly contaminated radioactive wastes (36 pCi/g radium-226) currently stored at the US Department of Energy's Niagara Falls Storage Site (NFSS), near Lewiston, New York. These wastes resulted from the cleanup of soils that were contaminated above the guidelines for unrestricted use of property. An alternative to long-term management of these wastes on land is dispersal in the ocean. A scenario for ocean disposal is presented for excavation, transport, and emplacement of these wastes in an ocean disposal site. The potential fate of the wastes and impacts on the ocean environment are analyzed, and uncertainties in the development of two worst-case scenarios for dispersion and pathway analyses are discussed. Based on analysis of a worst-case pathway back to man, the incremental dose from ingesting fish containing naturally occurring radionuclides from ocean disposal of the NFSS wastes is insignificant. Ocean disposal of this type of waste appears to be a technically promising alternative to the long-term maintenance costs and eventual loss of containment associated with management in a near-surface land burial facility

  11. Risk management for outsourcing biomedical waste disposal – Using the failure mode and effects analysis

    International Nuclear Information System (INIS)

    Liao, Ching-Jong; Ho, Chao Chung

    2014-01-01

    Highlights: • This study is based on a real case in hospital in Taiwan. • We use Failure Mode and Effects Analysis (FMEA) as the evaluation method. • We successfully identify the evaluation factors of bio-medical waste disposal risk. - Abstract: Using the failure mode and effects analysis, this study examined biomedical waste companies through risk assessment. Moreover, it evaluated the supervisors of biomedical waste units in hospitals, and factors relating to the outsourcing risk assessment of biomedical waste in hospitals by referring to waste disposal acts. An expert questionnaire survey was conducted on the personnel involved in waste disposal units in hospitals, in order to identify important factors relating to the outsourcing risk of biomedical waste in hospitals. This study calculated the risk priority number (RPN) and selected items with an RPN value higher than 80 for improvement. These items included “availability of freezing devices”, “availability of containers for sharp items”, “disposal frequency”, “disposal volume”, “disposal method”, “vehicles meeting the regulations”, and “declaration of three lists”. This study also aimed to identify important selection factors of biomedical waste disposal companies by hospitals in terms of risk. These findings can serve as references for hospitals in the selection of outsourcing companies for biomedical waste disposal

  12. Risk management for outsourcing biomedical waste disposal – Using the failure mode and effects analysis

    Energy Technology Data Exchange (ETDEWEB)

    Liao, Ching-Jong; Ho, Chao Chung, E-mail: ho919@pchome.com.tw

    2014-07-15

    Highlights: • This study is based on a real case in hospital in Taiwan. • We use Failure Mode and Effects Analysis (FMEA) as the evaluation method. • We successfully identify the evaluation factors of bio-medical waste disposal risk. - Abstract: Using the failure mode and effects analysis, this study examined biomedical waste companies through risk assessment. Moreover, it evaluated the supervisors of biomedical waste units in hospitals, and factors relating to the outsourcing risk assessment of biomedical waste in hospitals by referring to waste disposal acts. An expert questionnaire survey was conducted on the personnel involved in waste disposal units in hospitals, in order to identify important factors relating to the outsourcing risk of biomedical waste in hospitals. This study calculated the risk priority number (RPN) and selected items with an RPN value higher than 80 for improvement. These items included “availability of freezing devices”, “availability of containers for sharp items”, “disposal frequency”, “disposal volume”, “disposal method”, “vehicles meeting the regulations”, and “declaration of three lists”. This study also aimed to identify important selection factors of biomedical waste disposal companies by hospitals in terms of risk. These findings can serve as references for hospitals in the selection of outsourcing companies for biomedical waste disposal.

  13. Verification of Sulfate Attack Penetration Rates for Saltstone Disposal Unit Modeling

    Energy Technology Data Exchange (ETDEWEB)

    Flach, G. P. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL)

    2015-05-12

    Recent Special Analysis modeling of Saltstone Disposal Units consider sulfate attack on concrete and utilize degradation rates estimated from Cementitious Barriers Partnership software simulations. This study provides an independent verification of those simulation results using an alternative analysis method and an independent characterization data source. The sulfate penetration depths estimated herein are similar to the best-estimate values in SRNL-STI-2013-00118 Rev. 2 and well below the nominal values subsequently used to define Saltstone Special Analysis base cases.

  14. COMPILATION OF DISPOSABLE SOLID WASTE CASK EVALUATIONS

    International Nuclear Information System (INIS)

    THIELGES, J.R.; CHASTAIN, S.A.

    2007-01-01

    The Disposable Solid Waste Cask (DSWC) is a shielded cask capable of transporting, storing, and disposing of six non-fuel core components or approximately 27 cubic feet of radioactive solid waste. Five existing DSWCs are candidates for use in storing and disposing of non-fuel core components and radioactive solid waste from the Interim Examination and Maintenance Cell, ultimately shipping them to the 200 West Area disposal site for burial. A series of inspections, studies, analyses, and modifications were performed to ensure that these casks can be used to safely ship solid waste. These inspections, studies, analyses, and modifications are summarized and attached in this report. Visual inspection of the casks interiors provided information with respect to condition of the casks inner liners. Because water was allowed to enter the casks for varying lengths of time, condition of the cask liner pipe to bottom plate weld was of concern. Based on the visual inspection and a corrosion study, it was concluded that four of the five casks can be used from a corrosion standpoint. Only DSWC S/N-004 would need additional inspection and analysis to determine its usefulness. The five remaining DSWCs underwent some modification to prepare them for use. The existing cask lifting inserts were found to be corroded and deemed unusable. New lifting anchor bolts were installed to replace the existing anchors. Alternate lift lugs were fabricated for use with the new lifting anchor bolts. The cask tiedown frame was modified to facilitate adjustment of the cask tiedowns. As a result of the above mentioned inspections, studies, analysis, and modifications, four of the five existing casks can be used to store and transport waste from the Interim Examination and Maintenance Cell to the disposal site for burial. The fifth cask, DSWC S/N-004, would require further inspections before it could be used

  15. COMPILATION OF DISPOSABLE SOLID WASTE CASK EVALUATIONS

    Energy Technology Data Exchange (ETDEWEB)

    THIELGES, J.R.; CHASTAIN, S.A.

    2007-06-21

    The Disposable Solid Waste Cask (DSWC) is a shielded cask capable of transporting, storing, and disposing of six non-fuel core components or approximately 27 cubic feet of radioactive solid waste. Five existing DSWCs are candidates for use in storing and disposing of non-fuel core components and radioactive solid waste from the Interim Examination and Maintenance Cell, ultimately shipping them to the 200 West Area disposal site for burial. A series of inspections, studies, analyses, and modifications were performed to ensure that these casks can be used to safely ship solid waste. These inspections, studies, analyses, and modifications are summarized and attached in this report. Visual inspection of the casks interiors provided information with respect to condition of the casks inner liners. Because water was allowed to enter the casks for varying lengths of time, condition of the cask liner pipe to bottom plate weld was of concern. Based on the visual inspection and a corrosion study, it was concluded that four of the five casks can be used from a corrosion standpoint. Only DSWC S/N-004 would need additional inspection and analysis to determine its usefulness. The five remaining DSWCs underwent some modification to prepare them for use. The existing cask lifting inserts were found to be corroded and deemed unusable. New lifting anchor bolts were installed to replace the existing anchors. Alternate lift lugs were fabricated for use with the new lifting anchor bolts. The cask tiedown frame was modified to facilitate adjustment of the cask tiedowns. As a result of the above mentioned inspections, studies, analysis, and modifications, four of the five existing casks can be used to store and transport waste from the Interim Examination and Maintenance Cell to the disposal site for burial. The fifth cask, DSWC S/N-004, would require further inspections before it could be used.

  16. Fissile Material Disposition Program: Deep Borehole Disposal Facility PEIS data input report for direct disposal. Direct disposal of plutonium metal/plutonium dioxide in compound metal canisters. Version 3.0

    Energy Technology Data Exchange (ETDEWEB)

    Wijesinghe, A.M.; Shaffer, R.J.

    1996-01-15

    The US Department of Energy (DOE) is examining options for disposing of excess weapons-usable nuclear materials [principally plutonium (Pu) and highly enriched uranium (HEU)] in a form or condition that is substantially and inherently more difficult to recover and reuse in weapons production. This report is the data input report for the Programmatic Environmental Impact Statement (PEIS). The PEIS examines the environmental, safety, and health impacts of implementing each disposition alternative on land use, facility operations, and site infrastructure; air quality and noise; water, geology, and soils; biotic, cultural, and paleontological resources; socioeconomics; human health; normal operations and facility accidents; waste management; and transportation. This data report is prepared to assist in estimating the environmental effects associated with the construction and operation of a Deep Borehole Disposal Facility, an alternative currently included in the PEIS. The facility projects under consideration are, not site specific. This report therefore concentrates on environmental, safety, and health impacts at a generic site appropriate for siting a Deep Borehole Disposal Facility.

  17. Fissile Material Disposition Program: Deep Borehole Disposal Facility PEIS data input report for direct disposal. Direct disposal of plutonium metal/plutonium dioxide in compound metal canisters. Version 3.0

    International Nuclear Information System (INIS)

    Wijesinghe, A.M.; Shaffer, R.J.

    1996-01-01

    The US Department of Energy (DOE) is examining options for disposing of excess weapons-usable nuclear materials [principally plutonium (Pu) and highly enriched uranium (HEU)] in a form or condition that is substantially and inherently more difficult to recover and reuse in weapons production. This report is the data input report for the Programmatic Environmental Impact Statement (PEIS). The PEIS examines the environmental, safety, and health impacts of implementing each disposition alternative on land use, facility operations, and site infrastructure; air quality and noise; water, geology, and soils; biotic, cultural, and paleontological resources; socioeconomics; human health; normal operations and facility accidents; waste management; and transportation. This data report is prepared to assist in estimating the environmental effects associated with the construction and operation of a Deep Borehole Disposal Facility, an alternative currently included in the PEIS. The facility projects under consideration are, not site specific. This report therefore concentrates on environmental, safety, and health impacts at a generic site appropriate for siting a Deep Borehole Disposal Facility

  18. Preliminary risk assessment for nuclear waste disposal in space. Volume I. Executive summary of technical report

    International Nuclear Information System (INIS)

    Rice, E.E.; Denning, R.S.; Friedlander, A.L.

    1982-01-01

    Three major conclusions come from this preliminary risk assessment of nuclear waste disposal in space. Preliminary estimates of space disposal risk are low, even with the estimated uncertainty bounds. If calculated mined geologic repository (MGR) release risks remain low, and the EPA requirements continue to be met, then no additional space disposal study effort is warranted. If risks perceived by the public are significant in the acceptance of mined geologic repositories, then consideration of space disposal as an MGR complement is warranted. As a result of this study, the following recommendations are made to NASA and the US DOE: During the continued evaluation of the mined geologic repository risk over the years ahead by DOE, if any significant increase in the calculated health risk is predicted for the MGR, then space disposal should be reevaluated at that time. The risks perceived by the public for the MGR should be evaluated on a broad basis by an independent organization to evaluate acceptance. If, in the future, MGR risks are found to be significant due to some presently unknown technical or social factor, and space disposal is selected as an alternative that may be useful in mitigating the risks, then the following space disposal study activities are recommended: improvement in chemical processing technology for wastes; payload accident response analysis; risk uncertainty analysis for both MGR and space disposal; health risk modeling that includes pathway and dose estimates; space disposal cost modeling; assessment of space disposal perceived (by public) risk benefit; and space systems analysis supporting risk and cost modeling

  19. Suitable woody species for a land application alternative to pulp and paper mill wastewater disposal

    International Nuclear Information System (INIS)

    Aw, M.; Wagner, M.R.

    1993-01-01

    Saline pulp and paper wastewater produced by Stone Container Corporation in Snowflake, Arizona was used to irrigate 32 different species/genotypes/hybrids of woody plants to test their suitability as an alternative treatment to the current wastewater disposal method. Suitability was measured in terms of survival and height growth. Among the 32 species, six were found to be a very good choice for wastewater treatment and biomass production. Their suitability is further justified by the fact that some have salt tolerance and others fix nitrogen. These species are Tamarix ramosissima, Atriplex canescens, Robinia pseudoacacia, Eleagnus angustifoliz, Ulmus pumila, and Populus deltoides x Populus nigra. Three other species are possible candidates. These include Caragana arborescens, Gleditsia triacanthos and Populus deltoides var. siouxland. In general, conifers performed poorly because of the harsh environment and other silvicultural problems

  20. Economic and energy analysis about disposal interventions of waste tires produced in Calabria

    International Nuclear Information System (INIS)

    Florio, Gaetano; Cersosimo, Attilio.

    1997-01-01

    The present paper refers to an analysis aimed at researching disposal strategies, for waste tires produced in Calabria, which ensure correct disposal with regard to environmental compatibility and their evaluation in terms of material recovery and energy. The starting point has been an estimate of the quantities of potentially usable waste tires and disposal methods currently employed. It has therefore been possible to identify two specific disposal proposals for which an economic and energy evaluation has been conducted. The last part of the paper has faced the problem of plant location under consideration, with the aim of determining, for both proposal, the cost that each producer must bear to have his waste tires eliminated

  1. Near-surface land disposal

    International Nuclear Information System (INIS)

    Kittel, J.H.

    1989-01-01

    The Radioactive Waste Management Handbook provides a comprehensive, systematic treatment of nuclear waste management. Near-Surface Land Disposal, the first volume, is a primary and secondary reference for the technical community. To those unfamiliar with the field, it provides a bridge to a wealth of technical information, presenting the technology associated with the near-surface disposal of low or intermediate level wastes. Coverage ranges from incipient planning to site closure and subsequent monitoring. The book discusses the importance of a systems approach during the design of new disposal facilities so that performance objectives can be achieved; gives an overview of the radioactive wastes cosigned to near-surface disposal; addresses procedures for screening and selecting sites; and emphasizes the importance of characterizing sites and obtaining reliable geologic and hydrologic data. The planning essential to the development of particular sites (land acquisition, access, layout, surface water management, capital costs, etc.) is considered, and site operations (waste receiving, inspection, emplacement, closure, stabilization, etc.) are reviewed. In addition, the book presents concepts for improved confinement of waste, important aspects of establishing a monitoring program at the disposal facility, and corrective actions available after closure to minimize release. Two analytical techniques for evaluating alternative technologies are presented. Nontechnical issues surrounding disposal, including the difficulties of public acceptance are discussed. A glossary of technical terms is included

  2. 30 CFR 816.73 - Disposal of excess spoil: Durable rock fills.

    Science.gov (United States)

    2010-07-01

    ... 30 Mineral Resources 3 2010-07-01 2010-07-01 false Disposal of excess spoil: Durable rock fills...-SURFACE MINING ACTIVITIES § 816.73 Disposal of excess spoil: Durable rock fills. The regulatory authority may approve the alternative method of disposal of excess durable rock spoil by gravity placement in...

  3. 30 CFR 817.73 - Disposal of excess spoil: Durable rock fills.

    Science.gov (United States)

    2010-07-01

    ... 30 Mineral Resources 3 2010-07-01 2010-07-01 false Disposal of excess spoil: Durable rock fills...-UNDERGROUND MINING ACTIVITIES § 817.73 Disposal of excess spoil: Durable rock fills. The regulatory authority may approve the alternative method of disposal of excess durable rock spoil by gravity placement in...

  4. The effect of alternative constraints in radioactive waste disposal on minimum cost scenarios

    International Nuclear Information System (INIS)

    Laundy, R.S.; James, A.R.; Groom, M.S.

    1985-01-01

    The purpose of this report is to describe the results of a set of assessments of the optimum waste assignment and disposal schedule for intermediate and low level radioactive wastes using the DISPOSALS Linear Programming Model developed by CAP Scientific. The main purpose of the present study is to demonstrate the applicability of the DISPOSALS model to the field of radioactive waste management. The results presented provide a good indication of the practicability and usefulness of the model and also provide a number of detailed conclusions regarding specific cases. (author)

  5. Depleted uranium disposal options evaluation

    International Nuclear Information System (INIS)

    Hertzler, T.J.; Nishimoto, D.D.; Otis, M.D.

    1994-05-01

    The Department of Energy (DOE), Office of Environmental Restoration and Waste Management, has chartered a study to evaluate alternative management strategies for depleted uranium (DU) currently stored throughout the DOE complex. Historically, DU has been maintained as a strategic resource because of uses for DU metal and potential uses for further enrichment or for uranium oxide as breeder reactor blanket fuel. This study has focused on evaluating the disposal options for DU if it were considered a waste. This report is in no way declaring these DU reserves a ''waste,'' but is intended to provide baseline data for comparison with other management options for use of DU. To PICS considered in this report include: Retrievable disposal; permanent disposal; health hazards; radiation toxicity and chemical toxicity

  6. New Low-Level Radioactive Waste Storage/Disposal Facilities at the Savannah River Plant: Environmental information document

    International Nuclear Information System (INIS)

    Cook, J.R.; Grant, M.W.; Towler, O.O.

    1987-04-01

    Site selection, alternative facilities, and alternative operations are described for a new low-level solid radioactive waste storage/disposal operation at the Savannah River Plant. Performance assessments and cost estimates for the alternatives are presented. Appendix G contains an intensive archaeological survey of alternative waste disposal areas in the Savannah River Plant area. 117 refs., 99 figs., 128 tabs

  7. Removal of Legacy Low-Level Waste Reactor Moderator De-ionizer Resins Highly Contaminated with Carbon-14 from the 'Waste with no Path to Disposal List' Through Innovative Technical Analysis and Performance Assessment Techniques

    International Nuclear Information System (INIS)

    Goldston, W.T.; Hiergesell, R.A.; Kaplan, D.I.; Pope, H.L.

    2006-01-01

    At the Savannah River Site (SRS), nuclear production reactors used de-ionizers to control the chemistry of the reactor moderator during their operation to produce nuclear materials primarily for the weapons program. These de-ionizers were removed from the reactors and stored as a legacy waste and due to the relatively high carbon-14 (C-14) contamination (i.e., on the order of 740 giga becquerel (GBq) (20 curies) per de-ionizer) were considered a legacy 'waste with no path to disposal'. Considerable progress has been made in consideration of a disposal path for the legacy reactor de-ionizers. Presently, 48 - 50 de-ionizers being stored at SRS have 'no path to disposal' because the disposal limit for C-14 in the SRS's low-level waste disposal facility's Intermediate Level Vault (ILV) is only 160 GBq (4.2 curies) per vault. The current C-14 ILV disposal limit is based on a very conservative analysis of the air pathway. The paper will describe the alternatives that were investigated that resulted in the selection of a route to pursue. This paper will then describe SRS's efforts to reduce the conservatism in the analysis, which resulted in a significantly larger C-14 disposal limit. The work consisted of refining the gas-phase analysis to simulate the migration of C-14 from the waste to the ground surface and evaluated the efficacy of carbonate chemistry in cementitious environment of the ILV for suppressing the volatilization of C-14. During the past year, a Special Analysis was prepared for Department of Energy approval to incorporate the results of these activities that increased the C-14 disposal limits for the ILV, thus allowing for disposal of the Reactor Moderator De-ionizers. Once the Special Analysis is approved by DOE, the actual disposal would be dependent on priority and funding, but the de-ionizers will be removed from the 'waste with no path to disposal list'. (authors)

  8. Disposal criticality analysis for aluminum-based DOE fuels

    International Nuclear Information System (INIS)

    Davis, J.W.; Gottlieb, P.

    1997-11-01

    This paper describes the disposal criticality analysis for canisters containing aluminum-based Department of Energy fuels from research reactors. Different canisters were designed for disposal of highly enriched uranium (HEU) and medium enriched uranium (MEU) fuel. In addition to the standard criticality concerns in storage and transportation, such as flooding, the disposal criticality analysis must consider the degradation of the fuel and components within the waste package. Massachusetts Institute of Technology (MIT) U-Al fuel with 93.5% enriched uranium and Oak Ridge Research Reactor (ORR) U-Si-Al fuel with 21% enriched uranium are representative of the HEU and MEU fuel inventories, respectively. Conceptual canister designs with 64 MIT assemblies (16/layer, 4 layers) or 40 ORR assemblies (10/layer, 4 layers) were developed for these fuel types. Borated stainless steel plates were incorporated into a stainless steel internal basket structure within a 439 mm OD, 15 mm thick XM-19 canister shell. The Codisposal waste package contains 5 HLW canisters (represented by 5 Defense Waste Processing Facility canisters from the Savannah River Site) with the fuel canister placed in the center. It is concluded that without the presence of a fairly insoluble neutron absorber, the long-term action of infiltrating water can lead to a small, but significant, probability of criticality for both the HEU and MEU fuels. The use of 1.5kg of Gd distributed throughout the MIT fuel and the use of carbon steels for the structural basket or 1.1 kg of Gd distributed in the ORR fuel will reduce the probability of criticality to virtually zero for both fuels

  9. Geological disposal of heat generating radioactive waste

    International Nuclear Information System (INIS)

    1985-02-01

    A study has been made of the requirements and design features for containers to isolate vitrified heat generating radioactive waste from the environment for a period of 500 to 1000 years. The requirements for handling, storing and transporting containers have been identified following a study of disposal operations, and the pressures and temperatures which may possibly be experienced in clay, granite and salt formations have been estimated. A range of possible container designs have been proposed to satisfy the requirements of each of the disposal environments. Alternative design concepts in corrosion resistant or corrosion allowance material have been suggested. Potentially suitable container shell materials have been selected following a review of corrosion studies and although metals have not been specified in detail, titanium alloys and low carbon steels are thought to be appropriate for corrosion resistant and corrosion allowance designs respectively. Performance requirements for container filler materials have been identified and candidate materials assessed. A preliminary container stress analysis has shown the importance of thermal modelling and that if lead is used as a filler it dominates the stress response of the container. Possible methods of manufacturing disposal containers have been assessed and found to be generally feasible. (author)

  10. Comparison of potential greenhouse gas emissions from disposal of MSW in sanitary landfills vs. waste-to-energy facilities

    International Nuclear Information System (INIS)

    Taylor, H.F.

    1991-01-01

    The Environmental Protection Agency (EPA) estimates the US currently generates about 160 million tons of municipal solid waste (MSW) per year, and this figure will exceed 200 million tons annually by the year 2000. About 80 percent of the MSW will be disposed of in landfills and waste-to-energy (WTE) facilities, both of which generate greenhouse gases, namely methane and carbon dioxide. This paper provides an introductory level analysis of the potential long term greenhouse gas emissions from these two MSW disposal alternatives. Carbon dioxide credits are derived for fossil fuel offset by WTE and methane emissions are converted to equivalent CO 2 emissions in order to derive a single emission figure for comparison of the greenhouse contribution of the two disposal strategies. A secondary analysis is presented to compare the net equivalent CO 2 emissions from WTE facilities to those from landfills with methane gas recovery, combustion and energy generation. The conclusion is, that for a given amount of MSW, landfilling contributes to the greenhouse effect about 10 times more than a modern Waste-To-Energy facility. Even with 50% of all landfill methane emissions recovered and converted to electricity, the contribution to the greenhouse effect by the landfill alternative is about 6 times greater than the waste-to-energy alternative

  11. Disposal of Hanford defense waste

    International Nuclear Information System (INIS)

    Holten, R.A.; Burnham, J.B.; Nelson, I.C.

    1986-01-01

    An Environmental Impact Statement (EIS) on the disposal of Hanford Defense Waste is scheduled to be released near the end of March, 1986. This EIS will evaluate the impacts of alternatives for disposal of high-level, tank, and transuranic wastes which are now stored at the Department of Energy's Hanford Site or will be produced there in the future. In addition to releasing the EIS, the Department of Energy is conducting an extensive public participation process aimed at providing information to the public and receiving comments on the EIS

  12. Multi-Pack Disposal Concepts for Spent Fuel (Revision 1)

    International Nuclear Information System (INIS)

    Hardin, Ernest; Matteo, Edward N.; Hadgu, Teklu

    2016-01-01

    At the initiation of the Used Fuel Disposition (UFD) R&D campaign, international geologic disposal programs and past work in the U.S. were surveyed to identify viable disposal concepts for crystalline, clay/shale, and salt host media. Concepts for disposal of commercial spent nuclear fuel (SNF) and high-level waste (HLW) from reprocessing are relatively advanced in countries such as Finland, France, and Sweden. The UFD work quickly showed that these international concepts are all "enclosed,"whereby waste packages are emplaced in direct or close contact with natural or engineered materials . Alternative "open"modes (emplacement tunnels are kept open after emplacement for extended ventilation) have been limited to the Yucca Mountain License Application Design. Thermal analysis showed that if "enclosed"concepts are constrained by peak package/buffer temperature, that waste package capacity is limited to 4 PWR assemblies (or 9 BWR) in all media except salt. This information motivated separate studies: 1) extend the peak temperature tolerance of backfill materials, which is ongoing; and 2) develop small canisters (up to 4-PWR size) that can be grouped in larger multi-pack units for convenience of storage, transportation, and possibly disposal (should the disposal concept permit larger packages). A recent result from the second line of investigation is the Task Order 18 report: Generic Design for Small Standardized Transportation, Aging and Disposal Canister Systems. This report identifies disposal concepts for the small canisters (4-PWR size) drawing heavily on previous work, and for the multi-pack (16-PWR or 36-BWR).

  13. Multi-Pack Disposal Concepts for Spent Fuel (Revision 1)

    Energy Technology Data Exchange (ETDEWEB)

    Hardin, Ernest [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Matteo, Edward N. [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Hadgu, Teklu [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States)

    2016-01-01

    At the initiation of the Used Fuel Disposition (UFD) R&D campaign, international geologic disposal programs and past work in the U.S. were surveyed to identify viable disposal concepts for crystalline, clay/shale, and salt host media. Concepts for disposal of commercial spent nuclear fuel (SNF) and high-level waste (HLW) from reprocessing are relatively advanced in countries such as Finland, France, and Sweden. The UFD work quickly showed that these international concepts are all “enclosed,” whereby waste packages are emplaced in direct or close contact with natural or engineered materials . Alternative “open” modes (emplacement tunnels are kept open after emplacement for extended ventilation) have been limited to the Yucca Mountain License Application Design. Thermal analysis showed that if “enclosed” concepts are constrained by peak package/buffer temperature, that waste package capacity is limited to 4 PWR assemblies (or 9 BWR) in all media except salt. This information motivated separate studies: 1) extend the peak temperature tolerance of backfill materials, which is ongoing; and 2) develop small canisters (up to 4-PWR size) that can be grouped in larger multi-pack units for convenience of storage, transportation, and possibly disposal (should the disposal concept permit larger packages). A recent result from the second line of investigation is the Task Order 18 report: Generic Design for Small Standardized Transportation, Aging and Disposal Canister Systems. This report identifies disposal concepts for the small canisters (4-PWR size) drawing heavily on previous work, and for the multi-pack (16-PWR or 36-BWR).

  14. Quantification of Food Waste Disposal in the United States: A Meta-Analysis.

    Science.gov (United States)

    Thyberg, Krista L; Tonjes, David J; Gurevitch, Jessica

    2015-12-15

    Food waste has major consequences for social, nutritional, economic, and environmental issues, and yet the amount of food waste disposed in the U.S. has not been accurately quantified. We introduce the transparent and repeatable methods of meta-analysis and systematic reviewing to determine how much food is discarded in the U.S., and to determine if specific factors drive increased disposal. The aggregate proportion of food waste in U.S. municipal solid waste from 1995 to 2013 was found to be 0.147 (95% CI 0.137-0.157) of total disposed waste, which is lower than that estimated by U.S. Environmental Protection Agency for the same period (0.176). The proportion of food waste increased significantly with time, with the western U.S. region having consistently and significantly higher proportions of food waste than other regions. There were no significant differences in food waste between rural and urban samples, or between commercial/institutional and residential samples. The aggregate disposal rate for food waste was 0.615 pounds (0.279 kg) (95% CI 0.565-0.664) of food waste disposed per person per day, which equates to over 35.5 million tons (32.2 million tonnes) of food waste disposed annually in the U.S.

  15. Korean Reference HLW Disposal System

    Energy Technology Data Exchange (ETDEWEB)

    Choi, Heui Joo; Lee, J. Y.; Kim, S. S. (and others)

    2008-03-15

    This report outlines the results related to the development of Korean Reference Disposal System for High-level radioactive wastes. The research has been supported around for 10 years through a long-term research plan by MOST. The reference disposal method was selected via the first stage of the research during which the technical guidelines for the geological disposal of HLW were determined too. At the second stage of the research, the conceptual design of the reference disposal system was made. For this purpose the characteristics of the reference spent fuels from PWR and CANDU reactors were specified, and the material and specifications of the canisters were determined in term of structural analysis and manufacturing capability in Korea. Also, the mechanical and chemical characteristics of the domestic Ca-bentonite were analyzed in order to supply the basic design parameters of the buffer. Based on these parameters the thermal and mechanical analysis of the near-field was carried out. Thermal-Hydraulic-Mechanical behavior of the disposal system was analyzed. The reference disposal system was proposed through the second year research. At the final third stage of the research, the Korean Reference disposal System including the engineered barrier, surface facilities, and underground facilities was proposed through the performance analysis of the disposal system.

  16. Special Analysis: Revision of Saltstone Vault 4 Disposal Limits (U)

    Energy Technology Data Exchange (ETDEWEB)

    Cook, J

    2005-05-26

    New disposal limits have been computed for Vault 4 of the Saltstone Disposal Facility based on several revisions to the models in the existing Performance Assessment and the Special Analysis issued in 2002. The most important changes are the use of a more rigorous groundwater flow and transport model, and consideration of radon emanation. Other revisions include refinement of the aquifer mesh to more accurately model the footprint of the vault, a new plutonium chemistry model accounting for the different transport properties of oxidation states III/IV and V/VI, use of variable infiltration rates to simulate degradation of the closure system, explicit calculation of gaseous releases and consideration of the effects of settlement and seismic activity on the vault structure. The disposal limits have been compared with the projected total inventory expected to be disposed in Vault 4. The resulting sum-of-fractions of the 1000-year disposal limits is 0.2, which indicates that the performance objectives and requirements of DOE 435.1 will not be exceeded. This SA has not altered the conceptual model (i.e., migration of radionuclides from the Saltstone waste form and Vault 4 to the environment via the processes of diffusion and advection) of the Saltstone PA (MMES 1992) nor has it altered the conclusions of the PA (i.e., disposal of the proposed waste in the SDF will meet DOE performance measures). Thus a PA revision is not required and this SA serves to update the disposal limits for Vault 4. In addition, projected doses have been calculated for comparison with the performance objectives laid out in 10 CFR 61. These doses are 0.05 mrem/year to a member of the public and 21.5 mrem/year to an inadvertent intruder in the resident scenario over a 10,000-year time-frame, which demonstrates that the 10 CFR 61 performance objectives will not be exceeded. This SA supplements the Saltstone PA and supersedes the two previous SAs (Cook et al. 2002; Cook and Kaplan 2003).

  17. Principles and guidelines for radioactive waste disposal facilities

    International Nuclear Information System (INIS)

    1988-06-01

    Four basic principles relevant to radioactive waste disposal identified. These principles cover the justification of the activity giving rise to the waste, the consideration of risk to present and future generations, the minimization of the need for intervention in the future, and the financial obligations of the licensee. The use of risk limits as opposed to dose limits associated with disposal is discussed, as are the concepts of critical group, de minimis, and ALARA, in the context of a waste disposal facility. Guidance is given on the selection of the preferred waste disposal concept from among several alternatives, and for judging proposed design improvements to the chosen concept

  18. Low-level radioactive waste disposal. Study of a conceptual nuclear energy center at Green River, Utah

    International Nuclear Information System (INIS)

    Card, D.H.; Hunter, P.H.; Barg, D.; de Souza, F.; Felthauser, K.; Winkler, V.; White, R.

    1982-02-01

    This document constitutes a segment of a feasibility study investigating the ramifications of constructing a nuclear energy center in an arid western region. In this phase of the study, the alternatives for disposing of the low-level waste on the site are compared with the alternative of transporting the waste to the nearest commercial waste disposal site for permanent disposal. Both radiological and nonradiological impacts on the local socioeconomic infrastructure and the environment are considered. Disposal on the site was found to cost considerably less than off-site disposal with only negligible impacts associated with the disposal option on either mankind or the environment

  19. Risk management for outsourcing biomedical waste disposal - using the failure mode and effects analysis.

    Science.gov (United States)

    Liao, Ching-Jong; Ho, Chao Chung

    2014-07-01

    Using the failure mode and effects analysis, this study examined biomedical waste companies through risk assessment. Moreover, it evaluated the supervisors of biomedical waste units in hospitals, and factors relating to the outsourcing risk assessment of biomedical waste in hospitals by referring to waste disposal acts. An expert questionnaire survey was conducted on the personnel involved in waste disposal units in hospitals, in order to identify important factors relating to the outsourcing risk of biomedical waste in hospitals. This study calculated the risk priority number (RPN) and selected items with an RPN value higher than 80 for improvement. These items included "availability of freezing devices", "availability of containers for sharp items", "disposal frequency", "disposal volume", "disposal method", "vehicles meeting the regulations", and "declaration of three lists". This study also aimed to identify important selection factors of biomedical waste disposal companies by hospitals in terms of risk. These findings can serve as references for hospitals in the selection of outsourcing companies for biomedical waste disposal. Copyright © 2014 Elsevier Ltd. All rights reserved.

  20. Comparative life-cycle cost analysis for low-level mixed waste remediation alternatives

    International Nuclear Information System (INIS)

    Jackson, J.A.; White, T.P.; Kloeber, J.M.; Toland, R.J.; Cain, J.P.; Buitrago, D.Y.

    1995-03-01

    The purpose of this study is two-fold: (1) to develop a generic, life-cycle cost model for evaluating low-level, mixed waste remediation alternatives, and (2) to apply the model specifically, to estimate remediation costs for a site similar to the Fernald Environmental Management Project near Cincinnati, OH. Life-cycle costs for vitrification, cementation, and dry removal process technologies are estimated. Since vitrification is in a conceptual phase, computer simulation is used to help characterize the support infrastructure of a large scale vitrification plant. Cost estimating relationships obtained from the simulation data, previous cost estimates, available process data, engineering judgment, and expert opinion all provide input to an Excel based spreadsheet for generating cash flow streams. Crystal Ball, an Excel add-on, was used for discounting cash flows for net present value analysis. The resulting LCC data was then analyzed using multi-attribute decision analysis techniques with cost and remediation time as criteria. The analytical framework presented allows alternatives to be evaluated in the context of budgetary, social, and political considerations. In general, the longer the remediation takes, the lower the net present value of the process. This is true because of the time value of money and large percentage of the costs attributed to storage or disposal

  1. Alternatives for nuclear fuel disposal

    International Nuclear Information System (INIS)

    Ramirez S, J. R.; Badillo A, V.; Palacios H, J.; Celis del Angel, L.

    2010-10-01

    The spent fuel is one of the most important issues in the nuclear industry, currently spent fuel management is been cause of great amount of research, investments in the construction of repositories or constructing the necessary facilities to reprocess the fuel, and later to recycle the plutonium recovered in thermal reactors. What is the best solution? or, What is the best technology for a specific solution? Many countries have deferred the decision on selecting an option, while other works actively constructing repositories and others implementing the reprocessing facilities to recycle the plutonium obtained from nuclear spent fuel. In Mexico the nuclear power is limited to two reactors BWR type and medium size. So the nuclear spent fuel discharged has been accommodated at reactor's spent fuel pools. Originally these pools have enough capacity to accommodate spent fuel for the 40 years of designed plant operation. However, currently is under process an extended power up rate to 20% of their original power and also there are plans to extend operational life for 20 more years. Under these conditions there will not be enough room for spent fuel in the pools. So this work describes some different alternatives that have been studied in Mexico to define which will be the best alternative to follow. (Author)

  2. Disposal facility for spent nuclear fuel. Environmental impact assessment program

    International Nuclear Information System (INIS)

    1998-01-01

    The report presents the Environmental Impact Assessment (EIA) of the high level radioactive waste disposal in Finland. In EIA different alternatives concerning site selection, construction, operation and sealing of the disposal facility as well as waste transportation and encapsulation of the waste are considered

  3. Unreviewed Disposal Question: A Discipline Process to Manage Change in LLW Disposal

    International Nuclear Information System (INIS)

    Goldston, W.T.

    2000-01-01

    The Department of Energy's waste management Order, DOE O 435.1, requires that low--level waste disposal facilities develop and maintain a radiological performance assessment to ensure that disposal operations are within a performance envelope defined by performance objectives for long-term protection of the public and the environment. The Order also requires that a radiological composite analysis be developed and maintained to ensure that the disposal facility, in combination with other sources of radioactive material that may remain when all DOE activities have ceased, will not compromise future radiological protection of the public and the environment. The Order further requires that a Disposal Authorization Statement (DAS) be obtained from DOE Headquarters and that the disposal facility be operated within the performance assessment, composite analysis, and DAS. Maintenance of the performance assessment and composite analysis includes conducting test, research, and monitoring activities to increase confidence in the results of the analyses. It also includes updating the analyses as changes are proposed in the disposal operations, or other information requiring an update, becomes available. Personnel at the Savannah River Site have developed and implemented an innovative process for reviewing proposed or discovered changes in low-level radioactive waste disposal operations. The process is a graded approach to determine, in a disciplined manner, whether changes are within the existing performance envelope, as defined by the performance assessment, composite analysis, and DAS, or whether additional analysis is required to authorize the change. This process is called the Unreviewed Disposal Question (UDQ) process. It has been developed to be analogous to the Unreviewed Safety Question (UDQ) process that has been in use within DOE for many years. This is the first formalized system implemented in the DOE complex to examine low-level waste disposal changes the way the

  4. Life Cycle Analysis for Treatment and Disposal of PCB Waste at Ashtabula and Fernald

    International Nuclear Information System (INIS)

    Morris, M.I.

    2001-01-01

    This report presents the use of the life cycle analysis (LCA) system developed at Oak Ridge National Laboratory (ORNL) to assist two U.S. Department of Energy (DOE) sites in Ohio--the Ashtabula Environmental Management Project near Cleveland and the Fernald Environmental Management Project near Cincinnati--in assessing treatment and disposal options for polychlorinated biphenyl (PCB)-contaminated low-level radioactive waste (LLW) and mixed waste. We will examine, first, how the LCA process works, then look briefly at the LCA system's ''toolbox,'' and finally, see how the process was applied in analyzing the options available in Ohio. As DOE nuclear weapons facilities carry out planned decontamination and decommissioning (D and D) activities for site closure and progressively package waste streams, remove buildings, and clean up other structures that have served as temporary waste storage locations, it becomes paramount for each waste stream to have a prescribed and proven outlet for disposition. Some of the most problematic waste streams throughout the DOE complex are PCB low-level radioactive wastes (liquid and solid) and PCB low-level Resource Conservation and Recovery Act (RCRA) liquid and solid wastes. Several DOE Ohio Field Office (OH) sites have PCB disposition needs that could have an impact on the critical path of the decommissioning work of these closure sites. The Ashtabula Environmental Management Project (AEMP), an OH closure site, has an urgent problem with disposition of soils contaminated by PCB and low-level waste at the edge of the site. The Fernald Environmental Management Project (FEMP), another OH closure site, has difficulties in timely disposition of its PCB-low-level sludges and its PCB low-level RCRA sludges in order to avoid impacting the critical path of its D and D activities. Evaluation of options for these waste streams is the subject of this report. In the past a few alternatives for disposition of PCB low-level waste and PCB low

  5. Life Cycle Analysis for Treatment and Disposal of PCB Waste at Ashtabula and Fernald

    Energy Technology Data Exchange (ETDEWEB)

    Morris, M.I.

    2001-01-11

    This report presents the use of the life cycle analysis (LCA) system developed at Oak Ridge National Laboratory (ORNL) to assist two U.S. Department of Energy (DOE) sites in Ohio--the Ashtabula Environmental Management Project near Cleveland and the Fernald Environmental Management Project near Cincinnati--in assessing treatment and disposal options for polychlorinated biphenyl (PCB)-contaminated low-level radioactive waste (LLW) and mixed waste. We will examine, first, how the LCA process works, then look briefly at the LCA system's ''toolbox,'' and finally, see how the process was applied in analyzing the options available in Ohio. As DOE nuclear weapons facilities carry out planned decontamination and decommissioning (D&D) activities for site closure and progressively package waste streams, remove buildings, and clean up other structures that have served as temporary waste storage locations, it becomes paramount for each waste stream to have a prescribed and proven outlet for disposition. Some of the most problematic waste streams throughout the DOE complex are PCB low-level radioactive wastes (liquid and solid) and PCB low-level Resource Conservation and Recovery Act (RCRA) liquid and solid wastes. Several DOE Ohio Field Office (OH) sites have PCB disposition needs that could have an impact on the critical path of the decommissioning work of these closure sites. The Ashtabula Environmental Management Project (AEMP), an OH closure site, has an urgent problem with disposition of soils contaminated by PCB and low-level waste at the edge of the site. The Fernald Environmental Management Project (FEMP), another OH closure site, has difficulties in timely disposition of its PCB-low-level sludges and its PCB low-level RCRA sludges in order to avoid impacting the critical path of its D&D activities. Evaluation of options for these waste streams is the subject of this report. In the past a few alternatives for disposition of PCB low-level waste

  6. Waste Isolation Pilot Plant disposal phase final supplemental environmental impact statement. Summary

    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

  7. Engineered barrier durability: An issue for disposal near populated areas

    International Nuclear Information System (INIS)

    Porter, C.L.

    1995-01-01

    Under the current national policy for disposal of low-level radioactive waste (LLW) in the United States of America, each State is required to provide disposal capacity for the LLW generated within its borders. The formation of ''Compacts'' of several States is allowed if approved by Congress. Such forced regionalization of disposal facilities based on State boundaries results in some disposal facilities being sited near populated areas at locations with less than optimum site characteristics from a disposal standpoint. To compensate for this engineered barriers are included in the proposed designs. Portland cement based concrete (PCC), which is the dominant material for disposal vault designs, is degraded via many mechanisms, most of which are related to its permeability. The numerous uncertainties associated with the long-term performance of PCC has lead to many unsuccessful attempts to obtain public acceptance of proposed disposal facilities. These unsuccessful efforts have delayed establishing disposal capacity to the point that a crisis is looming on the horizon. This paper investigates the results of on-going research into the viability of commercially available, impermeable, mass-poured construction materials as an alternative to PCC in LLW disposal vaults. The results from testing and research on two such materials, concrete made from sulfur polymer cement (SPC) and ICOM (an epoxy based concrete) are reported. Material properties and test results include strength parameters, chemical resistance, porosity, permeability, deconability, radiation damage resistance, and biodegradation. The data indicates that with these alternative materials the uncertainties in predicting service life of an engineered barrier can be reduced

  8. Multi-pack Disposal Concepts for Spent Fuel (Rev. 0)

    Energy Technology Data Exchange (ETDEWEB)

    Hadgu, Teklu [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Hardin, Ernest [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Matteo, Edward N. [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States)

    2015-12-01

    At the initiation of the Used Fuel Disposition (UFD) R&D campaign, international geologic disposal programs and past work in the U.S. were surveyed to identify viable disposal concepts for crystalline, clay/shale, and salt host media (Hardin et al., 2012). Concepts for disposal of commercial spent nuclear fuel (SNF) and high-level waste (HLW) from reprocessing are relatively advanced in countries such as Finland, France, and Sweden. The UFD work quickly showed that these international concepts are all “enclosed,” whereby waste packages are emplaced in direct or close contact with natural or engineered materials . Alternative “open” modes (emplacement tunnels are kept open after emplacement for extended ventilation) have been limited to the Yucca Mountain License Application Design (CRWMS M&O, 1999). Thermal analysis showed that, if “enclosed” concepts are constrained by peak package/buffer temperature, waste package capacity is limited to 4 PWR assemblies (or 9-BWR) in all media except salt. This information motivated separate studies: 1) extend the peak temperature tolerance of backfill materials, which is ongoing; and 2) develop small canisters (up to 4-PWR size) that can be grouped in larger multi-pack units for convenience of storage, transportation, and possibly disposal (should the disposal concept permit larger packages). A recent result from the second line of investigation is the Task Order 18 report: Generic Design for Small Standardized Transportation, Aging and Disposal Canister Systems (EnergySolution, 2015). This report identifies disposal concepts for the small canisters (4-PWR size) drawing heavily on previous work, and for the multi-pack (16-PWR or 36-BWR).

  9. Suggestions on selection of clay site as a key alternative of underground repository for HLW geological disposal in China

    International Nuclear Information System (INIS)

    Zheng Hualing; Fu Bingjun; Fan Xianhua; Chen Shi; Sun Donghui

    2006-01-01

    Site selection for the underground repository is a vital problem with respect to the HLW geological disposal. Over the past decades, we have been focusing our attention on granite as a priority in China. However, there are some problems have to be discussed on this matter. In this paper, both experiences gained and lessons learned in the international community regarding the site selection are described. And then, after analyzing a lot of some key factors affecting the site selection, some comments and suggestions on selection of clay site as a key alternative before final decision making in China are presented. (authors)

  10. LLNL Input to SNL L2 MS: Report on the Basis for Selection of Disposal Options

    International Nuclear Information System (INIS)

    Sutton, M.; Blink, J.A.; Halsey, W.G.

    2011-01-01

    This mid-year deliverable has two parts. The first part is a synopsis of J. Blink's interview of the former Nevada Attorney General, Frankie Sue Del Papa, which was done in preparation for the May 18-19, 2010 Legal and Regulatory Framework Workshop held in Albuquerque. The second part is a series of sections written as input for the SNL L2 Milestone M21UF033701, due March 31, 2011. Disposal of high-level radioactive waste is categorized in this review into several categories. Section II discusses alternatives to geologic disposal: space, ice-sheets, and an engineered mountain or mausoleum. Section III discusses alternative locations for mined geologic disposal: islands, coastlines, mid-continent, and saturated versus unsaturated zone. Section IV discusses geologic disposal alternatives other than emplacement in a mine: well injection, rock melt, sub-seabed, and deep boreholes in igneous or metamorphic basement rock. Finally, Secton V discusses alternative media for mined geologic disposal: basalt, tuff, granite and other igneous/metamorphic rock, alluvium, sandstone, carbonates and chalk, shale and clay, and salt.

  11. LLNL Input to SNL L2 MS: Report on the Basis for Selection of Disposal Options

    Energy Technology Data Exchange (ETDEWEB)

    Sutton, M; Blink, J A; Halsey, W G

    2011-03-02

    This mid-year deliverable has two parts. The first part is a synopsis of J. Blink's interview of the former Nevada Attorney General, Frankie Sue Del Papa, which was done in preparation for the May 18-19, 2010 Legal and Regulatory Framework Workshop held in Albuquerque. The second part is a series of sections written as input for the SNL L2 Milestone M21UF033701, due March 31, 2011. Disposal of high-level radioactive waste is categorized in this review into several categories. Section II discusses alternatives to geologic disposal: space, ice-sheets, and an engineered mountain or mausoleum. Section III discusses alternative locations for mined geologic disposal: islands, coastlines, mid-continent, and saturated versus unsaturated zone. Section IV discusses geologic disposal alternatives other than emplacement in a mine: well injection, rock melt, sub-seabed, and deep boreholes in igneous or metamorphic basement rock. Finally, Secton V discusses alternative media for mined geologic disposal: basalt, tuff, granite and other igneous/metamorphic rock, alluvium, sandstone, carbonates and chalk, shale and clay, and salt.

  12. Low-level-waste-disposal methodologies

    International Nuclear Information System (INIS)

    Wheeler, M.L.; Dragonette, K.

    1981-01-01

    This report covers the followng: (1) history of low level waste disposal; (2) current practice at the five major DOE burial sites and six commercial sites with dominant features of these sites and radionuclide content of major waste types summarized in tables; (3) site performance with performance record on burial sites tabulated; and (4) proposed solutions. Shallow burial of low level waste is a continuously evolving practice, and each site has developed its own solutions to the handling and disposal of unusual waste forms. There are no existing national standards for such disposal. However, improvements in the methodology for low level waste disposal are occurring on several fronts. Standardized criteria are being developed by both the Nuclear Regulatory Commission (NRC) and by DOE. Improved techniques for shallow burial are evolving at both commercial and DOE facilities, as well as through research sponsored by NRC, DOE, and the Environmental Protection Agency. Alternatives to shallow burial, such as deeper burial or the use of mined cavities is also being investigated by DOE

  13. Advancing Alternative Analysis: Integration of Decision Science.

    Science.gov (United States)

    Malloy, Timothy F; Zaunbrecher, Virginia M; Batteate, Christina M; Blake, Ann; Carroll, William F; Corbett, Charles J; Hansen, Steffen Foss; Lempert, Robert J; Linkov, Igor; McFadden, Roger; Moran, Kelly D; Olivetti, Elsa; Ostrom, Nancy K; Romero, Michelle; Schoenung, Julie M; Seager, Thomas P; Sinsheimer, Peter; Thayer, Kristina A

    2017-06-13

    Decision analysis-a systematic approach to solving complex problems-offers tools and frameworks to support decision making that are increasingly being applied to environmental challenges. Alternatives analysis is a method used in regulation and product design to identify, compare, and evaluate the safety and viability of potential substitutes for hazardous chemicals. We assessed whether decision science may assist the alternatives analysis decision maker in comparing alternatives across a range of metrics. A workshop was convened that included representatives from government, academia, business, and civil society and included experts in toxicology, decision science, alternatives assessment, engineering, and law and policy. Participants were divided into two groups and were prompted with targeted questions. Throughout the workshop, the groups periodically came together in plenary sessions to reflect on other groups' findings. We concluded that the further incorporation of decision science into alternatives analysis would advance the ability of companies and regulators to select alternatives to harmful ingredients and would also advance the science of decision analysis. We advance four recommendations: a ) engaging the systematic development and evaluation of decision approaches and tools; b ) using case studies to advance the integration of decision analysis into alternatives analysis; c ) supporting transdisciplinary research; and d ) supporting education and outreach efforts. https://doi.org/10.1289/EHP483.

  14. Geological disposal of nuclear waste

    International Nuclear Information System (INIS)

    1979-01-01

    Fourteen papers dealing with disposal of high-level radioactive wastes are presented. These cover disposal in salt deposits, geologic deposits and marine disposal. Also included are papers on nuclear waste characterization, transport, waste processing technology, and safety analysis. All of these papers have been abstracted and indexed

  15. Roadmap for disposal of Electrorefiner Salt as Transuranic Waste.

    Energy Technology Data Exchange (ETDEWEB)

    Rechard, Robert P. [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Trone, Janis R. [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Kalinina, Elena Arkadievna [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Wang, Yifeng [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Hadgu, Teklu [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Sanchez, Lawrence C. [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States)

    2017-12-01

    The experimental breeder reactor (EBR-II) used fuel with a layer of sodium surrounding the uranium-zirconium fuel to improve heat transfer. Disposing of EBR-II fuel in a geologic repository without treatment is not prudent because of the potentially energetic reaction of the sodium with water. In 2000, the US Department of Energy (DOE) decided to treat the sodium-bonded fuel with an electrorefiner (ER), which produces metallic uranium product, a metallic waste, mostly from the cladding, and the salt waste in the ER, which contains most of the actinides and fission products. Two waste forms were proposed for disposal in a mined repository; the metallic waste, which was to be cast into ingots, and the ER salt waste, which was to be further treated to produce a ceramic waste form. However, alternative disposal pathways for metallic and salt waste streams may reduce the complexity. For example, performance assessments show that geologic repositories can easily accommodate the ER salt waste without treating it to form a ceramic waste form. Because EBR-II was used for atomic energy defense activities, the treated waste likely meets the definition of transuranic waste. Hence, disposal at the Waste Isolation Pilot Plant (WIPP) in southern New Mexico, may be feasible. This report reviews the direct disposal pathway for ER salt waste and describes eleven tasks necessary for implementing disposal at WIPP, provided space is available, DOE decides to use this alternative disposal pathway in an updated environmental impact statement, and the State of New Mexico grants permission.

  16. Alternatives for management of wastes generated by the formerly utilized sites remedial action program and supplement

    International Nuclear Information System (INIS)

    Gilbert, T.L.; Peterson, J.M.; Vocke, R.W.; Alexander, J.K.

    1983-03-01

    Alternatives for disposal or stabilization of the wastes generated by the US Department of Energy's Formerly Utilized Sites Remedial Action Program (FUSRAP) are identified and compared, with emphasis on the long-term aspects. These wastes consist of soil material and rubble containing trace amounts of radionuclides. A detailed pathway analysis for the dose to the maximally exposed individual is carried out using an adaptation of the natural analogue method. Comparisons of the different alternatives, based on the results of the pathway analysis and qualitative cost considerations, indicate that, if the hazard is such that the wastes must be removed and disposed of rather than stabilized in place, disposal by immediate dispersal is preferable to containment, and containment followed by slow planned dispersal is preferable to containment without dispersal. The Supplement presents refinements of work that was reported at the 1982 International Decommissioning Symposium. The new material consists of revisions of the estimates of the predicted potential dose to the maximally exposed individual and a more detailed comparative assessment of the radiological impacts of alternatives for management of wastes generated by the US Department of Energy's Formerly Utilized Sites Remedial Action Program (FUSRAP)

  17. Disposal of chemical agents and munitions stored at Pine Bluff Arsenal, Pine Bluff, Arkansas

    Energy Technology Data Exchange (ETDEWEB)

    Ensminger, J.T.; Hillsman, E.L.; Johnson, R.D.; Morrisey, J.A.; Staub, W.P.; Boston, C.R.; Hunsaker, D.B.; Leibsch, E.; Rickert, L.W.; Tolbert, V.R.; Zimmerman, G.P.

    1991-09-01

    The Pine Bluff Arsenal (PBA) near Pine Bluff, Arkansas, is one of eight continental United States (CONUS) Army installations where lethal unitary chemical agents and munitions are stored and where destruction of agents and munitions is proposed under the Chemical Stockpile Disposal Program (CSDP). The chemical agent inventory at PBA consists of approximately 12%, by weight, of the total US stockpile. The destruction of the stockpile is necessary to eliminate the risk to the public from continued storage and to dispose of obsolete and leaking munitions. In 1988 the US Army issued a Final Programmatic Environmental Impact Statement (FPEIS) for the CSDP that identified on-site disposal of agents and munitions as the environmentally preferred alternative (i.e., the alternative with the least potential to cause significant adverse impacts). The purpose of this report is to examine the proposed implementation of on-site disposal at PBA in light of more recent and more detailed data than those on which the FPEIS is based. New population data were used to compute fatalities using the same computation methods and values for all other parameters as in the FPEIS. Results indicate that all alternatives are indistinguishable when the potential health impacts to the PBA community are considered. However, risks from on-site disposal are in all cases equal to or less than risks from other alternatives. Furthermore, no unique resources with the potential to prevent or delay implementation of on-site disposal at PBA have been identified.

  18. Corrective Action Investigation Plan for Corrective Action Unit 137: Waste Disposal Sites, Nevada Test Site, Nevada, Rev. No.:0

    Energy Technology Data Exchange (ETDEWEB)

    Wickline, Alfred

    2005-12-01

    This Corrective Action Investigation Plan (CAIP) contains project-specific information including facility descriptions, environmental sample collection objectives, and criteria for conducting site investigation activities at Corrective Action Unit (CAU) 137: Waste Disposal Sites. This CAIP has been developed in accordance with the ''Federal Facility Agreement and Consent Order'' (FFACO) (1996) that was agreed to by the State of Nevada, the U.S. Department of Energy (DOE), and the U.S. Department of Defense. Corrective Action Unit 137 contains sites that are located in Areas 1, 3, 7, 9, and 12 of the Nevada Test Site (NTS), which is approximately 65 miles (mi) northwest of Las Vegas, Nevada (Figure 1-1). Corrective Action Unit 137 is comprised of the eight corrective action sites (CASs) shown on Figure 1-1 and listed below: (1) CAS 01-08-01, Waste Disposal Site; (2) CAS 03-23-01, Waste Disposal Site; (3) CAS 03-23-07, Radioactive Waste Disposal Site; (4) CAS 03-99-15, Waste Disposal Site; (5) CAS 07-23-02, Radioactive Waste Disposal Site; (6) CAS 09-23-07, Radioactive Waste Disposal Site; (7) CAS 12-08-01, Waste Disposal Site; and (8) CAS 12-23-07, Waste Disposal Site. The Corrective Action Investigation (CAI) will include field inspections, radiological surveys, geophysical surveys, sampling of environmental media, analysis of samples, and assessment of investigation results, where appropriate. Data will be obtained to support corrective action alternative evaluations and waste management decisions. The CASs in CAU 137 are being investigated because hazardous and/or radioactive constituents may be present in concentrations that could potentially pose a threat to human health and the environment. Existing information on the nature and extent of potential contamination is insufficient to evaluate and recommend corrective action alternatives for the CASs. Additional information will be generated by conducting a CAI before evaluating and selecting

  19. Study to optimize a disposal tunnel layout taking into account heterogeneous characteristics of the geological environment

    International Nuclear Information System (INIS)

    Suyama, Yasuhiro; Toida, Masaru; Yanagizawa, Koichi

    2007-01-01

    The geological environment has spatially heterogeneous characteristics with varied host rock types, fractures and so on. In this case the generic disposal tunnel layout, which has been designed by JNC, is not the most suitable for HLW disposal in Japan. The existence of spatially heterogeneous characteristics means that in the repository region there exist sub-regions that are more favorable from the perspective of long-term safety and ones that are less favorable. In order that the spatially heterogeneous environment itself may be utilized most effectively as an NBS, an alternative design of disposal tunnel layout is required. Focusing on the geological environment with spatially heterogeneous characteristics, the authors have developed an alternative design of disposal tunnel layout. The alternative design adopts an optimization approach using a 'variable disposal tunnel layout'. The optimization approach minimizes the number of locations where major water conducting fractures are intersected, and maximizes the number of emplacement locations for waste packages. This paper will outline the variable disposal tunnel layout and its applicability. (author)

  20. Direct ultimate disposal - state of investigations and prospects

    International Nuclear Information System (INIS)

    Gasterstaedt, N.

    1991-01-01

    Based on a decision adopted by the Prime Ministers on 25/10/90, the principles governing preventive waste management of nuclear power plants are reviewed. Increasing importance is attached to the direct ultimate disposal alternative. The legal and political framework, the technology involved, the state of developments, future activities under the R and D programme as well as a cost estimate of direct ultimate disposal are presented. (orig.) [de

  1. Waste Isolation Pilot Plant remote-handled transuranic waste disposal strategy

    International Nuclear Information System (INIS)

    1995-01-01

    The remote-handled transuranic (RH-TRU) waste disposal strategy described in this report identifies the process for ensuring that cost-effective initial disposal of RH-TRU waste will begin in Fiscal Year 2002. The strategy also provides a long-term approach for ensuring the efficient and sustained disposal of RH-TRU waste during the operating life of WIPP. Because Oak Ridge National Laboratory stores about 85 percent of the current inventory, the strategy is to assess the effectiveness of modifying their facilities to package waste, rather than constructing new facilities. In addition, the strategy involves identification of ways to prepare waste at other sites to supplement waste from Oak Ridge National Laboratory. DOE will also evaluate alternative packagings, modes of transportation, and waste emplacement configurations, and will select preferred alternatives to ensure initial disposal as scheduled. The long-term strategy provides a systemwide planning approach that will allow sustained disposal of RH-TRU waste during the operating life of WIPP. The DOE's approach is to consider the three relevant systems -- the waste management system at the generator/storage sites, the transportation system, and the WIPP disposal system -- and to evaluate the system components individually and in aggregate against criteria for improving system performance. To ensure full implementation, in Fiscal Years 1996 and 1997 DOE will: (1) decide whether existing facilities at Oak Ridge National Laboratory or new facilities to package and certify waste are necessary; (2) select the optimal packaging and mode of transportation for initial disposal; and (3) select an optimal disposal configuration to ensure that the allowable limits of RH-TRU waste can be disposed. These decisions will be used to identify funding requirements for the three relevant systems and schedules for implementation to ensure that the goal of initial disposal is met

  2. Thermal analysis in the near field for geological disposal of high-level radioactive waste. Establishment of the disposal tunnel spacing and waste package pitch on the 2nd progress report for the geological disposal of HLW in Japan

    International Nuclear Information System (INIS)

    Taniguchi, Wataru; Iwasa, Kengo

    1999-11-01

    For the underground facility of the geological disposal of high-level radioactive waste (HLW), the space is needed to set the engineered barrier, and the set engineered barrier and rock-mass of near field are needed to satisfy some conditions or constraints for their performance. One of the conditions above mentioned is thermal condition arising from heat outputs of vitrified waste and initial temperature at the disposal depth. Hence, it is needed that the temperature of the engineered barrier and rock mass is less degree than the constraint temperature of each other. Therefore, the design of engineered barrier and underground facility is conducted so that the temperature of the engineered barrier and rock mass is less degree than the constraint temperature of each other. One of these design is establishment of the disposal tunnel spacing and waste package pitch. In this report, thermal analysis is conducted to establish the disposal tunnel spacing and waste package pitch to satisfy the constraint temperature in the near field. Also, other conditions or constraints for establishment of the disposal tunnel spacing and waste package pitch are investigated. Then, design of the disposal tunnel spacing and waste package pitch, considering these conditions or constraints, is conducted. For the near field configuration using the results of the design above mentioned, the temperature with time dependency is studied by analysis, and then the temperature variation due to the gaps, that will occur within the engineered barrier and between the engineered barrier and rock mass in setting engineered barrier in the disposal tunnel or pit, is studied. At last, the disposal depth variation is studied to satisfy the temperature constraint in the near field. (author)

  3. Performance monitoring of an improved disposal trench in a humid environment in a fractured geology

    International Nuclear Information System (INIS)

    Mills, D.; Razor, J.

    1988-01-01

    An engineering evaluation of an improved disposal trench at the Maxey Flats Waste Disposal Site is being conducted in order to demonstrate the feasibility of a burial trench suitable for use at a site in a humid environment and underlain by complex and fractured geologic media. This demonstration is one of several proposed final site stabilization alternatives which will have to be evaluated prior to final site closure. Due to requirements in the Central Midwest Compact Commission, no waste generated as a result of the site closure may be disposed in the Commission's disposal site. Hence, the waste will be disposed on-site. The demonstration trench was constructed and filled with waste during the fall of 1985 with final trench capping being completed in July 1986. Since that time the trench has been evaluated utilizing trench settlement monument elevations, leachate production measurements, leachate radionuclide analysis, chemical tracer analysis and trench water balance. Measurements performed to date indicated that the trench lower infiltration barrier has a permeability of about 1E-7 cm/sec. Water balance measurements indicated that less than one percent of the total rainfall crossed the trench capillary barrier. No settlement of the trench cap has been observed. No liquid has appeared in the leachate collection and monitoring sumps

  4. Analysis of scenarios for the direct disposal of spent nuclear fuel disposal conditions as expected in Germany

    International Nuclear Information System (INIS)

    Ashton, P.; Mehling, O.; Mohn, R.; Wingender, H.J.

    1990-01-01

    This report contains an investigation of aspects of the waste management of spent light water reactor fuel by direct disposal in a deep geological formation on land. The areas covered are: interim dry storage of spent fuel with three options of pre-conditioning; conditioning of spent fuel for final disposal in a salt dome repository; disposal of spent fuel (heat-generating waste) in a salt dome repository; disposal of medium and low-level radioactive wastes in the Konrad mine. Dose commitments, effluent discharges and potential incidents were not found to vary significantly for the various conditioning options/salt dome repository types. Due to uncertainty in the cost estimates, in particular the disposal cost estimates, the variation between the three conditioning options examined is not considered as being significant. The specific total costs for the direct disposal strategy are estimated to lie in the range ECU 600 to 700 per kg hm (basis 1988)

  5. Self-disposal option for heat-generating waste - 59182

    International Nuclear Information System (INIS)

    Ojovan, Michael I.; Poluektov, Pavel P.; Kascheev, Vladimir A.

    2012-01-01

    Self-descending heat generating capsules can be used for disposal of dangerous radioactive wastes in extremely deep layers of the Earth preventing any release of radionuclides into the biosphere. Self-disposal option for heat-generating radioactive waste such as spent fuel, high level reprocessing waste or spent sealed radioactive sources, known also as rock melting concept, was considered in the 70's as a viable alternative disposal option by both Department of Energy in the USA and Atomic Industry Ministry in the USSR. Self-disposal is currently reconsidered as a potential alternative route to existing options for solving the nuclear waste problem and is associated with the renaissance of nuclear industry. Self- disposal option utilises the heat generated by decaying radionuclides of radioactive waste inside a heavy and durable capsule to melt the rock on its way down. As the heat from radionuclides within the capsule partly melts the enclosing rock, the relatively low viscosity and density of the silicate melt allow the capsule to be displaced upwards past the heavier capsule as it sinks. Eventually the melt cools and solidifies (e.g. vitrifies or crystallizes), sealing the route along which the capsule passed. Descending or self-disposal continues until enough heat is generated by radionuclides to provide partial melting of surrounding rock. Estimates show that extreme depths of several tens and up to hundred km can be reached by capsules which could never be achieved by other techniques. Self- disposal does not require complex and expensive disposal facilities and provides a minimal footprint used only at operational stage. It has also an extremely high non- proliferation character and degree of safety. Utilisation of heat generated by relatively short-lived radionuclides diminishes the environmental uncertainties of self-disposal and increases the safety of this concept. Self-sinking heat-generating capsules could be launched from the bottom of the sea as

  6. Exploratory Disposal and Reuse Feasibility Analysis of Winter Maintenance Wash Water.

    Science.gov (United States)

    Ullinger, Heather L; Kennedy, Marla J; Schneider, William H; Miller, Christopher M

    2016-01-01

    The Ohio Department of Transportation has more than 60 facilities without sewer access generating approximately 19 million gallons of winter maintenance wash water. Off-site disposal is costly, creating the need for sustainable management strategies. The objective of this study was to conduct an exploratory feasibility analysis to assess wash water disposal and potential reuse as brine. Based on a comprehensive literature review and relevant environmental chemistry, a sampling protocol consisting of 31 water quality constituents was utilized for monthly sampling at three geographically distinct Ohio Department of Transportation garages during the winter of 2012. Results were compared to local disposal and reuse guidance limits. Three constituents, including a maximum copper concentration of 858 ppb, exceeded disposal limits, and many constituents also failed to meet reuse limits. Some concentrations were orders of magnitude higher than reuse limits and suggest pre-treatment would be necessary if wash water were reused as brine. These water quality results, in conjunction with copper chemical equilibrium modeling, show pH and dissolved carbon both significantly impact the total dissolved copper concentration and should be measured to assess reuse potential. The sampling protocol and specific obstacles highlighted in this paper aid in the future development of sustainable wash water management strategies.

  7. Exploratory Disposal and Reuse Feasibility Analysis of Winter Maintenance Wash Water.

    Directory of Open Access Journals (Sweden)

    Heather L Ullinger

    Full Text Available The Ohio Department of Transportation has more than 60 facilities without sewer access generating approximately 19 million gallons of winter maintenance wash water. Off-site disposal is costly, creating the need for sustainable management strategies. The objective of this study was to conduct an exploratory feasibility analysis to assess wash water disposal and potential reuse as brine. Based on a comprehensive literature review and relevant environmental chemistry, a sampling protocol consisting of 31 water quality constituents was utilized for monthly sampling at three geographically distinct Ohio Department of Transportation garages during the winter of 2012. Results were compared to local disposal and reuse guidance limits. Three constituents, including a maximum copper concentration of 858 ppb, exceeded disposal limits, and many constituents also failed to meet reuse limits. Some concentrations were orders of magnitude higher than reuse limits and suggest pre-treatment would be necessary if wash water were reused as brine. These water quality results, in conjunction with copper chemical equilibrium modeling, show pH and dissolved carbon both significantly impact the total dissolved copper concentration and should be measured to assess reuse potential. The sampling protocol and specific obstacles highlighted in this paper aid in the future development of sustainable wash water management strategies.

  8. Product remanufacturing and disposal: A numerical comparison of alternative control strategies

    OpenAIRE

    Laan, Erwin; Dekker, Rommert; Salomon, Marc

    1996-01-01

    textabstractIn this paper we consider a single-product, single-echelon production and inventory system with product returns, product remanufacturing, and product disposal. For this system we consider three different procurement and inventory

  9. The effect of alternative cost and environmental impact minimisation strategies on radioactive waste disposal strategies

    International Nuclear Information System (INIS)

    Laundy, R.S.; James, A.R.; Groom, M.S.; Dalrymple, G.J.

    1985-06-01

    The study reported here investigates the effects of different cost and environmental impact minimisation strategies for a single waste disposal scenario. Four disposal options are considered. The study examines the environmental impacts from waste storage and transport and the disposal impacts in terms of collective dose, maximum individual dose and individual dose from intrusion. The total cost of disposing of waste takes account of storage, transport and disposal costs to each of the four facilities. Two minimum cost scenarios and seven minimum impact assessments were performed. The results showed clearly that a trade-off has to be made between the environmental impacts from transport and storage of waste. A low objective risk of transport is achieved by directing waste to the engineered trench, assumed to have a central location. This waste is stored until the facility is available in 1995 thus increasing the potential impact from storage. The results also show a trade-off has to be made between minimising the maximum individual dose from disposal and collective dose. The study shows that for relatively little cost large reductions in the impacts can be obtained particularly in short and long-term collective dose and the individual dose from intrusion. (author)

  10. Deep Borehole Disposal Safety Analysis.

    Energy Technology Data Exchange (ETDEWEB)

    Freeze, Geoffrey A. [Sandia National Laboratories (SNL-NM), Albuquerque, NM (United States); Stein, Emily [Sandia National Laboratories (SNL-NM), Albuquerque, NM (United States); Price, Laura L. [Sandia National Laboratories (SNL-NM), Albuquerque, NM (United States); MacKinnon, Robert J. [Sandia National Laboratories (SNL-NM), Albuquerque, NM (United States); Tillman, Jack Bruce [Sandia National Laboratories (SNL-NM), Albuquerque, NM (United States)

    2016-10-01

    This report presents a preliminary safety analysis for the deep borehole disposal (DBD) concept, using a safety case framework. A safety case is an integrated collection of qualitative and quantitative arguments, evidence, and analyses that substantiate the safety, and the level of confidence in the safety, of a geologic repository. This safety case framework for DBD follows the outline of the elements of a safety case, and identifies the types of information that will be required to satisfy these elements. At this very preliminary phase of development, the DBD safety case focuses on the generic feasibility of the DBD concept. It is based on potential system designs, waste forms, engineering, and geologic conditions; however, no specific site or regulatory framework exists. It will progress to a site-specific safety case as the DBD concept advances into a site-specific phase, progressing through consent-based site selection and site investigation and characterization.

  11. Comparing technical concepts for disposal of Belgian vitrified HLW

    International Nuclear Information System (INIS)

    Bel, J.; Bock, C. de; Boyazis, J.P.

    2004-01-01

    The choice of a suitable repository design for different categories of radioactive waste is an important element in the decisional process that will eventually lead to the waste disposal in geological ground layers during the next decades. Most countries are in the process of elaborating different technical solutions for their EBS '. Considering possible design alternatives offers more flexibility to cope with remaining uncertainties and allows optimizing some elements of the EBS in the future. However, it is not feasible to continue carrying out detailed studies for a large number of alternative design options. At different stages in the decisional process, choices, even preliminary ones, have to be made. Although the impact of different stakeholders (regulator, waste agencies, waste producers, research centers,...) in making these design choices can differ from one country to another, the choices should be based on sound, objective, clear and unambiguous justification grounds. Moreover, the arguments should be carefully reported and easy to understand by the decision makers. ONDRAF/NIRAS recently elaborated three alternative designs for the disposal of vitrified HLW. These three designs are briefly described in the next section. A first series of technological studies pointed out that the three options are feasible. It would however be unreasonable to continue R and D work on all three alternatives in parallel. It is therefore planned to make a preliminary choice of a reference design for the vitrified HLW in 2003. This selection will depend on the way the alternative design options can be evaluated against a number of criteria, mainly derived from general repository design requirements. The technique of multi-criteria analysis (MCA) will be applied as a tool for making the optimum selection, considering all selection criteria and considering different strategic approaches. This paper describes the used methodology. The decision on the actual selection will be

  12. Transuranic advanced disposal systems: preliminary 239Pu waste-disposal criteria for Hanford

    International Nuclear Information System (INIS)

    Kennedy, W.E. Jr.; Napier, B.A.; Soldat, J.K.

    1982-08-01

    An evaluation of the feasibility and potential application of advanced disposal systems is being conducted for defense transuranic (TRU) wastes at the Hanford Site. The advanced waste disposal options include those developed to provide greater confinement than provided by shallow-land burial. An example systems analysis is discussed with assumed performance objectives and various Hanford-specific disposal conditions, waste forms, site characteristics, and engineered barriers. Preliminary waste disposal criteria for 239 Pu are determined by applying the Allowable Residual Contamination Level (ARCL) method. This method is based on compliance with a radiation dose rate limit through a site-specific analysis of the potential for radiation exposure to individuals. A 10,000 year environmental performance period is assumed, and the dose rate limit for human intrusion is assumed to be 500 mrem/y to any exposed individual. Preliminary waste disposal criteria derived by this method for 239 Pu in soils at the Hanford Site are: 0.5 nCi/g in soils between the surface and a depth of 1 m, 2200 nCi/g of soil at a depth of 5 m, and 10,000 nCi/g of soil at depths 10 m and below. These waste disposal criteria are based on exposure scenarios that reflect the dependence of exposure versus burial depth. 2 figures, 5 tables

  13. Northeast Regional environmental impact study: Waste disposal technical report

    Science.gov (United States)

    Saguinsin, J. L. S.

    1981-04-01

    The potential for cumulative and interactive environmental impacts associated with the conversion of multiple generating stations in the Northeast is assessed. The estimated quantities and composition of wastes resulting from coal conversion, including ash and SO2 scrubber sludge, are presented. Regulations governing the use of ash and scrubber sludge are identified. Currently available waste disposal schemes are described. The location, capacity, and projected life of present and potential disposal sites in the region are identified. Waste disposal problems, both hazardous and nonhazardous, are evaluated. Environmental regulations within the region as they pertain to coal conversion and as they affect the choice of conversion alternatives are discussed. A regional waste management strategy for solid waste disposal is developed.

  14. Disposal of chemical agents and munitions stored at Anniston Army Depot, Anniston, Alabama

    Energy Technology Data Exchange (ETDEWEB)

    Hunsaker, D.B. Jr.; Zimmerman, G.P.; Hillsman, E.L.; Miller, R.L.; Schoepfle, G.M.; Johnson, R.O.; Tolbert, V.R.; Kroodsma, R.L.; Rickert, L.W.; Rogers, G.O.; Staub, W.P.

    1990-09-01

    The purpose of this Phase I report is to examined the proposed implementation of on-site disposal at Anniston Army Depot (ANAD) in light of more detailed and more recent data than those included in the Final Programmatic Environmental Impact Statement (EPEIS). Two principal issues are addressed: (1) whether or not the new data would result in identification of on-site disposal at ANAD as the environmentally preferred alternative (using the same selection method and data analysis tools as in the FPEIS), and (2) whether or not the new data indicate the presence of significant environmental resources that could be affected by on-site disposal at ANAD. In addition, a status report is presented on the maturity of the disposal technology (and now it could affect on-site disposal at ANAD). Inclusion of these more recent data into the FPEIS decision method resulted in confirmation of on-site disposal for ANAD. No unique resources with the potential to prevent or delay implementation of on-site disposal at ANAD have been identified. A review of the technology status identified four principal technology developments that have occurred since publication of the FPEIS and should be of value in the implementation of on-site disposal at ANAD: the disposal of nonlethal agent at Pine Bluff Arsenal, located near Pine Bluff, Arkansas; construction and testing of facilities for disposal of stored lethal agent at Johnston Atoll, located about 1300 km (800 miles) southwest of Hawaii in the Pacific Ocean; lethal agent disposal tests at the chemical agent pilot plant operations at Tooele Army Depot, located near Salt Lake City, Utah; and equipment advances. 18 references, 13 figs., 10 tabs.

  15. Social and institutional evaluation report for Greater-Than-Class C Low-Level Radioactive Waste Disposal

    International Nuclear Information System (INIS)

    Anderson, T.L.; Lewis, B.E.; Turner, K.H.; Rozelle, M.A.

    1993-10-01

    This report identifies and characterizes social and institutional issues that would be relevant to the siting, licensing, construction, closure, and postclosure of a Greater-Than-Class-C low-level radioactive waste (GTCC LLW) disposal facility. A historical perspective of high-level radioactive waste (HLW) and LLW disposal programs is provided as an overview of radioactive waste disposal and to support the recommendations and conclusions in the report. A characterization of each issue is provided to establish the basis for further evaluations. Where applicable, the regulatory requirements of 10 CFR 60 and 61 are incorporated in the issue characterizations. The issues are used to compare surface, intermediate depth, and deep geologic disposal alternatives. The evaluation establishes that social and institutional issues do not significantly discriminate among the disposal alternatives. Recommendations are provided for methods by which the issues could be considered throughout the lifecycle of a GTCC LLW disposal program

  16. Social and institutional evaluation report for Greater-Than-Class C Low-Level Radioactive Waste Disposal

    Energy Technology Data Exchange (ETDEWEB)

    Anderson, T.L.; Lewis, B.E.; Turner, K.H.; Rozelle, M.A. [Dames and Moore, Denver, CO (United States)

    1993-10-01

    This report identifies and characterizes social and institutional issues that would be relevant to the siting, licensing, construction, closure, and postclosure of a Greater-Than-Class-C low-level radioactive waste (GTCC LLW) disposal facility. A historical perspective of high-level radioactive waste (HLW) and LLW disposal programs is provided as an overview of radioactive waste disposal and to support the recommendations and conclusions in the report. A characterization of each issue is provided to establish the basis for further evaluations. Where applicable, the regulatory requirements of 10 CFR 60 and 61 are incorporated in the issue characterizations. The issues are used to compare surface, intermediate depth, and deep geologic disposal alternatives. The evaluation establishes that social and institutional issues do not significantly discriminate among the disposal alternatives. Recommendations are provided for methods by which the issues could be considered throughout the lifecycle of a GTCC LLW disposal program.

  17. The Remote Handled Immobilization Low-Activity Waste Disposal Facility Environmental Permits and Approval Plan

    International Nuclear Information System (INIS)

    DEFFENBAUGH, M.L.

    2000-01-01

    The purpose of this document is to revise Document HNF-SD-ENV-EE-003, ''Permitting Plan for the Immobilized Low-Activity Waste Project, which was submitted on September 4, 1997. That plan accounted for the interim storage and disposal of Immobilized-Low Activity Waste at the existing Grout Treatment Facility Vaults (Project W-465) and within a newly constructed facility (Project W-520). Project W-520 was to have contained a combination of concrete vaults and trenches. This document supersedes that plan because of two subsequent items: (1) A disposal authorization that was received on October 25, 1999, in a U. S. Department of Energy-Headquarters, memorandum, ''Disposal Authorization Statement for the Department of Energy Hanford site Low-Level Waste Disposal facilities'' and (2) ''Breakthrough Initiative Immobilized Low-Activity Waste (ILAW) Disposal Alternative,'' August 1999, from Lucas Incorporated, Richland, Washington. The direction within the U. S. Department of Energy-Headquarters memorandum was given as follows: ''The DOE Radioactive Waste Management Order requires that a Disposal authorization statement be obtained prior to construction of new low-level waste disposal facility. Field elements with the existing low-level waste disposal facilities shall obtain a disposal authorization statement in accordance with the schedule in the complex-wide Low-Level Waste Management Program Plan. The disposal authorization statement shall be issued based on a review of the facility's performance assessment and composite analysis or appropriate CERCLA documentation. The disposal authorization shall specify the limits and conditions on construction, design, operations, and closure of the low-level waste facility based on these reviews. A disposal authorization statement is a part of the required radioactive waste management basis for a disposal facility. Failure to obtain a disposal authorization statement or record of decision shall result in shutdown of an operational

  18. Unreviewed Disposal Question Evaluation: Waste Disposal In Engineered Trench #3

    Energy Technology Data Exchange (ETDEWEB)

    Hamm, L. L.; Smith, F. G. III; Flach, G. P.; Hiergesell, R. A.; Butcher, B. T.

    2013-07-29

    Because Engineered Trench #3 (ET#3) will be placed in the location previously designated for Slit Trench #12 (ST#12), Solid Waste Management (SWM) requested that the Savannah River National Laboratory (SRNL) determine if the ST#12 limits could be employed as surrogate disposal limits for ET#3 operations. SRNL documented in this Unreviewed Disposal Question Evaluation (UDQE) that the use of ST#12 limits as surrogates for the new ET#3 disposal unit will provide reasonable assurance that Department of Energy (DOE) 435.1 performance objectives and measures (USDOE, 1999) will be protected. Therefore new ET#3 inventory limits as determined by a Special Analysis (SA) are not required.

  19. Household waste disposal in Mekelle city, Northern Ethiopia

    International Nuclear Information System (INIS)

    Tadesse, Tewodros; Ruijs, Arjan; Hagos, Fitsum

    2008-01-01

    In many cities of developing countries, such as Mekelle (Ethiopia), waste management is poor and solid wastes are dumped along roadsides and into open areas, endangering health and attracting vermin. The effects of demographic factors, economic and social status, waste and environmental attributes on household solid waste disposal are investigated using data from household survey. Household level data are then analyzed using multinomial logit estimation to determine the factors that affect household waste disposal decision making. Results show that demographic features such as age, education and household size have an insignificant impact over the choice of alternative waste disposal means, whereas the supply of waste facilities significantly affects waste disposal choice. Inadequate supply of waste containers and longer distance to these containers increase the probability of waste dumping in open areas and roadsides relative to the use of communal containers. Higher household income decreases the probability of using open areas and roadsides as waste destinations relative to communal containers. Measures to make the process of waste disposal less costly and ensuring well functioning institutional waste management would improve proper waste disposal

  20. Home Sewage Disposal. Special Circular 212.

    Science.gov (United States)

    Wooding, N. Henry

    This circular provides current information for homeowners who must repair or replace existing on-lot sewage disposal systems. Site requirements, characteristics and preparation are outlined for a variety of alternatives such as elevated sand mounds, sand-lined beds and trenches, and oversized absorption area. Diagrams indicating construction…

  1. Analysis of heat and mass transfer in sub-seabed disposal of nuclear waste

    International Nuclear Information System (INIS)

    Hickox, C.E.; Gartling, D.K.; McVey, D.F.; Russo, A.J.; Nuttall, H.E.

    1980-01-01

    A mathematical basis is developed for the prediction of thermal and radionuclide transport in marine sediments. The theory is applied to the study of radioactive waste disposal by emplacement, in specially designed containers, well below the sediment/water interface. Numerical results are obtained for a specified model problem through use of two computer programs designed primarily for the analysis of waste disposal problems. One program (MARIAH) provides descriptions of the temperature and velocity fields induced by the presence of a container of thermally active nuclear waste. A second program (IONMIG), which utilizes the results of the thermal analysis, is used to provide predictions for the migration of four representative radionuclides: 239 Pu, 137 Cs, 129 I, and 99 Tc

  2. Implementation of multimode release criteria and dose standard alternatives

    International Nuclear Information System (INIS)

    Klett, R.

    1993-01-01

    The current standard that regulates the disposal of high-level radioactive wastes (HLW) and transuranic (TRU) wastes evaluates the cumulative risk of all repositories with a single derived set of generic release limits. This paper reviews the technical basis, attributes, and deficiencies of the present approach and two alternative modifications and extensions. The alternatives are the multimode release limits applied at the point of release and a dose standard alternative suggested at the first Electric Power Research Institute (EPRI) waste disposal workshop. Methods of developing and applying the alternatives are presented and some suggestions are given for incorporating them in the standards

  3. 2005 dossier: granite. Tome: safety analysis of the geologic disposal; Dossier 2005: granite. Tome analyse de surete du stockage geologique

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2005-07-01

    This document makes a status of the researches carried out by the French national agency of radioactive wastes (ANDRA) about the safety aspects of the geologic disposal of high-level and long-lived (HLLL) radioactive wastes in granite formations. Content: 1 - safety approach: context and general goal, references, design approach by safety functions, safety approach during the construction-exploitation-observation-closure phase, safety analysis during the post-closure phase; 2 - general description: HLLL wastes, granitic environment, general structure of the architecture of a disposal facility; 3 - safety functions and disposal design: general context, safety functions of the long-term disposal, design dispositions retained to answer the functions; 4 - operational safety: people's protection, radiological risks during exploitation, risk analysis in accident situation; 5 - qualitative safety analysis: methodology, main results of the analysis of the features, events and processes (FEP) database; 6 - disposal efficiency evaluation during post-closure phase: calculation models, calculation tools used for the modeling of radionuclides transport, calculation results and main lessons. (J.S.)

  4. 2005 dossier: granite. Tome: safety analysis of the geologic disposal; Dossier 2005: granite. Tome analyse de surete du stockage geologique

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2005-07-01

    This document makes a status of the researches carried out by the French national agency of radioactive wastes (ANDRA) about the safety aspects of the geologic disposal of high-level and long-lived (HLLL) radioactive wastes in granite formations. Content: 1 - safety approach: context and general goal, references, design approach by safety functions, safety approach during the construction-exploitation-observation-closure phase, safety analysis during the post-closure phase; 2 - general description: HLLL wastes, granitic environment, general structure of the architecture of a disposal facility; 3 - safety functions and disposal design: general context, safety functions of the long-term disposal, design dispositions retained to answer the functions; 4 - operational safety: people's protection, radiological risks during exploitation, risk analysis in accident situation; 5 - qualitative safety analysis: methodology, main results of the analysis of the features, events and processes (FEP) database; 6 - disposal efficiency evaluation during post-closure phase: calculation models, calculation tools used for the modeling of radionuclides transport, calculation results and main lessons. (J.S.)

  5. Ripening of clayey dredged sediments during temporary upland disposal, A Bioremediation technique.

    NARCIS (Netherlands)

    Vermeulen, J.; Grotenhuis, J.T.C.; Joziasse, J.; Rulkens, W.H.

    2003-01-01

    Background and Goal. In the Netherlands about 40 million m3 of sediment has to be dredged annually for both maintenance and environmental reasons. Temporary upland disposal is the most widely adopted alternative for dredged sediments worldwide. For good management of temporary disposal sites,

  6. Legal and regulatory issues regarding classification and disposal of wastes from actinide partitioning and transmutation

    International Nuclear Information System (INIS)

    Kocher, D.C.

    1989-01-01

    Partitioning and transmutation of actinide radioelements in spent nuclear fuel from civilian power reactors is potentially attractive because the resulting wastes might be acceptable for disposal using systems which are considerably less costly than a deep geologic repository. At present, there are no legal or regulatory prohibitions to seeking alternatives to a geologic repository for disposal of such wastes. However, additional laws and regulations would be needed, and the Nuclear Regulatory Commission has been reluctant to alter the current framework for radioactive waste management, in which geologic repositories or near-surface facilities are the only disposal options established in law and regulations unless a compelling need for alternatives with intermediate waste-isolation capabilities is demonstrated. There are also important technical considerations which are not encouraging with regard to the development of intermediate disposal systems for wastes from partitioning and transmutation of actinides in civilian spent fuel. First, the wastes may contain sufficient concentrations of fission products. Second, defense reprocessing wastes may contain sufficient concentrations of fission products and long-lived actinides. Thus, in developing the legal and regulatory framework for alternative disposal systems, there is a need to establish maximum concentrations of fission products and long-lived actinides that would be acceptable for intermediate disposal. 19 refs

  7. The deep disposal repository - an alternative general arrangement

    International Nuclear Information System (INIS)

    Wolofsky, L.

    1996-01-01

    For the disposal of nuclear fuel waste in Canada the current proposal requires a repository at or below 500 m depth in Precambrian plutonic igneous rock in Ontario, consisting of numerous horizontal parallel tunnels arranged in one or more horizontal planes i.e. a room-and-pillar arrangement. The pillars are three times as wide as the tunnels, giving as extraction ratio of 25%. The tunnels are tentatively designed to be excavated by drill and blast, with a flat-arched roof, vertical side walls and a flat invert. The fuel containing canisters are to be surrounded by a low-permeability bentonite-based buffer in vertical holes drilled for the purpose in the invert

  8. Disposal of chemical agents and munitions stored at Umatilla Depot Activity, Hermiston, Oregon

    Energy Technology Data Exchange (ETDEWEB)

    Zimmerman, G.P.; Hillsman, E.L.; Johnson, R.O.; Miller, R.L.; Patton, T.G.; Schoepfle, G.M.; Tolbert, V.R.; Feldman, D.L.; Hunsaker, D.B. Jr.; Kroodsma, R.L.; Morrissey, J.; Rickert, L.W.; Staub, W.P.; West, D.C.

    1993-02-01

    The Umatilla Depot Activity (UMDA) near Hermiston, Oregon, is one of eight US Army installations in the continental United States where lethal unitary chemical agents and munitions are stored, and where destruction of agents and munitions is proposed under the Chemical Stockpile Disposal Program (CSDP). The chemical agent inventory at UMDA consists of 11.6%, by weight, of the total US stockpile. The destruction of the stockpile is necessary to eliminate the risk to the public from continued storage and to dispose of obsolete and leaking munitions. In 1988 the US Army issued a Final Programmatic Environmental Impact Statement (FPEIS) for the CSDP that identified on-site disposal of agents and munitions as the environmentally preferred alternative (i.e., the alternative with the least potential to cause significant adverse impacts), using a method based on five measures of risk for potential human health and ecosystem/environmental effects; the effectiveness and adequacy of emergency preparedness capabilities also played a key role in the FPEIS selection methodology. In some instances, the FPEIS included generic data and assumptions that were developed to allow a consistent comparison of potential impacts among programmatic alternatives and did not include detailed conditions at each of the eight installations. The purpose of this Phase 1 report is to examine the proposed implementation of on-site disposal at UMDA in light of more recent and more detailed data than those included in the FPEIS. Specifically, this Phase 1 report is intended to either confirm or reject the validity of on-site disposal for the UMDA stockpile. Using the same computation methods as in the FPEIS, new population data were used to compute potential fatalities from hypothetical disposal accidents. Results indicate that onsite disposal is clearly preferable to either continued storage at UMDA or transportation of the UMDA stockpile to another depot for disposal.

  9. Limited risk assessment and some cost/benefit considerations for greater confinement disposal compared to shallow land burial

    International Nuclear Information System (INIS)

    Hunter, P.H.; Lester, D.H.; Robertson, L.D.; Spaeth, M.E.; Stoddard, J.A.; Dickman, P.T.

    1984-09-01

    A limited risk assessment and some cost/benefit considerations of greater confinement disposal (GCD) compared to shallow land burial (SLB) are presented. This study is limited to an analysis of the postclosure phase of hypothetical GCD and SLB facilities. Selected release scenarios are used which bound the range of risks to a maximally exposed individual and a hypothetical population. Based on the scenario assessments, GCD had a significant risk advantage over SLB for normal exposure pathways at both humid and arid sites, particularly for the human intrusion scenario. Since GCD costs are somewhat higher than SLB, it is necessary to weigh the higher costs of GCD against the higher risks of SLB. In this regard, GCD should be pursued as an alternative to SLB for certain types of low-level waste, and as an alternative to processing for wastes requiring improved stabilization or higher integrity packaging to be compatible with SLB. There are two reasons for this conclusion. First, GCD might diminish public apprehension regarding the disposal of wastes perceived to be too hazardous for SLB. Second, GCD may be a relatively cost-effective alternative to various stabilization and packaging schemes required to meet 10 CFR 61 near-surface requirements as well as being a cost-effective alternative to deep geologic disposal. Radionuclide transport through the biosphere and resultant dose consequences were determined using the RADTRAN radionuclide transport code. 19 references, 4 figures, 5 tables

  10. The analysis of geological formations from Romania available for disposal of spent nuclear fuel

    International Nuclear Information System (INIS)

    Barariu, Gheorghe; Alecu, Catalin

    2003-01-01

    The majority of countries possessing nuclear power industry has not yet decided upon the option about closing the nuclear cycle. There are still in progress projects concerning the final disposal, while worldwide it is not foreseen the reprocessing of the whole amount of reusable fissionable materials. The annual worldwide production of used nuclear fuel continues to be about 10 500 - 11 000 tones of heavy metal. The difficulties in designing used fuel final disposal repositories led to the design of some interim storage facilities, providing a satisfactory safety level for biosphere. On the other hand, regardless of the selected option we respect to closing the nuclear cycle, a final repository must exists, either for the high level wastes resulted from reprocessing the used nuclear fuel or for the used fuel considered radioactive waste. Although, presently, in Romania, the nuclear fuel extracted from the reactor after its 'useful life' is declared as radioactive waste, it may contain a certain amount of fissionable material that could be used in other types of reactors. This possibility implies taking into account the concept regarding the recovery of fuel after a certain period of time, although, by definition, final disposal means prevention of this possibility. The harmonization of the Romanian legislation with that of the European Community and the adhering to the European Conventions, poses among other issues the problem of the final disposal of the used nuclear fuel. Starting from these major requirements the paper presents the main aspects of the Project 011/11.10.2001, entitled 'Researches for the selection and preliminary characterization of the host rock for the final disposal of the used nuclear fuel', part of The National Research Program: Medium, Energy and Resources. A complex analysis regarding the implications on the design of the Used Nuclear Fuel Final Disposal Repository in Romania was performed, the analysis of the available geological

  11. Business System Planning Project, Alternatives Analysis

    International Nuclear Information System (INIS)

    EVOSEVICH, S.

    2000-01-01

    The CHG Chief Information Officer (CIO) requested a study of alternatives to the current business system computing environment. This Business Systems Planning (BSP) Project Alternatives Analysis document presents an analysis of the current Project Controls, Work Management, and Business Management systems environment and alternative solutions that support the business functions. The project team has collected requirements and priorities from stakeholders in each business area and documented them in the BSP System Requirements Specification (SRS), RPP-6297. The alternatives analysis process identifies and measures possible solutions in each of the business process areas against the requirements as documented in the SRS. The team gathered input from both internal and external sources to identify and grade the possible solutions. This document captures the results of that activity and recommends a suite of software products. This study was to select the best product based on how well the product met the requirements, not to determine the platform or hardware environment that would be used. Additional analysis documentation can be found in BSP project files

  12. Chemical Stockpile Disposal Program

    Energy Technology Data Exchange (ETDEWEB)

    Krummel, J.R.; Policastro, A.J.; Olshansky, S.J.; McGinnis, L.D.

    1990-10-01

    As part of the Chemical Stockpile Disposal Program mandated by Public Law 99--145 (Department of Defense Authorization Act), an independent review is presented of the US Army Phase I environmental report for the disposal program at the Umatilla Depot Activity (UMDA) in Hermiston, Oregon. The Phase I report addressed new and additional concerns not incorporated in the final programmatic environmental impact statement (FPEIS). Those concerns were addressed by examining site-specific data for the Umatilla Depot Activity and by recommending the scope and content of a more detailed site-specific study. This independent review evaluates whether the new site-specific data presented in the Phase I report would alter the decision in favor of on-site disposal that was reached in the FPEIS, and whether the recommendations for the scope and content of the site-specific study are adequate. Based on the methods and assumptions presented in the FPEIS, the inclusion of more detailed site-specific data in the Phase I report does not change the decision reached in the FPEIS (which favored on-site disposal at UMDA). It is recommended that alternative assumptions about meteorological conditions be considered and that site-specific data on water, ecological, socioeconomic, and cultural resources; seismicity; and emergency planning and preparedness be considered explicitly in the site-specific EIS decision-making process. 7 refs., 1 fig.

  13. Radwaste characteristics and Disposal Facility Waste Acceptance Criteria

    International Nuclear Information System (INIS)

    Sung, Suk Hyun; Jeong, Yi Yeong; Kim, Ki Hong

    2008-01-01

    The purpose of Radioactive Waste Acceptance Criteria (WAC) is to verify a radioactive waste compliance with radioactive disposal facility requirements in order to maintain a disposal facility's performance objectives and to ensure its safety. To develop WAC which is conformable with domestic disposal site conditions, we furthermore analysed the WAC of foreign disposal sites similar to the Kyung-Ju disposal site and the characteristics of various wastes which are being generated from Korea nuclear facilities. Radioactive WAC was developed in the technical cooperation with the Korea Atomic Energy Research Institute in consideration of characteristics of the wastes which are being generated from various facilities, waste generators' opinions and other conditions. The established criteria was also discussed and verified at an advisory committee which was comprised of some experts from universities, institutes and the industry. So radioactive WAC was developed to accept all wastes which are being generated from various nuclear facilities as much as possible, ensuring the safety of a disposal facility. But this developed waste acceptance criteria is not a criteria to accept all the present wastes generated from various nuclear facilities, so waste generators must seek an alternative treatment method for wastes which were not worth disposing of, and then they must treat the wastes more to be acceptable at a disposal site. The radioactive disposal facility WAC will continuously complement certain criteria related to a disposal concentration limit for individual radionuclide in order to ensure a long-term safety.

  14. The Remote Handled Immobilization Low Activity Waste Disposal Facility Environmental Permits & Approval Plan

    Energy Technology Data Exchange (ETDEWEB)

    DEFFENBAUGH, M.L.

    2000-08-01

    The purpose of this document is to revise Document HNF-SD-ENV-EE-003, ''Permitting Plan for the Immobilized Low-Activity Waste Project, which was submitted on September 4, 1997. That plan accounted for the interim storage and disposal of Immobilized-Low Activity Waste at the existing Grout Treatment Facility Vaults (Project W-465) and within a newly constructed facility (Project W-520). Project W-520 was to have contained a combination of concrete vaults and trenches. This document supersedes that plan because of two subsequent items: (1) A disposal authorization that was received on October 25, 1999, in a U. S. Department of Energy-Headquarters, memorandum, ''Disposal Authorization Statement for the Department of Energy Hanford site Low-Level Waste Disposal facilities'' and (2) ''Breakthrough Initiative Immobilized Low-Activity Waste (ILAW) Disposal Alternative,'' August 1999, from Lucas Incorporated, Richland, Washington. The direction within the U. S. Department of Energy-Headquarters memorandum was given as follows: ''The DOE Radioactive Waste Management Order requires that a Disposal authorization statement be obtained prior to construction of new low-level waste disposal facility. Field elements with the existing low-level waste disposal facilities shall obtain a disposal authorization statement in accordance with the schedule in the complex-wide Low-Level Waste Management Program Plan. The disposal authorization statement shall be issued based on a review of the facility's performance assessment and composite analysis or appropriate CERCLA documentation. The disposal authorization shall specify the limits and conditions on construction, design, operations, and closure of the low-level waste facility based on these reviews. A disposal authorization statement is a part of the required radioactive waste management basis for a disposal facility. Failure to obtain a disposal authorization statement

  15. Alternatives Analysis for the Resumption of Transient Testing Program

    Energy Technology Data Exchange (ETDEWEB)

    Lee Nelson

    2013-11-01

    An alternatives analysis was performed for resumption of transient testing. The analysis considered eleven alternatives – including both US international facilities. A screening process was used to identify two viable alternatives from the original eleven. In addition, the alternatives analysis includes a no action alternative as required by the National Environmental Policy Act (NEPA). The alternatives considered in this analysis included: 1. Restart the Transient Reactor Test Facility (TREAT) 2. Modify the Annular Core Research Reactor (ACRR) which includes construction of a new hot cell and installation of a new hodoscope. 3. No Action

  16. Regional LLRW [low-level radioactive waste] processing alternatives applying the DOE REGINALT systems analysis model

    International Nuclear Information System (INIS)

    Beers, G.H.

    1987-01-01

    The DOE Low-Level Waste Management Progam has developed a computer-based decision support system of models that may be used by nonprogrammers to evaluate a comprehensive approach to commercial low-level radioactive waste (LLRW) management. REGINALT (Regional Waste Management Alternatives Analysis Model) implementation will be described as the model is applied to a hypothetical regional compact for the purpose of examining the technical and economic potential of two waste processing alternaties. Using waste from a typical regional compact, two specific regional waste processing centers will be compared for feasibility. Example 1 will assume will assume that a regional supercompaction facility is being developed for the region. Example 2 will assume that a regional facility with both supercompation and incineration is specified. Both examples will include identical disposal facilities, except that capacity may differ due to variation in volume reduction achieved. The two examples will be compared with regard to volume reduction achieved, estimated occupational exposure for the processing facilities, and life cylcle costs per generated unit waste. A base case will also illustrate current disposal practices. The results of the comparisons will be evaluated, and other steps, if necessary, for additional decision support will be identified

  17. Groundwater flow analysis using mixed hybrid finite element method for radioactive waste disposal facilities

    International Nuclear Information System (INIS)

    Aoki, Hiroomi; Shimomura, Masanori; Kawakami, Hiroto; Suzuki, Shunichi

    2011-01-01

    In safety assessments of radioactive waste disposal facilities, ground water flow analysis are used for calculating the radionuclide transport pathway and the infiltration flow rate of groundwater into the disposal facilities. For this type of calculations, the mixed hybrid finite element method has been used and discussed about the accuracy of ones in Europe. This paper puts great emphasis on the infiltration flow rate of groundwater into the disposal facilities, and describes the accuracy of results obtained from mixed hybrid finite element method by comparing of local water mass conservation and the reliability of the element breakdown numbers among the mixed hybrid finite element method, finite volume method and nondegenerated finite element method. (author)

  18. Establishment of new disposal capacity for the Savannah River Plant

    International Nuclear Information System (INIS)

    Albenesius, E.L.; Wilhite, E.L.

    1987-01-01

    Two new low-level waste (LLW) disposal sites for decontaminated salt solidified with cement and fly ash (saltstone) and for conventional solid LLW are planned for SRP in the next several years. An above-ground vault disposal system for saltstone was designed to minimize impact on the environment by controlling permeability and diffusivity of the waste form and concrete liner. The experimental program leading to the engineered disposal system included formulation studies, multiple approaches to measurement of permeability and diffusivity, extensive mathematical modeling, and large-scale lysimeter tests to validate model projections. The overall study is an example of the systems approach to disposal site design to achieve a predetermined performance objective. The same systems approach is being used to develop alternative designs for disposal of conventional LLW at the Savannah River Plant. 14 figures

  19. Survey and analysis of the domestic technology level for the concept development of high level waste disposal

    Energy Technology Data Exchange (ETDEWEB)

    Kang, Chang Sun; Kim, Byung Su; Song, Jae Hyok [Seoul National University, Seoul (Korea); Park, Kwang Hon; Hwang, Ju Ho; Park, Sung Hyun; Lee, Jae Min [Kyunghee University, Seoul (Korea); Han, Joung Sang; Kim, Ku Young [Yonsei University, Seoul (Korea); Lee, Jae Ki; Chang, Jae Kwon [Hangyang University, Seoul (Korea)

    1998-09-01

    The objectives of this study are the analysis of the status of HLW disposal technology and the investigation of the domestic technology level. The study has taken two years to complete with the participation of forty five researchers. The study was mainly carried out through means of literature surveys, collection of related data, visits to research institutes, and meetings with experts in the specific fields. During the first year of this project, the International Symposium on the Concept Development of the High Level Waste Disposal System was held in Taejon, Korea in October, 1997. Eight highly professed foreign experts whose fields of expertise projected to the area of high level waste disposal were invited to the symposium. This study is composed of four major areas; disposal system design/construction, engineered barrier characterization, geologic environment evaluation and performance assessment and total safety. A technical tree scheme of HLW disposal has been illustrated according to the investigation and an analysis for each technical area. For each detailed technology, research projects, performing organization/method and techniques that are to be secured in the order of priority are proposed, but the suggestions are merely at a superfluous level of propositional idea due to the reduction of the budget in the second year. The detailed programs on HLW disposal are greatly affected by governmental HLW disposal policy and in this study, the primary decisions to be made in each level of HLW disposal enterprise and a rough scheme are proposed. (author). 20 refs., 97 figs., 33 tabs.

  20. Synthesis of the Results of the Field Verification Program Upland Disposal Alternative

    National Research Council Canada - National Science Library

    Folsom, Bobby

    1998-01-01

    ...) procedures for predicting potential contaminant mobility into animals. The upland disposal site was constructed within a protected area using conventional construction techniques and was hydraulically filled from barges...

  1. GNEP Material Transportation, Storage and Disposal Analysis FY-08 Summary Report

    Energy Technology Data Exchange (ETDEWEB)

    Halsey, W

    2009-01-15

    This report provides a summary for FY-2008 of activities, analyses and products from the Material Transportation, Storage and Disposal (M-TSD) sub-task of Systems Analysis within the Advanced Fuel Cycle Research & Development area of the Global Nuclear Energy Partnership. The objective of this work is to evaluate near-term material management requirements for initial GNEP facilities and activities, long-term requirements for large-scale GNEP technology deployment, and alternatives and paths forward to meet these needs. For FY-08, the work expanded to include the Integrated Waste Management Strategy as well as integration with the newly formed Waste Forms Campaign. The M-TSD team was expanded with the addition of support from Savannah River National Lab (SRNL) to the existing team of Lawrence Livermore National Lab (LLNL), Argonne National Lab (ANL), Idaho National Lab (INL), Sandia National Lab (SNL) and University of Nevada - Reno (UN-R). During the first half of the year, analysis was focused on providing supporting technical analysis and documentation to support anticipated high-level decisions on program direction. A number of analyses were conducted and reports prepared as program deliverables. This work is briefly summarized in this report. Analyses provided informally to other program efforts are included in this report to provide documentation. This year-end summary was planned primarily as a compilation of activities following the anticipated programmatic decisions. These decisions were deferred beyond the end of the year, and funds were reallocated in a number of areas, thus reducing the M-TSD activities. This report summarizes the miscellaneous 'ad-hoc' work conducted during the later part of the year, such as support to the draft Programmatic Environmental Impact Statement (PEIS), and support to other program studies. Major programmatic contributions from the M-TSD team during the year included: (1) Completion of the IWMS in March 2008 as the

  2. GNEP Material Transportation, Storage and Disposal Analysis FY-08 Summary Report

    International Nuclear Information System (INIS)

    Halsey, W.

    2009-01-01

    This report provides a summary for FY-2008 of activities, analyses and products from the Material Transportation, Storage and Disposal (M-TSD) sub-task of Systems Analysis within the Advanced Fuel Cycle Research and Development area of the Global Nuclear Energy Partnership. The objective of this work is to evaluate near-term material management requirements for initial GNEP facilities and activities, long-term requirements for large-scale GNEP technology deployment, and alternatives and paths forward to meet these needs. For FY-08, the work expanded to include the Integrated Waste Management Strategy as well as integration with the newly formed Waste Forms Campaign. The M-TSD team was expanded with the addition of support from Savannah River National Lab (SRNL) to the existing team of Lawrence Livermore National Lab (LLNL), Argonne National Lab (ANL), Idaho National Lab (INL), Sandia National Lab (SNL) and University of Nevada - Reno (UN-R). During the first half of the year, analysis was focused on providing supporting technical analysis and documentation to support anticipated high-level decisions on program direction. A number of analyses were conducted and reports prepared as program deliverables. This work is briefly summarized in this report. Analyses provided informally to other program efforts are included in this report to provide documentation. This year-end summary was planned primarily as a compilation of activities following the anticipated programmatic decisions. These decisions were deferred beyond the end of the year, and funds were reallocated in a number of areas, thus reducing the M-TSD activities. This report summarizes the miscellaneous 'ad-hoc' work conducted during the later part of the year, such as support to the draft Programmatic Environmental Impact Statement (PEIS), and support to other program studies. Major programmatic contributions from the M-TSD team during the year included: (1) Completion of the IWMS in March 2008 as the baseline

  3. Long-Term Management Strategy for Dredged Material Disposal for Naval Facilities at Pearl Harbor, Hawaii Phase III - Analysis of Alternatives and Development of an LTMS

    National Research Council Canada - National Science Library

    Palermo, Michael

    2000-01-01

    This report documents Phase III of a three-phase study to develop a Long-Term Management Study for disposal of dredged material unsuitable for ocean disposal from Pearl Harbor Naval Complex for the next 30 years...

  4. Supplement to the Disposal Criticality Analysis Methodology

    International Nuclear Information System (INIS)

    Thomas, D.A.

    1999-01-01

    The methodology for evaluating criticality potential for high-level radioactive waste and spent nuclear fuel after the repository is sealed and permanently closed is described in the Disposal Criticality Analysis Methodology Topical Report (DOE 1998b). The topical report provides a process for validating various models that are contained in the methodology and states that validation will be performed to support License Application. The Supplement to the Disposal Criticality Analysis Methodology provides a summary of data and analyses that will be used for validating these models and will be included in the model validation reports. The supplement also summarizes the process that will be followed in developing the model validation reports. These reports will satisfy commitments made in the topical report, and thus support the use of the methodology for Site Recommendation and License Application. It is concluded that this report meets the objective of presenting additional information along with references that support the methodology presented in the topical report and can be used both in validation reports and in answering request for additional information received from the Nuclear Regulatory Commission concerning the topical report. The data and analyses summarized in this report and presented in the references are not sufficient to complete a validation report. However, this information will provide a basis for several of the validation reports. Data from several references in this report have been identified with TBV-1349. Release of the TBV governing this data is required prior to its use in quality affecting activities and for use in analyses affecting procurement, construction, or fabrication. Subsequent to the initiation of TBV-1349, DOE issued a concurrence letter (Mellington 1999) approving the request to identify information taken from the references specified in Section 1.4 as accepted data

  5. Alternative way to dispose of high-level waste in outer space

    International Nuclear Information System (INIS)

    Takahashi, Hiroshi; Chen, Xinyi.

    1994-01-01

    We propose a new approach to dispose of Long-Lived Fission Products (LLFPs) of type II such as 99 T c and 129 I into outer solar space by providing an escape velocity from the solar system of 42 km/sec from a parking orbit or the moon's surface using a electrostatic accelerator and neutralizing the charged ions. LLFPs disposed uniformly in outer solar space pose no hazard as do LLFPs packages in Earth orbit, and have no effects on astronomical observations. This mode of disposition requires energy in the order of 1 keV for each nucleus, which is far smaller than the propulsion energy needed for launching a LLFPs package by rocket. Further, the power required of an accelerator ejecting most of the LLFPs generated by one LWR is 2.2 kW, which is much smaller than a medium-energy proton accelerator, a few tens of MW, which would be necessary to transmute these LLFPs using spallation neutrons created by protons

  6. Gas generation and migration analysis for TRU waste disposal system

    International Nuclear Information System (INIS)

    Ando, Kenichi; Noda, Masaru; Yamamoto, Mikihiko; Mihara, Morihiro

    2005-09-01

    In TRU waste disposal system, significant quantities of gases may be generated due to metal corrosion, radiolysis effect and microorganism activities. It is therefore recommended that the potential impact of gas generation and migration on TRU waste repository should be evaluated. In this study, gas generation rates were calculated in the repository and gas migration analysis in the disposal system were carried out using two phase flow model with results of gas generation rates. First, the time dependencies of gas generation rate in each TRU waste repositories were evaluated based on amounts of metal, organic matter and radioactivity. Next, the accumulation pressure of gases and expelled pore water volume nuclides in the repository were calculated by TOUGH2 code. After that, the results showed that the increase of gas pressure was the range of 1.3 to 1.4 MPa. In the repository with and without buffer, the rate of expelled pore water was 0.006 - 0.009 m 3 /y and 0.018 - 0.24m 3 /y, respectively. In addition, the radioactive gas migration through the repository and geosphere are evaluated. And re-saturation analysis is also performed to evaluate the initial condition of the system. (author)

  7. Disposal Site Information Management System

    International Nuclear Information System (INIS)

    Larson, R.A.; Jouse, C.A.; Esparza, V.

    1986-01-01

    An information management system for low-level waste shipped for disposal has been developed for the Nuclear Regulatory Commission (NRC). The Disposal Site Information Management System (DSIMS) was developed to provide a user friendly computerized system, accessible through NRC on a nationwide network, for persons needing information to facilitate management decisions. This system has been developed on NOMAD VP/CSS, and the data obtained from the operators of commercial disposal sites are transferred to DSIMS semiannually. Capabilities are provided in DSIMS to allow the user to select and sort data for use in analysis and reporting low-level waste. The system also provides means for describing sources and quantities of low-level waste exceeding the limits of NRC 10 CFR Part 61 Class C. Information contained in DSIMS is intended to aid in future waste projections and economic analysis for new disposal sites

  8. Conceptual Design Report for Remote-Handled Low-Level Waste Disposal Facility

    Energy Technology Data Exchange (ETDEWEB)

    Lisa Harvego; David Duncan; Joan Connolly; Margaret Hinman; Charles Marcinkiewicz; Gary Mecham

    2010-10-01

    This conceptual design report addresses development of replacement remote-handled low-level waste disposal capability for the Idaho National Laboratory. Current disposal capability at the Radioactive Waste Management Complex is planned until the facility is full or until it must be closed in preparation for final remediation (approximately at the end of Fiscal Year 2017). This conceptual design report includes key project assumptions; design options considered in development of the proposed onsite disposal facility (the highest ranked alternative for providing continued uninterrupted remote-handled low level waste disposal capability); process and facility descriptions; safety and environmental requirements that would apply to the proposed facility; and the proposed cost and schedule for funding, design, construction, and operation of the proposed onsite disposal facility.

  9. Assessment of the impacts of spent fuel disassembly alternatives on the Nuclear Waste Isolation System

    International Nuclear Information System (INIS)

    1984-07-01

    The objective of this report was to evaluate four possible alternative methods of preparing and packaging spent fuel assemblies for geologic disposal against the Reference Process of unmodified spent fuel. The four alternative processes were: (1) End fitting removal, (2) Fission gas venting and resealing, (3) Fuel bundle disassembly and close packing of fuel pins, and (4) Fuel shearing and immobilization. Systems analysis was used to develop a basis of comparison of the alternatives. Conceptual processes and facility layouts were devised for each of the alternatives, based on technology deemed feasible for the purpose. Assessments were made of 15 principal attributes from the technical, operational, safety/risk, and economic considerations related to each of the alternatives, including both the surface packaging and underground repository operations. Specific attributes of the alternative processes were evaluated by assigning a number for each that expressed its merit relative to the corresponding attribute of the Reference Process. Each alternative process was then ranked by summing the numbers for attributes in each of the four assessment areas and collectively. Fuel bundle disassembly and close packing of fuel pins was ranked the preferred method of disposal of spent fuel. 63 references, 46 figures, 46 tables

  10. Discussion on sealing performance required in disposal system. Hydraulic analysis of tunnel intersections

    International Nuclear Information System (INIS)

    Sugita, Yutaka; Takahashi, Yoshiaki; Uragami, Manabu; Kitayama, Kazumi; Fujita, Tomoo; Kawakami, Susumu; Yui, Mikazu; Umeki, Hiroyuki; Miyamoto, Yoichi

    2005-09-01

    The sealing performance of a repository must be considered in the safety assessment of the geological disposal system of the high-level radioactive waste. NUMO and JNC established 'Technical Commission on Sealing Technology of Repository' based on the cooperation agreement. The objectives of this commission are to present the concept on the sealing performance required in the disposal system and to develop the direction for future R and D programme for design requirements of closure components (backfilling material, clay plug, etc.) in the presented concept. In the first phase of this commission, the current status of domestic and international sealing technologies were reviewed; and repository components and repository environments were summarized subsequently, the hydraulic analysis of tunnel intersections, where a main tunnel and a disposal tunnel in a disposal panel meet, were performed, considering components in and around the engineered barrier system (EBS). Since all tunnels are connected in the underground facility, understanding the hydraulic behaviour of tunnel intersections is an important issue to estimate migration of radionuclides from the EBS and to evaluate the required sealing performance in the disposal system. In the analytical results, it was found that the direction of hydraulic gradient, hydraulic conductivities of concrete and backfilling materials and the position of clay plug had impact on flow condition around the EBS. (author)

  11. Intruder dose pathway analysis for the onsite disposal of radioactive wastes: the ONSITE/MAXI1 computer program. Supplement No. 1

    International Nuclear Information System (INIS)

    Kennedy, W.E. Jr.; Peloquin, R.A.; Napier, B.A.; Neuder, S.M.

    1986-05-01

    The document entitled Intruder Dose Pathway Analysis of the Onsite Disposal of Radioactive Wastes: The ONSITE/MAXI1 Computer Program (1984) summarizes initial efforts to develop human-intrustion scenarios and a modified version of the MAXI computer program for potential use by the NRC in reviewing applications for onsite radioactive waste disposal. This document is a supplement to that document and summarizes efforts to further modify and improve the ONSITE/MAXI1 software package. To facilitate cross-referencing, it follows the same format. Notable improvements to the software package include the capability to account for shielding conditions that represent noncompacted trash wastes and the option to indicate alternative land-use condition;s. This supplement contains a description of the implementation of these modifications. In addition, a series of discussions are included in an attempt to increase the user's understanding of the scenarios and dose calculation methods. These discussions respond to frequently asked questions about the mathematical models and use of the software. Computer listings of the ONSITE/MAXI1 computer program are included as Appendices A and B of this document. Appendix C lists external exposure dose-rate factor libraries

  12. Technical Scope and Approach for the 2004 Composite Analysis of Low Level Waste Disposal at the Hanford Site

    International Nuclear Information System (INIS)

    Kincaid, Charles T.; Bryce, Robert W.; Buck, John W.

    2004-01-01

    A composite analysis is required by U.S. Department of Energy (DOE) Manual 435.1-1 to ensure public safety through the management of active and planned low-level radioactive waste disposal facilities associated with the Hanford Site (DOE/HQ-Manual 435.1-1). A Composite Analysis is defined as ''a reasonably conservative assessment of the cumulative impact from active and planned low-level waste disposal facilities, and all other sources from radioactive contamination that could interact with the low-level waste disposal facility to affect the dose to future members of the public''. At the Hanford Site, a composite analysis is required for continued disposal authorization for the immobilized low-activity waste, tank waste vitrification plant melters, low level waste in the 200 East and 200 West Solid Waste Burial Grounds, and Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA) waste in the Environmental Restoration Disposal Facility. The 2004 Composite Analysis will be a site-wide analysis, considering final remedial actions for the Columbia River corridor and the Central Plateau at the Hanford Site. The river corridor includes waste sites and facilities in each of the 100 Areas as well as the 300, 400, and 600 Areas. The remedial actions for the river corridor are being conducted to meet residential land use standards with the vision of the river corridor being devoted to a combination of recreation and preservation. The ''Central Plateau'' describes the region associated with operations and waste sites of the 200 Areas. DOE is developing a strategy for closure of the Central Plateau area by 2035. At the time of closure, waste management activities will shrink to a Core Zone within the Central Plateau. The Core Zone will contain the majority of Hanford's permanently disposed waste

  13. Typing operations manual and disposal of fixed assets: directions of improvement of accounting

    Directory of Open Access Journals (Sweden)

    I.M. Vygivska

    2016-09-01

    Full Text Available The lack of studies on the structure of business operations for the operation and disposal of fixed assets leads to undeveloped organizational and methodological provisions of the relevant accounting operations. In particular, the lack of comprehensive understanding of these operations can not account for the loss of alternatives and economic benefits from the use of fixed assets in various areas of economic activity. To streamline the organizational and methodological approaches to accounting of fixed assets, and monitor the effectiveness of the use and preservation of the property of the owner of the enterprise, and according to the analysis of literary sources showing a considerable amount of controversy in the existing approach of the authors, to characterize the operations manual and the disposal of fixed assets, the article suggests typing operations, exploitation and disposal of fixed assets. The main types of these operations include: 1 operation – storage, use, maintenance, repair and improvement; 2 disposal - sale, free transfer, exchange, cancellation due to moral and physical deterioration, capital contribution, financial lease, the installation of shortage, the transfer in payment of debt, the loss resulting from emergencies.

  14. Special Analysis: Updated Analysis of the Effect of Wood Products on Trench Disposal Limits at the E-Area Low-Level Waste Facility

    International Nuclear Information System (INIS)

    Cook, J.R.

    2001-01-01

    This Special Analysis (SA) develops revised radionuclide inventory limits for trench disposal of low-level radioactive waste in the presence of wood products in the E-Area Low-Level Waste Facility. These limits should be used to modify the Waste Acceptance Criteria (WAC) for trench disposal. Because the work on which this SA is based employed data from tests using 100 percent wood products, the 40 percent limitation on wood products for trench (i.e., slit or engineered trench) disposal is not needed in the modified WAC

  15. Economic comparison of crystalline ceramic and glass waste forms for HLW disposal

    International Nuclear Information System (INIS)

    McKee, R.W.; Daling, P.M.; Wiles, L.E.

    1983-05-01

    A titanate-based, crystalline ceramic produced by hot isostatic pressing has been proposed as a potentially more stable and improved waste form for high-level nuclear waste disposal compared to the currently favored borosilicate glass waste form. This paper describes the results of a study to evaluate the relative costs for disposal of high-level waste from a 70,000 metric ton equivalent (MTE) system. The entire waste management system, including waste processing and encapsulation, transportation, and final repository disposal, was included in this analysis. The repository concept is based on the current basalt waste isolation project (BWIP) reference design. A range of design basis alternatives is considered to determine if this would influence the relative economics of the two waste forms. A thermal analysis procedure was utilized to define optimum canister sizes to assure that each waste form was compared under favorable conditions. Repository costs are found to favor the borosilicate glass waste form while transportation costs greatly favor the crystalline ceramic waste form. The determining component in the cost comparison is the waste processing cost, which strongly favors the borosilicate glass process because of its relative simplicity. A net cost advantage on the order of 12% to 15% on a waste management system basis is indicated for the glass waste form

  16. Waste Isolation Pilot Plant disposal phase final supplemental environmental impact statement. Volume 1, Chapters 1--6

    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. Chapters 1--6 include an introduction, background information, description of the proposed action and alternatives, description of the affected environments, environmental impacts, and consultations and permits

  17. Advancing Alternative Analysis: Integration of Decision Science

    DEFF Research Database (Denmark)

    Malloy, Timothy F; Zaunbrecher, Virginia M; Batteate, Christina

    2016-01-01

    Decision analysis-a systematic approach to solving complex problems-offers tools and frameworks to support decision making that are increasingly being applied to environmental challenges. Alternatives analysis is a method used in regulation and product design to identify, compare, and evaluate......, and civil society and included experts in toxicology, decision science, alternatives assessment, engineering, and law and policy. Participants were divided into two groups and prompted with targeted questions. Throughout the workshop, the groups periodically came together in plenary sessions to reflect......) engaging the systematic development and evaluation of decision approaches and tools; (2) using case studies to advance the integration of decision analysis into alternatives analysis; (3) supporting transdisciplinary research; and (4) supporting education and outreach efforts....

  18. Dimensionality of heavy metal distribution in waste disposal sites using nonlinear dynamics

    International Nuclear Information System (INIS)

    Modis, Kostas; Komnitsas, Kostas

    2008-01-01

    Mapping of heavy metal contamination in mining and waste disposal sites usually relies on geostatistical approaches and linear stochastic dynamics. The present paper aims to identify, using the Grassberger-Procaccia correlation dimension (CD) algorithm, the existence of a nonlinear deterministic and chaotic dynamic behaviour in the spatial pattern of arsenic, manganese and zinc concentration in a Russian coal waste disposal site. The analysis carried out yielded embedding dimension values ranging between 7 and 8 suggesting thus from a chaotic dynamic perspective that arsenic, manganese and zinc concentration in space is a medium dimensional problem for the regionalized scale considered in this study. This alternative nonlinear dynamics approach may complement conventional geostatistical studies and may be also used for the estimation of risk and the subsequent screening and selection of a feasible remediation scheme in wider mining and waste disposal sites. Finally, the synergistic effect of this study may be further elaborated if additional factors including among others presence of hot spots, density and depth of sampling, mineralogy of wastes and sensitivity of analytical techniques are taken into account

  19. Disposal of Hanford defense high-level, transuranic and tank wastes, Hanford Site, Richland, Washington. Draft environmental impact statement. Volume 3. Appendices M-V

    International Nuclear Information System (INIS)

    1986-03-01

    The purpose of this Environmental Impact Statement (EIS) is to provide environmental input into the selection and implementation of final disposal actions for high-level, transuranic and tank wastes located at the Hanford Site, Richland, Washington, and into the construction, operation and decommissioning of waste treatment facilities that may be required in implementing waste disposal alternatives. Specifically evaluated are a Hanford Waste Vitrification Plant, Transportable Grout Facility, and a Waste Receiving and Packaging Facility. Also an evaluation is presented to assist in determining whether any additional action should be taken in terms of long-term environmental protection for waste that was disposed of at Hanford prior to 1970 as low-level waste (before the transuranic waste category was established by the AEC) but which might fall into that category if generated today. The alternatives considered in this EIS are: (1) in-place stabilization and disposal, where waste is left in place but is isolated by protective and natural barriers; (2) geologic disposal, where most of the waste (to the extent practicable) is exhumed, treated, segregated, packaged and disposed of in a deep geologic repository; waste classified as high-level would be disposed of in a commercial repository developed pursuant to the Nuclear Waste Policy Act; transuranic waste would be disposed of in the Waste Isolation Pilot Plant near Carlsbad, New Mexico; (3) reference alternative, where some classes of waste are disposed of in geologic repositories and other classes of waste are disposed of by in-place stabilization and disposal; and (4) a ''no disposal'' action alternative (continued storage)

  20. Disposal of Hanford defense high-level, transuranic and tank wastes, Hanford Site, Richland, Washington. Draft environmental impact statement. Volume 2. Appendices A-L

    International Nuclear Information System (INIS)

    1986-03-01

    The purpose of this Environmental Impact Statement (EIS) is to provide environmental input into the selection and implementation of final disposal actions for high-level, transuranic and tank wastes located at the Hanford Site, Richland, Washington, and into the construction, operation and decommissioning of waste treatment facilities that may be required in implementing waste disposal alternatives. Specifically evaluated are a Hanford Waste Vitrification Plant, Transportable Grout Facility, and a Waste Receiving and Packaging Facility. Also an evaluation is presented to assist in determining whether any additional action should be taken in terms of long-term environmental protection for waste that was disposed of at Hanford prior to 1970 as low-level waste (before the transuranic waste category was established by the AEC) but which might fall into that category if generated today. The alternatives considered in this EIS are: (1) in-place stabilization and disposal, where waste is left in place but is isolated by protective and natural barriers; (2) geologic disposal, where most of the waste (to the extent practicable) is exhumed, treated, segregated, packaged and disposed of in a deep geologic repository; waste classified as high-level would be disposed of in a commercial repository developed pursuant to the Nuclear Waste Policy Act; transuranic waste would be disposed of in the Waste Isolation Pilot Plant near Carlsbad, New Mexico; (3) reference alternative, where some classes of waste are disposed of in geologic repositories and other classes of waste are disposed of by in-place stabilization and disposal; and (4) a ''no disposal'' action alternative (continued storage)

  1. Waste association in mass for coating formulations: a viable alternative to dispose; Associacao de residuos em formulacoes de massas para revestimentos: uma alternativa viavel ao descarte

    Energy Technology Data Exchange (ETDEWEB)

    Ferreira, E.A.C.; Soares Filho, J.E.; Souza, F.J.P.; Almeida, V.S. de; Oliveira, T.M. de, E-mail: erikcferreira@gmail.com [Universidade Federal do Rio Grande do Norte (UFRN), Natal RN (Brazil)

    2016-07-01

    The ceramic coatings industries are able to use in their formulations whose waste Eco disposal make the costly disposal, being able to reduce production costs by replacing traditional inputs for mining and industrial waste. Their raw materials are classified as plasticizers, fluxes and structural according to their physicochemical characteristics. Since waste falls within these classifications, their use in formulations becomes a viable and attractive alternative from an ecological point of view and marketing. Several studies have attested to waste incorporating viability porcelains formulations, however, is not common to find studies evaluating the addition of more than one simultaneously in formulations. It is the objective of the study, to examine whether fine waste rock and kaolin together with traditional raw materials are able to produce porcelain wet as technological properties defined by the NBR-13818. (author)

  2. Alternative comparison, analysis, and evaluation of solid waste and materials system alternatives

    International Nuclear Information System (INIS)

    Brothers, A.J.

    1995-09-01

    This paper presents a comprehensive analysis of the impact of solid waste technical options on values and objectives that are important to the public. It is written in support of the Solid Waste and Materials Systems Alternatives Study (WHC, 1995). Described are the values that were identified, the major programmatic risks, how the impacts were measured, the performance of alternatives, the methodology used for the analysis, and the implications of the results. Decision analysis was used to guide the collection and analysis of data and the logic of the evaluation. Decision analysis is a structured process for the analysis and evaluation of alternatives. It is theoretically grounded in a set of axioms that capture the basic principles of decision making (von Neuman and Morgenstern 1947). Decision analysis objectively specifies what factors are to be considered, how they are to be measured and evaluated, and heir relative importance. The result is an analysis in which the underlying rationale or logic upon which the decision is based is made explicit. This makes possible open discussion of the decision basis in which facts and values are clearly distinguished, resulting in a well- documented decision that can be clearly explained and justified. The strategy of decision analysis is to analyze the various components relevant to the decision separately and then integrate the individual judgments to arrive at an overall decision. This assures that all the relevant factors are identified and their relative importance is considered. The procedure for obtaining the individual judgments, and the decision rules, for combining them and evaluating alternatives, have both theoretical and empirical foundation in mathematics, economics, and psychology

  3. Criteria for high-level waste disposal

    International Nuclear Information System (INIS)

    Sousselier, Y.

    1981-01-01

    Disposal of radioactive wastes is storage without the intention of retrieval. But in such storage, it may be useful and in some cases necessary to have the possibility of retrieval at least for a certain period of time. In order to propose some criteria for HLW disposal, one has to examine how this basic concept is to be applied. HLW is waste separated as a raffinate in the first cycle of solvent extraction in reprocessing. Such waste contains the bulk of fission products which have long half lives, therefore the safety of a disposal site, at least after a certain period of time, must be intrinsic, i.e. not based on human intervention. There is a consensus that such a disposal is feasible in a suitable geological formation in which the integrity of the container will be reinforced by several additional barriers. Criteria for disposal can be proposed for all aspects of the question. The author discusses the aims of the safety analysis, particularly the length of time for this analysis, and the acceptable dose commitments resulting from the release of radionuclides, the number and role of each barrier, and a holistic analysis of safety external factors. (Auth.)

  4. Alternative way to dispose of high-level waste in outer space

    International Nuclear Information System (INIS)

    Takahasi, H.; Chen, X.

    1995-01-01

    We propose a new approach to dispose of Long-Lived Fission Products (LLFPs) of type II such as 99 Tc and 129 I into outer solar space by providing an escape velocity from the solar system of 42 km/sec from a parking orbit or the moon's surface using a electrostatic accelerator and neutralizing the charged ions. LLFPs disposed uniformly in outer solar space pose no hazard as do LLFPs packages in Earth orbit, and have no effects on astronomical observations. This mode of disposition requires energy in the order of 1 keV for each nucleus, which is far smaller than the propulsion energy needed for launching a LLFPs package by rocket. Further, the power required of an accelerator ejecting most of the LLFPs generated by one LWR is 2.2 kW, which is much smaller than a medium-energy proton accelerator, a few tens of MW, which would be necessary to transmute these LLFPs using spallation neutrons created by protons. copyright 1995 American Institute of Physics

  5. Radium bearing waste disposal

    International Nuclear Information System (INIS)

    Tope, W.G.; Nixon, D.A.; Smith, M.L.; Stone, T.J.; Vogel, R.A.; Schofield, W.D.

    1995-01-01

    Fernald radium bearing ore residue waste, stored within Silos 1 and 2 (K-65) and Silo 3, will be vitrified for disposal at the Nevada Test Site (NTS). A comprehensive, parametric evaluation of waste form, packaging, and transportation alternatives was completed to identify the most cost-effective approach. The impacts of waste loading, waste form, regulatory requirements, NTS waste acceptance criteria, as-low-as-reasonably-achievable principles, and material handling costs were factored into the recommended approach

  6. Future-oriented sewage sludge utilization/disposal; Zukunftsorientierte Klaerschlammverwertung/-entsorgung

    Energy Technology Data Exchange (ETDEWEB)

    Seiler, U.; Obid, G. [Fichtner GmbH und Co. KG, Stuttgart (Germany)

    1999-03-01

    Although the technical code on municipal waste (TASi) with its requirements regarding material to be deposited at landfills and its composition (annealing loss < 5 % for landfill disposal class II and < 3 % for landfill disposal class I) has been known for a long time, it is still not clear how the disposal of sewage sludge via alternative pathways can be implemented. To be economically effective, sewage sludge disposal concepts must cover the short, medium, and long term. (orig.) [Deutsch] Obwohl die Technische Anleitung Siedlungsabfall (TASi) mit den Forderungen fuer die abzulagernden Stoffe in Bezug auf deren Zusammensetzungen (Gluehverlust <5% fuer Deponieklasse II und <3% fuer Deponieklasse I) seit langem bekannt ist, fehlt fuer den Bereich Klaerschlamm die Umsetzung im Zusammenhang mit anderen moeglichen Entsorgungspfaden. Die Entsorgung soll die kurz-, mittel- und langfristigen Massnahmen beinhalten, um moeglichst oekonomisch wirksam zu werden. (orig.)

  7. DEVELOPMENT, QUALIFICATION, AND DISPOSAL OF AN ALTERNATIVE IMMOBILIZED LOW-ACTIVITY WASTE FORM AT THE HANFORD SITE

    International Nuclear Information System (INIS)

    Sams, T.L.; Edge, J.A.; Swanberg, D.J.; Robbins, R.A.

    2011-01-01

    Demonstrating that a waste form produced by a given immobilization process is chemically and physically durable as well as compliant with disposal facility acceptance criteria is critical to the success of a waste treatment program, and must be pursued in conjunction with the maturation of the waste processing technology. Testing of waste forms produced using differing scales of processing units and classes of feeds (simulants versus actual waste) is the crux of the waste form qualification process. Testing is typically focused on leachability of constituents of concern (COCs), as well as chemical and physical durability of the waste form. A principal challenge regarding testing immobilized low-activity waste (ILAW) forms is the absence of a standard test suite or set of mandatory parameters against which waste forms may be tested, compared, and qualified for acceptance in existing and proposed nuclear waste disposal sites at Hanford and across the Department of Energy (DOE) complex. A coherent and widely applicable compliance strategy to support characterization and disposal of new waste forms is essential to enhance and accelerate the remediation of DOE tank waste. This paper provides a background summary of important entities, regulations, and considerations for nuclear waste form qualification and disposal. Against this backdrop, this paper describes a strategy for meeting and demonstrating compliance with disposal requirements emphasizing the River Protection Project (RPP) Integrated Disposal Facility (IDF) at the Hanford Site and the fluidized bed steam reforming (FBSR) mineralized low-activity waste (LAW) product stream.

  8. Analysis for the high-level waste disposal cost object

    International Nuclear Information System (INIS)

    Kim, S. K.; Lee, J. R.; Choi, J. W.; Han, P. S.

    2003-01-01

    The purpose of this study is to analyse the ratio of cost object in terms of the disposal cost estimation. According to the result, the ratio of operating cost is the most significant object in total cost. There are a lot of differences between the disposal costs and product costs in view of their constituents. While the product costs may be classified by the direct materials cost, direct manufacturing labor cost, and factory overhead the disposal cost factors should be constituted by the technical factors and the non-technical factors

  9. Methodology for the technical evaluation of disposal systems for Greater-Than-Class C low-level radioactive waste

    International Nuclear Information System (INIS)

    Lamar, D.A.; Raymond, J.R.

    1990-07-01

    This paper presents the methodology that will be used for the evaluation of alternative disposal concepts for Greater-Than-Class C low-level radioactive waste. The primary focus will be on the technical evaluation of various disposal concepts leading toward the identification of technically feasible disposal systems

  10. Assessing the disposal of wastes containing NORM in nonhazardous waste landfills

    International Nuclear Information System (INIS)

    Smith, K. P.; Blunt, D. L.; Williams, G. P.; Arnish, J. J.; Pfingston, M. R.; Herbert, J.

    1999-01-01

    In the past few years, many states have established specific regulations for the management of petroleum industry wastes containing naturally occurring radioactive material (NORM) above specified thresholds. These regulations have limited the number of disposal options available for NORM-containing wastes, thereby increasing the related waste management costs. In view of the increasing economic burden associated with NORM management, industry and regulators are interested in identifying cost-effective disposal alternatives that still provide adequate protection of human health and the environment. One such alternative being considered is the disposal of NORM-containing wastes in landfills permitted to accept only nonhazardous wastes. The disposal of petroleum industry wastes containing radium-226 and lead-210 above regulated levels in nonhazardous landfills was modeled to evaluate the potential radiological doses and associated health risks to workers and the general public. A variety of scenarios were considered to evaluate the effects associated with the operational phase (i.e., during landfill operations) and future use of the landfill property. Doses were calculated for the maximally exposed receptor for each scenario. This paper presents the results of that study and some conclusions and recommendations drawn from it

  11. Study of an optimization approach for a disposal tunnel layout, taking into account the geological environment with spatially heterogeneous characteristics

    International Nuclear Information System (INIS)

    Suyama, Yasuhiro; Toida, Masaru; Yanagizawa, Koichi

    2009-01-01

    The geological environment has spatially heterogeneous characteristics with varied host rock types, fractures and so on. In this case the generic disposal tunnel layout, which has been designed by JNC, is not the most suitable for HLW disposal in Japan. The existence of spatially heterogeneous characteristics means that in the repository region there exist sub-regions that are more favourable from the perspective of long-term safety and ones that are less favourable. In order that the spatially heterogeneous environment itself may be utilized most effectively as a natural barrier system, an alternative design of disposal tunnel layout is required. Focusing on the geological environment with spatially heterogeneous characteristics, the authors have developed an alternative design of disposal tunnel layout. The alternative design adopts an optimization approach using a variable disposal tunnel layout. The optimization approach minimizes the number of locations where major water-conducting fractures are intersected, and maximizes the number of emplacement locations for waste packages. This paper will outline the variable disposal tunnel layout and its applicability.

  12. Environmental information document: New hazardous and mixed waste storage/disposal facilities at the Savannah River Plant

    International Nuclear Information System (INIS)

    Cook, J.R.; Grant, M.W.; Towler, O.O.

    1987-04-01

    Site selection, alternative facilities and alternative operations are described for new hazardous and mixed waste storage/disposal facilities at the Savannah River Plant. Performance assessments and cost estimates for the alternatives are presented

  13. Alternatives to shallow land burial

    International Nuclear Information System (INIS)

    Kuck, P.H.; Wacks, M.E.

    1980-01-01

    The paper discusses disposal alternatives that suggest there is a great diversity of man-made and natural spaces that should be considered as alternative sites for LLW disposal. Dry caverns outside of karst regions with integrated subsurface drainage might be given further consideration. The excavation of new space in tectonically and chemically stable rock formations also shows considerable promise. The principal problems in using either existing or new space involve hydrology, rock mechanics, chemical stability of the wall-rock minerals, and socio-political interactions. The chemical, physical and radiological properties of the wastes will also enter into the evaluation. All seven of these aspects will have to be examined in detail before a solution to the problem of minimizing radionuclide transport into the biosphere can be outlined

  14. DSEM, Radioactive Waste Disposal Site Economic Model

    International Nuclear Information System (INIS)

    Smith, P.R.

    2005-01-01

    1 - Description of program or function: The Disposal Site Economic Model calculates the average generator price, or average price per cubic foot charged by a disposal facility to a waste generator, one measure of comparing the economic attractiveness of different waste disposal site and disposal technology combinations. The generator price is calculated to recover all costs necessary to develop, construct, operate, close, and care for a site through the end of the institutional care period and to provide the necessary financial returns to the site developer and lender (when used). Six alternative disposal technologies, based on either private or public financing, can be considered - shallow land disposal, intermediate depth disposal, above or below ground vaults, modular concrete canister disposal, and earth mounded concrete bunkers - based on either private or public development. 2 - Method of solution: The economic models incorporate default cost data from the Conceptual Design Report (DOE/LLW-60T, June 1987), a study by Rodgers Associates Engineering Corporation. Because all costs are in constant 1986 dollars, the figures must be modified to account for inflation. Interest during construction is either capitalized for the private developer or rolled into the loan for the public developer. All capital costs during construction are depreciated over the operation life of the site using straight-line depreciation for the private sector. 3 - Restrictions on the complexity of the problem: Maxima of - 100 years post-operating period, 30 years operating period, 15 years pre-operating period. The model should be used with caution outside the range of 1.8 to 10.5 million cubic feet of total volume. Depreciation is not recognized with public development

  15. Conceptual Design Report for the Remote-Handled Low-Level Waste Disposal Project

    Energy Technology Data Exchange (ETDEWEB)

    David Duncan

    2011-05-01

    This conceptual design report addresses development of replacement remote-handled low-level waste disposal capability for the Idaho National Laboratory. Current disposal capability at the Radioactive Waste Management Complex is planned until the facility is full or until it must be closed in preparation for final remediation (approximately at the end of Fiscal Year 2017). This conceptual design report includes key project assumptions; design options considered in development of the proposed onsite disposal facility (the highest ranked alternative for providing continued uninterrupted remote-handled low level waste disposal capability); process and facility descriptions; safety and environmental requirements that would apply to the proposed facility; and the proposed cost and schedule for funding, design, construction, and operation of the proposed onsite disposal facility.

  16. Conceptual Design Report for the Remote-Handled Low-Level Waste Disposal Project

    Energy Technology Data Exchange (ETDEWEB)

    Lisa Harvego; David Duncan; Joan Connolly; Margaret Hinman; Charles Marcinkiewicz; Gary Mecham

    2011-03-01

    This conceptual design report addresses development of replacement remote-handled low-level waste disposal capability for the Idaho National Laboratory. Current disposal capability at the Radioactive Waste Management Complex is planned until the facility is full or until it must be closed in preparation for final remediation (approximately at the end of Fiscal Year 2017). This conceptual design report includes key project assumptions; design options considered in development of the proposed onsite disposal facility (the highest ranked alternative for providing continued uninterrupted remote-handled low level waste disposal capability); process and facility descriptions; safety and environmental requirements that would apply to the proposed facility; and the proposed cost and schedule for funding, design, construction, and operation of the proposed onsite disposal facility.

  17. Eco-efficiency analysis of techniques for disposal of urban solid waste; Analise de ecoeficiencia de tecnicas para tratamento e disposicao de residuos solidos urbanos

    Energy Technology Data Exchange (ETDEWEB)

    Dmitrijevas, Cibele

    2010-07-01

    Municipal solid waste is one of the major problems of modern society. In this sense it is necessary to discuss solutions to the fate of waste generated daily, increasingly in larger amounts, being imperative to advance the search for alternatives, not only in search of new technologies and solutions, as well as the improvement of methodologies currently employed to solve this relevant issue, especially in large urban centers. This paper presents the results of a comparative economic-environmental assessment performed by a method developed by BASF, two potential technologies: landfill and incineration with energy recovery. To facilitate the work, the information used were both real data - landfill and incinerator - Essencis Solucoes Ambientais S.A., (assuming some assumptions) and the use of secondary data, using the study of Arena et al., 2003. This ecoefficiency analysis tool covers the methodology of Life Cycle Assessment (LCA), which is a technique to evaluate the inputs and outputs of matter and energy and the potential environmental impacts associated with all stages of resource extraction and their transformations , and the use and final disposal of the product. The data in the environmental assessment are presented according to major categories, using a weighting method developed by BASF and understand the consumption of natural resources, consumption of energy resources, air emissions, water and soil, potential for human toxicity, accidents work, occupational diseases and land use. Economic evaluation in this work took into account the costs involved in operation and maintenance of disposal techniques or treatment of waste. The comparative study found the treatment or disposal of 7.324109 billion kilograms of waste. As a result, the array of eco-efficiency indicates that the incinerator is the alternative that stands out, considering the environmental and economic profile, within the assumptions made in this study and taking into account which is a

  18. Composite analysis for low-level waste disposal in the 200 area plateau of the Hanford Site

    International Nuclear Information System (INIS)

    Kincaid, C.T.; Bergeron, M.P.; Cole, C.R.

    1998-03-01

    This report presents the first iteration of the Composite Analysis for Low-Level Waste Disposal in the 200 Area Plateau of the Hanford Site (Composite Analysis) prepared in response to the U.S. Department of Energy Implementation Plan for the Defense Nuclear Facility Safety Board Recommendation 94-2. The Composite Analysis is a companion document to published analyses of four active or planned low-level waste disposal actions: the solid waste burial grounds in the 200 West Area, the solid waste burial grounds in the 200 East Area, the Environmental Restoration Disposal Facility, and the disposal facilities for immobilized low-activity waste. A single Composite Analysis was prepared for the Hanford Site considering only sources on the 200 Area Plateau. The performance objectives prescribed in U.S. Department of Energy guidance for the Composite Analysis were 100 mrem in a year and examination of a lower dose (30 mrem in a year) to ensure the open-quotes as low as reasonably achievableclose quotes concept is followed. The 100 mrem in a year limit was the maximum allowable all-pathways dose for 1000 years following Hanford Site closure, which is assumed to occur in 2050. These performance objectives apply to an accessible environment defined as the area between a buffer zone surrounding an exclusive waste management area on the 200 Area Plateau, and the Columbia River. Estimating doses to hypothetical future members of the public for the Composite Analysis was a multistep process involving the estimation or simulation of inventories; waste release to the environment; migration through the vadose zone, groundwater, and atmospheric pathways; and exposure and dose. Doses were estimated for scenarios based on agriculture, residential, industrial, and recreational land use. The radionuclides included in the vadose zone and groundwater pathway analyses of future releases were carbon-14, chlorine-36, selenium-79, technetium-99, iodine-129, and uranium isotopes

  19. Composite analysis for low-level waste disposal in the 200 area plateau of the Hanford Site

    Energy Technology Data Exchange (ETDEWEB)

    Kincaid, C.T.; Bergeron, M.P.; Cole, C.R. [and others

    1998-03-01

    This report presents the first iteration of the Composite Analysis for Low-Level Waste Disposal in the 200 Area Plateau of the Hanford Site (Composite Analysis) prepared in response to the U.S. Department of Energy Implementation Plan for the Defense Nuclear Facility Safety Board Recommendation 94-2. The Composite Analysis is a companion document to published analyses of four active or planned low-level waste disposal actions: the solid waste burial grounds in the 200 West Area, the solid waste burial grounds in the 200 East Area, the Environmental Restoration Disposal Facility, and the disposal facilities for immobilized low-activity waste. A single Composite Analysis was prepared for the Hanford Site considering only sources on the 200 Area Plateau. The performance objectives prescribed in U.S. Department of Energy guidance for the Composite Analysis were 100 mrem in a year and examination of a lower dose (30 mrem in a year) to ensure the {open_quotes}as low as reasonably achievable{close_quotes} concept is followed. The 100 mrem in a year limit was the maximum allowable all-pathways dose for 1000 years following Hanford Site closure, which is assumed to occur in 2050. These performance objectives apply to an accessible environment defined as the area between a buffer zone surrounding an exclusive waste management area on the 200 Area Plateau, and the Columbia River. Estimating doses to hypothetical future members of the public for the Composite Analysis was a multistep process involving the estimation or simulation of inventories; waste release to the environment; migration through the vadose zone, groundwater, and atmospheric pathways; and exposure and dose. Doses were estimated for scenarios based on agriculture, residential, industrial, and recreational land use. The radionuclides included in the vadose zone and groundwater pathway analyses of future releases were carbon-14, chlorine-36, selenium-79, technetium-99, iodine-129, and uranium isotopes.

  20. Summary of Conceptual Models and Data Needs to Support the INL Remote-Handled Low-Level Waste Disposal Facility Performance Assessment and Composite Analysis

    International Nuclear Information System (INIS)

    Sondrup, A. Jeff; Schafter, Annette L.; Rood, Arthur S.

    2010-01-01

    An overview of the technical approach and data required to support development of the performance assessment, and composite analysis are presented for the remote handled low-level waste disposal facility on-site alternative being considered at Idaho National Laboratory. Previous analyses and available data that meet requirements are identified and discussed. Outstanding data and analysis needs are also identified and summarized. The on-site disposal facility is being evaluated in anticipation of the closure of the Radioactive Waste Management Complex at the INL. An assessment of facility performance and of the composite performance are required to meet the Department of Energy's Low-Level Waste requirements (DOE Order 435.1, 2001) which stipulate that operation and closure of the disposal facility will be managed in a manner that is protective of worker and public health and safety, and the environment. The corresponding established procedures to ensure these protections are contained in DOE Manual 435.1-1, Radioactive Waste Management Manual (DOE M 435.1-1 2001). Requirements include assessment of (1) all-exposure pathways, (2) air pathway, (3) radon, and (4) groundwater pathway doses. Doses are computed from radionuclide concentrations in the environment. The performance assessment and composite analysis are being prepared to assess compliance with performance objectives and to establish limits on concentrations and inventories of radionuclides at the facility and to support specification of design, construction, operation and closure requirements. Technical objectives of the PA and CA are primarily accomplished through the development of an establish inventory, and through the use of predictive environmental transport models implementing an overarching conceptual framework. This document reviews the conceptual model, inherent assumptions, and data required to implement the conceptual model in a numerical framework. Available site-specific data and data sources

  1. The State of the Art of the Borehole Disposal Concept for High Level Radioactive Waste

    International Nuclear Information System (INIS)

    Ji, Sung Hoon; Koh, Yong Kwon; Choi, Jong Won

    2012-01-01

    As an alternative of the high-level radioactive waste disposal in the subsurface repository, a deep borehole disposal is reviewed by several nuclear advanced countries. In this study, the state of the art on the borehole disposal researches was reviewed, and the possibility of borehole disposal in Korean peninsula was discussed. In the deep borehole disposal concept radioactive waste is disposed at the section of 3 - 5 km depth in a deep borehole, and it has known that it has advantages in performance and cost due to the layered structure of deep groundwater and small surface disposal facility. The results show that it is necessary to acquisite data on deep geologic conditions of Korean peninsula, and to research the engineering barrier system, numerical modeling tools and disposal techniques for deep borehole disposal.

  2. SENSITIVITY ANALYSIS FOR SALTSTONE DISPOSAL UNIT COLUMN DEGRADATION ANALYSES

    Energy Technology Data Exchange (ETDEWEB)

    Flach, G.

    2014-10-28

    PORFLOW related analyses supporting a Sensitivity Analysis for Saltstone Disposal Unit (SDU) column degradation were performed. Previous analyses, Flach and Taylor 2014, used a model in which the SDU columns degraded in a piecewise manner from the top and bottom simultaneously. The current analyses employs a model in which all pieces of the column degrade at the same time. Information was extracted from the analyses which may be useful in determining the distribution of Tc-99 in the various SDUs throughout time and in determining flow balances for the SDUs.

  3. Radionuclide migration pathways analysis for the Oak Ridge Central Waste Disposal Facility on the West Chestnut Ridge site

    International Nuclear Information System (INIS)

    Pin, F.G.; Witherspoon, J.P.; Lee, D.W.; Cannon, J.B.; Ketelle, R.H.

    1984-10-01

    A dose-to-man pathways analysis is performed for disposal of low-level radioactive waste at the Central Waste Disposal Facility on the West Chestnut Ridge Site. Both shallow land burial (trench) and aboveground (tumulus) disposal methods are considered. The waste volumes, characteristics, and radionuclide concentrations are those of waste streams anticipated from the Oak Ridge National Laboratory, the Y-12 Plant, and the Oak Ridge Gaseous Diffusion Plant. The site capacity for the waste streams is determined on the basis of the pathways analysis. The exposure pathways examined include (1) migration and transport of leachate from the waste disposal units to the Clinch River (via the groundwater medium for trench disposal and Ish Creek for tumulus disposal) and (2) those potentially associated with inadvertent intrusion following a 100-year period of institutional control: an individual resides on the site, inhales suspended particles of contaminated dust, ingests vegetables grown on the plot, consumes contaminated water from either an on-site well or from a nearby surface stream, and receives direct exposure from the contaminated soil. It is found that either disposal method would provide effective containment and isolation for the anticipated waste inventory. However, the proposed trench disposal method would provide more effective containment than tumuli because of sorption of some radionuclides in the soil. Persons outside the site boundary would receive radiation doses well below regulatory limits if they were to ingest water from the Clinch River. An inadvertent intruder could receive doses that approach regulatory limits; however, the likelihood of such intrusions and subsequent exposures is remote. 33 references, 31 figures, 28 tables

  4. Rethinking high-level radioactive waste disposal: making the safety case

    International Nuclear Information System (INIS)

    Parker, F.L.

    1991-01-01

    There is worldwide consensus that geological disposal is best for disposing of high-level radioactive waste; nevertheless, the U.S. program is unlikely to succeed. The program is hampered by its high degree of inflexibility with respect to both schedule and technical specifications that assume the properties and future behavior of a geological repository can be determined and specified with a very high degree of certainty. Geological models, and scientific knowledge generally, have been inappropriately applied. Geophysical analysis can and should have a key role in the assessment of long-term repository isolation; however, geophysial models are being asked to predict the detailed structure and behavior of sites over thousands of years. This is scientifically unsound and will lead to bad engineering practice. The United States has written detailed regulations for repository siting and construction before all of the data are in and is thus bound by requirements that may be impossible to meet. An alternative approach emphasizing flexibility can succeed. It will require time to assess performance, a willingness to respond to problems as they arise, remediation if necessary, and revision of the design and regulations if they are found to impede progress toward the health goal already defined as safe disposal. 6 refs

  5. Safety analysis of disposal of decommissioning waste from the Olkiluoto nuclear power plant - PURKU-93

    International Nuclear Information System (INIS)

    Vieno, T.; Meszaros, F.; Nordman, H.; Taivassalo, V.

    1993-12-01

    Decommissioning waste from the Olkiluoto nuclear power plant will be disposed of at the depth between 60 and 100 meters in the bedrock at the power plant site. The existing VLJ repository for low and medium level operating waste will be extended with three new silos for the decommissioning waste of the TVO I and II reactors and the spent fuel interim store at the Olkiluoto site. Besides dismantling waste also used fuel boxes, control rods and other activated metal components accumulated during the operation of the reactors will be disposed of in the repository. The safety analysis is based on the detailed decommissioning plan of the Olkiluoto power plants and the comprehensive safety analysis carried out for the Final Safety Analysis Report of the VLJ repository. (58 refs., 31 figs., 38 tabs.)

  6. Advanced Post-Irradiation Examination Capabilities Alternatives Analysis Report

    Energy Technology Data Exchange (ETDEWEB)

    Jeff Bryan; Bill Landman; Porter Hill

    2012-12-01

    An alternatives analysis was performed for the Advanced Post-Irradiation Capabilities (APIEC) project in accordance with the U.S. Department of Energy (DOE) Order DOE O 413.3B, “Program and Project Management for the Acquisition of Capital Assets”. The Alternatives Analysis considered six major alternatives: ? No Action ? Modify Existing DOE Facilities – capabilities distributed among multiple locations ? Modify Existing DOE Facilities – capabilities consolidated at a few locations ? Construct New Facility ? Commercial Partnership ? International Partnerships Based on the alternatives analysis documented herein, it is recommended to DOE that the advanced post-irradiation examination capabilities be provided by a new facility constructed at the Materials and Fuels Complex at the Idaho National Laboratory.

  7. Development and improvement of safety analysis code for geological disposal

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2013-08-15

    In order to confirm the long-term safety concerning geological disposal, probabilistic safety assessment code and other analysis codes, which can evaluate possibility of each event and influence on engineered barrier and natural barrier by the event, were introduced. We confirmed basic functions of those codes and studied the relation between those functions and FEP/PID which should be taken into consideration in safety assessment. We are planning to develop 'Nuclide Migration Assessment System' for the purpose of realizing improvement in efficiency of assessment work, human error prevention for analysis, and quality assurance of the analysis environment and analysis work for safety assessment by using it. As the first step, we defined the system requirements and decided the system composition and functions which should be mounted in them based on those requirements. (author)

  8. Treatment alternatives for non-fuel-bearing hardware

    International Nuclear Information System (INIS)

    Ross, W.A.; Clark, L.L.; Oma, K.H.

    1987-01-01

    This evaluation compared four alternatives for the treatment or processing of non-fuel bearing hardware (NFBH) to reduce its volume and prepare it for disposal. These treatment alternatives are: shredding; shredding and low pressure compaction; shredding and supercompaction; and melting. These alternatives are compared on the basis of system costs, waste form characteristics, and process considerations. The study recommends that melting and supercompaction alternatives be further considered and that additional testing be conducted for these two alternatives

  9. Regional waste treatment facilities with underground monolith disposal for all low-heat-generating nuclear wastes

    International Nuclear Information System (INIS)

    Forsberg, C.W.

    1982-01-01

    An alternative system for treatment and disposal of all ''low-heat-generating'' nuclear wastes from all sources is proposed. The system, Regional Waste Treatment Facilities with Underground Monolith Disposal (RWTF/UMD), integrates waste treatment and disposal operations into single facilities at regional sites. Untreated and/or pretreated wastes are transported from generation sites such as reactors, hospitals, and industries to regional facilities in bulk containers. Liquid wastes are also transported in bulk after being gelled for transport. The untreated and pretreated wastes are processed by incineration, crushing, and other processes at the RWTF. The processed wastes are mixed with cement. The wet concrete mixture is poured into large low-cost, manmade caverns or deep trenches. Monolith dimensions are from 15 to 25 m wide, and 20 to 60 m high and as long as required. This alternative waste system may provide higher safety margins in waste disposal at lower costs

  10. Unreviewed Disposal Question Evaluation: Waste Disposal in Engineered Trenches 3 and 4

    Energy Technology Data Exchange (ETDEWEB)

    Butcher, T. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL); Hamm, L. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL); Flach, G. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL)

    2017-12-12

    Revision 0 of this UDQE addressed the proposal to place Engineered Trench #3 (ET#3) in the footprint designated for Slit Trench #12 (ST#12) and operate using ST#12 disposal limits. Similarly, Revision 1 evaluates whether ET#4 can be located in and operated to Slit Trench #13 (ST#13) disposal limits. Both evaluations conclude that the proposed operations result in an acceptably small risk of exceeding a SOF of 1.0 and approve these actions from a performance assessment (PA) perspective. Because ET#3 will be placed in the location previously designated for ST#12, Solid Waste Management (SWM) requested that the Savannah River National Laboratory (SRNL) determine if the ST#12 limits could be employed as surrogate disposal limits for ET#3 operations. SRNL documented in this Unreviewed Disposal Question Evaluation (UDQE) that the use of ST#12 limits as surrogates for the new ET#3 disposal unit will provide reasonable assurance that Department of Energy (DOE) 435.1 performance objectives and measures (USDOE, 1999) will be protected. Therefore, new ET#3 inventory limits as determined by a Special Analysis (SA) are not required.

  11. Industry petition for rulemaking on the disposal of below-regulatory-concern wastes

    International Nuclear Information System (INIS)

    Tipton, T.E.

    1989-01-01

    The Nuclear Management and Resources Council, Inc., in conjunction with the Edison Electric Institute, plans to submit a petition for rulemaking entitled Petition for Rulemaking Regarding Disposal of Below Regulatory Concern Wastes from commercial Nuclear Power Plants to the U.S. Nuclear Regulatory Commission (NRC). This petition for rulemaking, which is being filed pursuant to 10CFR2.802 and 10CFR2, Appendix B of the Code of Federal Regulations, requests the NRC to promulgate a rule authorizing the treatment and disposal of low-level radioactive wastes (LLW) determined to be below regulatory concern (BRC) in other than licensed LLW disposal facilities. The proposed rule will apply only to LLW generated at commercial nuclear power plants. The petition is based on detailed scientific and technical data derived through an extensive research program conducted by the Electric Power Research Institute, Inc. It addresses the 14 decision criteria that the NRC will employ in judging whether to grant the petition. The petition also provides an environmental assessment and finding of no significant impact and regulatory analysis. The purpose of the environmental assessment is to discuss alternatives, consequences, and impacts analyzed to support the recommendation of the proposed rule. The regulatory analysis addresses the need for and consequences of the proposed regulatory action as it relates to the protection of public health and safety

  12. Advances in Geologic Disposal System Modeling and Shale Reference Cases

    Energy Technology Data Exchange (ETDEWEB)

    Mariner, Paul E. [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Stein, Emily R. [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Frederick, Jennifer M. [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Sevougian, S. David [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Hammond, Glenn Edward [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States)

    2017-09-22

    The Spent Fuel and Waste Science and Technology (SFWST) Campaign of the U.S. Department of Energy (DOE) Office of Nuclear Energy (NE), Office of Fuel Cycle Technology (OFCT) is conducting research and development (R&D) on geologic disposal of spent nuclear fuel (SNF) and high level nuclear waste (HLW). Two high priorities for SFWST disposal R&D are design concept development and disposal system modeling (DOE 2011, Table 6). These priorities are directly addressed in the SFWST Generic Disposal Systems Analysis (GDSA) work package, which is charged with developing a disposal system modeling and analysis capability for evaluating disposal system performance for nuclear waste in geologic media (e.g., salt, granite, shale, and deep borehole disposal).

  13. Radioactive waste disposal: an international law perspective

    International Nuclear Information System (INIS)

    Barrie, G.N.

    1989-01-01

    The question of radioactive waste disposal is the most intractable technical and political problem facing nuclear industry. Environmentalists world-wide demand a nuclear waste policy that must be ecologically acceptable internationally. Radioactive wastes and oil pollution were the first two types of marine pollution to receive international attention and various marine pollution controls were established. Ocean disposal was co-ordinated by the Nuclear Energy Agency and the Organization of Economic Co-operation and Development in 1967. The first treaty was the 1958 Convention on the High Seas (High Seas Convention). In response to its call for national co-operation the International Atomic Energy Agency (IAEA) established its Brynielson panel. The IAEA first issued guidelines on sea dumping in 1961. The London Dumping Convention, written in 1972, is the only global agreement concerned solely with the disposal of wastes in the marine environment by dumping. None of the global agreements make specific reference to sea-bed disposal of high-level radioactive wastes. Negotiations began at the Third UN Conference on the Law of the Sea (UNCLOS III) for the codification of a comprehensive treaty concerned with the protection, conservation, sustainable use and development of the marine environment. Burial in deep geological formations is a method of HLW disposal which decreases the chances of accidental intrusion by mankind and has little likelihood of malicious intrusion. National waste management programmes of different countries differ but there is agreement on the acceptable technical solutions to issues of waste management. The final disposition of HLW - storage or disposal - has not been decisively determined, but there is growing consensus that geological land-based disposal is the most viable alternative. Expanded international technical co-operation could well reduce the time needed to develop effective waste disposal mechanisms

  14. The Ypresian clays as alternative host rock for radioactive waste disposal in Belgium. A transferability study

    International Nuclear Information System (INIS)

    Van Baelen, Herve; Wouters, Laurent; Brassinnes, Stephane; Van Geet, Maarten; Vandenberghe, Noel

    2012-01-01

    adaptations to the current design might be necessary due to the dissimilarities with Boom Clay. From our analysis of the available data, it is remarkable that for a number of parameters, the Ypresian clays appear to be less homogeneous than Boom Clay. Therefore special research efforts will be needed to get a hold on this spatial variability. Additionally, there are indications that the precision and accuracy of measurements are low for some of the parameters, which might explain a part of the heterogeneity observed. This seems to be the case for the pore-water chemistry, which will, given the impact it might have on corrosion, the durability of cementitious phases and the retention mechanisms within the host rock, be one of the major issues in future research and one of the reasons to adapt the design. Another important issue to be studied specifically for the Ypresian clays will be its mechanical behaviour at the conditions prevailing at excavation, exploitation and after closure of the disposal system. This might again, in the light of feasibility as well as safety issues, have an impact on the design. Apart from these major research questions arising from dissimilarities between both potential host rocks, a number of research questions are host-rock independent or can, at this stage of research, be treated as similar or followed-up by small-scale studies, because of comparable host rock properties. On the basis of the current knowledge it is concluded that the Ypresian clays remain a valuable alternative to Boom Clay as potential host rock for the geological disposal of high-level and/or long-lived radioactive waste

  15. Disposal of chemical agents and munitions stored at Pine Bluff Arsenal, Pine Bluff, Arkansas. Final phase 1, Environmental report

    Energy Technology Data Exchange (ETDEWEB)

    Ensminger, J.T.; Hillsman, E.L.; Johnson, R.D.; Morrisey, J.A.; Staub, W.P.; Boston, C.R.; Hunsaker, D.B.; Leibsch, E.; Rickert, L.W.; Tolbert, V.R.; Zimmerman, G.P.

    1991-09-01

    The Pine Bluff Arsenal (PBA) near Pine Bluff, Arkansas, is one of eight continental United States (CONUS) Army installations where lethal unitary chemical agents and munitions are stored and where destruction of agents and munitions is proposed under the Chemical Stockpile Disposal Program (CSDP). The chemical agent inventory at PBA consists of approximately 12%, by weight, of the total US stockpile. The destruction of the stockpile is necessary to eliminate the risk to the public from continued storage and to dispose of obsolete and leaking munitions. In 1988 the US Army issued a Final Programmatic Environmental Impact Statement (FPEIS) for the CSDP that identified on-site disposal of agents and munitions as the environmentally preferred alternative (i.e., the alternative with the least potential to cause significant adverse impacts). The purpose of this report is to examine the proposed implementation of on-site disposal at PBA in light of more recent and more detailed data than those on which the FPEIS is based. New population data were used to compute fatalities using the same computation methods and values for all other parameters as in the FPEIS. Results indicate that all alternatives are indistinguishable when the potential health impacts to the PBA community are considered. However, risks from on-site disposal are in all cases equal to or less than risks from other alternatives. Furthermore, no unique resources with the potential to prevent or delay implementation of on-site disposal at PBA have been identified.

  16. Concept development for HLW disposal research tunnel

    International Nuclear Information System (INIS)

    Queon, S. K.; Kim, K. S.; Park, J. H.; Jeo, W. J.; Han, P. S.

    2003-01-01

    In order to dispose high-level radioactive waste in a geological formation, it is necessary to assess the safety of a disposal concept by excavating a research tunnel in the same geological formation as the host rock mass. The design concept of a research tunnel depends on the actual disposal concept, repository geometry, experiments to be carried at the tunnel, and geological conditions. In this study, analysis of the characteristics of the disposal research tunnel, which is planned to be constructed at KAERI site, calculation of the influence of basting impact on neighbor facilities, and computer simuation for mechanical stability analysis using a three-dimensional code, FLAC3D, had been carried out to develop the design concept of the research tunnel

  17. Assessment and analysis of industrial liquid waste and sludge disposal at unlined landfill sites in arid climate

    International Nuclear Information System (INIS)

    Al Yaqout, Anwar F.

    2003-01-01

    Municipal solid waste disposal sites in arid countries such as Kuwait receive various types of waste materials like sewage sludge, chemical waste and other debris. Large amounts of leachate are expected to be generated due to the improper disposal of industrial wastewater, sewage sludge and chemical wastes with municipal solid waste at landfill sites even though the rainwater is scarce. Almost 95% of all solid waste generated in Kuwait during the last 10 years was dumped in five unlined landfills. The sites accepting liquid waste consist of old sand quarries that do not follow any specific engineering guidelines. With the current practice, contamination of the ground water table is possible due to the close location of the water table beneath the bottom of the waste disposal sites. This study determined the percentage of industrial liquid waste and sludge of the total waste dumped at the landfill sites, analyzed the chemical characteristics of liquid waste stream and contaminated water at disposal sites, and finally evaluated the possible risk posed by the continuous dumping of such wastes at the unlined landfills. Statistical analysis has been performed on the disposal and characterization of industrial wastewater and sludge at five active landfill sites. The chemical analysis shows that all the industrial wastes and sludge have high concentrations of COD, suspended solids, and heavy metals. Results show that from 1993 to 2000, 5.14±1.13 million t of total wastes were disposed per year in all active landfill sites in Kuwait. The share of industrial liquid and sludge waste was 1.85±0.19 million t representing 37.22±6.85% of total waste disposed in all landfill sites. Such wastes contribute to landfill leachate which pollutes groundwater and may enter the food chain causing adverse health effects. Lined evaporation ponds are suggested as an economical and safe solution for industrial wastewater and sludge disposal in the arid climate of Kuwait

  18. Toward a risk assessment of the spent fuel and high-level nuclear waste disposal system. Risk assessment requirements, literature review, methods evaluation: an interim report

    Energy Technology Data Exchange (ETDEWEB)

    Hamilton, L.D.; Hill, D.; Rowe, M.D.; Stern, E.

    1986-04-01

    This report provides background information for a risk assessment of the disposal system for spent nuclear fuel and high-level radioactive waste (HLW). It contains a literature review, a survey of the statutory requirements for risk assessment, and a preliminary evaluation of methods. The literature review outlines the state of knowledge of risk assessment and accident consequence analysis in the nuclear fuel cycle and its applicability to spent fuel and HLW disposal. The survey of statutory requirements determines the extent to which risk assessment may be needed in development of the waste-disposal system. The evaluation of methods reviews and evaluates merits and applicabilities of alternative methods for assessing risks and relates them to the problems of spent fuel and HLW disposal. 99 refs.

  19. Toward a risk assessment of the spent fuel and high-level nuclear waste disposal system. Risk assessment requirements, literature review, methods evaluation: an interim report

    International Nuclear Information System (INIS)

    Hamilton, L.D.; Hill, D.; Rowe, M.D.; Stern, E.

    1986-04-01

    This report provides background information for a risk assessment of the disposal system for spent nuclear fuel and high-level radioactive waste (HLW). It contains a literature review, a survey of the statutory requirements for risk assessment, and a preliminary evaluation of methods. The literature review outlines the state of knowledge of risk assessment and accident consequence analysis in the nuclear fuel cycle and its applicability to spent fuel and HLW disposal. The survey of statutory requirements determines the extent to which risk assessment may be needed in development of the waste-disposal system. The evaluation of methods reviews and evaluates merits and applicabilities of alternative methods for assessing risks and relates them to the problems of spent fuel and HLW disposal. 99 refs

  20. The effects of transuranic separation on waste disposal

    International Nuclear Information System (INIS)

    1991-04-01

    Rogers and Associates Engineering has analyzed waste streams from fuel cycles involving actinide partitioning and transmutation to determine appropriate disposal facilities for the waste and the cost of disposal. The focus of the study is the economic impact of actinide partitioning and transmutation on waste disposal, although there is a qualitative discussion of the impacts of actinide burning on disposal risk. This effort is part of a multi-contractor task being coordinated by the Electric Power Research Institute to address the technical feasibility and economic impact of transuranic burning. Waste streams were defined by General Electric Corporation for eight alternative processing cases -- involving aqueous and pyrochemical processing of spent fuel from light water reactors and liquid metal reactors and for low-actinide-recovery and high-actinide-recovery technologies. Disposal options are determined for three possible futures: one involving the present socio-political-licensing environment and using cost estimates for existing or planned facilities, an optimistic future with lower siting and licensing costs, and a pessimistic future with high siting and licensing costs and some extraordinary measures to assure waste isolation. The optimistic future allows the disposal of certain types of waste in a facility that provides a degree of waste isolation that is intermediate between a repository and a low-level-waste facility. 30 refs., 18 figs., 45 tabs

  1. International Collaboration Activities in Different Geologic Disposal Environments

    International Nuclear Information System (INIS)

    Birkholzer, Jens

    2015-01-01

    This report describes the current status of international collaboration regarding geologic disposal research in the Used Fuel Disposition (UFD) Campaign. Since 2012, in an effort coordinated by Lawrence Berkeley National Laboratory, UFD has advanced active collaboration with several international geologic disposal programs in Europe and Asia. Such collaboration allows the UFD Campaign to benefit from a deep knowledge base with regards to alternative repository environments developed over decades, and to utilize international investments in research facilities (such as underground research laboratories), saving millions of R&D dollars that have been and are being provided by other countries. To date, UFD's International Disposal R&D Program has established formal collaboration agreements with five international initiatives and several international partners, and national lab scientists associated with UFD have conducted specific collaborative R&D activities that align well with its R&D priorities.

  2. International Collaboration Activities in Different Geologic Disposal Environments

    Energy Technology Data Exchange (ETDEWEB)

    Birkholzer, Jens [Lawrence Berkeley National Lab. (LBNL), Berkeley, CA (United States)

    2015-09-01

    This report describes the current status of international collaboration regarding geologic disposal research in the Used Fuel Disposition (UFD) Campaign. Since 2012, in an effort coordinated by Lawrence Berkeley National Laboratory, UFD has advanced active collaboration with several international geologic disposal programs in Europe and Asia. Such collaboration allows the UFD Campaign to benefit from a deep knowledge base with regards to alternative repository environments developed over decades, and to utilize international investments in research facilities (such as underground research laboratories), saving millions of R&D dollars that have been and are being provided by other countries. To date, UFD’s International Disposal R&D Program has established formal collaboration agreements with five international initiatives and several international partners, and national lab scientists associated with UFD have conducted specific collaborative R&D activities that align well with its R&D priorities.

  3. Waste Isolation Pilot Plant disposal phase final supplemental environmental impact statement. Volume 3: Comment response document

    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 provides responses to public comments on the Draft SEIS-II. Comments are related to: Alternatives; TRU waste; DOE credibility; Editorial; Endorsement/opposition; Environmental justice; Facility accidents; Generator site operations; Health and safety; Legal and policy issues; NEPA process; WIPP facilities; WIPP waste isolation performance; Purpose and need; WIPP operations; Site characterization; Site selection; Socioeconomics; and Transportation

  4. Assessment of Deep Geological Environmental Condition for HLW Disposal in Korea

    International Nuclear Information System (INIS)

    Koh, Yong Kweon; Bae, Dae Seok; Kim, Kyung Su

    2010-04-01

    The research developed methods to study and evaluate geological factors and items to select radioactive waste disposal site, which should meet the safety requirements for radioactive waste disposal repositories according to the guidelines recommended by IAEA. A basic concept of site evaluation and selection for high level radioactive waste disposal and develop systematic geological data management with geological data system which will be used for site selection in future are provided. We selected 36 volcanic rock sites and 26 gneissic sites as the alternative host rocks for high level radioactive waste disposal and the geochemical characteristics of groundwaters of the four representative sites were statistically analyzed. From the hydrogeological and geochemical investigation, the spatial distribution characteristics were provided for the disposal system development and preliminary safety assessment. Finally, the technology and scientific methods were developed to obtain accurate data on the hydrogeological and geochemical characteristics of the deep geological environments

  5. Application of intelligence based uncertainty analysis for HLW disposal

    International Nuclear Information System (INIS)

    Kato, Kazuyuki

    2003-01-01

    Safety assessment for geological disposal of high level radioactive waste inevitably involves factors that cannot be specified in a deterministic manner. These are namely: (1) 'variability' that arises from stochastic nature of the processes and features considered, e.g., distribution of canister corrosion times and spatial heterogeneity of a host geological formation; (2) 'ignorance' due to incomplete or imprecise knowledge of the processes and conditions expected in the future, e.g., uncertainty in the estimation of solubilities and sorption coefficients for important nuclides. In many cases, a decision in assessment, e.g., selection among model options or determination of a parameter value, is subjected to both variability and ignorance in a combined form. It is clearly important to evaluate both influences of variability and ignorance on the result of a safety assessment in a consistent manner. We developed a unified methodology to handle variability and ignorance by using probabilistic and possibilistic techniques respectively. The methodology has been applied to safety assessment of geological disposal of high level radioactive waste. Uncertainties associated with scenarios, models and parameters were defined in terms of fuzzy membership functions derived through a series of interviews to the experts while variability was formulated by means of probability density functions (pdfs) based on available data set. The exercise demonstrated applicability of the new methodology and, in particular, its advantage in quantifying uncertainties based on expert's opinion and in providing information on dependence of assessment result on the level of conservatism. In addition, it was also shown that sensitivity analysis could identify key parameters in reducing uncertainties associated with the overall assessment. The above information can be used to support the judgment process and guide the process of disposal system development in optimization of protection against

  6. Review of technologies and alternatives for dispositioning DOE/INEL spent nuclear fuels

    International Nuclear Information System (INIS)

    Bendixsen, C.L.; Olson, A.L.; Christian, J.D.; Thomas, T.R.

    1994-01-01

    Following the decision to cease processing of spent nuclear fuels (SNF) for purposes of uranium recovery, the Idaho National Engineering Laboratory is evaluating alternatives for management of the 90+ types of SNF now stored thereon. Two major classes of alternatives include direct disposal of SNF with little or minimal repackaging and chemical processing to reduce high-activity waste volumes and to reduce the number and type of waste forms requiring regulatory approval. The disposal alternatives are described and the primary advantages and disadvantages identified

  7. Social Sustainability of Provinces in China: A Data Envelopment Analysis (DEA Window Analysis under the Concepts of Natural and Managerial Disposability

    Directory of Open Access Journals (Sweden)

    Toshiyuki Sueyoshi

    2017-11-01

    Full Text Available Natural and managerial disposability are two important strategic concepts, whose priorities are economic prosperity and environmental protection, respectively. This study defines social sustainability as the simultaneous achievement of economic prosperity and environmental protection, and then assesses the degree of social sustainability across provinces in China. In addition, this study combines the concepts of natural and managerial disposability with Data Envelopment Analysis window analysis. The method allows for frontier shifts among different time periods and thus can provide more stable and reliable results. This method is applied to assess the energy and environmental performances across the provinces of China during 2003–2014, and provides detailed information about provincial variations, which are valuable and important to policy makers (especially for those in local governments. This study identifies three important findings. First, there were no significant improvements in China’s environmental performance during the analysis periods, since, historically, the governments have not paid enough attention to environmental protection. Second, there are increasing trends in the provincial gaps regarding the environmental performance. In this regard, the central government should help the poor provinces to protect the environment. Third, there are significant differences between the results obtained under natural disposability and those obtained under managerial disposability, since they have different priorities regarding the operational and the environmental performances. Thus, significant contributions can be made by eco-technology progress combined with managerial performance improvements by business leaders and policy makers. This can be a new policy direction for the Chinese government.

  8. Planning for greater-confinement disposal

    International Nuclear Information System (INIS)

    Gilbert, T.L.; Luner, C.; Meshkov, N.K.; Trevorrow, L.E.; Yu, C.

    1984-01-01

    This contribution is a progress report for preparation of a document that will summarize procedures and technical information needed to plan for and implement greater-confinement disposal (GCD) of low-level radioactive waste. Selection of a site and a facility design (Phase I), and construction, operation, and extended care (Phase II) will be covered in the document. This progress report is limited to Phase I. Phase I includes determination of the need for GCD, design alternatives, and selection of a site and facility design. Alternative designs considered are augered shafts, deep trenches, engineered structures, high-integrity containers, hydrofracture, and improved waste form. Design considerations and specifications, performance elements, cost elements, and comparative advantages and disadvantages of the different designs are covered. Procedures are discussed for establishing overall performance objectives and waste-acceptance criteria, and for comparative assessment of the performance and cost of the different alternatives. 16 references

  9. Planning for greater-confinement disposal

    International Nuclear Information System (INIS)

    Gilbert, T.L.; Luner, C.; Meshkov, N.K.; Trevorrow, L.E.; Yu, C.

    1984-01-01

    This contribution is a progress report for preparation of a document that will summarize procedures and technical information needed to plan for and implement greater-confinement disposal (GCD) of low-level radioactive waste. Selection of a site and a facility design (Phase I), and construction, operation, and extended care (Phase II) will be covered in the document. This progress report is limited to Phase I. Phase I includes determination of the need for GCD, design alternatives, and selection of a site and facility design. Alternative designs considered are augered shafts, deep trenches, engineered structures, high-integrity containers, hydrofracture, and improved waste form. Design considerations and specifications, performance elements, cost elements, and comparative advantages and disadvantages of the different designs are covered. Procedures are discussed for establishing overall performance objecties and waste-acceptance criteria, and for comparative assessment of the performance and cost of the different alternatives. 16 refs

  10. Review and evaluation of alternative chemical disposal technologies

    National Research Council Canada - National Science Library

    National Research Council Staff; Commission on Engineering and Technical Systems; Division on Engineering and Physical Sciences; National Research Council; National Academy of Sciences

    ... in comparison to the Army's baseline incineration system. The volume's main finding was that no alternative technology was preferable to incineration but that work should continue on the neutralization technologies under Army consideration...

  11. Review and Evaluation of Alternative Chemical Disposal Technologies

    National Research Council Canada - National Science Library

    2000-01-01

    ... in comparison to the Army's baseline incineration system. The volume's main finding was that no alternative technology was preferable to incineration but that work should continue on the neutralization technologies under Army consideration...

  12. A risk-based decision-aiding tool for waste disposal

    International Nuclear Information System (INIS)

    Weiner, R.F.; Reiser, A.S.; Elcock, C.G.; Nevins, S.

    1997-01-01

    N-CART (the National Spent Nuclear Fuel Program Cost Analysis and Risk Tool) is being developed to aid in low-risk, cost-effective, timely management of radioactive waste and spent nuclear fuel, and can therefore be used in management of mixed waste. N-CART provides evaluation of multiple alternatives and presents the consequences of proposed waste management activities in a clear and concise format. N-CART's decision-aiding analyses include comparisons and sensitivity analyses of multiple alternatives and allows the user to perform quick turn-around open-quotes what ifclose quotes studies to investigate various scenarios. Uncertainties in data (such as cost and schedule of various activities) are represented as distributions. N-CART centralizes documentation of the bases of program alternatives and program decisions, thereby supporting responses to stakeholders concerns. The initial N-CART design considers regulatory requirements, costs, and schedules for alternative courses of action. The final design will include risks (public health, occupational, economic, scheduling), economic benefits, and the impacts of secondary waste generation. An optimization tool is being incorporated that allows the user to specify the relative importance of cost, time risks, and other bases for decisions. The N-CART prototype can be used to compare the costs and schedules of disposal alternatives for mixed low-level radioactive waste (MLLW) and greater-than-Class-C (GTCC) waste, as well as spent nuclear fuel (SNF) and related scrap material

  13. Stability of disposal rooms during waste retrieval

    International Nuclear Information System (INIS)

    Brandshaug, T.

    1989-03-01

    This report presents the results of a numerical analysis to determine the stability of waste disposal rooms for vertical and horizontal emplacement during the period of waste retrieval. It is assumed that waste retrieval starts 50 years after the initial emplacement of the waste, and that access to and retrieval of the waste containers take place through the disposal rooms. It is further assumed that the disposal rooms are not back-filled. Convective cooling of the disposal rooms in preparation for waste retrieval is included in the analysis. Conditions and parameters used were taken from the Nevada Nuclear Waste Storage Investigation (NNWSI) Project Site Characterization Plan Conceptual Design Report (MacDougall et al., 1987). Thermal results are presented which illustrate the heat transfer response of the rock adjacent to the disposal rooms. Mechanical results are presented which illustrate the predicted distribution of stress, joint slip, and room deformations for the period of time investigated. Under the assumption that the host rock can be classified as ''fair to good'' using the Geomechanics Classification System (Bieniawski, 1974), only light ground support would appear to be necessary for the disposal rooms to remain stable. 23 refs., 28 figs., 2 tabs

  14. Shielding design of disposal container for disused sealed radioactive source

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Suk Hoon; Kim, Ju Youl [FNC Technology Co., Yongin (Korea, Republic of)

    2017-06-15

    Disused Sealed Radioactive Sources (DSRSs), which are stored temporally in the centralized storage facility of Korea Radioactive Waste Agency (KORAD), will be disposed of in the low- and intermediate-level radioactive waste disposal facility located in Wolsong. Accordingly, the future plan on DSRS disposal should be established as soon as possible in connection with the construction and operation plan of disposal facility. In this study, as part of developing the systematic management plan, the radiation shielding analysis for three types of disposal container was performed for all kinds of radionuclides (excluding mixed sources) contained in DSRSs generated from domestic area using MicroShield and MCNP5 codes in consideration of the preliminary post-closure safety assessment result for disposal options, source-specific characteristics, and etc. In accordance with the analysis result, thickness of inner container for general disposal container and dimensions (i.e. diameter and height) of inner capsule for two types of special disposal container were determined as 3 mm, OD40×H120 mm (for type 1), and OD100× H240 mm (for type 2), respectively. These values were reflected in the conceptual design of DSRS disposal container, and the structural integrity of each container was confrmed through the structural analysis carried out separately from this study. Given the shielding and structural analysis results, the conceptual design derived from this study sufficiently fulfills the technical standards in force and the design performance level. And consequently, it is judged that the safe management for DSRSs to be disposed of is achieved by utilizing the disposal container with the conceptual design devised.

  15. Shielding design of disposal container for disused sealed radioactive source

    International Nuclear Information System (INIS)

    Kim, Suk Hoon; Kim, Ju Youl

    2017-01-01

    Disused Sealed Radioactive Sources (DSRSs), which are stored temporally in the centralized storage facility of Korea Radioactive Waste Agency (KORAD), will be disposed of in the low- and intermediate-level radioactive waste disposal facility located in Wolsong. Accordingly, the future plan on DSRS disposal should be established as soon as possible in connection with the construction and operation plan of disposal facility. In this study, as part of developing the systematic management plan, the radiation shielding analysis for three types of disposal container was performed for all kinds of radionuclides (excluding mixed sources) contained in DSRSs generated from domestic area using MicroShield and MCNP5 codes in consideration of the preliminary post-closure safety assessment result for disposal options, source-specific characteristics, and etc. In accordance with the analysis result, thickness of inner container for general disposal container and dimensions (i.e. diameter and height) of inner capsule for two types of special disposal container were determined as 3 mm, OD40×H120 mm (for type 1), and OD100× H240 mm (for type 2), respectively. These values were reflected in the conceptual design of DSRS disposal container, and the structural integrity of each container was confrmed through the structural analysis carried out separately from this study. Given the shielding and structural analysis results, the conceptual design derived from this study sufficiently fulfills the technical standards in force and the design performance level. And consequently, it is judged that the safe management for DSRSs to be disposed of is achieved by utilizing the disposal container with the conceptual design devised

  16. EVALUATION OF TIRE RUBBER DISPOSAL IN CONCRETE FOR PAVEMENTS

    Directory of Open Access Journals (Sweden)

    Rosa Cristina Cecche Lintz

    2009-01-01

    Full Text Available The production of waste by the tire industry has been a growing problem, indicating the need for its reuse. More than thirty million tires are discharged per year in Brazil, where regulation for the environment states that for each four new tires, five unusable ones must be adequately disposed by manufacturers and importers. Paving consumes an extremely large quantity of materials, which can be the source of rational application of waste and rejected materials. Research shows that tire rubber can be added to asphalt, which increases its durability and improves pavement quality and safety conditions by absorbing the rubber elastic properties, and also be used for architectural applications, among others. This study deals with the addition of rubber fibers from tire crushing in concrete for roadway pavements in order to provide proper indication about the alternative material disposal through an evaluation of the mechanical behavior of the modified concrete. Different concrete mixes were produced, within which, part of fine aggregates were substituted by tire rubber and mechanical experiment tests were performed, which show that, due to great resistance losses, the disposal of this alternative material in concrete should be considered for light traffic pavements, with the addition of rubber ranging up to 10% in mass.

  17. EVALUATION OF TIRE RUBBER DISPOSAL IN CONCRETE FOR PAVEMENTS

    Directory of Open Access Journals (Sweden)

    Rosa Cristina Cecche Lintz

    2009-12-01

    Full Text Available The production of waste by the tire industry has been a growing problem, indicating the need for its reuse. More than thirty million tires are discharged per year in Brazil, where regulation for the environment states that for each four new tires, five unusable ones must be adequately disposed by manufacturers and importers. Paving consumes an extremely large quantity of materials, which can be the source of rational application of waste and rejected materials. Research shows that tire rubber can be added to asphalt, which increases its durability and improves pavement quality and safety conditions by absorbing the rubber elastic properties, and also be used for architectural applications, among others. This study deals with the addition of rubber fibers from tire crushing in concrete for roadway pavements in order to provide proper indication about the alternative material disposal through an evaluation of the mechanical behavior of the modified concrete. Different concrete mixes were produced, within which, part of fine aggregates were substituted by tire rubber and mechanical experiment tests were performed, which show that, due to great resistance losses, the disposal of this alternative material in concrete should be considered for light traffic pavements, with the addition of rubber ranging up to 10% in mass.

  18. Disposal method of radioactive wastes

    International Nuclear Information System (INIS)

    Uetake, Naoto; Fukazawa, Tetsuo.

    1986-01-01

    Purpose: To improve the safety of underground disposal of radioactive wastes for a long period of time by surrounding the periphery of the radioactive wastes with materials that can inhibit the migration of radioactive nuclides and are physically and chemically stable. Method: Hardening products prepared from a water-hardenable calcium silicate compound and an aqueous solution of alkali silicate have compression strength as comparable with that of concretes, high water tightness and adsorbing property to radioactive isotopes such as cobalt similar to that of concretes and they also show adsorption to cesium which is not adsorbed to concretes. Further, the kneaded slurry thereof is excellent in the workability and can be poured even into narrow gaps. Accordingly, by alternately charging granular radioactive wastes and this slurry before hardening into the ground, the radioactive wastes can be put to underground disposal stably with simple procedures. (Kamimura, M.)

  19. Environmental restoration disposal facility applicable or relevant and appropriate requirements study report. Revision 00

    International Nuclear Information System (INIS)

    Roeck, F.V.; Vedder, B.L.; Rugg, J.E.

    1995-10-01

    The Environmental Restoration Disposal Facility (ERDF) will be a landfill authorized under the Comprehensive Environmental Response, Compensation, and Liability Act of 1980 (CERCLA) and will comply with the Resource Conservation and Recovery Act of 1976 (RCRA) substantive requirements. The facility will also comply with applicable or relevant and appropriate requirements (ARAR), including portions of the U.S. Environmental Protection Agency (EPA) regulations, Washington Administrative Code (WAC), and to-be-considered (TBC) elements such as U.S. Department of Energy (DOE) Orders. In considering the requirements of CERCLA, a detailed analysis of various alternatives for ERDF was completed using the nine CERCLA criteria, National Environmental Policy Act of 1969 (NEPA), and public comments. The ERDF record of decision (ROD) selected an alternative that includes a RCRA-compliant double-lined trench for the disposal of radioactive, hazardous, and mixed wastes resulting from the remediation of operable units (OU) within the National Priorities List (NPL) sites in the 100, 200, and 300 Areas. Only wastes resulting from the remediation of Hanford NPL sites will be allowed in the ERDF. Of the various siting and design alternatives proposed for ERDF, the selected alternative provides the best combination of features by balancing the nine CERCLA criteria, ARAR compliance, environmentally protective site, and various stakeholder and public recommendations. The ERDF trench design, compliant with RCRA Subtitle C minimum technical requirements (MTR), will be double lined and equipped with a leachate collection system. This design provides a more reliable system to protect groundwater than other proposed alternatives. The ERDF is located on the Hanford Site Central Plateau, southeast of the 200 West Area

  20. Low-level radioactive waste disposal in the United States: An overview of current commercial regulations and concepts

    International Nuclear Information System (INIS)

    Kennedy, W.E. Jr.

    1993-08-01

    Commercial low-level radioactive waste disposal in the United States is regulated by the US Nuclear Regulatory Commission (NRC) under 10 CFR 61 (1991). This regulation was issued in 1981 after a lengthy and thorough development process that considered the radionuclide concentrations and characteristics associated with commercial low-level radioactive waste streams; alternatives for waste classification; alternative technologies for low-level radioactive waste disposal; and data, modeling, and scenario analyses. The development process also included the publication of both draft and final environmental impact statements. The final regulation describes the general provisions; licenses; performance objectives; technical requirements for land disposal; financial assurances; participation by state governments and Indian tribes; and records, reports, tests, and inspections. This paper provides an overview of, and tutorial on, current commercial low-level radioactive waste disposal regulations in the United States

  1. Sea transport of used nuclear fuel and radiactive disposals to a Swedish central store

    International Nuclear Information System (INIS)

    1977-10-01

    Sea transport of used nuclear fuel and radioactive disposals to a Swedish central store. A vessel for transporting used nuclear fuel and radioactive disposals from the power stations at Ringhals, Barsebaeck, Simpevarp and Forsmark to a central store has been projected. Safety aspects, technical and economical aspects have been taken into consideration with regard to the actual volume of goods to be transported. Three different types of vessels are presented and a specification is given for the main alternative. A safety study of the main alternative is shown, regarding collision safety, fire risks and fire extinguishing equipment. (author)

  2. The EVEREST project: sensitivity analysis of geological disposal systems

    International Nuclear Information System (INIS)

    Marivoet, Jan; Wemaere, Isabelle; Escalier des Orres, Pierre; Baudoin, Patrick; Certes, Catherine; Levassor, Andre; Prij, Jan; Martens, Karl-Heinz; Roehlig, Klaus

    1997-01-01

    The main objective of the EVEREST project is the evaluation of the sensitivity of the radiological consequences associated with the geological disposal of radioactive waste to the different elements in the performance assessment. Three types of geological host formations are considered: clay, granite and salt. The sensitivity studies that have been carried out can be partitioned into three categories according to the type of uncertainty taken into account: uncertainty in the model parameters, uncertainty in the conceptual models and uncertainty in the considered scenarios. Deterministic as well as stochastic calculational approaches have been applied for the sensitivity analyses. For the analysis of the sensitivity to parameter values, the reference technique, which has been applied in many evaluations, is stochastic and consists of a Monte Carlo simulation followed by a linear regression. For the analysis of conceptual model uncertainty, deterministic and stochastic approaches have been used. For the analysis of uncertainty in the considered scenarios, mainly deterministic approaches have been applied

  3. Alternative routes to improved fuel utilization: Analysis of near-term economic incentives

    International Nuclear Information System (INIS)

    Salo, J.P.; Vieno, T.; Vira, J.

    1984-01-01

    The potential for savings in the nuclear fuel cycle costs is discussed from the point of view of a single utility. The analysis is concentrated on the existing and near-term economic incentives for improved fuel utilization, and the context is that of a small country without domestic fuel cycle services. In the uranium fuel cycle the extended burnup produces savings in the uranium feed as well as in the fuel fabrication and waste management requirements. The front-end fuel cycle cost impact is evaluated for BWRs. In the back-end part the situation is more specific of the concrete back-end solution. Estimates for savings in the cost of direct disposal of spent fuel are presented for a Finnish case. The economics of recycle is reviewed from a recent study on the use of MOX fuel in the Finnish BWRs. The results from a comparison with once-through alternative show that spent fuel reprocessing with consequent recycle of uranium and plutonium would be economically justified only with very high uranium prices. (author)

  4. Alternative jet fuel scenario analysis report

    Science.gov (United States)

    2012-11-30

    This analysis presents a bottom up projection of the potential production of alternative aviation (jet) fuels in North America (United States, Canada, and Mexico) and the European Union in the next decade. The analysis is based on available pla...

  5. Study of alternative methods for the management of liquid scintillation counting wastes

    International Nuclear Information System (INIS)

    Roche-Farmer, L.

    1980-02-01

    The Nuclear Engineering Waste Disposal Site in Richland, Washington, is the only radioactive waste disposal facility that will accept liquid scintillation counting wastes (LSCW) for disposal. That site is scheduled to discontinue receiving LSCW by the end of 1982. This document explores alternatives presently available for management of LSCW: evaporation, distillation, solidification, conversion, and combustion

  6. Are Disposable and Standard Gonioscopy Lenses Comparable?

    Science.gov (United States)

    Lee, Bonny; Szirth, Bernard C; Fechtner, Robert D; Khouri, Albert S

    2017-04-01

    produced with standard versus disposable gonioscopy lenses. Disposable gonioscopy lenses may be an acceptable alternative to standard reusable lenses, especially in conditions where sterilization is difficult.

  7. Selection of heat disposal methods for a Hanford Nuclear Energy Center

    International Nuclear Information System (INIS)

    Young, J.R.; Kannberg, L.D.; Ramsdell, J.V.; Rickard, W.H.; Watson, D.G.

    1976-06-01

    Selection of the best method for disposal of the waste heat from a large power generation center requires a comprehensive comparison of the costs and environmental effects. The objective is to identify the heat dissipation method with the minimum total economic and environmental cost. A 20 reactor HNEC will dissipate about 50,000 MWt of waste heat; a 40 reactor HNEC would release about 100,000 MWt. This is a much larger discharge of heat than has occurred from other concentrated industrial facilities and consequently a special analysis is required to determine the permissibility of such a large heat disposal and the best methods of disposal. It is possible that some methods of disposal will not be permissible because of excessive environmental effects or that the optimum disposal method may include a combination of several methods. A preliminary analysis is presented of the Hanford Nuclear Energy Center heat disposal problem to determine the best methods for disposal and any obvious limitations on the amount of heat that can be released. The analysis is based, in part, on information from an interim conceptual study, a heat sink management analysis, and a meteorological analysis

  8. An alternative plutonium disposition method

    International Nuclear Information System (INIS)

    Kueppers, C.

    2002-01-01

    This paper provides a feasibility study on vitrification of plutonium with high active waste concentrate, and fabrication of MOX fuel rods for direct final disposal. These are potential alternatives to the direct use of MOX fuel in a reactor. (author)

  9. An environmental LCA of alternative scenarios of urban sewage sludge treatment and disposal

    Directory of Open Access Journals (Sweden)

    Tarantini Mario

    2007-01-01

    Full Text Available The majority of pollutants that affect wastewater are concentrated by treatment processes in sludge; it is therefore critical to have a suitable evaluation methodology of sludge management options to analyze if pollution is redirected from water to other media, such as air and soil. Life cycle assessment is one of the most widely known and internationally accepted methodologies to compare environmental impacts of processes and systems and to evaluate their sustainability in the entire life cycle. In this study the methodology was applied to assess and compare three scenarios of urban sewage sludge treatment and disposal: sludge anaerobic digestion followed by dedicated incineration, sludge incineration without previous digestion, and sludge anaerobic digestion followed by composting. The potential benefits of spreading the compost to soil were not included in the system boundaries even if, due to its nutrients contents and soil improving features, compost could partially replace the use of commercial products. The study was aimed at finding out the environmental critical points of the treatment alternatives selected and at providing a technical and scientific contribution for further debates with national and local authorities on the environmental optimization of sewage sludge management. Life cycle assessment results confirmed the major contribution of electricity and methane consumption on several environmental impact categories. Incineration contributes more than sludge composting to almost all categories, although the heavy metals content of urban wastewater sludge raises substantial concerns when composted sludge is spread to soil. In this paper the models adopted, the hypotheses assumed and the main findings of the study are presented and discussed. .

  10. Post-disposal safety assessment of toxic and radioactive waste: waste types, disposal practices, disposal criteria, assessment methods and post-disposal impacts

    International Nuclear Information System (INIS)

    Torres, C.; Simon, I.; Little, R.H.; Charles, D.; Grogan, H.A.; Smith, G.M.; Sumerling, T.J.; Watkins, B.M.

    1993-01-01

    The need for safety assessments of waste disposal stems not only from the implementation of regulations requiring the assessment of environmental effects, but also from the more general need to justify decisions on protection requirements. As waste-disposal methods have become more technologically based, through the application of more highly engineered design concepts and through more rigorous and specific limitations on the types and quantities of the waste disposed, it follows that assessment procedures also must become more sophisticated. It is the overall aim of this study to improve the predictive modelling capacity for post-disposal safety assessments of land-based disposal facilities through the development and testing of a comprehensive, yet practicable, assessment framework. This report records all the work which has been undertaken during Phase 1 of the study. Waste types, disposal practices, disposal criteria and assessment methods for both toxic and radioactive waste are reviewed with the purpose of identifying those features relevant to assessment methodology development. Difference and similarities in waste types, disposal practices, criteria and assessment methods between countries, and between toxic and radioactive wastes are highlighted and discussed. Finally, an approach to identify post-disposal impacts, how they arise and their effects on humans and the environment is described

  11. Integrated model of Korean spent fuel and high level waste disposal options - 16091

    International Nuclear Information System (INIS)

    Hwang, Yongsoo; Miller, Ian

    2009-01-01

    This paper describes an integrated model developed by the Korean Atomic Energy Research Institute (KAERI) to simulate options for disposal of spent nuclear fuel (SNF) and reprocessing products in South Korea. A companion paper (Hwang and Miller, 2009) describes a systems-level model of Korean options for spent nuclear fuel (SNF) management in the 21. century. The model addresses alternative design concepts for disposal of SNF of different types (Candu, PWR), high level waste, and fission products arising from a variety of alternative fuel cycle back ends. It uses the GoldSim software to simulate the engineered system, near-field and far-field geosphere, and biosphere, resulting in long-term dose predictions for a variety of receptor groups. The model's results allow direct comparison of alternative repository design concepts, and identification of key parameter uncertainties and contributors to receptor doses. (authors)

  12. Design alternatives report for the cesium removal demonstration

    Energy Technology Data Exchange (ETDEWEB)

    Walker, J.F. Jr.; Youngblood, E.L.

    1995-09-01

    The Cesium Removal Demonstration (CRD) project will use liquid low-level waste (LLLW) stored in the Oak Ridge National Laboratory Melton Valley Storage Tanks to demonstrate cesium removal from sodium nitrate-based supernates. This report presents the results of a conceptual design study to scope the alternatives for conducting the demonstration at ORNL. Factors considered included (1) sorbent alternatives, (2) facility alternatives, (3) process alternatives, (4) process disposal alternatives, and (5) relative cost comparisons. Recommendations included (1) that design of the CRD system move forward based on information obtained to date from tests with Savannah River Resin, (2) that the CRD system be designed so it could use crystalline silicotitanates (CST) if an engineered form of CST becomes available prior to the CRD, (3) that the system be designed without the capability for resin regeneration, (4) that the LLLW solidification facility be used for the demonstration (5) that vitrification of the loaded resins from the CRD be demonstrated at the Savannah River Site, and (6) that permanent disposal of the loaded and/or vitrified resin at the Nevada Test Site be pursued.

  13. Design alternatives report for the cesium removal demonstration

    International Nuclear Information System (INIS)

    Walker, J.F. Jr.; Youngblood, E.L.

    1995-09-01

    The Cesium Removal Demonstration (CRD) project will use liquid low-level waste (LLLW) stored in the Oak Ridge National Laboratory Melton Valley Storage Tanks to demonstrate cesium removal from sodium nitrate-based supernates. This report presents the results of a conceptual design study to scope the alternatives for conducting the demonstration at ORNL. Factors considered included (1) sorbent alternatives, (2) facility alternatives, (3) process alternatives, (4) process disposal alternatives, and (5) relative cost comparisons. Recommendations included (1) that design of the CRD system move forward based on information obtained to date from tests with Savannah River Resin, (2) that the CRD system be designed so it could use crystalline silicotitanates (CST) if an engineered form of CST becomes available prior to the CRD, (3) that the system be designed without the capability for resin regeneration, (4) that the LLLW solidification facility be used for the demonstration (5) that vitrification of the loaded resins from the CRD be demonstrated at the Savannah River Site, and (6) that permanent disposal of the loaded and/or vitrified resin at the Nevada Test Site be pursued

  14. Efficacy of Alkaline Hydrolysis as an Alternative Method for Treatment and Disposal of Infectious Animal Waste.

    Science.gov (United States)

    Kaye, Gordon; Weber, Peter; Evans, Ann; Venezia, Richard

    1998-05-01

    The efficacy of alkaline hydrolysis as an alternative for incineration or autoclaving during treatment and disposal of infectious waste was evaluated by testing for the destruction of samples of pure cultures of selected infectious microorganisms during digestion of 114 to 136-kg loads of animal carcasses in an animal tissue digestor at the Albany Medical College. Ten milliliter samples of pure cultures of each microorganism were divided among 3 dialysis bags made from narrow diameter dialysis tubing, and each of these bags was placed inside another dialysis bag made from larger diameter dialysis tubing. Each double-bagged sample was suspended from the cover of the carcass basket of the tissue digestor so that it was completely covered by hot alkaline digestion solution during the carcass digestion process. The following organisms were required by the New York State Department of Health as representative pathogens for testing sterilization capabilities of the procedure: Staphylococcus aureus, Mycobacterium fortuitum, Candida albicans, Bacillus subtilis, Pseudomonas aeruginosa, Aspergillus fumigatus, Mycobacterium bovis BCG, MS-2 bacteriophage, and Giardia muris. Animal carcasses included pigs, sheep, rabbits, dogs, rats, mice, and guinea pigs. The tissue digestor was operated at 110 to 120 C and approximately 15 lb/in2 (gauge) for 18 h before the system was allowed to cool to 50 C and dialysis bags were retrieved and submitted for microbial culture. None of the samples obtained from the dialysis bags after the digestion process yielded indicator bacteria or yeast. Giardia cysts were completely destroyed; only small fragments of what appeared to be cyst wall could be recognized with light microscopic examination. No plaque-forming units were detected with MS-2 bacteriophage after digestion. Samples of the hydrolyzate also did not yield growth on culture media. Animal carcasses were completely solubilized and digested, with only the inorganic components of the bones

  15. Disposal of high level radioactive wastes in geological formations

    International Nuclear Information System (INIS)

    Martins, L.A.M.; Carvalho Bastos, J.P. de

    1978-01-01

    The disposal of high-activity radioactive wastes is the most serious problem for the nuclear industry. Among the solutions, the disposal of wastes in approriated geological formations is the most realistic and feasible. In this work the methods used for geological disposal, as well as, the criteria, programs and analysis for selecting a bite for waste disposal are presented [pt

  16. Closure Report for Corrective Action Unit 139: Waste Disposal Sites, Nevada Test Site, Nevada

    Energy Technology Data Exchange (ETDEWEB)

    NSTec Environmental Restoration

    2009-07-31

    Corrective Action Unit (CAU) 139 is identified in the Federal Facility Agreement and Consent Order (FFACO) as 'Waste Disposal Sites' and consists of the following seven Corrective Action Sites (CASs), located in Areas 3, 4, 6, and 9 of the Nevada Test Site: CAS 03-35-01, Burn Pit; CAS 04-08-02, Waste Disposal Site; CAS 04-99-01, Contaminated Surface Debris; CAS 06-19-02, Waste Disposal Site/Burn Pit; CAS 06-19-03, Waste Disposal Trenches; CAS 09-23-01, Area 9 Gravel Gertie; and CAS 09-34-01, Underground Detection Station. Closure activities were conducted from December 2008 to April 2009 according to the FFACO (1996, as amended February 2008) and the Corrective Action Plan for CAU 139 (U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office, 2007b). The corrective action alternatives included No Further Action, Clean Closure, and Closure in Place with Administrative Controls. Closure activities are summarized. CAU 139, 'Waste Disposal Sites,' consists of seven CASs in Areas 3, 4, 6, and 9 of the NTS. The closure alternatives included No Further Action, Clean Closure, and Closure in Place with Administrative Controls. This CR provides a summary of completed closure activities, documentation of waste disposal, and confirmation that remediation goals were met. The following site closure activities were performed at CAU 139 as documented in this CR: (1) At CAS 03-35-01, Burn Pit, soil and debris were removed and disposed as LLW, and debris was removed and disposed as sanitary waste. (2) At CAS 04-08-02, Waste Disposal Site, an administrative UR was implemented. No postings or post-closure monitoring are required. (3) At CAS 04-99-01, Contaminated Surface Debris, soil and debris were removed and disposed as LLW, and debris was removed and disposed as sanitary waste. (4) At CAS 06-19-02, Waste Disposal Site/Burn Pit, no work was performed. (5) At CAS 06-19-03, Waste Disposal Trenches, a native soil cover was installed

  17. Closure Report for Corrective Action Unit 139: Waste Disposal Sites, Nevada Test Site, Nevada

    International Nuclear Information System (INIS)

    2009-01-01

    Corrective Action Unit (CAU) 139 is identified in the Federal Facility Agreement and Consent Order (FFACO) as 'Waste Disposal Sites' and consists of the following seven Corrective Action Sites (CASs), located in Areas 3, 4, 6, and 9 of the Nevada Test Site: CAS 03-35-01, Burn Pit; CAS 04-08-02, Waste Disposal Site; CAS 04-99-01, Contaminated Surface Debris; CAS 06-19-02, Waste Disposal Site/Burn Pit; CAS 06-19-03, Waste Disposal Trenches; CAS 09-23-01, Area 9 Gravel Gertie; and CAS 09-34-01, Underground Detection Station. Closure activities were conducted from December 2008 to April 2009 according to the FFACO (1996, as amended February 2008) and the Corrective Action Plan for CAU 139 (U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office, 2007b). The corrective action alternatives included No Further Action, Clean Closure, and Closure in Place with Administrative Controls. Closure activities are summarized. CAU 139, 'Waste Disposal Sites,' consists of seven CASs in Areas 3, 4, 6, and 9 of the NTS. The closure alternatives included No Further Action, Clean Closure, and Closure in Place with Administrative Controls. This CR provides a summary of completed closure activities, documentation of waste disposal, and confirmation that remediation goals were met. The following site closure activities were performed at CAU 139 as documented in this CR: (1) At CAS 03-35-01, Burn Pit, soil and debris were removed and disposed as LLW, and debris was removed and disposed as sanitary waste. (2) At CAS 04-08-02, Waste Disposal Site, an administrative UR was implemented. No postings or post-closure monitoring are required. (3) At CAS 04-99-01, Contaminated Surface Debris, soil and debris were removed and disposed as LLW, and debris was removed and disposed as sanitary waste. (4) At CAS 06-19-02, Waste Disposal Site/Burn Pit, no work was performed. (5) At CAS 06-19-03, Waste Disposal Trenches, a native soil cover was installed, and a UR was

  18. Land suitability for waste disposal in metropolitan areas.

    Science.gov (United States)

    Baiocchi, Valerio; Lelo, Keti; Polettini, Alessandra; Pomi, Raffaella

    2014-08-01

    Site selection for waste disposal is a complex task that should meet the requirements of communities and stakeholders. In this article, three decision support methods (Boolean logic, index overlay and fuzzy gamma) are used to perform land suitability analysis for landfill siting. The study was carried out in one of the biggest metropolitan regions of Italy, with the objective of locating suitable areas for waste disposal. Physical and socio-economic information criteria for site selection were decided by a multidisciplinary group of experts, according to state-of-the-art guidelines, national legislation and local normative on waste management. The geographic information systems (GIS) based models used in this study are easy to apply but require adequate selection of criteria and weights and a careful evaluation of the results. The methodology is arranged in three steps, reflecting the criteria defined by national legislation on waste management: definition of factors that exclude location of landfills or waste treatment plants; classification of the remaining areas in terms of suitability for landfilling; and evaluation of suitable sites in relation to preferential siting factors (such as the presence of quarries or dismissed plants). The results showed that more than 80% of the provincial territory falls within constraint areas and the remaining territory is suitable for waste disposal for 0.72% or 1.93%, according to the model. The larger and most suitable sites are located in peripheral areas of the metropolitan system. The proposed approach represents a low-cost and expeditious alternative to support the spatial decision-making process. © The Author(s) 2014.

  19. Panel session: Disposal of HLW - ready for implementation

    International Nuclear Information System (INIS)

    Heremans, R.; Come, B.; Barbreau, A.; Girardi, F.

    1986-01-01

    The paper is a report of a panel session at the European Community conference on radioactive waste management and disposal, Luxembourg 1985, concerning the safe and long-term disposal of high-activity and long-lived waste. The subjects discussed include: geological barriers including deep sea-bed sediments, engineered barriers, technological problems (repository construction, waste emplacement, backfilling and sealing), safety analysis, performance assessment of disposal system components, and finally institutional, legal and financial aspects of geological disposal. (U.K.)

  20. Making waves with undersea (radioactive waste) disposal

    International Nuclear Information System (INIS)

    Milne, Roger.

    1987-01-01

    Following the Government's decision to halt the search for land-based disposal sites for low-level radioactive wastes, the search for alternative means of disposal of low- and intermediate-level wastes continues. Off-shore sites now seems to be the most likely. Two approaches are mentioned. The first is that proposed by Consolidated Environmental Technologies Ltd., to sink a shaft 15 metre in diameter under the seabed in an area of tectonic stability, possibly off Lincolnshire. The shaft could be 3000 metres deep. Waste packages and large decommissioning items would be lowered in from a giant barge. This would be expensive but environmentally more acceptable than the other approach. That is to tunnel out from the land and store the waste offshore, below the seabed. (U.K.)

  1. Status of commercial nuclear high-level waste disposal. Special report

    International Nuclear Information System (INIS)

    Dau, G.J.; Williams, R.F.

    1976-09-01

    The results of this review, presented in the form of a functional description of high level waste management system, shows that technology is available to dispose of nuclear waste safely by several different processes. The most attractive alternative in terms of available technology and shortness of time to demonstrate it at commercial scale is a system that converts the waste to a solid by immobilizing the radioactive elements in a glass matrix. Brief comments are also given on international efforts in high level waste management and advanced disposal concepts

  2. Estimating waste disposal quantities from raw waste samples

    International Nuclear Information System (INIS)

    Negin, C.A.; Urland, C.S.; Hitz, C.G.; GPU Nuclear Corp., Middletown, PA)

    1985-01-01

    Estimating the disposal quantity of waste resulting from stabilization of radioactive sludge is complex because of the many factors relating to sample analysis results, radioactive decay, allowable disposal concentrations, and options for disposal containers. To facilitate this estimation, a microcomputer spread sheet template was created. The spread sheet has saved considerable engineering hours. 1 fig., 3 tabs

  3. Fluorescent lamp and ballast disposal-efficiency and the environment: Panel discussion

    Energy Technology Data Exchange (ETDEWEB)

    Bleasby, P.

    1996-01-01

    This panel discussion looked at the present state of problems related to the disposal of fluorescent lamps and ballasts. EPA has not issued a ruling defining what is to be done, and as a result different areas of the country, and different users are treating the products differently. The authors review the history of the problem, where the environmental concerns are, possible alternatives for disposal, be it landfill, recycling, incineration, or treatment as hazardous wastes, and policy concerns with regard to this issue.

  4. Alternatives for long-term management of transuranic waste at the Savannah River Plant

    International Nuclear Information System (INIS)

    Towler, O.A. Jr.; Molen, G.F.

    1981-01-01

    The six alternatives proposed consider the effects of making no decision (Alternative 1), delaying a decision for up to 100 years (Alternatives 2 and 3), or taking significant action (Alternatives 4, 5, or 6). Alternative 4 exhibits intermediate cost and risk values, and indicates good agreement with ideal disposal characteristics. Alternative 6, which is comparable to Alternative 4 in risk and disposal characteristics, would require a large single outlay of capital funds, whereas funds for Alternative 4 could be staged. The cases described, excluding the no-action case, represent the better alternatives of the 34 that have been studied. Their costs range from 80 to 270 million dollars, while the sum of the population risk and worker dose ranges from 95 to 13,800 man-rem. The naturally occurring dose from cosmic rays and terrestrial activity to the same population over the same period is many times larger

  5. Thermal analysis of the horizontal disposal for HLW

    International Nuclear Information System (INIS)

    Zhao Honggang

    2012-01-01

    The temperature on the canister surface is set to be not more than 100 in the repository, a criterion which dictates the dimension of the repository. The factors that affect the highest temperature on the canister surface include the initial power of the canister, the material thermal properties of the engineered barrier system (EBS), the gaps around the canister in the EBS, the initial ground temperature and thermal properties of the host rock, the repository layout, etc. The article examines the material thermal properties of the host rock and the EBS, the thermal conductivity properties of the different gaps in the EBS, the temperature evolution around the single canister by using the analysis method and the numerical method for horizontal disposal concept. The findings are as follows: 1) The most important and the most sensitive parameter is the initial disposal power of the canister; 2) The two key factors that affect the highest temperature on the canister surface are the material parameter's uncertainty and nature variability of the host rock and the EBS, and the gaps around the canister in the EBS; 3) The temperature offsets between the canister and bentonite is not more than 10, and the bigger the inner gaps, the bigger temperature offsets between the canister and bentonite; When the gap between the bentonite and the host rock is filled with water, the gap's temperature offsets is small, but it will be 1∼3 higher when the gaps between the bentonite and the host rock is filled with air. (author)

  6. Disposal of chemical agents and munitions stored at Umatilla Depot Activity, Hermiston, Oregon. Final Phase 1 environmental report

    Energy Technology Data Exchange (ETDEWEB)

    Zimmerman, G.P.; Hillsman, E.L.; Johnson, R.O.; Miller, R.L.; Patton, T.G.; Schoepfle, G.M.; Tolbert, V.R.; Feldman, D.L.; Hunsaker, D.B. Jr.; Kroodsma, R.L.; Morrissey, J.; Rickert, L.W.; Staub, W.P.; West, D.C.

    1993-02-01

    The Umatilla Depot Activity (UMDA) near Hermiston, Oregon, is one of eight US Army installations in the continental United States where lethal unitary chemical agents and munitions are stored, and where destruction of agents and munitions is proposed under the Chemical Stockpile Disposal Program (CSDP). The chemical agent inventory at UMDA consists of 11.6%, by weight, of the total US stockpile. The destruction of the stockpile is necessary to eliminate the risk to the public from continued storage and to dispose of obsolete and leaking munitions. In 1988 the US Army issued a Final Programmatic Environmental Impact Statement (FPEIS) for the CSDP that identified on-site disposal of agents and munitions as the environmentally preferred alternative (i.e., the alternative with the least potential to cause significant adverse impacts), using a method based on five measures of risk for potential human health and ecosystem/environmental effects; the effectiveness and adequacy of emergency preparedness capabilities also played a key role in the FPEIS selection methodology. In some instances, the FPEIS included generic data and assumptions that were developed to allow a consistent comparison of potential impacts among programmatic alternatives and did not include detailed conditions at each of the eight installations. The purpose of this Phase 1 report is to examine the proposed implementation of on-site disposal at UMDA in light of more recent and more detailed data than those included in the FPEIS. Specifically, this Phase 1 report is intended to either confirm or reject the validity of on-site disposal for the UMDA stockpile. Using the same computation methods as in the FPEIS, new population data were used to compute potential fatalities from hypothetical disposal accidents. Results indicate that onsite disposal is clearly preferable to either continued storage at UMDA or transportation of the UMDA stockpile to another depot for disposal.

  7. Regulatory analysis and lessons learned from the LLRW [low-level radioactive waste] disposal area at West Valley, New York: Final report

    International Nuclear Information System (INIS)

    1986-12-01

    The New York State Energy Research and Development Authority has sponsored a project to develop an integrated set of site management plans for the West Valley low-level radioactive waste (LLRW) disposal area. The plans were directed to upgrade the disposal area so that passive custodial care and monitoring activities would be sufficient to protect public health and safety and the environment. Tasks 5 and 6, Regulatory Analysis and Lessons Learned, are the subject of this report. The regulatory analysis identified areas of inconsistencies between the historic site operations and the current state and federal LLRW disposal regulations and guidelines. The lessons learned task identified the causes of the disposal problems at West Valley, discussed the lessons learned, and described the responses developed by the NRC and industry to the lessons learned. 85 refs., 6 figs., 19 tabs

  8. Review of available options for low level radioactive waste disposal

    International Nuclear Information System (INIS)

    1992-07-01

    The scope of this report includes: descriptions of the options available; identification of important elements in the selection process; discussion and assessment of the relevance of the various elements for the different options; cost data indicating the relative financial importance of different parts of the systems and the general cost level of a disposal facility. An overview of the types of wastes included in low level waste categories and an approach to the LLW management system is presented. A generic description of the disposal options available and the main activities involved in implementing the different options are described. Detailed descriptions and cost information on low level waste disposal facility concepts in a number of Member States are given. Conclusions from the report are summarized. In addition, this report provides a commentary on various aspects of land disposal, based on experience gained by IAEA Member States. The document is intended to complement other related IAEA publications on LLW management and disposal. It also demonstrates that alternatives solutions for the final disposal of LLW are available and can be safely operated but the choice of an appropriate solution must be a matter for national strategy taking into account local conditions. 18 refs, 16 figs, 1 tab

  9. The AGP-Project conceptual design for a Spanish HLW final disposal facility

    International Nuclear Information System (INIS)

    Biurrun, E.; Engelmann, H.-J.; Huertas, F.; Ulibarri, A.

    1992-01-01

    Within the framework of the AGP Project a Conceptual Design for a HLW Final Disposal Facility to be eventually built in an underground salt formation in Spain has been developed. The AGP Project has the character of a system analysis. In the current project phase I several alternatives has been considered for different subsystems and/or components of the repository. The system variants, developed to such extent as to allow a comparison of their advantages and disadvantages, will allow the selection of a reference concept, which will be further developed to technical maturity in subsequent project phases. (author)

  10. Risk and safety analyses for disposal of alpha-contaminated waste in INEL

    International Nuclear Information System (INIS)

    Smith, T.

    1982-01-01

    The author first discusses the context, objectives, and scope of the risk analysis. Then he gives some background on the waste and how its managed, including the alternatives for long-term management. These are followed by risk evaluation approach, results, and 7 conclusions and problems. One of his conclusions is that a 100 nCi/g limit would provide adequate safety margins. Raising the limit to 100 nCi/g would allow about 20% of the stored waste to be diverted to near-surface disposal. He added that analyzing waste packages at 10 nCi/g is not now practical. 21 figures

  11. Remote Sensing Analysis Techniques and Sensor Requirements to Support the Mapping of Illegal Domestic Waste Disposal Sites in Queensland, Australia

    Directory of Open Access Journals (Sweden)

    Katharine Glanville

    2015-10-01

    Full Text Available Illegal disposal of waste is a significant management issue for contemporary governments with waste posing an economic, social, and environmental risk. An improved understanding of the distribution of illegal waste disposal sites is critical to enhance the cost-effectiveness and efficiency of waste management efforts. Remotely sensed data has the potential to address this knowledge gap. However, the literature regarding the use of remote sensing to map illegal waste disposal sites is incomplete. This paper aims to analyze existing remote sensing methods and sensors used to monitor and map illegal waste disposal sites. The purpose of this paper is to support the evaluation of existing remote sensing methods for mapping illegal domestic waste sites in Queensland, Australia. Recent advances in technology and the acquisition of very high-resolution remote sensing imagery provide an important opportunity to (1 revisit established analysis techniques for identifying illegal waste disposal sites, (2 examine the applicability of different remote sensors for illegal waste disposal detection, and (3 identify opportunities for future research to increase the accuracy of any illegal waste disposal mapping products.

  12. Waste management system alternatives for treatment of wastes from spent fuel reprocessing

    International Nuclear Information System (INIS)

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

    1986-09-01

    This study was performed to help identify a preferred TRU waste treatment alternative for reprocessing wastes with respect to waste form performance in a geologic repository, near-term waste management system risks, and minimum waste management system costs. The results were intended for use in developing TRU waste acceptance requirements that may be needed to meet regulatory requirements for disposal of TRU wastes in a geologic repository. The waste management system components included in this analysis are waste treatment and packaging, transportation, and disposal. The major features of the TRU waste treatment alternatives examined here include: (1) packaging (as-produced) without treatment (PWOT); (2) compaction of hulls and other compactable wastes; (3) incineration of combustibles with cementation of the ash plus compaction of hulls and filters; (4) melting of hulls and failed equipment plus incineration of combustibles with vitrification of the ash along with the HLW; (5a) decontamination of hulls and failed equipment to produce LLW plus incineration and incorporation of ash and other inert wastes into HLW glass; and (5b) variation of this fifth treatment alternative in which the incineration ash is incorporated into a separate TRU waste glass. The six alternative processing system concepts provide progressively increasing levels of TRU waste consolidation and TRU waste form integrity. Vitrification of HLW and intermediate-level liquid wastes (ILLW) was assumed in all cases

  13. Applying multi-criteria analysis to radiation protection optimisation of low and intermediate level radioactive waste disposal

    International Nuclear Information System (INIS)

    Pages, P.; Schneider, T.; Lombard, J.

    1991-01-01

    Introduction of ALARA principles in the field of radioactive waste management implies a definition of the main characteristics of the decisional framework. Specific aspects should be taken into account: long term effects, large uncertainties and/or probabilistic events, with particular attention to the public and the political authorities. Traditional cost-benefit analysis is not qualified to deal with these different dimensions of the risk. The aim of this paper is to describe the principles of multi-criteria analysis applied to low and intermediate level radioactive waste disposal. Three categories of barriers can be distinguished acting at different protection levels: site characteristics, waste package and disposal system. A set of possible solutions can be identified, but the selection of the 'optimum' is not easy because of the diversity of the factors to be allowed for. For example, the following problem needs to be addressed: is it preferable to limit public radiation exposure several hundred years ahead or to reduce occupational exposure during the monitoring period of the disposal facility? An optimisation study is currently being performed on the various components of the structure, assuming given site and waste package characteristics. Four steps are distinguished: identification and analysis of options for the structure; selection and estimation of the qualitative and quantitative criteria; determination of the 'most interesting' solutions using multi-criteria analysis; sensitivity analysis and discussion on uncertainties related to the various assumptions. Based on the preliminary findings, the paper focuses on practical solutions to address the methodological issues raised in applying the optimisation procedures to radioactive waste management. (au)

  14. Evaluation of a disposable plastic Neubauer counting chamber for semen analysis.

    Science.gov (United States)

    Kirkman-Brown, Jackson; Björndahl, Lars

    2009-02-01

    To evaluate whether disposable plastic counting chambers effectively could replace nondisposable, time-consuming, and potentially dangerous glass hemocytometers. Evaluation of equipment in modern laboratory andrology. Comparison of results obtained with plastic chambers with results obtained with "gold-standard" glass hemocytometer counts. Diagnostic laboratory for andrology. Twenty-one patients undergoing investigation for infertility problems. No interventions with patients; sperm in diluted semen samples were used when patients had allowed the use for research and training. Sperm concentration, difference from results obtained with standard equipment. In the first three experimental series, with use of standard routine phase-contrast microscopy, significantly lower count results were obtained consistently from the plastic chambers than from standard chambers. In the fourth series, with use of specialized equipment, equivalent results were obtained but with a considerably greater time commitment because of difficulties in distinguishing sperm adjacent to the gridlines in the plastic chambers. The plastic disposable chamber type was not suitable for routine semen analysis because results are variable depending on the microscope used, and increased time is necessary to do the assessment accurately.

  15. Feasibility of deep ocean disposal of heat generating waste. V.1

    International Nuclear Information System (INIS)

    Hemming, C.R.

    1988-06-01

    This report summarises the research performed in the UK during the period 1977 to 1987 as part of the international programme investigating the feasibility of ocean disposal of heat generating radioactive waste. This study has involved: (i) the definition of the disposal operations needed to meet the minimum requirements for safely emplacing waste on or under the floor of the deep ocean; (ii) the identification and characterisation of areas of the deep ocean that might be suitable for containing heat generating waste; (iii) a study of the processes by which radionuclides might migrate through the multiple barriers that isolate the waste from man's environment; and (iv) a calculation of the radiological impact of the conceptual deep ocean repository. It is concluded that, from a technical and scientific viewpoint, disposal of heat generating waste in the deep ocean could provide a safe, economic and feasible alternative to deep disposal on land. (author)

  16. Comparative analysis of traditional and alternative energy sources

    Directory of Open Access Journals (Sweden)

    Adriana Csikósová

    2008-11-01

    Full Text Available The presented thesis with designation of Comparing analysis of traditional and alternative energy resources includes, on basisof theoretical information source, research in firm, internal data, trends in company development and market, descriptionof the problem and its application. Theoretical information source is dedicated to the traditional and alternative energy resources,reserves of it, trends in using and development, the balance of it in the world, EU and in Slovakia as well. Analysis of the thesisis reflecting profile of the company and the thermal pump market evaluation using General Electric method. While the companyis implementing, except other products, the thermal pumps on geothermal energy base and surround energy base (air, the missionof the comparing analysis is to compare traditional energy resources with thermal pump from the ecological, utility and economic sideof it. The results of the comparing analysis are resumed in to the SWOT analysis. The part of the thesis includes he questionnaire offerfor effectiveness improvement and customer satisfaction analysis, and expected possibilities of alternative energy resources assistance(benefits from the government and EU funds.

  17. Low-level waste disposal performance assessments - Total source-term analysis

    Energy Technology Data Exchange (ETDEWEB)

    Wilhite, E.L.

    1995-12-31

    Disposal of low-level radioactive waste at Department of Energy (DOE) facilities is regulated by DOE. DOE Order 5820.2A establishes policies, guidelines, and minimum requirements for managing radioactive waste. Requirements for disposal of low-level waste emplaced after September 1988 include providing reasonable assurance of meeting stated performance objectives by completing a radiological performance assessment. Recently, the Defense Nuclear Facilities Safety Board issued Recommendation 94-2, {open_quotes}Conformance with Safety Standards at Department of Energy Low-Level Nuclear Waste and Disposal Sites.{close_quotes} One of the elements of the recommendation is that low-level waste performance assessments do not include the entire source term because low-level waste emplaced prior to September 1988, as well as other DOE sources of radioactivity in the ground, are excluded. DOE has developed and issued guidance for preliminary assessments of the impact of including the total source term in performance assessments. This paper will present issues resulting from the inclusion of all DOE sources of radioactivity in performance assessments of low-level waste disposal facilities.

  18. The disposal of radioactive waste in Sweden, West Germany and France

    International Nuclear Information System (INIS)

    1987-01-01

    Representatives from Humberside, Lincolnshire and Bedford County Councils have visited radioactive waste disposal sites in Sweden (Forsmak), West Germany (Konrad) and France (Centre de la Manche). The British regions are those in which there are sites which NIREX (Nuclear Industry Radioactive Waste Executive) have been investigating with a view to disposing of low and intermediate level radioactive waste. The sites, methods of disposal, cost and radiation levels are detailed for the three countries visited and compared with the NIREX proposals for shallow trench disposal for wastes at low and intermediate levels. The general findings were that the three countries visited are more advanced in the development of policies and practices for radioactive waste disposal with better technical alternatives to the NIREX proposals. Secondly, that the overall cost may be greater than for a shallow repository but would still be less than 1% of the nuclear electricity generation cost. Thirdly, the need to gain and sustain public acceptance for what was being done was more clearly understood and acted on than in the UK. (U.K.)

  19. Data analysis of the 1984 and 1986 soil sampling programs at Materials Disposal Area T in the Los Alamos National Laboratory

    International Nuclear Information System (INIS)

    Nyhan, J.W.; Drennon, B.J.

    1993-09-01

    An environmental surveillance program for Materials Disposal Area T (MDA-T) at Los Alamos, New Mexico is described. The waste-use history of this disposal site is described, followed by a description of the materials and methods used to analyze data from two surface soil radionuclide sampling programs performed at this disposal site. The disposal site's physical features are related to the spatial distribution of radionuclide concentration contours in an attempt to evaluate radionuclide migration mechanisms in and around the site. The usefulness of the data analysis efforts is evaluated and recommendations are made for future studies

  20. Multi-level governance-perspective on management of nuclear waste disposal. A comparative analysis

    Energy Technology Data Exchange (ETDEWEB)

    Brunnengraeber, Achim; Haefner, Daniel

    2015-07-01

    The primary aim of the project is to conduct a detailed social and political analysis of the preconditions for the development of an acceptable strategy for nuclear waste disposal in Germany. This includes the identification of stakeholders and their interests, responsibilities, value systems, views and expectations as well as paths for a constructive approach to dialogue and problem-solving. A focus of the research project will be an international comparative multi-level governance analysis of acceptance patterns and steering mechanisms for conflict resolution.

  1. Multi-level governance-perspective on management of nuclear waste disposal. A comparative analysis

    International Nuclear Information System (INIS)

    Brunnengraeber, Achim; Haefner, Daniel

    2015-01-01

    The primary aim of the project is to conduct a detailed social and political analysis of the preconditions for the development of an acceptable strategy for nuclear waste disposal in Germany. This includes the identification of stakeholders and their interests, responsibilities, value systems, views and expectations as well as paths for a constructive approach to dialogue and problem-solving. A focus of the research project will be an international comparative multi-level governance analysis of acceptance patterns and steering mechanisms for conflict resolution.

  2. HEU to LEU conversion and blending facility: Metal blending alternative to produce LEU oxide for disposal

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1995-09-01

    US DOE is examining options for disposing of surplus weapons-usable fissile materials and storage of all weapons-usable fissile materials. The nuclear material is converted to a form more proliferation- resistant than the original form. Blending HEU (highly enriched uranium) with less-enriched uranium to form LEU has been proposed as a disposition option. Five technologies are being assessed for blending HEU. This document provides data to be used in environmental impact analysis for the HEU-LEU disposition option that uses metal blending with an oxide waste product. It is divided into: mission and assumptions, conversion and blending facility descriptions, process descriptions and requirements, resource needs, employment needs, waste and emissions from plant, hazards discussion, and intersite transportation.

  3. HEU to LEU conversion and blending facility: Metal blending alternative to produce LEU oxide for disposal

    International Nuclear Information System (INIS)

    1995-09-01

    US DOE is examining options for disposing of surplus weapons-usable fissile materials and storage of all weapons-usable fissile materials. The nuclear material is converted to a form more proliferation- resistant than the original form. Blending HEU (highly enriched uranium) with less-enriched uranium to form LEU has been proposed as a disposition option. Five technologies are being assessed for blending HEU. This document provides data to be used in environmental impact analysis for the HEU-LEU disposition option that uses metal blending with an oxide waste product. It is divided into: mission and assumptions, conversion and blending facility descriptions, process descriptions and requirements, resource needs, employment needs, waste and emissions from plant, hazards discussion, and intersite transportation

  4. Organizing and managing radioactive waste disposal as an experiment

    International Nuclear Information System (INIS)

    Cook, B.J.; Emel, J.L.; Kasperson, R.E.

    1990-01-01

    This paper examines organization and management issues engendered by the national program for permanent disposal of commercial radioactive wastes. The description of current organizational and managerial responses to the waste disposal problem serves as a springboard for consideration of the technical, political, and organizational constraints that impinge upon the waste-management effort. Taking these constraints into account, the authors apply ideas that have emerged from previous radioactive waste-management studies and research on organizations, concluding that a change of course is needed. As an alternative, they propose an experimental approach predicated on the waste-management organization's acknowledging uncertainty and constructing responses that seek to reduce uncertainty systematically and without distortion

  5. Using performance assessment for radioactive waste disposal decision making -- implementation of the methodology into the third performance assessment iteration of the Greater Confinement Disposal site

    International Nuclear Information System (INIS)

    Gallegos, D.P.; Conrad, S.H.; Baer, T.A.

    1993-01-01

    The US Department of Energy is responsible for the disposal of a variety of radioactive wastes. Some of these wastes are prohibited from shallow land burial and also do not meet the waste acceptance criteria for proposed waste repositories at the Waste Isolation Pilot Plant (WIPP) and Yucca Mountain. These have been termed ''special-case'' waste and require an alternative disposal method. From 1984 to 1989, the Department of Energy disposed of a small quantity of special-case transuranic wastes at the Greater Confinement Disposal (GCD) site at the Nevada Test Site. In this paper, an iterative performance assessment is demonstrated as a useful decision making tool in the overall compliance assessment process for waste disposal. The GCD site has been used as the real-site implementation and test of the performance assessment approach. Through the first two performance assessment iterations for the GCD site, and the transition into the third, we demonstrate how the performance assessment methodology uses probabilistic risk concepts to guide affective decisions about site characterization activities and how it can be used as a powerful tool in bringing compliance decisions to closure

  6. Spent nuclear fuel disposal liability insurance

    International Nuclear Information System (INIS)

    Martin, D.W.

    1984-01-01

    This thesis examines the social efficiency of nuclear power when the risks of accidental releases of spent fuel radionuclides from a spent fuel disposal facility are considered. The analysis consists of two major parts. First, a theoretical economic model of the use of nuclear power including the risks associated with releases of radionuclides from a disposal facility is developed. Second, the costs of nuclear power, including the risks associated with a radionuclide release, are empirically compared to the costs of fossil fuel-fired generation of electricity. Under the provisions of the Nuclear Waste Policy Act of 1982, the federally owned and operated spent nuclear fuel disposal facility is not required to maintain a reserve fund to cover damages from an accidental radionuclide release. Thus, the risks of a harmful radionuclide release are not included in the spent nuclear fuel disposal fee charged to the electric utilities. Since the electric utilities do not pay the full, social costs of spent fuel disposal, they use nuclear fuel in excess of the social optimum. An insurance mechanism is proposed to internalize the risks associated with spent fueled disposal. Under this proposal, the Federal government is required to insure the disposal facility against any liabilities arising from accidental releases of spent fuel radionuclides

  7. [Analysis on relationship between regional economic development and sewage disposal].

    Science.gov (United States)

    Wang, La-Chun; Huo, Yu; Zhu, Ji-Ye; Li, Sheng-Feng; Gao, Chao

    2008-03-01

    Based on the relationship between district GDP and sewage disposal, the water environment protection effect in 3 cities, Suzhou, Nanjing and Xuzhou, with different economic development degrees in Jiangsu Province was dynamically analyzed. The economy in Suzhou was well developed, where the foreign capital proportion was in a high level. Its GDP per capita was 53,800 yuan in 2005 and the sewage disposal grew linearly when its GDP increased in the study time period. Nanjing was less developed than Suzhou, and the state-owned enterprises in large and medium sizes were in a high percentage. Its GDP per capita was 37,100 yuan in 2005, while the sewage disposal reduced linearly when its GDP increased in the study time period. The economy in Xuzhou is under-developed, where coal-based heavy industry was the most important one. The GDP per capita in this city was 13,200 yuan in 2005 and the sewage disposal fluctuated when its GDP increased in the study time period. According to the relationship between economic development and sewage disposal in different cities, we suggested that the water environment protection in Suzhou should focus on the control of both water pollutant total emission and emission concentration, the major work in Nanjing should focus on adjusting the industrial structure and meanwhile controlling the total emission of water pollutants, while in Xuzhou the water pollutant emission concentration should be firstly controlled.

  8. 10 CFR 61.52 - Land disposal facility operation and disposal site closure.

    Science.gov (United States)

    2010-01-01

    ... DISPOSAL OF RADIOACTIVE WASTE Technical Requirements for Land Disposal Facilities § 61.52 Land disposal... wastes by placing in disposal units which are sufficiently separated from disposal units for the other... between any buried waste and the disposal site boundary and beneath the disposed waste. The buffer zone...

  9. Assessment of alternative disposal methods to reduce greenhouse gas emissions from municipal solid waste in India.

    Science.gov (United States)

    Yedla, Sudhakar; Sindhu, N T

    2016-06-01

    Open dumping, the most commonly practiced method of solid waste disposal in Indian cities, creates serious environment and economic challenges, and also contributes significantly to greenhouse gas emissions. The present article attempts to analyse and identify economically effective ways to reduce greenhouse gas emissions from municipal solid waste. The article looks at the selection of appropriate methods for the control of methane emissions. Multivariate functional models are presented, based on theoretical considerations as well as the field measurements to forecast the greenhouse gas mitigation potential for all the methodologies under consideration. Economic feasibility is tested by calculating the unit cost of waste disposal for the respective disposal process. The purpose-built landfill system proposed by Yedla and Parikh has shown promise in controlling greenhouse gas and saving land. However, these studies show that aerobic composting offers the optimal method, both in terms of controlling greenhouse gas emissions and reducing costs, mainly by requiring less land than other methods. © The Author(s) 2016.

  10. Interim Control Strategy for the Test Area North/Technical Support Facility Sewage Treatment Facility Disposal Pond - Two-year Update

    International Nuclear Information System (INIS)

    L. V. Street

    2007-01-01

    The Idaho Cleanup Project has prepared this interim control strategy for the U.S. Department of Energy Idaho Operations Office pursuant to DOE Order 5400.5, Chapter 11.3e (1) to support continued discharges to the Test Area North/Technical Support Facility Sewage Treatment Facility Disposal Pond. In compliance with DOE Order 5400.5, a 2-year review of the Interim Control Strategy document has been completed. This submittal documents the required review of the April 2005 Interim Control Strategy. The Idaho Cleanup Project's recommendation is unchanged from the original recommendation. The Interim Control Strategy evaluates three alternatives: (1) re-route the discharge outlet to an uncontaminated area of the TSF-07; (2) construct a new discharge pond; or (3) no action based on justification for continued use. Evaluation of Alternatives 1 and 2 are based on the estimated cost and implementation timeframe weighed against either alternative's minimal increase in protection of workers, the public, and the environment. Evaluation of Alternative 3, continued use of the TSF-07 Disposal Pond under current effluent controls, is based on an analysis of four points: - Record of Decision controls will protect workers and the public - Risk of increased contamination is low - Discharge water will be eliminated in the foreseeable future - Risk of contamination spread is acceptable. The Idaho Cleanup Project recommends Alternative 3, no action other than continued implementation of existing controls and continued deactivation, decontamination, and dismantlement efforts at the Test Area North/Technical Support Facility

  11. An overview of biosphere modelling for the assessment of solid waste disposal

    International Nuclear Information System (INIS)

    Smith, G.M.

    1990-01-01

    The purpose of this paper is to discuss the role of biosphere modelling in relation to the overall assessment of disposal of solid radioactive waste. Model structure and data requirements are strongly influenced by a number of basic factors. Firstly, the alternative forms of safety criteria and regulatory requirements imply different end-points for biosphere models. Secondly, alternative disposal concepts can influence the significance of the biosphere as a barrier or diluting/concentrating feature affecting exposure of man. Thirdly, the range of different possibilities for release to the biosphere, including releases following intrusion, is very extensive. The requirements and state of development of biosphere models are discussed in relation to these factors along with methods being adopted to provide some expression of confidence in model results. 37 refs

  12. Preliminary environmental assessments of disposal of rock mined during excavation of a federal repository for radioactive waste

    International Nuclear Information System (INIS)

    1977-09-01

    Since the environmental impact of mined rock handling will be dependent not only upon the nature of the material and the way in which it might be disposed but also upon the features of the disposal site area and surroundings, it was necessary to select ''reference environmental locii'' within the regions of geological interest to typify the environmental setting into which the rock would be placed. Reference locii (locations) were developed for consideration of the environmental implications of mined rock from: bedded rock salt from the Salina region, bedded rock salt from the Permian region, dome rock salt from the Gulf Interior region, Pierre shale from the Argillaceous region, granite from the crystalline rock region, volcanic basalt rock from the crystalline ash region, and carbonate rock from the limestone region. Each of these reference locii was examined with respect to those demographic, geographic, physical and ecological attributes which might be impacted by various mined rock disposal alternatives. Alternatives considered included: onsite surface storage, industrial or commercial use, offsite disposal, and environmental blending. Potential impact assessment consists of a qualitative look at the environmental implications of various alternatives for handling the mined rock, given baseline characteristics of an area typified by those represented by the ''reference locus''

  13. Analyses of the deep borehole drilling status for a deep borehole disposal system

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Jong Youl; Choi, Heui Joo; Lee, Min Soo; Kim, Geon Young; Kim, Kyung Su [KAERI, Daejeon (Korea, Republic of)

    2016-05-15

    The purpose of disposal for radioactive wastes is not only to isolate them from humans, but also to inhibit leakage of any radioactive materials into the accessible environment. Because of the extremely high level and long-time scale radioactivity of HLW(High-level radioactive waste), a mined deep geological disposal concept, the disposal depth is about 500 m below ground, is considered as the safest method to isolate the spent fuels or high-level radioactive waste from the human environment with the best available technology at present time. Therefore, as an alternative disposal concept, i.e., deep borehole disposal technology is under consideration in number of countries in terms of its outstanding safety and cost effectiveness. In this paper, the general status of deep drilling technologies was reviewed for deep borehole disposal of high level radioactive wastes. Based on the results of these review, very preliminary applicability of deep drilling technology for deep borehole disposal analyzed. In this paper, as one of key technologies of deep borehole disposal system, the general status of deep drilling technologies in oil industry, geothermal industry and geo scientific field was reviewed for deep borehole disposal of high level radioactive wastes. Based on the results of these review, the very preliminary applicability of deep drilling technology for deep borehole disposal such as relation between depth and diameter, drilling time and feasibility classification was analyzed.

  14. Environmental impact assessment of the Swedish high-level radioactive waste disposal system - examples of likely considerations

    International Nuclear Information System (INIS)

    1994-01-01

    Sweden is investigating the feasibility of establishing a high-level radioactive waste (HLW) disposal system consisting of three components as follows: (1) Encapsulation facility, (2) system for transporting waste and (3) geologic repository. Swedish law requires that an Environmental Impact Assessment (EIA) be written for any planned action expected to have a significant impact on the environment. Before embarking on construction and operation of a HLW disposal system, the Swedish government will evaluate the expected environmental impacts to assure that the Swedish people and environmental will not be unduly affected by the disposal system. The EIA process requires that reasonable alternatives to the proposed action, including the 'zero' or 'no action' alternative, be considered so that the final approved plan for disposal will have undergone scrutiny and comparison of alternatives to arrive at a plan which is the best achievable given reasonable physical and monetary constraints. This report has been prepared by the Center for Nuclear Waste Regulatory Analyses (CNWRA) for use by the Swedish Radiation Protection Institute (SSI). The purpose of this report is to establish a document which outlines the types of information which would be in an EIA for a three part disposal system like that envisioned by the Swedish Nuclear Fuel and Waste Management Company (SKB) for the disposal of Sweden's HLW. Technical information that would normally be included in an EIA is outlined in this document. The SSI's primary interest is in radiological impacts. However, for the sake of completeness and also to evaluate all environmental impacts in a single document, non-radiological impacts are also included. Swedish authorities other than the SSI may have interest in the non-radiological parts of the document. 26 refs

  15. Reliability of tonosafe disposable tonometer prisms: clinical implications from the Veterans Affairs Boston Healthcare System Quality Assurance Study.

    Science.gov (United States)

    Thomas, V; Daly, M K; Cakiner-Egilmez, T; Baker, E

    2011-05-01

    Given the Veterans Affairs Boston Healthcare System's recent introduction of single-use Tonosafe disposable tonometer prisms as an alternative to Goldmann applanation tonometers (GATs), this study had two aims: to conduct a large-scale quality assurance trial to assess the reliability of intraocular pressure (IOP) measurements of the Tonosafe disposable tonometer compared with GAT, particularly at extremes of pressure; to evaluate the suitability of Tonosafe disposable tonometer prisms as an acceptable substitute for GATs and for clinic-wide implementation in an academic tertiary referral setting. Ophthalmology resident physicians measured the IOPs of patients in general and specialty eye clinics with the Tonosafe disposable tonometer and GAT. Tonosafe test-retest reliability data were also collected. A retrospective review of patient charts and data analysis were performed to determine the reliability of measurements. The IOPs of 652 eyes (326 patients) were measured with both GAT and Tonosafe, with a range of 3-34 mm Hg. Linear regression analysis showed R=0.93, slope=0.91, both of which supported the proposed hypothesis, and the y-intercept=-1.05 was significantly different from the hypothesized value. The Tonosafe test-retest repeatability (40 eyes of 40 patients), r=0.977, was very high, which was further supported by linear regression slope=0.993, y-intercept=0.118, and a Tonosafe repeatability coefficient of 2.06, similar to GAT repeatability. The IOP measurements by Tonosafe disposable prisms correlated closely with Goldmann measurements, with similar repeated measurement variability to GAT. This suggests that the Tonosafe is an acceptable substitute for GAT to measure IOP in ophthalmology clinic settings.

  16. Geographic factors related to site suitability of low-level waste disposal

    Science.gov (United States)

    Zittel, H. E.

    Factors related to the site suitability of low level waste disposal sites are discussed including those which might be considered environmental and those dealing with site criteria. Possible population criteria, alternative site selection, transportation criteria, and community involvement are considered. All these factors are based on the premise that the technology exists to carry out low level waste disposal in a manner such that public health and safety can be insured. It is concluded that problems encountered in siting low level waste facilities are largely societal and political in nature.

  17. Optimizing High Level Waste Disposal

    International Nuclear Information System (INIS)

    Dirk Gombert

    2005-01-01

    If society is ever to reap the potential benefits of nuclear energy, technologists must close the fuel-cycle completely. A closed cycle equates to a continued supply of fuel and safe reactors, but also reliable and comprehensive closure of waste issues. High level waste (HLW) disposal in borosilicate glass (BSG) is based on 1970s era evaluations. This host matrix is very adaptable to sequestering a wide variety of radionuclides found in raffinates from spent fuel reprocessing. However, it is now known that the current system is far from optimal for disposal of the diverse HLW streams, and proven alternatives are available to reduce costs by billions of dollars. The basis for HLW disposal should be reassessed to consider extensive waste form and process technology research and development efforts, which have been conducted by the United States Department of Energy (USDOE), international agencies and the private sector. Matching the waste form to the waste chemistry and using currently available technology could increase the waste content in waste forms to 50% or more and double processing rates. Optimization of the HLW disposal system would accelerate HLW disposition and increase repository capacity. This does not necessarily require developing new waste forms, the emphasis should be on qualifying existing matrices to demonstrate protection equal to or better than the baseline glass performance. Also, this proposed effort does not necessarily require developing new technology concepts. The emphasis is on demonstrating existing technology that is clearly better (reliability, productivity, cost) than current technology, and justifying its use in future facilities or retrofitted facilities. Higher waste processing and disposal efficiency can be realized by performing the engineering analyses and trade-studies necessary to select the most efficient methods for processing the full spectrum of wastes across the nuclear complex. This paper will describe technologies being

  18. Systems impacts of spent fuel disassembly alternatives

    International Nuclear Information System (INIS)

    1984-07-01

    Three studies were completed to evaluate four alternatives to the disposal of intact spent fuel assemblies in a geologic repository. A preferred spent fuel waste form for disposal was recommended on consideration of (1) package design and fuel/package interaction, (2) long-term, in-repository performance of the waste form, and (3) overall process performance and costs for packaging, handling, and emplacement. The four basic alternative waste forms considered were (1) end fitting removal, (2) fission gas venting, (3) disassembly and close packing, and (4) shearing/immobilization. None of the findings ruled out any alternative on the basis of waste package considerations or long-term performance of the waste form. The third alternative offers flexibility in loading that may prove attractive in the various geologic media under consideration, greatly reduces the number of packages, and has the lowest unit cost. These studies were completed in October, 1981. Since then Westinghouse Electric Corporation and the Office of Nuclear Waste Isolation have completed studies in related fields. This report is now being published to provide publicly the background material that is contained within. 47 references, 28 figures, 31 tables

  19. Interim radiological safety standards and evaluation procedures for subseabed high-level waste disposal

    International Nuclear Information System (INIS)

    Klett, R.D.

    1997-06-01

    The Seabed Disposal Project (SDP) was evaluating the technical feasibility of high-level nuclear waste disposal in deep ocean sediments. Working standards were needed for risk assessments, evaluation of alternative designs, sensitivity studies, and conceptual design guidelines. This report completes a three part program to develop radiological standards for the feasibility phase of the SDP. The characteristics of subseabed disposal and how they affect the selection of standards are discussed. General radiological protection standards are reviewed, along with some new methods, and a systematic approach to developing standards is presented. The selected interim radiological standards for the SDP and the reasons for their selection are given. These standards have no legal or regulatory status and will be replaced or modified by regulatory agencies if subseabed disposal is implemented. 56 refs., 29 figs., 15 tabs

  20. OPTIMAL ALLOCATION OF LANDFILL DISPOSAL SITE: A FUZZY MULTI-CRITERIA APPROACH

    Directory of Open Access Journals (Sweden)

    Ajit P. Singh, A. K. Vidyarthi

    2008-01-01

    Full Text Available The arbitrary disposal through land-fill sites and also the unscientific management of solid wastes generated by domestic, commercial and industrial activities leading to serious problems of health, sanitation and environmental degradation in India demand an immediate proper solid waste disposal planning otherwise it may cause a serious problem, especially in small and medium-sized cities/towns if proper steps are not initiated now. The present paper aims to develop decision support systems to allocate the best landfill disposal site among the given alternative sites for Vidya Vihar, Pilani, Rajasthan, India. The technique is applied to determine the overall strategy for planning of solid waste disposal and management, while taking into account its environmental impact, as well as economical, technical and sustainable development issues. The model effectively reflects dynamic, interactive, and uncertain characteristics of the solid waste management system and provides decision-makers with a decision tool to make a better decision while choosing a municipal solid waste management strategy.

  1. Disposal of spent nuclear fuel from NPP Krsko

    International Nuclear Information System (INIS)

    Mele, I.

    2004-01-01

    In order to get a clear view of the future liabilities of Slovenia and Croatia regarding the long term management of radioactive waste and spent nuclear fuel produced by the NPP Krsko, an estimation of disposal cost for low and intermediate level waste (LILW) as well as for spent nuclear fuel is needed. This cost estimation represents the basis for defining the target value for the financial resources to be accrued by the two national decommissioning and waste disposal funds, as determined in the agreement between Slovenia and Croatia on the ownership and exploitation of the NPP Krsko from March 2003, and for specifying their financial strategies. The one and only record of the NPP Krsko spent fuel disposal costs was made in the NPP Krsko Decommissioning Plan from 1996 [1]. As a result of incomplete input data, the above SF disposal cost estimate does not incorporate all cost elements. A new cost estimation was required in the process of preparation of the Joint Decommissioning and Waste Management Programme according to the provisions of the above mentioned agreement between Slovenia and Croatia. The basic presumptions and reference scenario for the disposal of spent nuclear fuel on which the cost estimation is based, as well as the applied methodology and results of cost estimation, are presented in this paper. Alternatives to the reference scenario and open questions which need to be resolved before the relevant final decision is taken, are also briefly discussed. (author)

  2. PLUTONIUM FINISHING PLANT (PFP) SUB-GRADE EE/CA EVALUATION OF ALTERNATIVES: A NEW MODEL

    International Nuclear Information System (INIS)

    HOPKINS, A.M.

    2007-01-01

    An engineering evaluation/cost analysis (EE/CA) was performed at the Hanford Site's Plutonium Finishing Plant (PFP). The purpose of the EVCA was to identify the sub-grade items to be evaluated; determine the Comprehensive Environmental Response, Compensation, and Liability Act of 1980 (CERCLA) hazardous substances through process history and available data; evaluate these hazards; and as necessary, identify the available alternatives to reduce the risk associated with the contaminants. The sub-grade EWCA considered four alternatives for an interim removal action: (1) No Action; (2) Surveillance and Maintenance (S and M); (3) Stabilize and Leave in Place (Stabilization); and (4) Remove, Treat and Dispose (RTD). Each alternative was evaluated against the CERCLA criteria for effectiveness, implementability, and cost

  3. Elk Valley Rancheria Energy Efficiency and Alternatives Analysis

    Energy Technology Data Exchange (ETDEWEB)

    Ed Wait, Elk Valley Rancheria; Frank Ziano & Associates, Inc.

    2011-11-30

    Elk Valley Rancheria; Tribe; renewable energy; energy options analysis. The Elk Valley Rancheria, California ('Tribe') is a federally recognized Indian tribe located in Del Norte County, California, in the northwestern corner of California. The Tribe, its members and Tribal enterprises are challenged by increasing energy costs and undeveloped local energy resources. The Tribe currently lacks an energy program. The Tribal government lacked sufficient information to make informed decisions about potential renewable energy resources, energy alternatives and other energy management issues. To meet this challenge efficiently, the Tribe contracted with Frank Zaino and Associates, Inc. to help become more energy self-sufficient, by reducing their energy costs and promoting energy alternatives that stimulate economic development. Frank Zaino & Associates, Inc. provided a high level economic screening analysis based on anticipated electric and natural gas rates. This was in an effort to determine which alternative energy system will performed at a higher level so the Tribe could reduce their energy model by 30% from alternative fuel sources. The feasibility study will identify suitable energy alternatives and conservation methods that will benefit the Tribe and tribal community through important reductions in cost. The lessons learned from these conservation efforts will yield knowledge that will serve a wider goal of executing energy efficiency measures and practices in Tribal residences and business facilities. Pacific Power is the provider of electrical power to the four properties under review at $ 0.08 per Kilowatt-hour (KWH). This is a very low energy cost compared to alternative energy sources. The Tribe used baseline audits to assess current and historic energy usage at four Rancheria owned facilities. Past electric and gas billing statements were retained for review for the four buildings that will be audited. A comparative assessment of the various

  4. Oak Ridge low-level waste disposal facility designs

    International Nuclear Information System (INIS)

    Van Hoesen, S.D.; Jones, L.S.

    1991-01-01

    The strategic planning process that culuminates in the identification, selection, construction, and ultimate operation of treatment, storage, and disposal facilities for all types of low-level waste (LLW) generated on the Oak Ridge Reservation (ORR) was conducted under the Low-Level Waste Disposal Development and Demonstration (LLWDDD) Program. This program considered management of various concentrations of short half-life radionuclides generated principally at Oak Ridge National Laboratory (ORNL) and long half-life radionuclides (principally uranium) generated at the Oak Ridge Y-12 Plant and the Oak Ridge K-25 Plant. The LLWDDD Program is still ongoing and involves four phases: (1) alternative identification and evaluation, (2) technology demonstration, (3) limited operational implementation, and (4) full operational implementation. This document provides a discussion of these phases

  5. DOE's planning process for mixed low-level waste disposal

    International Nuclear Information System (INIS)

    Case, J.T.; Letourneau, M.J.; Chu, M.S.Y.

    1995-01-01

    A disposal planning process was established by the Department of Energy (DOE) Mixed Low-Level Waste (MLLW) Disposal Workgroup. The process, jointly developed with the States, includes three steps: site-screening, site-evaluation, and configuration study. As a result of the screening process, 28 sites have been eliminated from further consideration for MLLW disposal and 4 sites have been assigned a lower priority for evaluation. Currently 16 sites are being evaluated by the DOE for their potential strengths and weaknesses as MLLW disposal sites. The results of the evaluation will provide a general idea of the technical capability of the 16 disposal sites; the results can also be used to identify which treated MLLW streams can be disposed on-site and which should be disposed of off-site. The information will then serve as the basis for a disposal configuration study, which includes analysis of both technical as well as non-technical issues, that will lead to the ultimate decision on MLLW disposal site locations

  6. Final Environmental Impact Statement on 10 CFR Part 61 licensing requirements for land disposal of radioactive waste

    International Nuclear Information System (INIS)

    1982-11-01

    The three-volume final environmental impact statement (FEIS) is prepared to guide and support publication of a final regulation, 10 CFR Part 61, for the land disposal of low-level radioactive waste. The FEIS is prepared in response to public comments received on the draft environmental impact statement (DEIS) on the proposed Part 61 regulation. The DEIS was published in September 1981 as NUREG-0782. Public comments received on the proposed Part 61 regulation separate from the DEIS are also considered in the FEIS. The FEIS is not a rewritten version of the DEIS, which contains an exhaustive and detailed analysis of alternatives, but rather references the DEIS and presents the final decision bases and conclusions (costs and impacts) which are reflected in the Part 61 requirements. Four cases are specifically considered in the FEIS representing the following: past disposal practice, existing disposal practice, Part 61 requirements, and an upper bound example. The Summary and Main Report are contained in Volume 1. Volume 2 consists of Appendices A - Staff Analysis of Public Comments on the DEIS for 10 CFR Part 61, and Appendices B - Staff Analysis of Public Comments on Proposed 10 CFR Part 61 Rulemaking. Volume 3 contains Appendices C-F, entitled as follows: Appendix C - Revisions to Impact Analysis Methodology, Appendix D - Computer Codes Used for FEIS Calculations, Appendix E - Errata for the DEIS for 10 CFR Part 61 and last, Appendix F - Final Rule and Supplementary Information

  7. Mechanisms of long-term concrete degradation in LLW disposal facilities

    International Nuclear Information System (INIS)

    Rogers, V.C.

    1987-01-01

    Most low-level waste (LLW) disposal alternatives, except shallow land burial and improved shallow land burial, involve the use of concrete as an extra barrier for containment. Because concrete is a porous-type material, its moisture retention and transport properties can be characterized with parameters that are also used to characterize the geohydrologic properties of soils. Several processes can occur with the concrete to degrade it and to increase both the movement of water and contaminants through the disposal facility. The effect of these processes must be quantified in designing and estimating the long-term performance of disposal facilities. Modeling the long-term performance of LLW disposal technologies involves, first, estimating the degradation rate of the concrete in a particular facility configuration and environmental setting; second, calculating the water flow through the facility as a function of time; third, calculating the contaminant leaching usually by diffusion or dissolution mechanisms, and then coupling the facility water and contaminant outflow to a hydrogeological and environmental uptake model for environmental releases or doses

  8. Special Analysis: 2017-001 Disposal of Drums Containing Enriched Uranium in Pit 38 at Technical Area 54, Area G

    Energy Technology Data Exchange (ETDEWEB)

    Birdsell, Kay Hanson [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Stauffer, Philip H. [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); French, Sean B. [Los Alamos National Lab. (LANL), Los Alamos, NM (United States)

    2017-06-05

    Los Alamos National Laboratory (LANL) generates radioactive waste as a result of various activities. Operational waste is generated from a wide variety of research and development activities including nuclear weapons development, energy production, and medical research. Environmental restoration (ER), and decontamination and decommissioning (D&D) waste is generated as contaminated sites and facilities at LANL undergo cleanup or remediation. The majority of this waste is low-level radioactive waste (LLW) and is disposed of at the Technical Area 54 (TA-54), Area G disposal facility. This special analysis, SA 2017-001, evaluates the potential impacts of disposing of this waste in Pit 38 at Area G based on the assumptions that form the basis of the Area G PA/CA. Section 2 describes the methods used to conduct the analysis; the results of the evaluation are provided in Section 3; and conclusions and recommendations are provided in Section 4.

  9. Food waste disposal units in UK households: the need for policy intervention.

    Science.gov (United States)

    Iacovidou, Eleni; Ohandja, Dieudonne-Guy; Voulvoulis, Nikolaos

    2012-04-15

    The EU Landfill Directive requires Member States to reduce the amount of biodegradable waste disposed of to landfill. This has been a key driver for the establishment of new waste management options, particularly in the UK, which in the past relied heavily on landfill for the disposal of municipal solid waste (MSW). MSW in the UK is managed by Local Authorities, some of which in a less conventional way have been encouraging the installation and use of household food waste disposal units (FWDs) as an option to divert food waste from landfill. This study aimed to evaluate the additional burden to water industry operations in the UK associated with this option, compared with the benefits and related savings from the subsequent reductions in MSW collection and disposal. A simple economic analysis was undertaken for different FWD uptake scenarios, using the Anglian Region as a case study. Results demonstrated that the significant savings from waste collection arising from a large-scale uptake of FWDs would outweigh the costs associated with the impacts to the water industry. However, in the case of a low uptake, such savings would not be enough to cover the increased costs associated with the wastewater provision. As a result, this study highlights the need for policy intervention in terms of regulating the use of FWDs, either promoting them as an alternative to landfill to increase savings from waste management, or banning them as a threat to wastewater operations to reduce potential costs to the water industry. Copyright © 2012 Elsevier B.V. All rights reserved.

  10. Alternative additives; Alternative additiver

    Energy Technology Data Exchange (ETDEWEB)

    2007-08-15

    In this project a number of industrial and agricultural waste products have been characterised and evaluated in terms of alkali-getter performance. The intended use is for biomass-fired power stations aiming at reducing corrosion or slagging related problems. The following products have been obtained, characterised and evaluated: 1) Brewery draff 2) Danish de-gassed manure 3) Paper sludge 4) Moulding sand 5) Spent bleaching earth 6) Anorthosite 7) Sand 8) Clay-sludge. Most of the above alternative additive candidates are deemed unsuitable due to insufficient chemical effect and/or expensive requirements for pre-treatment (such as drying and transportation). 3 products were selected for full-scale testing: de-gassed manure, spent bleaching earth and clay slugde. The full scale tests were undertaken at the biomass-fired power stations in Koege, Slagelse and Ensted. Spent bleaching earth (SBE) and clay sludge were the only tested additive candidates that had a proven ability to react with KCl, to thereby reduce Cl-concentrations in deposits, and reduce the deposit flux to superheater tubes. Their performance was shown to nearly as good as commercial additives. De-gassed manure, however, did not evaluate positively due to inhibiting effects of Ca in the manure. Furthermore, de-gassed manure has a high concentration of heavy metals, which imposes a financial burden with regard to proper disposal of the ash by-products. Clay-sludge is a wet clay slurring, and drying and transportation of this product entails substantial costs. Spent bleaching does not require much pre-treatment and is therefore the most promising alternative additive. On the other hand, bleaching earth contains residual plant oil which means that a range of legislation relating to waste combustion comes into play. Not least a waste combustion fee of 330 DKK/tonne. For all alternative (and commercial) additives disposal costs of the increase ash by-products represents a significant cost. This is

  11. Screening and comparison of remedial alternatives for the South Field and flyash piles at the Fernald site

    International Nuclear Information System (INIS)

    Bumb, A.C.; Jones, G.N.

    1996-05-01

    The South Field, the Inactive Flyash Pile, and the Active Flyash Pile are in close proximity to each other and are part of Operable Unit 2 (OU2) at the Fernald Environmental Management Project (FEMP). The baseline risk assessment indicated that the exposure pathways which pose the most significant risk are external radiation from radionuclides in surface soils and use of uranium contaminated groundwater. This paper presents screening and comparison of various remedial alternatives considered to mitigate risks from the groundwater pathway. Eight remedial alternatives were developed which consisted of consolidation and capping, excavation and off-site disposal with or without treatment, excavation and on-site disposal with or without treatment and combinations of these. Risk-based source (soil) preliminary remediation levels (PRLs) and waste acceptance criteria (WACs) were developed for consolidation and capping, excavation, and on-site disposal cell. The PRLs and WACs were developed using an integrated modeling tool consisting of an infiltration model, a surface water model, a vadose zone model, and a three-dimensional contaminant migration model in saturated media. The PRLs and WACs were then used to determine need for soil treatment, determine excavation volumes, and screen remedial alternatives. The selected remedial alternative consisted of excavation and on-site disposal with off-site disposal of the fraction exceeding the WAC

  12. Analysis of space systems study for the space disposal of nuclear waste study report. Volume 2: Technical report

    Science.gov (United States)

    1981-01-01

    Reasonable space systems concepts were systematically identified and defined and a total system was evaluated for the space disposal of nuclear wastes. Areas studied include space destinations, space transportation options, launch site options payload protection approaches, and payload rescue techniques. Systems level cost and performance trades defined four alternative space systems which deliver payloads to the selected 0.85 AU heliocentric orbit destination at least as economically as the reference system without requiring removal of the protective radiation shield container. No concepts significantly less costly than the reference concept were identified.

  13. EXPERIENCES FROM THE SOURCE-TERM ANALYSIS OF A LOW AND INTERMEDIATE LEVEL RADWASTE DISPOSAL FACILITY

    International Nuclear Information System (INIS)

    Park, Jin Beak; Park, Joo-Wan; Lee, Eun-Young; Kim, Chang-Lak

    2003-01-01

    Enhancement of a computer code SAGE for evaluation of the Korean concept for a LILW waste disposal facility is discussed. Several features of source term analysis are embedded into SAGE to analyze: (1) effects of degradation mode of an engineered barrier, (2) effects of dispersion phenomena in the unsaturated zone and (3) effects of time dependent sorption coefficient in the unsaturated zone. IAEA's Vault Safety Case (VSC) approach is used to demonstrate the ability of this assessment code. Results of MASCOT are used for comparison purposes. These enhancements of the safety assessment code, SAGE, can contribute to realistic evaluation of the Korean concept of the LILW disposal project in the near future

  14. Recommendations to the NRC for review criteria for alternative methods of low-level radioactive waste disposal: Task 2a, Below-ground vaults

    International Nuclear Information System (INIS)

    Denson, R.H.; Bennett, R.D.; Wamsley, R.M.; Bean, D.L.; Ainsworth, D.L.

    1987-12-01

    The US Army Engineer Waterways Experiment Station (WES) and the US Army Engineer Division, Huntsville (HNDED) have developed general design criteria and specific design review criteria for the below-ground vault (BGV) alternative method of low-level radioactive waste (LLW) disposal. A BGV is a reinforced concrete vault (floor, walls, and roof) placed underground below the frost line, and above the water table, surrounded by filter blanket and drainage zones and covered with a low permeability earth layer and top soil with vegetation. Eight major review criteria categories have been developed ranging from the loads imposed on the BGV structure through material quality and durability considerations. Specific design review criteria have been developed in detail for seven of the eight major categories. 59 refs., 14 figs., 2 tabs

  15. Disposal of olive mill wastewater with DC arc plasma method.

    Science.gov (United States)

    Ibrahimoglu, Beycan; Yilmazoglu, M Zeki

    2018-07-01

    Olive mill wastewater is an industrial waste, generated as a byproduct of olive oil production process and generally contains components such as organic matter, suspended solids, oil, and grease. Although various methods have been developed to achieve the disposal of this industrial wastewater, due to the low cost, the most common disposal application is the passive storage in the lagoons. The main objective of this study is to reduce pollution parameters in olive mill wastewater and draw water to discharge limits by using plasma technology. Plasma-assisted disposal of olive mill wastewater method could be an alternative disposal technique when considering potential utilization of treated water in agricultural areas and economic value of flammable plasma gas which is the byproduct of disposal process. According to the experimental results, the rates of COD (chemical oxygen demand) and BOD (biological oxygen demand) of olive mill wastewater are decreased by 94.42% and 95.37%, respectively. The dissolved oxygen amount is increased from 0.36 to 6.97 mg/l. In addition, plasma gas with high H 2 content and treated water that can be used in agricultural areas for irrigation are obtained from non-dischargeable wastewater. Copyright © 2018 Elsevier Ltd. All rights reserved.

  16. Advances in Geologic Disposal System Modeling and Application to Crystalline Rock

    Energy Technology Data Exchange (ETDEWEB)

    Mariner, Paul E. [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Stein, Emily R. [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Frederick, Jennifer M. [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Sevougian, S. David [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Hammond, Glenn Edward [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Fascitelli, D. G. [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States)

    2016-09-22

    The Used Fuel Disposition Campaign (UFDC) of the U.S. Department of Energy (DOE) Office of Nuclear Energy (NE), Office of Fuel Cycle Technology (OFCT) is conducting research and development (R&D) on geologic disposal of used nuclear fuel (UNF) and high-level nuclear waste (HLW). Two of the high priorities for UFDC disposal R&D are design concept development and disposal system modeling (DOE 2011). These priorities are directly addressed in the UFDC Generic Disposal Systems Analysis (GDSA) work package, which is charged with developing a disposal system modeling and analysis capability for evaluating disposal system performance for nuclear waste in geologic media (e.g., salt, granite, clay, and deep borehole disposal). This report describes specific GDSA activities in fiscal year 2016 (FY 2016) toward the development of the enhanced disposal system modeling and analysis capability for geologic disposal of nuclear waste. The GDSA framework employs the PFLOTRAN thermal-hydrologic-chemical multi-physics code and the Dakota uncertainty sampling and propagation code. Each code is designed for massively-parallel processing in a high-performance computing (HPC) environment. Multi-physics representations in PFLOTRAN are used to simulate various coupled processes including heat flow, fluid flow, waste dissolution, radionuclide release, radionuclide decay and ingrowth, precipitation and dissolution of secondary phases, and radionuclide transport through engineered barriers and natural geologic barriers to the biosphere. Dakota is used to generate sets of representative realizations and to analyze parameter sensitivity.

  17. Execution techniques for high-level radioactive waste disposal. 2. Fundamental concept of geological disposal and implementing approach of disposal project

    International Nuclear Information System (INIS)

    Kawanishi, Motoi; Komada, Hiroya; Tsuchino, Susumu; Shiozaki, Isao; Kitayama, Kazumi; Akasaka, Hidenari; Inagaki, Yusuke; Kawamura, Hideki

    1999-01-01

    The making high activity of the high-level radioactive waste disposal business shall be fully started after establishing of the implementing organization which is planned around 2000. Considering each step of disposal business, in this study, the implementation procedure for a series of disposal business such as the selection of the disposal site, the construction and operation of the disposal facility, the closure and decommissioning of the disposal facility and the management after closure, which are carried forward by the implementation body is discussed in detail from the technical viewpoint and an example of the master schedule is proposed. Furthermore, we investigate and propose the concept of the geological disposal which becomes important in carrying forward to making of the business of the disposal, such as the present site selection smoothly, the fundamental idea of the safe securing for disposal, the basic idea to get trust to the disposal technique and the geological environmental condition which is the basic condition of this whole study for the disposal business making. (author)

  18. An industry perspective on commercial radioactive waste disposal conditions and trends.

    Science.gov (United States)

    Romano, Stephen A

    2006-11-01

    The United States is presently served by Class-A, -B and -C low-level radioactive waste and naturally-occurring and accelerator-produced radioactive material disposal sites in Washington and South Carolina; a Class-A and mixed waste disposal site in Utah that also accepts naturally-occurring radioactive material; and hazardous and solid waste facilities and uranium mill tailings sites that accept certain radioactive materials on a site-specific basis. The Washington site only accepts low-level radioactive waste from 11 western states due to interstate Compact restrictions on waste importation. The South Carolina site will be subject to geographic service area restrictions beginning 1 July 2008, after which only three states will have continued access. The Utah site dominates the commercial Class-A and mixed waste disposal market due to generally lower state fees than apply in South Carolina. To expand existing commercial services, an existing hazardous waste site in western Texas is seeking a Class-A, -B and -C and mixed waste disposal license. With that exception, no new Compact facilities are proposed. This fluid, uncertain situation has inspired national level rulemaking initiatives and policy studies, as well as alternative disposal practices for certain low-activity materials.

  19. Regional waste treatment with monolith disposal for low-level radioactive waste

    International Nuclear Information System (INIS)

    Forsberg, C.W.

    1983-01-01

    An alternative system is proposed for the disposal of low-level radioactive waste. This system, called REgional Treatment with MOnolith Disposal (RETMOD), is based on integrating three commercial technologies: automated package warehousing, whole-barrel rotary kiln incineration, and cement-based grouts for radioactive waste disposal. In the simplified flowsheet, all the sludges, liquids, resins, and combustible wastes are transported to regional facilities where they are incinerated. The ash is then mixed with special cement-based grouts, and the resulting mixture is poured into trenches to form large waste-cement monoliths. Wastes that do not require treatment, such as damaged and discarded equipment, are prepositioned in the trenches with the waste-cement mixture poured on top. The RETMOD system may provide higher safety margins by conversion of wastes into a solidified low-leach form, creation of low-surface area waste-cement monoliths, and centralization of waste processing into a few specialized facilities. Institutional problems would be simplified by placing total responsibility for safe disposal on the disposal site operator. Lower costs may be realized through reduced handling costs, the economics of scale, simplified operations, and less restrictive waste packaging requirements

  20. Validation of analytical methods in GMP: the disposable Fast Read 102® device, an alternative practical approach for cell counting.

    Science.gov (United States)

    Gunetti, Monica; Castiglia, Sara; Rustichelli, Deborah; Mareschi, Katia; Sanavio, Fiorella; Muraro, Michela; Signorino, Elena; Castello, Laura; Ferrero, Ivana; Fagioli, Franca

    2012-05-31

    The quality and safety of advanced therapy products must be maintained throughout their production and quality control cycle to ensure their final use in patients. We validated the cell count method according to the International Conference on Harmonization of Technical Requirements for Registration of Pharmaceuticals for Human Use and European Pharmacopoeia, considering the tests' accuracy, precision, repeatability, linearity and range. As the cell count is a potency test, we checked accuracy, precision, and linearity, according to ICH Q2. Briefly our experimental approach was first to evaluate the accuracy of Fast Read 102® compared to the Bürker chamber. Once the accuracy of the alternative method was demonstrated, we checked the precision and linearity test only using Fast Read 102®. The data were statistically analyzed by average, standard deviation and coefficient of variation percentages inter and intra operator. All the tests performed met the established acceptance criteria of a coefficient of variation of less than ten percent. For the cell count, the precision reached by each operator had a coefficient of variation of less than ten percent (total cells) and under five percent (viable cells). The best range of dilution, to obtain a slope line value very similar to 1, was between 1:8 and 1:128. Our data demonstrated that the Fast Read 102® count method is accurate, precise and ensures the linearity of the results obtained in a range of cell dilution. Under our standard method procedures, this assay may thus be considered a good quality control method for the cell count as a batch release quality control test. Moreover, the Fast Read 102® chamber is a plastic, disposable device that allows a number of samples to be counted in the same chamber. Last but not least, it overcomes the problem of chamber washing after use and so allows a cell count in a clean environment such as that in a Cell Factory. In a good manufacturing practice setting the disposable

  1. Validation of analytical methods in GMP: the disposable Fast Read 102® device, an alternative practical approach for cell counting

    Directory of Open Access Journals (Sweden)

    Gunetti Monica

    2012-05-01

    Full Text Available Abstract Background The quality and safety of advanced therapy products must be maintained throughout their production and quality control cycle to ensure their final use in patients. We validated the cell count method according to the International Conference on Harmonization of Technical Requirements for Registration of Pharmaceuticals for Human Use and European Pharmacopoeia, considering the tests’ accuracy, precision, repeatability, linearity and range. Methods As the cell count is a potency test, we checked accuracy, precision, and linearity, according to ICH Q2. Briefly our experimental approach was first to evaluate the accuracy of Fast Read 102® compared to the Bürker chamber. Once the accuracy of the alternative method was demonstrated, we checked the precision and linearity test only using Fast Read 102®. The data were statistically analyzed by average, standard deviation and coefficient of variation percentages inter and intra operator. Results All the tests performed met the established acceptance criteria of a coefficient of variation of less than ten percent. For the cell count, the precision reached by each operator had a coefficient of variation of less than ten percent (total cells and under five percent (viable cells. The best range of dilution, to obtain a slope line value very similar to 1, was between 1:8 and 1:128. Conclusions Our data demonstrated that the Fast Read 102® count method is accurate, precise and ensures the linearity of the results obtained in a range of cell dilution. Under our standard method procedures, this assay may thus be considered a good quality control method for the cell count as a batch release quality control test. Moreover, the Fast Read 102® chamber is a plastic, disposable device that allows a number of samples to be counted in the same chamber. Last but not least, it overcomes the problem of chamber washing after use and so allows a cell count in a clean environment such as that in a

  2. Effect of long-lived containers on the postclosure performance of a reference disposal system

    International Nuclear Information System (INIS)

    Goodwin, B.W.; Hajas, W.C.; LeNeveu, D.M.

    1996-05-01

    The concept for disposal of Canada's nuclear fuel waste involves isolating the waste in corrosion-resistant containers emplaced in a scaled vault at a depth of 500 to 1000 m in plutonic rock of the Canadian Shield. The concept permits a choice of methods, materials, site locations, and designs. The technical feasibility of this concept and its impact on the environment and human health are summarized in an Environmental Impact Statement (AECL 1994a,b), supported by nine detailed reference documents (Davis et al. 1993; Davison et al. 1994a,b; Goodwin et al. 1994; Greber et al. 1994; Grondin et al. 1994; Johnson et al. 1994a,b; Simmons and Baumgartner 1994). In the assessment of the reference disposal system, we assumed the containers encapsulating the nuclear fuel waste were constructed from Grade-2 titanium. In this report, we investigate the effect of a different choice, and assume the use of long-lived containers constructed from materials such as high-purity copper or Grades-12 or -16 titanium alloys. These alternative materials would provide much longer periods of protection, based on the expectation that the only container failure mechanism, for times up to 10 5 a, involves initial fabrication defects. We explore the effects of long-lived containers for the same vault layout and orientation that were assumed for the reference disposal vault. We also explore effects for two less favourable situations, in which the vault is closer to a nearby fracture zone and in which the vault is extended to have emplacement rooms on both sides of the fracture zone. Our analyses use the probabilistic assessment computer code, SYVAC3-CC3, an acronym for SYstems Variability Analysis Code, generation 3. with a system model describing the Canadian Concept, generation 3, for the disposal of nuclear fuel waste. The input data for the code have been adjusted to approximate the expected protection characteristics of alternative container materials. (author). 31 refs., 1 tab., 16 figs

  3. Evaluation of alternatives to shallow land burial at the radioactive waste management complex

    International Nuclear Information System (INIS)

    Cerven, F.

    1988-01-01

    Alternative waste disposal technologies were reviewed relative to Nuclear Regulatory Commission (NRC) 10 CFR 61 low-level waste (LLW) disposal criteria and the emerging DOE 5820.2 Chapter 3 criteria. The intent of the review was to select a technology which would meet or improve upon the disposal practices set forth in these regulations and orders. The evaluation of the disposal technologies yielded a disposal design which incorporates three elements: an all earth cover, earth vaults for the Class A (1) bottom discharge cask inserts, and a concrete vault for the Class B and C (2 and 3) bulk waste

  4. Disposal Criticality Analysis Methodology Topical Report

    International Nuclear Information System (INIS)

    Horton, D.G.

    1998-01-01

    The fundamental objective of this topical report is to present the planned risk-informed disposal criticality analysis methodology to the NRC to seek acceptance that the principles of the methodology and the planned approach to validating the methodology are sound. The design parameters and environmental assumptions within which the waste forms will reside are currently not fully established and will vary with the detailed waste package design, engineered barrier design, repository design, and repository layout. Therefore, it is not practical to present the full validation of the methodology in this report, though a limited validation over a parameter range potentially applicable to the repository is presented for approval. If the NRC accepts the methodology as described in this section, the methodology will be fully validated for repository design applications to which it will be applied in the License Application and its references. For certain fuel types (e.g., intact naval fuel), a ny processes, criteria, codes or methods different from the ones presented in this report will be described in separate addenda. These addenda will employ the principles of the methodology described in this report as a foundation. Departures from the specifics of the methodology presented in this report will be described in the addenda

  5. Disposal Criticality Analysis Methodology Topical Report

    International Nuclear Information System (INIS)

    D.G. Horton

    1998-01-01

    The fundamental objective of this topical report is to present the planned risk-informed disposal criticality analysis methodology to the NRC to seek acceptance that the principles of the methodology and the planned approach to validating the methodology are sound. The design parameters and environmental assumptions within which the waste forms will reside are currently not fully established and will vary with the detailed waste package design, engineered barrier design, repository design, and repository layout. Therefore, it is not practical to present the full validation of the methodology in this report, though a limited validation over a parameter range potentially applicable to the repository is presented for approval. If the NRC accepts the methodology as described in this section, the methodology will be fully validated for repository design applications to which it will be applied in the License Application and its references. For certain fuel types (e.g., intact naval fuel), any processes, criteria, codes or methods different from the ones presented in this report will be described in separate addenda. These addenda will employ the principles of the methodology described in this report as a foundation. Departures from the specifics of the methodology presented in this report will be described in the addenda

  6. Spent Nuclear Fuel Alternative Technology Risk Assessment

    Energy Technology Data Exchange (ETDEWEB)

    Perella, V.F.

    1999-11-29

    A Research Reactor Spent Nuclear Fuel Task Team (RRTT) was chartered by the Department of Energy (DOE) Office of Spent Fuel Management with the responsibility to recommend a course of action leading to a final technology selection for the interim management and ultimate disposition of the foreign and domestic aluminum-based research reactor spent nuclear fuel (SNF) under DOE''s jurisdiction. The RRTT evaluated eleven potential SNF management technologies and recommended that two technologies, direct co-disposal and an isotopic dilution alternative, either press and dilute or melt and dilute, be developed in parallel. Based upon that recommendation, the Westinghouse Savannah River Company (WSRC) organized the SNF Alternative Technology Program to further develop the direct co-disposal and melt and dilute technologies and provide a WSRC recommendation to DOE for a preferred SNF alternative management technology. A technology risk assessment was conducted as a first step in this recommendation process to determine if either, or both, of the technologies posed significant risks that would make them unsuitable for further development. This report provides the results of that technology risk assessment.

  7. Spent Nuclear Fuel Alternative Technology Risk Assessment

    International Nuclear Information System (INIS)

    Perella, V.F.

    1999-01-01

    A Research Reactor Spent Nuclear Fuel Task Team (RRTT) was chartered by the Department of Energy (DOE) Office of Spent Fuel Management with the responsibility to recommend a course of action leading to a final technology selection for the interim management and ultimate disposition of the foreign and domestic aluminum-based research reactor spent nuclear fuel (SNF) under DOE''s jurisdiction. The RRTT evaluated eleven potential SNF management technologies and recommended that two technologies, direct co-disposal and an isotopic dilution alternative, either press and dilute or melt and dilute, be developed in parallel. Based upon that recommendation, the Westinghouse Savannah River Company (WSRC) organized the SNF Alternative Technology Program to further develop the direct co-disposal and melt and dilute technologies and provide a WSRC recommendation to DOE for a preferred SNF alternative management technology. A technology risk assessment was conducted as a first step in this recommendation process to determine if either, or both, of the technologies posed significant risks that would make them unsuitable for further development. This report provides the results of that technology risk assessment

  8. Recommendations to the NRC for review criteria for alternative methods of low-level radioactive waste disposal: Task 2b: Earth-mounded concrete bunkers

    International Nuclear Information System (INIS)

    Denson, R.H.; Bennett, R.D.; Wamsley, R.M.; Bean, D.L.; Ainsworth, D.L.

    1988-01-01

    The US Army Engineers Waterways Experiment Station (WES) and US Army Engineer Division, Huntsville (HNDED) have developed general design criteria and specific design review criteria for the earth-mounded concrete bunker (EMCB) alternative method of low-level radioactive waste (LLW) disposal. An EMCB is generally described as a reinforced concrete vault placed below grade, underneath a tumulus, surrounded by filter-blanket and drainage zones. The tumulus is covered over with a low permeability cover layer and top soil with vegetation. Eight major review criteria categories have been developed ranging from the loads imposed on the EMCB structure through material quality and durability considerations. Specific design review criteria have been developed in detail for each of the eight major categories. 63 refs., 13 figs., 2 tabs

  9. Analysis of Gas Vent System in Overseas LILW Disposal Facilities

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Ju Yub; Kim, Ju Youl [FNC Technology Co., Yongin (Korea, Republic of); Jung, Hae Ryong; Ha, Jae Chul [Korea Radioactive Waste Management Corporation, Daejeon (Korea, Republic of)

    2012-05-15

    A Low- and Intermediate-Level Radioactive Waste (LILW) disposal facility is currently under construction in Korea. It is located in the aquifer, 80{approx}130 m below the ground surface. Thus, it is expected that disposal facility will be saturated after closure and various gases will be generated from metal corrosion, microbial degradation of organic materials and radiolysis. Generated gases will move up to the upper part of the silo, and it will increase the pressure of the silo. Since the integrity of the engineered barrier could be damaged, development of effective gas vent system which can prevent the gas accumulation in the silo is essential. In order to obtain basic data needed to develop site-specific gas vent system, gas vent systems of Sweden, Finland and Switzerland, which have the disposal concept of underground facility, were analyzed

  10. Improvement of safety approach for accident during operation of LILW disposal facility: Application for operational safety assessment of the near-surface LILW disposal facility in Korea

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Hyun Joo; Kim, Min Seong; Park, Jin Beak [Korea Radioactive Waste Agency, Daejeon (Korea, Republic of)

    2017-06-15

    To evaluate radiological impact from the operation of a low- and intermediate-level radioactive waste disposal facility, a logical presentation and explanation of expected accidental scenarios is essential to the stakeholders of the disposal facility. The logical assessment platform and procedure, including analysis of the safety function of disposal components, operational hazard analysis, operational risk analysis, and preparedness of remedial measures for operational safety, are improved in this study. In the operational risk analysis, both design measures and management measures are suggested to make it possible to connect among design, operation, and safety assessment within the same assessment platform. For the preparedness of logical assessment procedure, classifcation logic of an operational accident is suggested based on the probability of occurrence and consequences of assessment results. The improved assessment platform and procedure are applied to an operational accident analysis of the Korean low- and intermediate-level radioactive waste disposal facility and partly presented in this paper.

  11. Improvement of safety approach for accident during operation of LILW disposal facility: Application for operational safety assessment of the near-surface LILW disposal facility in Korea

    International Nuclear Information System (INIS)

    Kim, Hyun Joo; Kim, Min Seong; Park, Jin Beak

    2017-01-01

    To evaluate radiological impact from the operation of a low- and intermediate-level radioactive waste disposal facility, a logical presentation and explanation of expected accidental scenarios is essential to the stakeholders of the disposal facility. The logical assessment platform and procedure, including analysis of the safety function of disposal components, operational hazard analysis, operational risk analysis, and preparedness of remedial measures for operational safety, are improved in this study. In the operational risk analysis, both design measures and management measures are suggested to make it possible to connect among design, operation, and safety assessment within the same assessment platform. For the preparedness of logical assessment procedure, classifcation logic of an operational accident is suggested based on the probability of occurrence and consequences of assessment results. The improved assessment platform and procedure are applied to an operational accident analysis of the Korean low- and intermediate-level radioactive waste disposal facility and partly presented in this paper

  12. Text mining analysis of public comments regarding high-level radioactive waste disposal

    International Nuclear Information System (INIS)

    Kugo, Akihide; Yoshikawa, Hidekazu; Shimoda, Hiroshi; Wakabayashi, Yasunaga

    2005-01-01

    In order to narrow the risk perception gap as seen in social investigations between the general public and people who are involved in nuclear industry, public comments on high-level radioactive waste (HLW) disposal have been conducted to find the significant talking points with the general public for constructing an effective risk communication model of social risk information regarding HLW disposal. Text mining was introduced to examine public comments to identify the core public interest underlying the comments. The utilized test mining method is to cluster specific groups of words with negative meanings and then to analyze public understanding by employing text structural analysis to extract words from subjective expressions. Using these procedures, it was found that the public does not trust the nuclear fuel cycle promotion policy and shows signs of anxiety about the long-lasting technological reliability of waste storage. To develop effective social risk communication of HLW issues, these findings are expected to help experts in the nuclear industry to communicate with the general public more effectively to obtain their trust. (author)

  13. A sensitivity analysis of hazardous waste disposal site climatic and soil design parameters using HELP3

    International Nuclear Information System (INIS)

    Adelman, D.D.; Stansbury, J.

    1997-01-01

    The Resource Conservation and Recovery Act (RCRA) Subtitle C, Comprehensive Environmental Response, Compensation, And Liability Act (CERCLA), and subsequent amendments have formed a comprehensive framework to deal with hazardous wastes on the national level. Key to this waste management is guidance on design (e.g., cover and bottom leachate control systems) of hazardous waste landfills. The objective of this research was to investigate the sensitivity of leachate volume at hazardous waste disposal sites to climatic, soil cover, and vegetative cover (Leaf Area Index) conditions. The computer model HELP3 which has the capability to simulate double bottom liner systems as called for in hazardous waste disposal sites was used in the analysis. HELP3 was used to model 54 combinations of climatic conditions, disposal site soil surface curve numbers, and leaf area index values to investigate how sensitive disposal site leachate volume was to these three variables. Results showed that leachate volume from the bottom double liner system was not sensitive to these parameters. However, the cover liner system leachate volume was quite sensitive to climatic conditions and less sensitive to Leaf Area Index and curve number values. Since humid locations had considerably more cover liner system leachate volume than and locations, different design standards may be appropriate for humid conditions than for and conditions

  14. Control of an air pressure actuated disposable bioreactor for cultivating heart valves

    NARCIS (Netherlands)

    Beelen, M.J.; Neerincx, P.E.; Molengraft, van de M.J.G.

    2011-01-01

    A disposable injection molded bioreactor for growing tissue-engineered heart valves is controlled to mimic the physiological heart cycle. Tissue-engineered heart valves, cultured from human stem cells, are a possible alternative for replacing failing aortic heart valves, where nowadays biological

  15. Environmental considerations in the selection of isolation gowns: A life cycle assessment of reusable and disposable alternatives.

    Science.gov (United States)

    Vozzola, Eric; Overcash, Michael; Griffing, Evan

    2018-04-11

    Isolation gowns serve a critical role in infection control by protecting healthcare workers, visitors, and patients from the transfer of microorganisms and body fluids. The decision of whether to use a reusable or disposable garment system is a selection process based on factors including sustainability, barrier effectiveness, cost, and comfort. Environmental sustainability is increasingly being used in the decision-making process. Life cycle assessment is the most comprehensive and widely used tool used to evaluate environmental performance. The environmental impacts of market-representative reusable and disposable isolation gown systems were compared using standard life cycle assessment procedures. The basis of comparison was 1,000 isolation gown uses in a healthcare setting. The scope included the manufacture, use, and end-of-life stages of the gown systems. At the healthcare facility, compared to the disposable gown system, the reusable gown system showed a 28% reduction in energy consumption, a 30% reduction in greenhouse gas emissions, a 41% reduction in blue water consumption, and a 93% reduction in solid waste generation. Selecting reusable garment systems may result in significant environmental benefits compared to selecting disposable garment systems. By selecting reusable isolation gowns, healthcare facilities can add these quantitative benefits directly to their sustainability scorecards. Copyright © 2018 Association for Professionals in Infection Control and Epidemiology, Inc. Published by Elsevier Inc. All rights reserved.

  16. Soil Segregation Methods for Reducing Transportation and Disposal Costs - 13544

    Energy Technology Data Exchange (ETDEWEB)

    Frothingham, David; Andrews, Shawn; Barker, Michelle; Boyle, James; Buechi, Stephen; Graham, Marc; Houston, Linda; Polek, Michael; Simmington, Robert; Spector, Harold [U.S. Army Corps of Engineers, Buffalo District, 1776 Niagara St., Buffalo, NY 14207 (United States); Elliott, Robert ' Dan' [U.S. Army Reserve, 812A Franklin St.,Worcester, MA 01604 (United States); Durham, Lisa [Argonne National Laboratory, Environmental Science Division, 9700 S. Cass Ave., Argonne, IL 60439 (United States)

    2013-07-01

    At Formerly Utilized Sites Remedial Action Program (FUSRAP) sites where the selected alternative for contaminated soil is excavation and off-site disposal, the most significant budget items of the remedial action are the costs for transportation and disposal of soil at an off-site facility. At these sites, the objective is to excavate and dispose of only those soils that exceed derived concentration guideline levels. In situ soil segregation using gross gamma detectors to guide the excavation is often challenging at sites where the soil contamination is overlain by clean soil or where the contaminated soil is located in isolated, subsurface pockets. In addition, data gaps are often identified during the alternative evaluation and selection process, resulting in increased uncertainty in the extent of subsurface contamination. In response, the U.S. Army Corps of Engineers, Buffalo District is implementing ex situ soil segregation methods. At the remediated Painesville Site, soils were excavated and fed through a conveyor-belt system, which automatically segregated them into above- and below-cleanup criteria discharge piles utilizing gamma spectroscopy. At the Linde Site and the Shallow Land Disposal Area (SLDA) Site, which are both in the remediation phase, soils are initially segregated during the excavation process using gross gamma detectors and then transported to a pad for confirmatory manual surveying and sampling. At the Linde Site, the ex situ soils are analyzed on the basis of a site-specific method, to establish compliance with beneficial reuse criteria that were developed for the Linde remediation. At the SLDA Site, the ex situ soils are surveyed and sampled based on Multi-Agency Radiation Survey and Site Investigation Manual (MARSSIM) final status survey guidance to demonstrate compliance with the derived concentration guideline levels. At all three sites, the ex situ soils that meet the site- specific DCGLs are retained on-site and used as backfill

  17. Soil Segregation Methods for Reducing Transportation and Disposal Costs - 13544

    International Nuclear Information System (INIS)

    Frothingham, David; Andrews, Shawn; Barker, Michelle; Boyle, James; Buechi, Stephen; Graham, Marc; Houston, Linda; Polek, Michael; Simmington, Robert; Spector, Harold; Elliott, Robert 'Dan'; Durham, Lisa

    2013-01-01

    At Formerly Utilized Sites Remedial Action Program (FUSRAP) sites where the selected alternative for contaminated soil is excavation and off-site disposal, the most significant budget items of the remedial action are the costs for transportation and disposal of soil at an off-site facility. At these sites, the objective is to excavate and dispose of only those soils that exceed derived concentration guideline levels. In situ soil segregation using gross gamma detectors to guide the excavation is often challenging at sites where the soil contamination is overlain by clean soil or where the contaminated soil is located in isolated, subsurface pockets. In addition, data gaps are often identified during the alternative evaluation and selection process, resulting in increased uncertainty in the extent of subsurface contamination. In response, the U.S. Army Corps of Engineers, Buffalo District is implementing ex situ soil segregation methods. At the remediated Painesville Site, soils were excavated and fed through a conveyor-belt system, which automatically segregated them into above- and below-cleanup criteria discharge piles utilizing gamma spectroscopy. At the Linde Site and the Shallow Land Disposal Area (SLDA) Site, which are both in the remediation phase, soils are initially segregated during the excavation process using gross gamma detectors and then transported to a pad for confirmatory manual surveying and sampling. At the Linde Site, the ex situ soils are analyzed on the basis of a site-specific method, to establish compliance with beneficial reuse criteria that were developed for the Linde remediation. At the SLDA Site, the ex situ soils are surveyed and sampled based on Multi-Agency Radiation Survey and Site Investigation Manual (MARSSIM) final status survey guidance to demonstrate compliance with the derived concentration guideline levels. At all three sites, the ex situ soils that meet the site- specific DCGLs are retained on-site and used as backfill

  18. Interim Control Strategy for the Test Area North/Technical Support Facility Sewage Treatment Facility Disposal Pond - Two-year Update

    Energy Technology Data Exchange (ETDEWEB)

    L. V. Street

    2007-04-01

    The Idaho Cleanup Project has prepared this interim control strategy for the U.S. Department of Energy Idaho Operations Office pursuant to DOE Order 5400.5, Chapter 11.3e (1) to support continued discharges to the Test Area North/Technical Support Facility Sewage Treatment Facility Disposal Pond. In compliance with DOE Order 5400.5, a 2-year review of the Interim Control Strategy document has been completed. This submittal documents the required review of the April 2005 Interim Control Strategy. The Idaho Cleanup Project's recommendation is unchanged from the original recommendation. The Interim Control Strategy evaluates three alternatives: (1) re-route the discharge outlet to an uncontaminated area of the TSF-07; (2) construct a new discharge pond; or (3) no action based on justification for continued use. Evaluation of Alternatives 1 and 2 are based on the estimated cost and implementation timeframe weighed against either alternative's minimal increase in protection of workers, the public, and the environment. Evaluation of Alternative 3, continued use of the TSF-07 Disposal Pond under current effluent controls, is based on an analysis of four points: - Record of Decision controls will protect workers and the public - Risk of increased contamination is low - Discharge water will be eliminated in the foreseeable future - Risk of contamination spread is acceptable. The Idaho Cleanup Project recommends Alternative 3, no action other than continued implementation of existing controls and continued deactivation, decontamination, and dismantlement efforts at the Test Area North/Technical Support Facility.

  19. Natural weathering in dry disposed ash dump: Insight from chemical, mineralogical and geochemical analysis of fresh and unsaturated drilled cores.

    Science.gov (United States)

    Akinyemi, S A; Akinlua, A; Gitari, W M; Khuse, N; Eze, P; Akinyeye, R O; Petrik, L F

    2012-07-15

    Some existing alternative applications of coal fly ash such as cement manufacturing; road construction; landfill; and concrete and waste stabilisation use fresh ash directly collected from coal-fired power generating stations. Thus, if the rate of usage continues, the demand for fresh ash for various applications will exceed supply and use of weathered dry disposed ash will become necessary alternative. As a result it's imperative to understand the chemistry and pH behaviour of some metals inherent in dry disposed fly ash. The bulk chemical composition as determined by XRF analysis showed that SiO2, Al2O3 and Fe2O3 were the major oxides in fresh ash and unsaturated weathered ashes. The unsaturated weathered ashes are relatively depleted in CaO, Fe2O3, TiO2, SiO2, Na2O and P2O5 due to dissolution and hydrolysis caused by chemical interaction with ingressing CO2 from the atmosphere and infiltrating rain water. Observed accumulations of Fe2O3, TiO2, CaO, K2O, Na2O and SO3 and Zn, Zr, Sr, Pb, Ni, Cr and Co in the lower layers indicate progressive downward movement through the ash dump though at a slow rate. The bulk mineralogy of unsaturated weathered dry disposed ash, as determined by XRD analysis, revealed quartz and mullite as the major crystalline phases; while anorthite, hematite, enstatite, lime, calcite, and mica were present as minor mineral phases. Pore water chemistry revealed a low concentration of readily soluble metals in unsaturated weathered ashes in comparison with fresh ash, which shows high leachability. This suggests that over time the precipitation of transient minor secondary mineral phases; such as calcite and mica might retard residual metal release from unsaturated weathered ash. Chloride and sulphate species of the water soluble extracts of weathered ash are at equilibrium with Na+ and K+; these demonstrate progressive leaching over time and become supersaturated at the base of unsaturated weathered ash. This suggests that the ash dump does not

  20. Application of systems analysis to the disposal of high level waste in deep ocean sediments

    International Nuclear Information System (INIS)

    De Marsily, G.; Dorp, F. van

    1982-01-01

    Emplacement in deep ocean sediments is one of the disposal options being considered for solidified high level radioactive waste. Task groups set up within the framework of the NEA Seabed Working Group have been studying many aspects of this option since 1976. The methods of systems analysis have been applied to enable the various parts of the problem to be assessed within an integrated framework. This paper describes the progress made by the Systems Analysis Task Group towards the development of an overall system model. The Task Group began by separating the problem into elements and defining the interfaces between these elements. A simple overall system model was then developed and used in both a preliminary assessment and a sensitivity analysis to identify the most important parameters. These preliminary analyses used a very simple model of the overall system and therefore the results cannot be used to draw any conclusions as to the acceptability of the sub-seabed disposal option. However they served to show the utility of the systems analysis method. The work of the other task groups will focus on the important parameters so that improved results can be fed back into an improved system model. Subsequent iterations will eventually provide an input to an acceptability decision. (Auth.)

  1. 77 FR 14587 - FY 2012 Discretionary Livability Funding Opportunity: Alternatives Analysis Program

    Science.gov (United States)

    2012-03-12

    ... alternatives analysis or to support additional technical tasks in an on-going alternatives analysis that will.... FTA will consider proposals for all areas of technical work that can better develop information about... analysis, or for work performed after the Locally Preferred Alternative (LPA) has been selected. There is...

  2. Environmental impact and risk analysis of direct disposal of spent fuel as compared to reprocessing

    International Nuclear Information System (INIS)

    Vuori, S.; Peltonen, E.; Vira, J.

    1984-01-01

    It is important to put the estimated environmental impacts and radiation exposures of alternatives considered into perspective with each other as well as with similar man-made or natural exposures taking into account all the stages of the pertinent fuel cycles and all relevant impact factors. The likely differences in safety between the reprocessing case and the direct disposal case are not very significant taking into account the uncertainties involved in the analyses and the problems of value judgement in the comparison of different types of impacts. Furthermore the difference of costs of measures to achieve a desired level of safety in each case should be considered in view of the other cost impacts arising from the choice of the fuel cycle

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

    International Nuclear Information System (INIS)

    Suryanto

    1998-01-01

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

  4. Quantitative assessment of consequences of natural events for the performance of waste disposal isolation system: Part (II)

    International Nuclear Information System (INIS)

    Ohkubo, Hiroo

    1999-12-01

    This year, first, regarding to the volcanism, seismicity and faulting, and uplift and erosion scenarios, in addition to the evaluation of those scenarios are variant cases carried out last year, variant cases where directly impacted repository could be also treated have been studied and evaluated. Secondly, based on a series of discussions in these years, a comprehensive study was made to evaluate the complex effect caused by combining natural events such as volcanism, seismicity and faulting, uplift and erosion, and climate change as well as human activity, where discussions have been made on which combined scenario was more important and how to set the analysis framework. Finally, in order to discuss alternatives such as non-groundwater scenario and/or non-geological disposal strategy, long-term storage scenario was considered to be compared with geological disposal scenario. (author)

  5. An Alternative Front End Analysis Strategy for Complex Systems

    Science.gov (United States)

    2014-12-01

    missile ( ABM ) system . Patriot is employed in the field through a battalion echelon organizational structure. The line battery is the basic building...Research Report 1981 An Alternative Front End Analysis Strategy for Complex Systems M. Glenn Cobb U.S. Army Research Institute...NUMBER W5J9CQ11D0003 An Alternative Front End Analysis Strategy for Complex Systems 5b. PROGRAM ELEMENT NUMBER 633007 6

  6. Facility Description 2012. Summary report of the encapsulation plant and disposal facility designs

    International Nuclear Information System (INIS)

    Palomaeki, J.; Ristimaeki, L.

    2013-10-01

    license. Operating phase begins in the beginning of 2020s after obtaining an operating license. More deposition and central tunnels are excavated as the disposal proceeds. The spent nuclear fuel from interim storages is encapsulated into canisters in an encapsulation plant and then transferred into the underground disposal facility with a canister lift. According to the current design, the repository layout is based on one-storey layout alternative at the level of -400...-450m. The underground disposal facility is accessed by the access tunnel and a personnel shaft, which is located in a hoist building. Other alternatives for the design and operation of the nuclear facilities are described at the end of the report. (orig.)

  7. Supplement to the final environmental statement related to the decommissioning of the rare earths facility, West Chicago, Illinois: Volume 1: Main test and appendices A-G

    International Nuclear Information System (INIS)

    1989-04-01

    This Supplement to the Final Environmental Statement (SFES) assesses the impacts of permanent disposal of wastes located at the Kerr-McGee Rare Earths Facility in West Chicago, Illinois. In this SFES, additional alternative sites are analyzed, the analysis is more detailed, and the NRC expressly considers the suitability of these sites for permanent waste disposal. The analysis describes the Proposed Action, which is permanent disposal of the wastes in an above-grade disposal cell at the West Chicago site, and four alternatives for permanent disposal at other sites in Illinois. The four alternatives are: Alternative A, disposal at an active surface coal mine in a deep-trench disposal cell; Alternative B, disposal in a reclaimed surface coal mine in a deep-trench disposal cell; Alternative C, disposal in an underground coal mine in a worked-out panel; and Alternative D, disposal on a farmland site in a partially above-grade disposal cell. The environmental issues considered in the impact assessment are topography, air quality, socioeconomics, land resources, archaeology, mineral resources, water resources, ecology, and radiation exposure. A cost-benefit analysis of the Proposed Action and its alternatives is also presented. Based on the information and analysis given within this SFES, the NRC concluded that the Proposed Action is the preferred course of action. 220 refs., 7 figs., 125 Tabs

  8. Research on near-surface disposal of very low level radioactive waste

    International Nuclear Information System (INIS)

    Wang Shaowei; Yue Huiguo; Hou Jie; Chen Haiying; Zuo Rui; Wang Jinsheng

    2012-01-01

    Radioactive waste disposal is one of the most sensitive environmental problems to control and solve. As the arriving of decommissioning of early period nuclear facilities in China, large amounts of very low level radioactive waste will be produced inevitably. The domestic and abroad definitions about very low level radioactive waste and its disposal were introduced, and then siting principles of near-surface disposal of very low level radioactive waste were discussed. The near- surface disposal siting methods of very low level radioactive waste were analyzed from natural and geographical conditions assessment, geological conditions analysis, hydrogeological conditions analysis, geological hazard assessment and radioactive background investigation; the near-surface disposal sites'natural barriers of very low level radioactive waste were analyzed from the crustal structure and physico-chemical characteristics, the dynamics characteristics of groundwater, the radionuclide adsorption characteristics of natural barriers and so on; the near-surface disposal sites' engineered barriers of very low level radioactive waste were analyzed from the repository design, the repository barrier materials selection and so on. Finally, the improving direction of very low level radioactive waste disposal was proposed. (authors)

  9. Final disposal of spent fuel in the Finnish bedrock. Scope and requirements for site-specific safety analysis

    International Nuclear Information System (INIS)

    1996-12-01

    The report is a summary of the research conducted in the period 1993 to 1996 into safety of spent fuel final disposal. The principal goal of the research in this period, as set in 1993, was to develop a strategy for site-specific safety analysis. At the same time efforts were to be continued to gather data and validate the technical approach for the analysis. The work aimed at having the data needed for the analysis available at the end of year 1998. A safety assessment update, TILA-96, prepared by VTT Energy, is published as a separate report. The assessment is based on the TVO-92 safety analysis, but takes into account the knowledge acquired after 1992 on safety aspects of the disposal system and the data gathered from the site investigations made by TVO and from the beginning of 1996, by Posiva. Since the site investigations are still ongoing and much of the data gathered still pending interpretation, only limited amount of new site-specific information has been available for the present assessment. (172 refs.)

  10. Lessons Learned from the On-Site Disposal Facility at Fernald Closure Project

    International Nuclear Information System (INIS)

    Kumthekar, U.A.; Chiou, J.D.

    2006-01-01

    The On-Site Disposal Facility (OSDF) at the U.S. Department of Energy's (DOE) Fernald Closure Project near Cincinnati, Ohio is an engineered above-grade waste disposal facility being constructed to permanently store low level radioactive waste (LLRW) and treated mixed LLRW generated during Decommissioning and Demolition (D and D) and soil remediation performed in order to achieve the final land use goal at the site. The OSDF is engineered to store 2.93 million cubic yards of waste derived from the remediation activities. The OSDF is intended to isolate its LLRW from the environment for at least 200 years and for up to 1,000 years to the extent practicable and achievable. Construction of the OSDF started in 1997 and waste placement activities will complete by the middle of April 2006 with the final cover (cap) placement over the last open cell by the end of Spring 2006. An on-site disposal alternative is considered critical to the success of many large-scale DOE remediation projects throughout the United States. However, for various reasons this cost effective alternative is not readily available in many cases. Over the last ten years Fluor Fernald Inc. has cumulated many valuable lessons learned through the complex engineering, construction, operation, and closure processes of the OSDF. Also in the last several years representatives from other DOE sites, State agencies, as well as foreign government agencies have visited the Fernald site to look for proven experiences and practices, which may be adapted for their sites. This paper present a summary of the major issues and lessons leaned at the Fernald site related to engineering, construction, operation, and closure processes for the disposal of remediation waste. The purpose of this paper is to share lessons learned and to benefit other projects considering or operating similar on-site disposal facilities from our successful experiences. (authors)

  11. Long-Term Evaluation of Times Beach Confined Disposal Facility, Buffalo, New York; An Update

    National Research Council Canada - National Science Library

    Simmers, John

    1997-01-01

    After the open-water disposal of dredged sediments was observed to have deleterious effects on the aquatic ecosystems of the Great Lakes, an alternative was sought to reduce the exposure of lake biota...

  12. Geological disposal: security and R and D. Security of 'second draft for R and D of geological disposal'

    International Nuclear Information System (INIS)

    Shiotsuki, Masao; Miyahara, Kaname

    2003-01-01

    The second draft for R and D of geological disposal (second draft) was arranged in 1999. The idea of security of geological disposal in the second draft is explained. The evaluation results of the uncertainty analysis and an example of evaluation of the effect of separation nuclear transmutation on the geological disposal are shown. The construction of strong engineered barrier is a basic idea of geological disposal system. Three processes such as isolation, engineering countermeasures and safety evaluation are carried out for the security of geological disposal. The security of geological environment for a long time of 12 sites in Japan was studied by data. Provability of production and enforcement of engineered barrier were confirmed by trial of over pack, tests and the present and future technologies developed. By using the conditions of reference case in the second draft, the evaluation results of dose effects in the two cases: 1) 90 to 99% Cs and Sr removed from HLW (High Level radioactive Waste) and 2) high stripping ratio of actinium series are explained. (S.Y.)

  13. Institutional aspects of siting nuclear waste disposal facilities in the United States

    International Nuclear Information System (INIS)

    Stewart, J.C.; Prichard, W.C.

    1987-01-01

    This paper has dealt with the institutional issues associated with disposal of nuclear waste in the US. The authors believe that these institutional problems must be resolved, no matter how technologically well suited a site may be for disposal, before site selection may take place. The authors have also pointed out that the geography of the US, with its large arid regions of very low population density, contributes to the institutional acceptability of nuclear waste disposal. Economic factors, especially in sparsely populated areas where the uranium mining and milling industry has caused operation, also weigh on the acceptability of nuclear waste to local communities. This acceptability will be highest where there are existing nuclear facilities and/or facilities which are closed - thus creating unemployment especially where alternative economic opportunities are few

  14. Disposal of spent fuel from German nuclear power plants - paper work or technology?

    International Nuclear Information System (INIS)

    Graf, R.; Filbert, W.

    2006-01-01

    The reference concept 'direct disposal of spent fuel' was developed as an alternative to spent fuel reprocessing and vitrified HLW disposal. The technical facilities necessary for the implementation of this reference concept - the so called POLLUX-concept, e.g. interim storages for casks containing spent fuel, a pilot conditioning facility, and a special cask 'POLLUX' for final disposal have been built. With view to a geological salt formation all handling procedures for the repository were tested aboveground in a test facility at a 1:1 scale. To optimise the concept all operational steps are reviewed for possible improvement. Most promising are a concept using canisters (BSK 3) instead of POLLUX casks, and the direct disposal of transport and storage casks (DIREGT-concept) which is the most recent one and has been designed for the direct disposal of large transport and storage casks. The final exploration of the pre-selected repository site is still pending, from the industries point of view due to political reasons only. The present paper describes the main concepts and their status as of today. (author)

  15. Disposal of chemical agents and munitions stored at Pueblo Depot Activity, Colorado. Final, Phase 1: Environmental report

    Energy Technology Data Exchange (ETDEWEB)

    Terry, J.W.; Blasing, T.J.; Ensminger, J.T.; Johnson, R.O.; Schexnayder, S.M.; Shor, J.T.; Staub, W.P.; Tolbert, V.R.; Zimmerman, G.P.

    1995-04-01

    Under the Chemical Stockpile Disposal Program (CSDP), the US Army proposes to dispose of lethal chemical agents and munitions stored at eight existing Army installations in the continental United States. In 1988, the US Army issued the final programmatic environmental impact statement (FPEIS) for the CSDP. The FPEIS and the subsequent Record of Decision (ROD) identified an on-site disposal process as the preferred method for destruction of the stockpile. That is, the FPEIS determined the environmentally preferred alternative to be on-site disposal in high-temperature incinerators, while the ROD selected this alternative for implementation as the preferred method for destruction of the stockpile. In this Phase I report, the overall CSDP decision regarding disposal of the PUDA Stockpile is subjected to further analyses, and its validity at PUDA is reviewed with newer, more detailed data than those providing the basis for the conclusions in the FPEIS. The findings of this Phase I report will be factored into the scope of a site-specific environmental impact statement to be prepared for the destruction of the PUDA stockpile. The focus of this Phase I report is on those data identified as having the potential to alter the Army`s previous decision regarding disposal of the PUDA stockpile; however, several other factors beyond the scope of this Phase I report must also be acknowledged to have the potential to change or modify the Army`s decisions regarding PUDA.

  16. Preparation of safety analysis reports (SARs) for near surface radioactive waste disposal facilities. Format and content of SARs

    International Nuclear Information System (INIS)

    1995-02-01

    All facilities at which radioactive wastes are processed, stored and disposed of have the potential for causing hazards to humans and to the environment. Precautions must be taken in the siting, design and operation of the facilities to ensure that an adequate level of safety is achieved. The processes by which this is evaluated is called safety assessment. An important part of safety assessment is the documentation of the process. A well prepared safety analysis report (SAR) is essential if approval of the facility is to be obtained from the regulatory authorities. This TECDOC describes the format and content of a safety analysis report for a near surface radioactive waste disposal facility and will serve essentially as a checklist in this respect

  17. Disposal safety

    International Nuclear Information System (INIS)

    Bartlett, J.W.

    International consensus does not seem to be necessary or appropriate for many of the issues concerned with the safety of nuclear waste disposal. International interaction on the technical aspects of disposal has been extensive, and this interaction has contributed greatly to development of a consensus technical infrastructure for disposal. This infrastructure provides a common and firm base for regulatory, political, and social actions in each nation

  18. Summary of the Supplemental Model Reports Supporting the Disposal Criticality Analysis Methodology Topical Report

    International Nuclear Information System (INIS)

    Brownson, D. A.

    2002-01-01

    The Department of Energy (DOE) Office of Civilian Radioactive Waste Management (OCRWM) has committed to a series of model reports documenting the methodology to be utilized in the Disposal Criticality Analysis Methodology Topical Report (YMP 2000). These model reports detail and provide validation of the methodology to be utilized for criticality analyses related to: (1) Waste form/waste package degradation; (2) Waste package isotopic inventory; (3) Criticality potential of degraded waste form/waste package configurations (effective neutron multiplication factor); (4) Probability of criticality (for each potential critical configuration as well as total event); and (5) Criticality consequences. This purpose of this summary report is to provide a status of the model reports and a schedule for their completion. This report also provides information relative to the model report content and validation. The model reports and their revisions are being generated as a result of: (1) Commitments made in the Disposal Criticality Analysis Methodology Topical Report (YMP 2000); (2) Open Items from the Safety Evaluation Report (Reamer 2000); (3) Key Technical Issue agreements made during DOE/U.S. Nuclear Regulatory Commission (NRC) Technical Exchange Meeting (Reamer and Williams 2000); and (4) NRC requests for additional information (Schlueter 2002)

  19. Waste isolation pilot plant disposal room model

    Energy Technology Data Exchange (ETDEWEB)

    Butcher, B.M.

    1997-08-01

    This paper describes development of the conceptual and mathematical models for the part of the Waste Isolation Pilot Plant (WIPP) repository performance assessment that is concerned with what happens to the waste over long times after the repository is decommissioned. These models, collectively referred to as the {open_quotes}Disposal Room Model,{close_quotes} describe the repository closure process during which deformation of the surrounding salt consolidates the waste. First, the relationship of repository closure to demonstration of compliance with the Environmental Protection Agency (EPA) standard (40 CFR 191 Appendix C) and how sensitive performance results are to it are examined. Next, a detailed description is provided of the elements of the disposal region, and properties selected for the salt, waste, and other potential disposal features such as backfill. Included in the discussion is an explanation of how the various models were developed over time. Other aspects of closure analysis, such as the waste flow model and method of analysis, are also described. Finally, the closure predictions used in the final performance assessment analysis for the WIPP Compliance Certification Application are summarized.

  20. Waste isolation pilot plant disposal room model

    International Nuclear Information System (INIS)

    Butcher, B.M.

    1997-08-01

    This paper describes development of the conceptual and mathematical models for the part of the Waste Isolation Pilot Plant (WIPP) repository performance assessment that is concerned with what happens to the waste over long times after the repository is decommissioned. These models, collectively referred to as the open-quotes Disposal Room Model,close quotes describe the repository closure process during which deformation of the surrounding salt consolidates the waste. First, the relationship of repository closure to demonstration of compliance with the Environmental Protection Agency (EPA) standard (40 CFR 191 Appendix C) and how sensitive performance results are to it are examined. Next, a detailed description is provided of the elements of the disposal region, and properties selected for the salt, waste, and other potential disposal features such as backfill. Included in the discussion is an explanation of how the various models were developed over time. Other aspects of closure analysis, such as the waste flow model and method of analysis, are also described. Finally, the closure predictions used in the final performance assessment analysis for the WIPP Compliance Certification Application are summarized

  1. Update of Part 61 Impacts Analysis Methodology. Methodology report. Volume 1

    International Nuclear Information System (INIS)

    Oztunali, O.I.; Roles, G.W.

    1986-01-01

    Under contract to the US Nuclear Regulatory Commission, the Envirosphere Company has expanded and updated the impacts analysis methodology used during the development of the 10 CFR Part 61 rule to allow improved consideration of the costs and impacts of treatment and disposal of low-level waste that is close to or exceeds Class C concentrations. The modifications described in this report principally include: (1) an update of the low-level radioactive waste source term, (2) consideration of additional alternative disposal technologies, (3) expansion of the methodology used to calculate disposal costs, (4) consideration of an additional exposure pathway involving direct human contact with disposed waste due to a hypothetical drilling scenario, and (5) use of updated health physics analysis procedures (ICRP-30). Volume 1 of this report describes the calculational algorithms of the updated analysis methodology

  2. Update of Part 61 Impacts Analysis Methodology. Methodology report. Volume 1

    Energy Technology Data Exchange (ETDEWEB)

    Oztunali, O.I.; Roles, G.W.

    1986-01-01

    Under contract to the US Nuclear Regulatory Commission, the Envirosphere Company has expanded and updated the impacts analysis methodology used during the development of the 10 CFR Part 61 rule to allow improved consideration of the costs and impacts of treatment and disposal of low-level waste that is close to or exceeds Class C concentrations. The modifications described in this report principally include: (1) an update of the low-level radioactive waste source term, (2) consideration of additional alternative disposal technologies, (3) expansion of the methodology used to calculate disposal costs, (4) consideration of an additional exposure pathway involving direct human contact with disposed waste due to a hypothetical drilling scenario, and (5) use of updated health physics analysis procedures (ICRP-30). Volume 1 of this report describes the calculational algorithms of the updated analysis methodology.

  3. 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

  4. Report on the Savannah River Site aluminum-based spent nuclear fuel alternatives cost study

    International Nuclear Information System (INIS)

    1998-12-01

    Initial estimates of costs for the interim management and disposal of aluminum-based spent nuclear fuel (SNF) were developed during preparation of the Environmental Impact Statement (EIS) on the Nuclear Weapons Nonproliferation Policy Concerning Foreign Research Reactor Spent Nuclear Fuel. The Task Team evaluated multiple alternatives, assessing programmatic, technical, and schedule risks, and generated life-cycle cost projections for each alternative. The eight technology alternatives evaluated were: direct co-disposal; melt and dilute; reprocessing; press and dilute; glass material oxidation dissolution system (GMODS); electrometallurgical treatment; dissolve and vitrify; and plasma arc. In followup to the Business Plan that was developed to look at SNF dry storage, WSRC prepared an addendum to the cost study. This addendum estimated the costs for the modification and use of an existing (105L) reactor facility versus a greenfield approach for new facilities (for the Direct Co-Disposal and Melt and Dilute alternatives). WSRC assessed the impacts of a delay in reprocessing due to the potential reservation of H-Canyon for other missions (i.e., down blending HEU for commercial use or the conversion of plutonium to either MOX fuel or an immobilized repository disposal form). This report presents the relevant results from these WSRC cost studies, consistent with the most recent project policy, technology implementation, canyon utilization, and inventory assumptions. As this is a summary report, detailed information on the technical alternatives or the cost assumptions raised in each of the above-mentioned cost studies is not provided. A comparison table that briefly describes the bases used for the WSRC analyses is included as Appendix A

  5. A simple analysis of potential radiological exposure from geological disposal of Canada's nuclear fuel waste

    International Nuclear Information System (INIS)

    Amiro, B.D.; Dormuth, K.W.

    1996-02-01

    AECL has submitted an environmental impact statement (EIS) describing its proposal for geological disposal of Canada's nuclear fuel waste. The EIS presents a detailed analysis of potential radiation exposure of an individual of a critical group of people in a hypothetical case. In this report, we provide a simpler analysis of potential exposure in the hope that the inherent safety of the disposal will be more readily evident from the analysis. A key to the simplification is the elimination from the analysis of the complex transport processes through disposal vault sealing materials and the geosphere. We also eliminate the relatively complex function describing the failure of the thin-walled titanium containers in the case study presented in the EIS. We therefore conceptually replace the thin-walled titanium containers with thicker-walled copper containers, are expected to remain intact much longer than 10,000 a, the period for which a quantitative estimate of individual exposure is made. However, about 1 in 5000 containers could have small defects that were undetected during manufacture. Our analysis applies only to the case of an undisrupted vault. We assume that the vault and geosphere barriers remain intact and prevent immobile radionuclides from reaching the biosphere. However, we also assume that the three most important mobile radionuclides can escape through an undected manufacturing defect in the container wall, and that the flux of these radionuclides is diluted by well water being used by people. We have focused on 129 I, 36 Cl and 14 C, because these nuclides are found to be the dominant source of exposure in more complex analyses. If a single container released radionuclides to well water, we estimate dose rates of about 1 μSv.a -1 from drinking water and 29 μSv.a -1 , which the Atomic Eenrgy Control Board has adopted as a de minimis dose rate, i.e., a dose rate so small as to not warrant institutional control. We believe that the dose rates are

  6. The material politics of waste disposal - decentralization and integrated systems

    Directory of Open Access Journals (Sweden)

    Penelope Harvey

    2012-12-01

    Full Text Available This article and the previous «Convergence and divergence between the local and regional state around solid waste management. An unresolved problem in the Sacred Valley» from Teresa Tupayachi are published as complementary accounts on the management of solid waste in the Vilcanota Valley in Cusco. Penelope Harvey and Teresa Tupayachi worked together on this theme. The present article explores how discontinuities across diverse instances of the state are experienced and understood. Drawing from an ethnographic study of the Vilcanota Valley in Cusco, the article looks at the material politics of waste disposal in neoliberal times. Faced with the problem of how to dispose of solid waste, people from Cusco experience a lack of institutional responsibility and call for a stronger state presence. The article describes the efforts by technical experts to design integrated waste management systems that maximise the potential for re-cycling, minimise toxic contamination, and turn ‘rubbish’ into the altogether more economically lively category of ‘solid waste’. However while the financialization of waste might appear to offer an indisputable public good, efforts to instigate a viable waste disposal business in a decentralizing political space elicit deep social tensions and contradictions. The social discontinuities that decentralization supports disrupt ambitions for integrated solutions as local actors resist top-down models and look not just for alternative solutions, but alternative ways of framing the problem of urban waste, and by extension their relationship to the state.

  7. Safety assessment for radwaste disposal in Korea: Pt. 1

    International Nuclear Information System (INIS)

    Suh, I.S.; Park, H.H.; Han, K.W.; Hahn, P.S.

    1986-01-01

    A simplified safety analysis code has been established in order to provide a basic methodology for the preliminary selection of a disposal method. The disposal type selection is prerequisite to meet the requirements of low and intermediate level radwaste management program in Korea. The code covers resaturation and leaching, migration through fracture-porous media transport such that the rock cavern disposal option can be evaluated compared with that of shallow land burial

  8. Disposal criticality analysis for immobilized plutonium: Internal configurations

    International Nuclear Information System (INIS)

    Gottlieb, P.; Massari, J.R.; Cloke, P.L.

    1998-03-01

    The analysis for immobilized Pu follows the disposal criticality analysis methodology. In this study the focus is on determining the range of chemical compositions of the configurations which can occur following the aqueous degradation processes, particularly with respect to the concentrations of uranium, plutonium, and the principal neutron absorber, gadolinium. The principal analysis tool is a mass balance program that computes the amounts of plutonium, uranium, gadolinium, and chromium in solution as a function of time with inputs from a range of possible waste form dissolution rates, stainless steel corrosion rates, and compound solubilities for the neutronically significant elements. For the waste forms and degradation modes considered here, it is possible to preclude the possibility of criticality by maintaining a plutonium loading limit. Since the presence of hafnium is shown to increase this loading limit, the defense-in-depth policy would suggest the maximization of the amount of Hf as a backup criticality control material. At the end of 1997, after this study was completed, the ceramic waste form was downselected and a new formulation was developed, with the amount of Hf increased to the point where internal criticality may no longer be possible. In addition, recent calculations indicate that GdPO 4 is insoluble over a much broader range of pH than is Gd 2 O 3 , so that its use as the Gd carrier in the waste form would provide an extra margin of defense-in-depth

  9. Lessons from radioactive waste disposal applied to other pollutants

    International Nuclear Information System (INIS)

    Templeton, W.L.

    1983-01-01

    In order to manage scientifically the quantities and kinds of waste disposal in coastal waters and open oceans, one needs to assess the environment's capacity to assimilate these materials. This knowledge may help us avoid an unacceptable biological impact on components of the ecosystem and on humans who harvest its resources. One approach available is the one that has been demonstrated to be applicable for the management of the disposal of radioactive wastes in the ocean. New generic and site-specific methodologies can establish relationships between discharge or release rates and associated radiation doses. The International Commission on Radiological Protection (ICRP) has developed guidelines and recommendations that govern acceptable amounts of radiation that people can be exposed to. The ICRP recommendations on justification and optimization can be integrated into an overall management philosophy in order to quantify alternative waste disposal options. These methodologies, which were developed for the control of radioactive wastes, should be applied directly to public health protection from nonradioactive wastes such as metals and organochlorine pesticides

  10. Annual Status Report (FY2008) Composite Analysis of Low-Level Waste Disposal in the Central Plateau at the Hanford Site

    Energy Technology Data Exchange (ETDEWEB)

    Nichols, W. E. [Hanford Site (HNF), Richland, WA (United States)

    2009-12-18

    In accordance with the U.S. Department of Energy (DOE) requirements in DOE 0 435.1, Radioactive to be considered or purposes of Waste Management, and implemented by DOE/RL-2000-292, Maintenance Plan for the Composite Analysis of the Hanford Site, Southeast Washington, the DOE Richland Operations Office has prepared this annual report for fiscal year 2008 of PNNL-1 1800, Composite Analysis for the Low-Level Waste Disposal in the 200-Area Plateau of the Hanford Site, hereafter referred to as the Composite Analysis. The main emphasis of DOE/RL-2000-29 Is to identify additional data and information to enhance the Composite Analysis and the subsequent PNNL- 11800 Addendum, Addendum to Composite Analysis for Low-Level Waste Disposal in the 200 Area Plateau of the Hanford Site, hereafter referred to as the Addendum, and to address secondary issues identified during the review of the Composite Analysis.

  11. Geoenvironmental considerations for assessments of the potential of solid waste disposal in rural Lebanon, Metn-Kesserwan

    International Nuclear Information System (INIS)

    Nasser, Rima Souheil

    1994-02-01

    This investigation deals with the problem capitalizing on a mountainous area in Lebanon, and allocating potential sanitary landfill sites for solid waste disposal. The current solid waste management scheme is studied through questionnaires distributed to the community, and field investigations on the operation and effects of the final dump sites. The assessment of the potential for solid waste disposal is approached through evaluating the general suitability of that area for sanitary land filling. This is done by studying various socio-economic and technical parameters on both existing dump sites and others that are here proposed. The environmental impacts of existing dump sites are also described; a modified drastic scheme is used to assess potential ground water pollution in these sites. All of the sites ranked high with respect to their potential pollution of ground water. This is mainly due to their being located directly over highly fractured and karstified limestones. Four areas that proved favourable, in suitability analysis, for solid waste disposal are further subjected to geotechnical investigations to arrive at their capability for sanitary land filling. These include permeability, texture, particle density, Atterberg limits, organic content, clay content and type. As a result of capability analysis, the four sites are ranked from most to least capable for sanitary land filling, according to a quantified weighted rating scale. Sanitary land filling is thus proposed. Solid waste disposal, however, must be followed through an integrated management approach which includes, in addition to land filling, composting, incineration and recycling in a comprehensive waste management scheme. These alternatives are discussed in view of their advantages and disadvantages

  12. Comparative life cycle assessment and life cycle costing of four disposal scenarios for used polyethylene terephthalate bottles in Mauritius.

    Science.gov (United States)

    Foolmaun, Rajendra Kumar; Ramjeeawon, Toolseeram

    2012-09-01

    The annual rise in population growth coupled with the flourishing tourism industry in Mauritius has lead to a considerable increase in the amount of solid waste generated. In parallel, the disposal of non-biodegradable wastes, especially plastic packaging and plastic bottles, has also shown a steady rise. Improper disposal of used polyethylene terephthalate (PET) bottles constitutes an eyesore to the environmental landscape and is a threat to the flourishing tourism industry. It is of utmost importance, therefore, to determine a suitable disposal method for used PET bottles which is not only environmentally efficient but is also cost effective. This study investigated the environmental impacts and the cost effectiveness of four selected disposal alternatives for used PET bottles in Mauritius. The four disposal routes investigated were: 100% landfilling; 75% incineration with energy recovery and 25% landfilling; 40% flake production (partial recycling) and 60% landfilling; and 75% flake production and 25% landfilling. Environmental impacts of the disposal alternatives were determined using ISO standardized life cycle assessment (LCA) and with the support of SimaPro 7.1 software. Cost effectiveness was determined using life cycle costing (LCC). Collected data were entered into a constructed Excel-based model to calculate the different cost categories, Net present values, damage costs and payback periods. LCA and LCC results indicated that 75% flake production and 25% landfilling was the most environmentally efficient and cost-effective disposal route for used PET bottles in Mauritius.

  13. Approach for systematic evaluation of transuranic waste management alternatives

    International Nuclear Information System (INIS)

    Hong, K.; Koebnick, B.; Kotek, T.

    1994-01-01

    This paper describes an approach for systematic evaluation of management alternatives that are being considered for the treatment, storage, and disposal of transuranic waste (TRUW) at U.S. Department of Energy sites. The approach, which is currently under development, would apply WASTE-MGMT, a database application model developed at Argonne National Laboratory, to estimate projected environmental releases and would evaluate impact measures such as health risk and costs associated with each of the waste management alternatives. The customized application would combine site-specific TRUW inventory and characterization data with treatment and transportation parameters to estimate the quantities and characteristics of the wastes to be treated, emissions of hazardous substances from the treatment facilities, and the quantities and characteristics of the wastes to be shipped between sites. These data would then be used to estimate for several TRUW management scenarios the costs and health risks of constructing and operating the required treatment facilities and of transporting TRUW for treatment and final disposal. Treatment, storage, and disposal of TRUW at DOE sites is composed of many variables and options at each stage. The approach described in this paper would provide for efficient consideration of all of these facets when evaluating potentially feasible TRUW management alternatives. By expanding existing databases, this model could eventually be adapted to accommodate the introduction of new treatment technologies, updated TRUW characterization data, and/or revised waste acceptance criteria

  14. Formulation and Presentation of Risk Assessments to Address Risk Targets for Radioactive Waste Disposal

    International Nuclear Information System (INIS)

    Wilmot, R.D.

    2002-10-01

    The Swedish regulators have been active in the field of performance assessment of radioactive waste disposal facilities for many years and have developed sophisticated approaches to the development of scenarios and other aspects of assessments. These assessments have generally used dose as the assessment end-point. Regulations recently established in Sweden (SSI FS 1998:1) have introduced a risk criterion for radioactive waste disposal: the annual risk of harmful effects after closure of a disposal facility should not exceed 10 -6 for a representative individual in the group exposed to the greatest risk. This report evaluates different approaches to the definition and use of probabilities in the context of risk assessments, and examines the presentation of the results of risk assessments in safety cases to meet risk targets. The report illustrates the strengths and weaknesses of different possible approaches to risk assessment by reference to assessments in other countries, and provides suggestions for future activity and development in this area by the Swedish regulators. The review of experience in other countries has led to a number of key observations relevant to the conduct of regulatory work on risk assessments and preparations for review. These highlight the importance of developing a protocol for conducting calculations, and linking such a protocol to the requirements of risk assessment calculations and to existing code and model capabilities. There are a number of decisions and assumptions required in developing a risk assessment methodology that could potentially affect the calculated results. These assumptions are independent of the analysis of performance, and relate to issues such as the expectation value of risk, risk dilution, the definition of probability density functions and achieving convergence. A review of a proponent's risk assessment should address these issues in determining the appropriateness and validity of the results presented

  15. Formulation and Presentation of Risk Assessments to Address Risk Targets for Radioactive Waste Disposal

    Energy Technology Data Exchange (ETDEWEB)

    Wilmot, R.D. [Galson Sciences Ltd, Oakham (United Kingdom)

    2002-10-01

    The Swedish regulators have been active in the field of performance assessment of radioactive waste disposal facilities for many years and have developed sophisticated approaches to the development of scenarios and other aspects of assessments. These assessments have generally used dose as the assessment end-point. Regulations recently established in Sweden (SSI FS 1998:1) have introduced a risk criterion for radioactive waste disposal: the annual risk of harmful effects after closure of a disposal facility should not exceed 10{sup -6} for a representative individual in the group exposed to the greatest risk. This report evaluates different approaches to the definition and use of probabilities in the context of risk assessments, and examines the presentation of the results of risk assessments in safety cases to meet risk targets. The report illustrates the strengths and weaknesses of different possible approaches to risk assessment by reference to assessments in other countries, and provides suggestions for future activity and development in this area by the Swedish regulators. The review of experience in other countries has led to a number of key observations relevant to the conduct of regulatory work on risk assessments and preparations for review. These highlight the importance of developing a protocol for conducting calculations, and linking such a protocol to the requirements of risk assessment calculations and to existing code and model capabilities. There are a number of decisions and assumptions required in developing a risk assessment methodology that could potentially affect the calculated results. These assumptions are independent of the analysis of performance, and relate to issues such as the expectation value of risk, risk dilution, the definition of probability density functions and achieving convergence. A review of a proponent's risk assessment should address these issues in determining the appropriateness and validity of the results presented

  16. Geographic factors related to site suitability of low-level waste disposal

    International Nuclear Information System (INIS)

    Zittel, H.E.

    1981-01-01

    A number of factors related to the site suitability of low-level waste disposal sites are discussed. The factors are a combination of those which might be considered environmental and those dealing with site criteria. Among the factors covered are: possible population criteria, alternative site selection, transportation criteria and community involvement considerations. All these factors are discussed in a manner based on the premise that the technology exists to carry out low-level waste disposal in a manner such that public health and safety can be insured. The conclusion of the discussion is that problems encountered in siting low-level waste facilities will be largely societal and political in nature

  17. Status of the nuclear industry's petition for BRC waste disposal rule

    International Nuclear Information System (INIS)

    Fairobent, L.A.

    1989-01-01

    This paper discusses the petition for rulemaking regarding disposal of the Below Regulatory Concern radioactive waste from commercial nuclear power plants. The author addresses Section 10 of the Low Level Radioactive Waste Policy Amendments Act of 1985 which directed NRC to develop standards and procedures for expeditious handling of rulemaking petitions to exempt specific radioactive waste streams from regulation by the Commission due to the presence of radionuclides in sufficiently low concentrations or quantities as to be below regulatory concern. Basically, this means that NRC may grant rulemaking petitions for alternative disposal of waste that is low enough in radioactivity to present no undue risk to public health and safety

  18. Radioactive waste disposal and constitution

    International Nuclear Information System (INIS)

    Stober, R.

    1983-01-01

    The radioactive waste disposal has many dimensions with regard to the constitutional law. The central problem is the corret delimitation between adequate governmental precautions against risks and or the permitted risk which the state can impose on the citizen, and the illegal danger which nobody has to accept. The solution requires to consider all aspects which are relevant to the constitutional law. Therefore, the following analysis deals not only with the constitutional risks and the risks of the nuclear energy, but also with the liberal, overall-economic, social, legal, and democratic aspects of radioactive waste disposal. (HSCH) [de

  19. 40 CFR 268.49 - Alternative LDR treatment standards for contaminated soil.

    Science.gov (United States)

    2010-07-01

    ... 40 Protection of Environment 26 2010-07-01 2010-07-01 false Alternative LDR treatment standards for contaminated soil. 268.49 Section 268.49 Protection of Environment ENVIRONMENTAL PROTECTION AGENCY (CONTINUED) SOLID WASTES (CONTINUED) LAND DISPOSAL RESTRICTIONS Treatment Standards § 268.49 Alternative LDR treatment standards for contaminated...

  20. An assessment of the disposal of radioactive petroleum industry waste in nonhazardous landfills using risk-based modeling

    International Nuclear Information System (INIS)

    Smith, K.P.; Arnish, J.J.; Williams, G.P.; Blunt, D.L.

    2003-01-01

    Certain petroleum production activities cause naturally occurring radioactive materials (NORM) to accumulate in concentrations above natural background levels, making safe and cost-effective management of such technologically enhanced NORM (TENORM) a key issue for the petroleum industry. As a result, both industry and regulators are interested in identifying cost-effective disposal alternatives that provide adequate protection of human health and the environment. One such alternative, currently allowed in Michigan with restrictions, is the disposal of TENORM wastes in nonhazardous waste landfills. The disposal of petroleum industry wastes containing radium-226 (Ra-226) in nonhazardous landfills was modeled to evaluate the potential radiological doses and health risks to workers and the public. Multiple scenarios were considered in evaluating the potential risks associated with landfill operations and the future use of the property. The scenarios were defined, in part, to evaluate the Michigan policy; sensitivity analyses were conducted to evaluate the impact of key parameters on potential risks. The results indicate that the disposal of petroleum industry TENORM wastes in nonhazardous landfills in accordance with the Michigan policy and existing landfill regulations presents a negligible risk to most of the potential receptors considered in this study.